ML083640089

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Draft - Operating Exam (Folder 2)
ML083640089
Person / Time
Site: Beaver Valley
Issue date: 10/23/2008
From:
FirstEnergy Nuclear Operating Co
To: David Silk
Operations Branch I
Hansell S
Shared Package
ML081060562 List:
References
TAC U01628
Download: ML083640089 (343)


Text

RTL#AS. 640U 112-ADM-1301.FO i Page 1 of Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Plot and Evaluate 1/M Data TRAINING MATERIAL NUMBER: 2AD-016 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-016 REVISION NUMBER: 0 TECHNICAL

REFERENCES:

20M-50.4.F, Perform An ECP Calculation Rev. 7 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 30 Minutes PREPARED BY: R. J. Brooks PEER REVIEW BY:

Date APPROVED FOR USE: ,, c Training Supervise? or Designee

~

Date,

1/2-ADM-I 301 .FO Page 2 of Revision TRAINING MATERIAL CHANGE FORM iffected Training Materials: 2AD-016 rype of Change:

Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision 0Yes E l No

_] Changes Not The Change Does Not Impact Learning I Existing Rev. #

Requiring Revision Objectives or Material Quality I New Change #

,ist/Description of Chanj k):

ieason for Change (s):

APPROVALS:

R. J. Brooks NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Date Qualification Matnx. See rraining Superintendent/Superisor/Peer Incumbent Impact Review, f"Changes Not Requiring Revision" only) NOBP-TR-1104.

lI2-ADM-1301.FC I Page 3 of 7 Revision I

' 1 NUMBER: 2AD-016 IPM REVISION: 0 JPM TITLE: Plot and Evaluate l/M Data 7

W A

REFERENCE:

2.1.43 4.114.3 TASK ID: 001 1-003-01-013 JPM APPLICATION: [XI REQUALIFICATION [XI INITIAL EXAM TRAINING 0 FAULTEDJPM [XI ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE:

0 Perform 0 Plant Site 0 AnnualRequalExam 0 BVT 0 Simulate 0 Simulator [7 Initial Exam 0 Classroom 0 OJTiTPE Other:

0 Training 0 Other:

Performer Name: Performer SSN:

JPM RESULTS:

0 SAT 0 WSAT (Comments required for UNSAT evaluation)

Name/SSN: Name/SSN:

Name/SSN: NameiSSN:

112-ADM-I301.F( I Page 4 of 7 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Determine that liM data predicts >500 pcm below ECP value for critical rod height. Notify SM/US that appropriate actions of 20M-50.4.D must be taken. (No further rod withdrawal)

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to perform the task Evaluate l/M data INITIAL CONDITIONS: The unit is in Mode 2.

A reactor startup is in progress.

Control Bank C is at 129 steps.

Control Bank D is at 1 step.

RCS Boron concentration is 1875 ppm.

INITIATING CUE: The Unit Supervisor directs you to complete the 1/M plot per 20M-50.4.F data sheet 3 using the SR count rate data provided. Compare the 1/M data with the predicted ECP data and make a recommendatim for further rod withdrawal. Document your recommendation in the box below. (Located on candidate direction sheet )

REFERENCES:

20M-50.4.F, Performing An Estimated Critical Position Calculation, Rev. 7 TOOLS: Calculator; Ruleristraight edge.

HANDOUT: 20M-50.4.F, Performing An Estimated Critical Position Calculatior ,

Rev. 7 partially completed Data Sheet 3 & Figure 1

BVPS-IFR Unit 2 20M. 50.4.F Station Startup Rei sion 7 Operating Procedures Page 2 ;of 28 Performing An Estimated Critical Position Calculation FIGURE 1 cn

RTL#AS,640U 112-ADM-1301.FC I Page 5 of 7 Revision I CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GlVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task Evaluate l N data INITIAL CONDITIONS: The unit is in Mode 2.

A reactor startup is in progress.

Control Bank C is at 129 steps.

Control Bank D is at 1 step.

RCS Boron concentration is 1875 ppm.

INITIATING CUE: The Unit Supervisor directs you to complete the 1/M plot per 20M-50.4.F data sheet 3 using the SR count rate data provided. Compare the 1 N data with the predicted ECP data and make a recommendation for further rod withdrawal. Document your recommendation in the box below.

RECOMMENDATION:

c

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

When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

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

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

112-ADM-1301.FO I Page 6 of '

Revision OPERATIONS JOB PERFORMANCE MEASURE IPM IJPM REVISION: 0 1 JPM TITLE: Plot and Evaluate 1/M Data 1

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

START TIME:

1. Refer to data sheet 3 I. I Applicant refers to data sheet 3 for count rate data ZOMMENTS:

~ ~~

2.C Refer to liM plot 2.1C Candidate evaluates count rate data from data sheet 3 and plots on the liM for 300, 325, 375, AND 385 total steps.

EVALUATOR NOTE: See attached Answer Key for 1/M plot values.

COMMENTS:

3.C Evaluate l/M plot data 3.1C Applicant determines that the l/M plot predicts criticality

>500 pcm helow ECP. Maximum rod height is Bank D at 40 steps versus ECP of Bank D 101 steps.

COMMENTS:

1/2-ADM-1301.Fl 4 Page 7 ol 7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE IPM NUMBER:

I JPM REVISION: 0 I JPM TITLE: Plot and Evaluate l/M Data 7

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR 1.c InfOrmSM/uS 1.1C Applicant informs SMAJS that 1/M data indicates that criticality will occur >500 pcm below the ECP. Recommend NO FURTHER ROD WITHDRAWALS.

30MMENTS:

TERMINATING CUE: When the applicant makes a recommendation on continued startup, the evaluation for this JPM is comolete.

STOP TIME:

RTLiYA5.640U 1/2-ADM-l301.FO I Page 1 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Perform the Daily Heat Balance TRAINING MATERIAL NUMBER: 2CR-558 PROGRAM TITLE: Licensed Operator Training (Retraining)

COMPUTER CODE: 2CR-558 REVISION hTJMBER: 1 TECHNICAL

REFERENCES:

20M-54.4.C1, Rev 19 Steam Tables INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 30 minutes

' A 4

c 0

PREPARED BY: R. J. Brooks PEER REVIEW BY: t

+e - > L

'\

J

\ z Date APPROVED FOR USE:

  • i- __

Training Supervisoi Asignee Date

1/2-ADM-1301.F( 1 Page 2 of 1 I Revision I TRAINING MATERIAL CHANGE FORM iffected Training Materials: 2CR-558 rype of Change:

4 Changes Requiring Learning Objective Related Change? New Rev. # 1 Revision 0 Yes [XI No 7Changes Not Requiring Revision The Change Does Not Impact Learning Objectives or Material Quality.

Existing Rev. #O New Change #

h/Description of Chang 1s):

Jpdated JPM to cuKent JPM format.

Ydded data sheet C which forces a gain adjustment for N41, N42, and N43 ieason for Change (s):

ncrease Faulted JPM bank APPROVALS :

R. J. Brooks NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Training Superintendent/Superisor/Peer Date Incumbent Impact Review, (Changes Not Requiring Revision onIy) NOBP-TR-1104.

112-ADM-I 301 .FC I Page 3 of 1 I Revision I JPM JPM NUMBER: 2CR-558 REVISION: 1 I JPM TITLE: Perform the Daily Heat Balance 1

WA

REFERENCE:

015 A1.O1 3.513.8 TASK ID: 0021-009-06-013 193007K1.08 3.113.4 2.1.7 4.414.7 JPM APPLICATION: REQUALIFICATION INITIAL EXAM 0 TRAINING

[XI FAULTEDJPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE:

0 Perform 0 Plant Site AnnualRequalExam BVT 0 Simulate 0 Simulator 0 Initial Exam 0 Classroom 0 OJTiTPE 0 Other:

0 Training Performer Name: Performer SSN:

JPM RESULTS:

0 SAT WSAT (Comments required for UNSAT evaluation)

Comments: -

NameiSSN: NameiSSN:

Name1SSN: NameiSSN:

RTL#AS .640U 112-ADM-1301.FO Page 4 of 1 Revision EVALUATOR DIRECTION SHEET TASK STANDARD: The daily heat balance calculation is calculated and the required Pow :r Range instrument gain adjustments are identified as specified in the Answer Key.

RECOMMENDED Control Room STARTING LOCATION:

DIRECTIONS: You are to perform the task Calculating the Daily Heat Balance.

INITIAL CONDITIONS: The Unit is in Mode 1. Tavg matches Tref and power has been stablL for at least 30 minutes. The plant computers are unavailable.

INITIATING CUE: The Unit Supervisor directs you to perform a daily heat balance in accordance with 20M-S4.4.C1, Daily Heat Balance, Part D, to comply with the Tech Spec Surveillance Logs. Perform steps D1 thru D6 an?

report the results. The LEFM Channel Check has been performed satisfactorily.

REFERENCES:

20M-S4.4.C1, Daily Heat Balance, Rev. 19 TOOLS: Calculator Steam Tables HANDOUT: 20M-S4.4.C1, Daily Heat Balance, Rev. 19 Plant Parameters Data Sheet

1/2-ADM-1301.FO I Page 5 of 1 Revision CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task of Calculating a Daily Heat Balance.

INITIAL CONDITIONS: The Unit is in Mode 1. Tavg matches Tref and power has been stab]{:

for at least 30 minutes. The plant computers are unavailable.

INITIATING CUE: The Unit Supervisor directs you to perform a daily heat balance in accordance with 20M-54.4.C1, Daily Heat Balance, Part D, to comply with the Tech Spec Surveillance Logs. Perform steps D1 t h D6 ant report the results. The LEFM Channel Check has been performed satisfactorily.

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

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

Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

1/2-ADM-l301.FC I Page 6 of 1 !

Revision I OPERATIONS JOB PERFORMANCE MEASURE

, NUMBER 2CR-558 JPM REVISION: 1 1 JPM TITLE: Perform the Daily Heat Balance

'I STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)a START TIME:

Simulator Setup: Simulator is not required for this JPM performance, a Plant Parameter Data sheet is to be provided to each candidate.

EVALUATOR NOTE:

Plant Parameter Data Sheet to contain the following; 1 S/G Blowdown flow AP in Inches HzO 1 Power Range NI indications Feedwater Temperature from LEFM 10 min avg Feedwater Mass Flow rate from LEFM 9 S/G Steam Pressures 1, Candidate locates appropriate 1.1 Provide candidate with a copy of 20M-54.4.Cl and a procedure plant parameter data sheet.

EVALUATOR NOTE: Procedure can be provided to candidate, if provided, N/A this JPM step.

COMMENTS:

Gathers the necessary data. 2. I , Candidate records AP's from plant parameter data sheet.

2.2. Candidate records NIS Indicated power levels from the plant parameter data sheet.

EVALUATOR NOTE: Part " A of procedure can be completed prior to providing to candidate, if previously completed, N/A this JPM step.

COMMENTS:

RTL#AS.640U I/2-ADM-I 301.FO I Page I of I Revision OPERATIONS JOB PERFORMANCE MEASURE JPM lPMNUMBER: 2CR-558 REVISION: 1 I JPM TITLE: Perform the Daily Heat Balance 1

STEP STANDARD

( C Denotes CRITICAL STEP ) (Indicate S FOR SAT or U FOR UNSAT)a

( 1 Candidate notes that a LEFM Channel check is required.

3.1 Candidate notes that per the initial conditions, a Channel Check has been performed.

~~~~~ ~~ ~ ~

EVALUATOR CUE: If candidate asks question, restate that a Channel Check has been previously performed per the initial conditions.

COMMENTS:

I 4.

Converts S/G blowdown flow from AP in Inches H 2 0 to lbmihr

4.1 COMMENTS

Candidate converts each S/G blowdown flow from AP in Inches H 2 0 to lbm/hr

5. Obtain and record appropriate 5.1 Candidate records data from the plant parameter data sheet plant data. 5.2 Records the LEFM Feedwater temperature.

5.3 Records the LEFM Feedwater Mass Flow Rate.

5.4 Records the SIG Steam pressures and converts to PSIA.

provided on the plant 5.5 Records the SIC Blowdown flowrates previously parameter data sheet. calculated.

COMMENTS:

RTL#AS .640U 1R-ADM- 1301.FO Page 8 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE

'PMmBER JPM REVISION: 1 2CR-558 1 JPM TITLE: Perform the Daily Heat Balance J

TEP ;TANDARD "C"Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR U N S A Q J i.C Perform calculations  ;.IC Candidate calculates the average steam pressure for all 3 SiG's by adding all 3 indications and dividing by 3.

i.2C Candidate calculates the total SIG Blowdown mass flowrate by adding all 3 SIG blowdown flowrates together.

i.3C Candidate calculates the total Steam Mass flowrate by subtracting the total blowdown mass flowrate from the feedwater mass flowrate.

ZOMMENTS:

7.C Obtain Enthalpy's 7.1C Candidate obtains the steam enthalpy (hsT) from the saturated steam table using "h," at the calculated average steam pressure.

7.2C Candidate obtains blowdown enthalpy (hBD)of the blowdown from each steam generator by determining "h;'

for saturated fluid, based on the respective steam generator steam pressure.

7.3C Candidate obtains feedwater enthalpy (hw) by determining the "hi' for saturated fluid, based on the LEFM feedwater temperature COMMENTS:

112-ADM-1301.FO, Page 9 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE

, IPM NUMBER 2CR-558 JPM REVISION: 1 1 JPM TITLE: Perform the Daily Heat Balance 1

STEP STANDARD

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

8.C Determine the Heat Transfer LlC Candidate multiplies the total steam mass flow rate times the steam enthalpy.

L2C Candidate multiplies the blowdown mass flow rate from each steam generator times the respective blowdown enthalpy for each steam generator.

3.3C Candidate adds the blowdown mass flow rates for each steam generator

%.4C Candidate multiplies the total feedwater mass flow rate times the feedwater enthalpy.

ZOMMENTS:

J.1C Candidate calculates the RCS Output by adding the Stean and blowdown heat transfers AND THEN subtracting the Feedwater heat transfer.

3.2C Candidate calculates the Net Reactor Power by subtractin:

"33.105" from the RCS Output.

9.3C Candidate calculates the Megawatt Thermal by multiplying the Net Reactor Power times AND the1 dividing the resultant by "3.413".

9.4C Candidate calculates the "% Reactor Power" by dividing the Megawatt Thermal by "2900" AND then Multiplying the resultant by "100%".

COMMENTS:

1/2-ADM-1301.FO1 Page IO of 1 Revision OPERATIONS JOB PERFORMANCE M E A S W rpM NUMBER 2CR-558 SPM REVISION: 1 I JPM TITLE: Perform the Daily Heat Balance 1

STEP iTANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UKSAT)z

.O. Review the results ~0.1 Candidate compares the calculated power level to 2900 MWt and determines that 2OM-52.2.A does not need to be referred to for limitations on power.

EVAIAJATOR CUE: Power is less than 2900 ZOMMENTS:

Il.C Determine if Power Range Il.1C Candidate reviews criteria and determines that a gain Channels gain adjustment s adjustment will be required.

necessary.

EVALUATOR NOTE: The Criteria and required EVALUATOR NOTE: NI(s) needing gain adjustment is dependant upon Alternate Path, Gain adjustment the data given in the particular plant parameter data will be required to successfully sheet.

complete JPM.

IOMMENTS:

12. Determine if calculated power 12.1 Candidate determines that calculated power level is greater is less than 70% than 70% therefore I&C does NOT need to reduce the Setpoints to 85%.

EVALUATOR NOTE: Candidate should N/A the step.

COMMENTS:

112-ADM-1301.FO :

Page 1 1 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE

'PM NUMBER: 2CR-558 1 JPM REVISION: 1 1 JPM TITLE: Perform the Daily Heat Balance 1

S1h.Y jTANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)S 13.C Complete table check marks for 13.1C Candidate completes procedure table with check marks in NI's needing adjustment. the appropriate locations for each NI.

E V A L U A T O R NOTE: The required NI(s) needing gain adjustment is dependant upon the data given in the particular plant parameter data sheet.

ZOMMENTS:

1 14. Candidate requests review and approval of Heat Balance 14.1 14.2 Candidate reports to the SMiUS the results of the Heat Balance and which specific NI's need gain adjustment.

Candidate requests that the results he reviewed and results.

approved prior to NI Gain adjustment.

E V A L U A T O R CUE: Report to candidate that another operator will review the heat balance results prior to performing NI Gain adjustment.

E V A L U A T O R NOTE: Grader discretion is required when evaluating calculations.

COMMENTS:

STOP TIME:

JPM NUMBER: 2cR-558 JPM REVISION: 1 I JPM TITLE: Perform the Daily Heat Balance 7

Plant Parameter Data Sheet - C I I A I R I I I

112-ADM-1301.FO Page 1 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Prepare a Clearance Tagout (2SWE*P21B)

TRAINING MATERIAL NUMBER: 2AD-017 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-017 REVISION NUMBER: 0 TECHNICAL

REFERENCES:

NOBP-OP-1001, Clearance Program, Rev. 0 NOP-OP-1001, ClearanceiTagging Program, Rev. 9 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 25 Minutes PREPARED BY: R. J. Brooks PEER REVIEW BY:

($J+ - 7 Dati APPROVED FOR USE: + Lr c Training Superc f,;dDesignee Datc 4

1/2-ADM-1301 .FO.

Page 2 of Revision TRAINING MATERIAL CHANGE FORM Ufected Training Materials: 2AD-017 rype of Change:

7Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision 17 Yes 0 No 3 Changes Not The Change Does Not Impact Learning Existing Rev. #

Requiring Revision Objectives or Material Quality.

New Change #

A/Description of Chang ieason 1 Change (s):

WPROVALS :

i. J. Brooks NOTE: Additions, deletions or

'repared by Date changes to training materials must be reviewed for their possible impact to the Training rraining Superintendent/Superisor/F'eer Date Qualification Matrix. See Incumbent Impact Review,

"'Changes Not Requiring Revision" only)

NOBP-TR-1104.

RTL#AS .640U II2-ADM-I 301.FC I Page 3 of i Revision

' JPM NUMBER: 2AD-017 JPM REVISION: 0 1 JPM TITLE: Prepare a Clearance Tagout (2SWE*P21B) 1 WA

REFERENCE:

2.2.13 (3.6) TASK ID: 0481-020-03-013 JPM APPLICATION: [XI REQUALIFICATION [XI INITIAL EXAM 0 TRAINING 0 FAULTEDJPM [XI ADMINISTRATIVE JPM EVALUATION METHOD:

0 Perform 0 LOCATION:

Plant Site 0 TYPE:

AnnualRequalExam ADMINISTERED B 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 NRc 0 Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other: -

I EVALUATION RESULTS -

I Performer Name: I I

Performer SSN:

ITime 0 Yes Iritical: [XI NO I Time:

I 25 Minutes Actual Time:

minutes JPM RESULTS:

0 SAT 0 mSAT (Comments required for UNSAT evaluation)

Comments: .-

Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

Evaluator Signature:

1R-ADM-1301.FO Page 4 of I Revision EVALUATOR DIRECTION SHEET TASK STANDMU): Identify the tags and sequence of placement for a tagout of 2SWE*P21B Standby Service Water Pump.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to perform the task Prepare a Clearance Tagout INITIAL CONDITIONS: The plant is in Refueling Mode, no fuel is in the reactor. 2SWE*P2113 Standby Service Water Pump is to be placed on clearance. Service Water Pumps 2SWS*P21A AND B are Operable and running.

2SWE*P21A Standby Service Water Pump is operable.

INITIATING CUE: You are to identify the required clearance points (equipment), positim (placement configuration), and sequence for clearing 2SWE*P21B Standby Service Water Pump, for pump inspection. NO seal cooler work OR motor work will be performed. SOMS is out of service.

Document your results on the table provided.

REFERENCES:

NOBP-OP-1001, Clearance Program, Rev. 0 NOP-OP-1001, Clearance/Tagging Program, Rev. 9 TOOLS: None HANDOUT: NOBP-OP-1001, Clearance Program, Rev. 0 NOP-OP- 1001, Clearance/Tagging Program, Rev. 9 OP Manual Fig. No. 30-1A, 10080-RM-430-1A, Rev. 4 OM Chapter 20M-30.3.C Power Supply and Control Switch Checklist.

1/2-ADM- 1301 .FOI Page 5 of (

Revision I CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

TASK: You are to perform the task Prepare a Clearance Tagout INITIAL CONDITIONS: The plant is in Refueling Mode, no fuel is in the reactor. 2SWE*P211 I Standby Service Water Pump is to be placed on clearance. Service Water Pumps 2SWS*P21A AND B are Operable and running.

2SWE*P21A Standby Service Water Pump is operable.

INITIATING CUE: You are to identify the required clearance points (equipment), position (placement configuration), and sequence for clearing 2SWE*P21B Standby Service Water Pump, for pump inspection. NO seal cooler work OR motor work will be performed. SOMS is out of service.

Document your results on the table provided.

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

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

Simulate performance or perform as directed the required task.

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

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

Then hand this sheet to the evaluator.

112-ADM-1301.FO 1 Page 6 of i Revision OPERATIONS JOB PERFORMANCE MEASURE IPMNUMBER: 2AD017 I JPM REVISION: 0 I JPM TITLE: Prepare a Clearance Tagout (2SWE*P21B) 1 STEP jTANDARD

' "C" Denotes CRITICAL STEP (Indicate "S" FOR SAT or "U" FOR U N S A T p 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.

EVALUATOR NOTE: Provide JPM handout and student copy of table. I l.C Candidate completes the table. 1.1C Candidates table matches the ANSWER KEY.

ZOMMENTS:

1TERMINATING CUE: When the candidate identifies and reports that all tags are identified, the evaluation for this JPM is complete.

STOP TIME

ANSWER KEY (DO NOT GIVE TO STUDENTS)

Component I D

. - Component Description Position I Sequence Control Switch for Standby Service PUI I-To-Lock 1 (AE) Water Pump 2SWS*P21C (AE) (PTL) 4 KVS-2DF-2FI9 Supply to Standby Service Water Pump Racked Out 2 2SWE* P21B SWE-224 Disch Is01 Valve Shut 3 SWE-260 Seal WTR Supply to STBY SW PP Shut 3 (2SWE-P21B) Is01 SWE-228 Disch Is01 Valve To Screen Wash Shut 3 SWE-308 Drain Is01 On Discharqe At 2SWE-P21B Open 4 Evaluator NOTE: Student may identify additional points. The points listed above are the minimum required for this JPM. All additional points must be evaluated to ensure the clearance is correct.

E 0

E I-n 8

I n1 H

I

T-TT-TT # , I / , I , ,

' I!,

i2 6 7 I 8 I 9 I 10

1/2-ADM-1301.FC I Page 1 of 1 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Respond to a Radiation Monitor Alarm TRAINING MATERIAL NUMBER: 2AD-018 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-018 REVISION NUMBER: 0 TECHNICAL

REFERENCES:

20M-43.4.AEE Rev. 5 20M-43.4.AAC Rev. 1 20M-43.4.ACC Rev. 4 20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Con'ents To Cooling Tower Blowdown. Rev. 24 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 10 Minutes PREPARED BY: R. J. Brooks PEER REVIEW BY:

Dale APPROVED FOR USE:

'i 3

+ -

Training Supervisolb?<esignee Dare

112-ADM-1301.FO Page 2 of 1 Revision TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-018 Type

.. of Change:-

7Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision 0Y e s 0No 7Changes Not The Change Does Not Impact Learning- Existing Rev. #

Objectivesor Material Quality.

Requiring Revision New Change ##

LisVDescription of Chang i):

Original issue Reason for Change (s):

APPROVALS:

R. J. Brooks Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Training SiiperintendentlSupervisorlPeer Date Qualification Matrix. See Incumbent Impact Review, (Changes Not Requiring Revision only) NOBP-TR-1104.

1R-ADM-1301.FO Page 3 of 1 Revision

' JPM NUMBER: 2AD-018 IPM REVISION: 0 I JPM TITLE: Respond to a Radiation Monitor Alarm 1

WA

REFERENCE:

2.3.1 1 3.8 TASK ID: 0171-016-01-013 JPM APPLICATION: [XI REQUALIFICATION INITIAL EXAM 0 TRAINING

[XI FAULTEDJPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE:

0 Perform 0 Plant Site 0 AnnualRequalExam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 Classroom 0 OJT/TPE 0 Other:

n Training EVALUATION RESULTS -

Performer Name: Performer SSN:

JPM RESULTS:

0 SAT 0 mSAT (Comments required for UNSAT evaluation)

Comments: ..

Name/SSN: Name/SSN:

NameiSSN: Name/SSN:

Evaluator (Print): Date:

Evaluator Signature:

1/2-ADM-l301,FO L Page 4 of 1 Revision EVALUATOR DIRECTION SHEET TASK STANDARD: Liquid Waste Eff Isol Vlv 2SGC-HCV100 is CLOSED and SG Blowdown Test Tank Pump 2SGC-P26B is stopped. RWDA-L Discharge Stop Data is documented.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform the task Respond to a Radiation Monitor Alarm.

INITIAL CONDITIONS: Unit 2 is Mode 3 with the Shutdown banks withdrawn. A liquid wast.:

discharge of Steam Generator Blowdown Test Tank 2SGC-TK23B is.

in progress to Unit 1 blowdown. A Discharge permit (RWDA-L -

99999T) has been issued for this discharge. A4-5C, Radiation Monitoring Level High alarm has been received in the control room.

INITIATING CUE: The Unit Supervisor directs you to respond to the Radiation Monitoring Level High alarm in accordance with plant procedures.

REFERENCES:

20M-43.4.AEE Rev. 5 20M-43.4.AAC Rev. 1 20M-43.4.ACC Rev. 4 TOOLS: None HANDOUT: RWDA-L-99999T filled out up to the discharge in progress point.

20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Contents To Cooling Tower Blowdow 1 filled out up to the discharge in progress point.

RTL#A5 .640U 1/2-ADM-1301 .FO Page 5 of 1 Revision CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task Respond to a Radiation Monitor Alarm.

INITIAL CONDITIONS: Unit 2 is Mode 3 with the Shutdown banks withdrawn. A liquid was?e discharge of Steam Generator Blowdown Test Tank 2SGC-TK23B i..

in progress to Unit 1 blowdown. A Discharge permit (RWDA-L -

99999T) has been issued for this discharge. A4-5C, Radiation Monitoring Level High alarm has been received in the control room.

INITIATING CUE: The Unit Supervisor directs you to respond to the Radiation Monitoring Level High alarm in accordance with plant procedures.

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

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

Simulate performance or perform as directed the required task.

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

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

Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F( 1 Page 6 of 1 I Revision I OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2AD-018 JPM REVISION: 0 I JPM TITLE: Respond to a Radiation Monitor Alarm 1

I Fg' Denotes CRITICAL STEP STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=

START TIME:

Simulator Setup:

POST GREEN MAGNETIC PLACARD FOR SITE LIQUID WASTE DISCHARGE IN PROGRESS Mode 3 Snap (IC-240 for 2LOT6 NRC exam)

1. Setup a LW discharge of 2SGC-TK23B using 2SGC-P26B, SG Blowdown Test Tank Pump.
2. Set ALERT setpoint of 2SGC-RQ100 to 1.22E-3 pCi/ml (1065 sel; channel items; 122-3 enter)
3. Set HIGH setpoint of 2SGC-RQ100 to 1.74E-3 pCi/ml.

(174-3 enter)

4. Start sample pump.
5. Insert a failure to prevent 2SGC-HCV100 Liquid Waste Eff Is01 Vlv. from AUTO closing on HIGH alarm from 2SGC-RQ100.
6. Insert malfunction to raise 2SGC-RQ100 above the high alarm setpoint.
7. Verify A4-5C, Radiation Monitoring Level High alarms Items 2 , 3 , and 4 will need to be done each time the simulator is reset. (they do not carryover in the IC) 1, Applicant refers to ARF' for A4- 1.1 Locates and refers to 20M-43.4.AAC 5C, Radiation Monitoring Level High 20M-43.4.AAC. COMMENTS:

RTL#A5 640U 1/2-ADM-1301.F( 3 Page 7 of 1 I Revision I OPERATIONS JOB PERFORMANCE MEASURE IJPM JPM REVISION: 0 2AD-018 I JPM TITLE: Respond to a Radiation Monitor Alarm 1

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "Ut' FOR UNSAT)J  :.

2. Perform the following at the R b 2.1 At DRMS panel depresses Grid 6 11 operators console: 2.2 Verifies ILXO65 is blinking and RED Press the gnd 6 pushbutton ANI Determine which radiation 30MMENTS:

monitor in alarm (blinking and has turned red).

EVALUTOR NOTE:

The four digit number is the radiation monitor number less the letters (1.e. 1PA234 will be 1234).

3. Type in the 4-digit numerical 3.1 Types 1065 on DRMS keyboard AND depresses the SEL code number of the alarming pushbutton monitor AND Press the SEL pushbutton. SOMMENTS:

1.1 Depresses the STATUS pushbutton on the DRMS keyboard.

JOMMENTS:

1/2-ADM-1301.F(I Page 8 of 1 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I IPM NUMBER: 2AD-018 JPM REVISION: 0 I JPM TITLE: Respond to a Radiation Monitor Alarm 7

I STEP

( "C" Denotes CRITICAL STEP )

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)= 7 4N I

I

5. Press SYSTEM ACK to silence the console alarm.

5.1 Depresses the SYSTEM ACK pushbutton on the DRMS keyboard.

COMMENTS:

6. If any radiation monitor is at OR 6.1 NIA approaching, 1000 times normal background, Immediately notify EVALUTOR CUE:

the SM/US AND Refer to Role-play SMiUS and inform the candidate that 2SGC-1120111-57, "Emergency RQlOO is NOT 1000 times normal background.

Preparedness Plan" for further actions COMMENTS:

EVALUTOR NOTE:

Candidate may also refer to 20M-43.4.ACC in the next step. This would be acceptable. (This procedure also contains the "Critical" steps necessary to isolate the LW discharge) .

7. Refer to local alarm response 7.1 Refers to 20M-43.4.AEE.

procedures 20M-43.4.ACN through 20M-43.4.AEJ and COMMENTS:

20M-43.4.AEL for corrective actions.

RTL#AS 640U 1/2-ADM-1301.F( 3 Page 9 of 1 I Revision I OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER:

JPM REVISION: 0

  • 1 JPM TITLE: Respond to a Radiation Monitor Alarm 7

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)a 8.C If a high radiation condition is 3.1 Verifies 2SGC-HCV100 Liquid Waste Eff High Rad Is01 suspected in [2SGC-TK23B]: Vlv Green light NOT LIT and RED light LIT 3.2C Rotates 2SGC-HIC100 Liquid Waste Eff High Rad Isol Verify Closed [2SGC-HCV100], Vlv Controller counterclockwise until demand output is Liquid Waste Eff Isol Vlv. (BB- ZERO.

A). 3.3 Verifies 2SGC-HCV100 Liquid Waste Eff High Rad Is01 Vlv Green light - LIT and RED light - NOT LIT EOMMENTS:

I 9.C Stop [2SGC-P26A(B)], SG Blowdown Test Tank Pumps 9.1C Places CS for SG Blowdown Test Tank Pump 2SGC-P26B to STOP (BB-A).

COMMENTS:

10.1 Contacts Health Physics to inform them that the discharge was secured due to High Alarm on 2SGC-RQ100.

EVALUTOR CUE:

Role-play Health Physic and acknowledge the report.

COMMENTS:

RTL#AS.640U 112-ADM-1301.FO 1 Page 10 of 1 ,

Revision OPERATIONS JOB PERFORMANCE MEASURE IJpM JPM REVISION: 0 2AD-018 I JPM TITLE: Respond to a Radiation Monitor Alarm STEP STANDARD

( CDenotes CNTICAL STEP ) (Indicate S FOR SAT or U FOR UNSAT)=,

11. Have chemistry sample the 11.1 Contacts Chemistry to inform them that the discharge was contents of the in service SG secured due to High Alarm on 2SGC-RQ100 AND request Blowdown Test Tank to verify SG Blowdown Test Tank to verify high radiation high radiation condition. condition.

EVALUTOR CUE:

Role-play Chemistry and achowledge the report.

ZOMMENTS:

EVALUTOR CUE:

Role-play SM/US and direct the candidate to complete the required documentation on the RWDA-L for stopping r

the discharee.

EVALUTOR NOTE:

The guidance for completing the RWDA-L documentation is contained in 20M-25.4.L Attachment 12.C Record the following on the 12.1C Records the following information on space provided on RWDA-L at the Discharge the RWDA-L Stop Date Date Time Time Tank Level equal to -95 inches Initials COMMENTS:

RTL#A5 640U 1/2-ADM-1301.F( 1 Page 1 1 of I I Revision I OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2AD-018 JPM REVISION: 0 I JPM TITLE: Respond to a Radiation Monitor Alarm 1

I STEP I STANDARD I ( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)a 13.C Calculates the volume 13.1 Determines volume discharged by subtracting current discharged and records on the volume for 95 inches from original volume of 17,705 RWDA-L at the "Discharge 13.2 IAW Table 1 on page 29 of 20M-25.4.L 95 inches is Stop" 13,341 gals.

13.3 17705 13341 =4,364gals

~

13.4C Records 4, 364 gals on RWDA-L JOMMENTS:

EVALUTOR CUE:

That completes this JPM STOP TIME:

Form 1/2-ENV-05.04.F01,Rev 0 (Page 1 of 5) RTL#319 .52OA RwP4-L: Part 1, Summary of Discharge Data RWDA L,99999T' Bf ?r Valley Power Station-2 This ermit authorizes the dischar e of a maximum of 17705.3 gallons from %mk 2SGC-TK23B at a maximum &charge rate of 85 .O g p m to the environment via U1 blowdown with.a minimum total coolin tower blowdown Of 4000.0 at Unit 1 and Unit 2 with a monitor ALdT alarm setpo-nt o f 1.22E-03 u%/ml and a monitor HIGH alarm set oint of 1.74E-03 uCi/ml on 2SGC-RQ100 (See Below for Alternate 8 a m SetDoints) m i s t- was recirculated _YESTERDAY 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to YESTERDAY 2001 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.613805e-4 months <br /> (at which time it was sampled) for a total-of 1200 minutes.

Pre ared By Reviewed BY Remarks :

Cooling Tower Plow Set Monitor Source Unit 1 W U l & U 2 Init

?/#

nit Check Init Monitor Alarms Adjusted ALERT )@

nit fHIGH I

gpm)

C.T. Flow x ( en) = ( qal1 Discharge Time Dilution Vo ume

Form 1/2-gW-05.04.F01, 1ev.O [page 2 of 51 KTMA9.52QA BRDB-I:Part 2 Tank Analysis RWDA-G99999T Beaver valley h e r station-2 tMK: 2SSC-1I23B T A U VDLUIIB: 17705.3 gal, 6.70Et07 li LgvW: 130,.0 in SBlIpLB IDKPIIFICATIDB: 2DDBD422005 TOO1111 C.1. E'LOR: 4000.0 gpm Concentration OBC. Count EPA-&

EUCLIDX m-51 5%&

Fraction' 1.061-03 Pate 1.071102 fraction 3.561-07 co-58 3.968-05 1.988-01 1.218103 2.658-04 CO-60 1.478-06 4.90G02 3.508t02 9.868-06 PB-59 1.4%-06 1.4%-02 1.83~saz 9.7~1-06 A6-11011 5.201-07 8.668-03 2.22B+02 3.48B-06 SB-124 8 . 821-06 1.26B-01 2.378103 5.91B-05 SB-12.5 1.m-05 3.70B-02 1.618103 7.44B-05

F a n 1/2-Blm-05.04.F0l Kev 0 [pa e 3 of 5 )

KIIDA-L: Part 3 , Pre-Keiease Dose jrojections ~nt~9.5; lA Beaver Valley Power Statlon-2 RWA-L-9999T (All Dose Values in @em]

WCLIDB CORCEUIUTIOB BOHB LIVn T o m BODS' IEYKUID KIDHBY CP-51 5.328-06 U.OO8tOO 0.008t00 1.67B-07 LW6 GI-ll CO-58 P.968-08 3.618m 2.218-07 4.13- 3 3.968-05 U.UO8tO0 8.718-05 1.95B-04 0.00Bt00 0.00Bt00 O.OU8tUO CO-60 1.478-06 U.tlUBtU0 9.318-06 1.178- 3 FB-59 1.458-06 3.71B-05 2.058-05 U.OOB+UU O.O08+OU 0. UUBtUD 1.748- 4 8.738-05 3.34B-05 U.OO8tUU 0. 00BtOU 1.98B-05 2.91B-,4 116-llM 5.208-07 1.21g-08 1.128-08 6.658-09 O.OOBt00 2.2UB-08 SB-124 8.82B-06 1.71B-06 O.0OBtDO 4.588-1 6 3.238-08 6.758-07 4.118-09 0.008+00 1.338-06 4.848-15 SB-125 1.118-05 1.378-06 1.53B-08 3.288-07 1.(OB- 09 O.UO8tUO 1.068-06 1.518-1 j FB-55 0. UOBtUU 0.008t00 0.008+00 0.OUBtOU O.OUB+UO 0.008+00 0.00Bt00 O.OUBtl3 SP-89 0. UOB+UU 0. 008t00 0.OOBtUO 0. OOBt00 0. OOBiOO U.UOB+UO O.UUBtU0 SP-90 0.008+00 U.UO~+UU 0.OUBtUO 0.008+00 0.00Bt00 0. 008tI3 0.008+00 0.00B+00 0.00BtE1 E- 3 1.408-02 0.008t00 9.308-05 9.308-05 9.308-05 9.308-05 9.308-05 9.308-0 G.ALPBA 0. UDB+OO 0. 008+0O 0 .00Bt00 0.00Bt00 0.008tOO 0.00Bt00 0.00k00 U.OO8tO' 2.778-04 3.438-04 9.318-05 9.308-05 1.158-04 2.g8-0 1.388-04 1.118-04 4.658-05 4.658-05 5.778-05 1.228-0 4.138-03 3.828-03 2.778-03 3.9417-0j 2.808-03 1.868-03 3.998-03 2.818-03 6.288-0 3.99B-03 2.86B-03 7.508-0.

4.738-03 3.828-03 2.178-03 3.948-03 2.8UB-03 4.868-03 3.998-03 2.818-03 6.28B-0:

3.99B-03 2.868-03 7.508-0:

4.738-03 3.828-03 2.77B-43 4.868-03 3.998-03 .?.BE-03 4.738-03 3.82B-03 2.778-03 1.868-03 3.998-03 2.818-03 Unit 1 Current Fear Dose = 2.828-02 5.958-02 3.82B-02 8.848-03 3.238-02 1.268-02 WIT.1 PKOJKCTED YBBP DOSE = 2.838-02 5.96B-02 3.848-02 8. 89B-03 2.92B-02 3.238-02 1.268-02 3 .U58-02 Unt 2 Current Year Dose = 2.82842 5-958-02 3.828-02 8 .84B.-03 3.23B-02 1.268-02 2.928-02 WIT 2 PKoJBfl'KD YEAR DOSE = 2.838-02 5.968-02 3.848-02 8.898-03 3.238-02 1.26B-02 3.058-02 rhe SIII of the Bo's is < 1; this is not considered a Beportable Quantity.

BXEKCISK HODB OBLY

Form lR-ENV45.M.FOl. Rev 0 (Page 4 of 5) f n~ 9 . 5 2 0 ~

RWDA-L: P a r t 4 . Checklist, P r e - R e l e a s e Data and Alternate A l a r m Setpoint Determination Beaver Valley Power Station 1 I 2 -

I RWDA-L-9% [TI Inilials&&  : Pre-Release Data obtained from Operations /Ref: procedure la-ENV-05.041 Initials ffie  : Samples obtained &Valve Verifications performed IRef: procedure 112-ENV-05 011 Jnitials PA-3  : Samples analyled (Ret procedure 112-ENV-05.251

!nitlacs r ' G 0  : Sample bottks marked wlh the RWDA-L number IRef: procedure 1R-ENV-05.011

.Initials &/3  : RWDA-L prepared via rhe LIQDIS ComDuter Code IRef procedure 1R-ENV-05.041 Initials 'G f3 :Alarm Setpoints adjusted IFarm l-HPP4.02.OOI.FOl & 1-HPP4.02.040.F01or 2-HPP4.02.022.FOl 8 Z-HPP4.02.037.F011 Initlals P6.e  : RWDA-L turned-aver to Control Room Shin Manaqer or Unit Supervisor [Ref: procedure l/Z-ENV-05.04]

lnitial~  : EffluentMonilor Readings obtained dunnq discharqe IRef: Form lR-ENV-05.04.FOl ( p a w 5 of 511 RWDA-L Pre-Release Data: Complete this portion of the form PRIOR to entrance i n t o the LIQDIS Computer Code Source of Discharge: [ ] CUI> Unit 1 H<uz> Unit 2 Tank [ 1 4 2 for 1LW-TK-GA. or [ I c2r for 6B [ 1 <I, for ZLWS-TKZIA, or [ 1 for 218 Identification: [ 1 c3z far ILW-TK-3A. or [ 1 c4> for 38 [ Ic3~forZSGC-TKZlA.o r [ ]<4WforZlB

[ ] <5> for 1LW-TK-SA. or [ 1 <6> for 5B [ 1 for 2SGC-TKZ3A. or [ q < 6 rfor 23B

- I 157, for iLW-TK-7A. or 1 1 for 78 [ 1 <7> far Not Applicable, or 1 ] ( 8 ) for NIA Note: Use 1 <7, for Other Releases (e.g.: Chemical Waste Sump) Note: Use [ 1 cl, for Other Releases 1e.g.: Fire Sump)

TankVolume: /7705.3 qallons Tank Level; / 30.0 I Ifeel. or I*lincher Recirculation Start: Sample T i m e : Y E S T E R D A Y 2001 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.613805e-4 months <br /> YESTERDAY 0001 to YESTERDAY 2001 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.613805e-4 months <br />

- ~

Sample ID: I 1 Unit 1 Sample ID No. , o r [ y D n i t 2 s a m p l e 1 ~ ~ 0a . ~8oyaaooS I Sample NOTE: For independent sampl.ng, record the Cancentratlono hlghnstnuclido c o n c m l m i o n lram eacn sample Independent I Replicate SampleCompar~sgp(

Form 1/2-ENV-05.04 FOI, Rev 0 (page 5 of 5) RTL# A I 5 2 0 ~

RWDA-L Part 5, Effluent Radiation Monitor Tracking Beaver Valley Power Station I I 2 ~ lTank Identification:

RWDA-L-99999T LSGC - rK 2 3 6 3 Discharge Period Initial Start D a t e K i m e : 1h d u f l AG O I Final Stop Datemime: 3 See RWDA Cover Shest lor Adba Times RWDA-L Count Rate: Form lR-ENV65.04.FOl (page 2 of 5) =

NOTE: MDCR = Minimum Detectable Count Rate 1 ]Ethe RWDA-L Count Rate is 9 . 1 4 1 net cpm (MDCR), THEN the discharge is controlled by the alarm setpoints (No further calculations required

[ 1 E the RWDA-L Count Rate is >1,141 net cpm. THEN determine the Acceptable Range 01 Readings for control of the discharge. as follows:

Maximum = (RWDA-L Count Rate cpm) x (2) + (bkgd RWDA-L Count Rate: Form lR-ENV-05.04.FOl (page 2 of 5) =

NOTE MDCR = Minimum Detectable Count Rate

[] E the RWDA-L Count Rate is 5236 net cpm (MDCR). T U the discharge is controlled by th

[ ]Ethe RWDA-L Count Rate is ,236 net cpm. THEN determine the Acceptable Range of Readings for ~ ~ n t ofmthe l discharge. as follows:

Maximum = (RWDA-L Count Rate cprn) x (2) + (bkgd NOTE MDCR = Minimum Detectable Count Rate

[ 1 E the RWDA-L Count Rate is 5247 net cpm (MDCR). THEN the discharge is controlled by the a

[ J E the RWDA-L Count Rate is s247 net cpm, THEN determine the Acceptable Range of Readings for Control of the discharge. as follows:

Maximum = (RWDA-L C w n t Rate cpm) x (5.61E-9uCilrnllcpm) x (2) + (bkgd 1 Minimum = (RWDA-L Count Rate cpm) x (5.61E-9 uCi1mVcpm) l ( 2 ) + (bkgd uCilml) =

Dale ITime 1-  : Reading  : 1s reading within range? Yes[ 1 No[ 1: RT initials__ : SAP NO.

Dale ITime 1-  : Reading  : 1s reading within rang@?Yes[ ] No[ 1: RT Initials:- SAP NO.

Date ITime -I  : Reading  : 1s reading within range? Yes[ ] NO[1: RT Initials :- SAP No.

Date ITime 1-  : Reading 15 reading within range? Yen[ ] No[ 1: RT Initials:- SAP No.

Dale I Time 1-  : Reading  : 1s reading within range? Yes[ 1 No[ 1: RT Initials __ :SAP NO.

Date ITime 1-  : Reading  : 1s reading within range? Yes[ 1 No[ 1: RT Initials__ : SAP NO.

[ ]EEffluent Monitor Readings are not within the Acceptable Range of Readings. =contact Chemistry Supervi~ion I ] Chemistry Supervision has determined that the discharge Should be terminated: and Operations has been notified lo terminate the discharge.

[ ] Chemistw Supervision has determined that the discharge may continue. Reasoning:

SAP No: Date:

112-ADM-1301.FI 4 Page 1 of 7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Plot and Evaluate 1/M Data and Determine Required Actions (SI .O Only) ~

TRAINING MATERIAL NUMBER: 2AD-019 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-019 REVISION NUMBER: 0 TECHNICAL

REFERENCES:

20M-50.4.D 20M-50.4.F INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 20 Minutes

? ." . 4 PREPARED BY: R. J. Brooks t ,

i

\,

"\

4

,,A*'

I Datf:

'~.' i PEER REVIEW BY:

Dat':

APPROVED FOR USE:

7L'

/

Training Supervigor or Designee Dat .;

1/2-ADM-l301.F 4 Page 2 o I Revisior 1 TRAINING MATERIAL CHANGE FORM 4ffected Training Materials: 2AD-019 rype

~. of Change:

7Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision 3 Changes Not The Change Does Not Impact Learning Existing Rev. #

Requiring Revision Objectives or Material Quality.

New Change #

ListiDescription of Chang S):

Reason for Change (s):

4PPROVALS:

NOTE: Additions, deletions or R. J . Brooks changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See rraining Superintendent/Superisor/Peer Date Incumbent Impact Review, Changes Not Requiring Revision only) NOBP-TR-1104.

112-ADM-1301.FI 4 Page 3 ol 7 Revision I I JPM NUMBER: 2AD-019 1 JPM TITLE: Plot and Evaluate l/M Data and Determine Required ' 1 JPM REVISION: 0 1 Actions (SRO Onlv) I EVALUATION METHOD: LOCATION: TYPE:

Perform Plant Site 0 AnnualRequalExam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam Classroom 0 OJTITPE 0 Other:

0 Training Performer Name: Performer SSN:

I I

I Time 0 Yes *'lotted 20 Minutes Actual minutes Critical: No Time: Time:

JPM RESULTS:

SAT 0 mSAT (Comments required for UNSAT evaluation)

Comments: -

Name/SSN Name/SSN Name/SSN Name/SSN

RTLffA5.640U 1/2-ADM-1301.F14 Page 4 01 7 Revisior 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Determine that 1/M data predicts >500 pcm below ECP value for critical rod height. Determines No further rod withdrawal will be allowed, and the following actions must be taken:

Insert all control rods to 0 Steps.

Verify RCS Boron Concentration.

Verify SDM DO NOT recommence SAJ without Plant Manager approval.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to perform the task Evaluate 1/M data.

INITIAL CONDITIONS: The Unit is in Mode 2.

A reactor startup is in progress.

Control Bank C is at 129 steps.

Control Bank D is at 1 step.

RCS Boron concentration is 1875 ppm.

INITIATING CUE: The Unit Supervisor directs you to complete the 1/M plot per 20M-50.4.F data sheet 3 using the SR count rate data provided. Compare the 1/M data with the predicted ECP data and determine actions related to further rod withdrawal. Document any recommended actions in tk e box below. (Located on the candidate direction sheet)

REFERENCES:

20M-50.4.D, Reactor Startup From Mode 3 To Mode 2, Rev. 49 20M-50.4.F, Performing An Estimated Critical Position Calculation Rev. 7 TOOLS: None HANDOUT: 20M-50.4.F, Performing An Estimated Critical Position Calculation Rev. 7 partially completed Data Sheet 3 & Figure 1 20M-50.4.D, Reactor Startup From Mode 3 To Mode 2, Rev. 49

BVPS-IFR Unit 2 Station Startup R ?vision 7 Operating Procedures Page 24 of 28 Performing An Estimated Critical Position Calculation FIGURE 1 u?

2 q

FlGUf?E 1

RTL#AS .640U lR-ADM-1301.Fl 4 Page S of 7 Revision 1 CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • 0 Read:

TASK. You are to perform the task Evaluate IN data.

INITIAL CONDITIONS: The Unit is in Mode 2.

A reactor startup is in progress.

Control Bank C is at 129 steps.

Control Bank D is at 1 step.

RCS Boron concentration is 1875 ppm INITIATING CUE: The Unit Supervisor directs you to complete the 1/M plot per 2 0 M -

50.4.F data sheet 3 using the SR count rate data provided. Compare the 1/M data with the predicted ECP data and determine actions re1ati.d to further rod withdrawal. Document any recommended actions in tht box below.

I RECOMMENDED ACTIONS:

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

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

Simulate performance or perform as directed the required task.

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".

0 Then hand this sheet to the evaluator.

1/2-ADM-l301.FI 4 Page 6 01 7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-019 1 JPM TITLE Plot and Evaluate 1/M Data and Determine Required 7 I JPM REVISION: 0 I Actions (SRO Onlv) I 1 Denotes CRITICAL STEP STANDARD r START TIME:

1 1.

Refer to Data sheet 3 1.1 Applicant refers to data sheet 3 for count rate data.

IOMMENTS:

2.C Refer to 1IM plot. 2.1C Candidate evaluates count rate data from data sheet 3 and plots on the l/M for 300,325, 375, AND 385 total steps.

EVALUATOR NOTE: See Attached Answer Key for 1/M plot values. I COMMENTS:

3.1C Applicant determines that the l h 4 plot predicts criticality

>500 pcm below ECP. Maximum rod height is Bank D at 40 steps versus ECP of Bank D 101 steps.

COMMENTS:

RTL#AS.640U 112-ADM-1301.F 4 Page 7 01 7 Revisior 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-019 JPM TITLE Plot and Evaluate 1/M Data and Determine Required EVALUATOR CUE:

If necessary ask candidate to provide specific actions required.

4.C Determines action for continued 4.1C Applicant determines that l/M data indicates that startup IAW 20M-50.4.D criticality will occur 7500 pcm helow the ECP.

Attachment 3 Action #4. Insert all control rods to 0 steps.

Verify RCS boron concentration.

Verify SDM Do not continue without Plant Manager approval.

~~

TERMINATING CUE: When the applicant makes a recommendation on continued startup, the evaluation for this JPM is complete.

COMMENTS:

I STOP TIME:

112-ADM-I 301.FO Page 1 of Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Prepare Partial OST [20ST-6.6] for Performance (SRO ONLY)

TRAINING MATERIAL NUMBER 2AD-025 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-02s REVISION NUMBER: 0 TECHNICAL

REFERENCES:

NOP-LP-2601, Procedure Use And Adherence (Rev. 1) 20ST-6.6, PORV Isolation Valve Test and Position Check (Rev. 18)

INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 15 Minutes PEER REVIEW BY: -

Date APPROVED FOR USE: \ - .-

Training Superv, ><$Designee Date

II2-ADM-I 301.FC I Page 2 of <

Revision I TRAINING MATERIAL CHANGE FORM

~ ~ ~ _ _ _ _

4ffected Training Materials: 2AD-025 rype of Change:

~~ -

7Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision u Yes 3 Changes Not The Change Does Not Impact Learning Existing Rev. #

Requiring Revision Objectives or Material Quality.

New Change #

ListDescription of Chang S):

Reason for Change (s):

4PPROVALS:

NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training rraining SuperintendenUSuperisorPeer Date Qualification Matrix. See Incumbent Impact Review, (Changes Not Requiring Revision only)

NOBP-TR-I 104.

112-ADM-1301.FO 1 Page 3 of ;

Revision I JPM NUMBER: 2AD-025 I JPM TITLE: Prepare Partial OST 120ST-6.61 for Performance (SRO 1 JPM REVISION: 0 I ONLY) I W A

REFERENCE:

2.1.20 4.6 TASK ID: 1320-006-03-023 JPM APPLICATION: REQUALIFICATION INITIAL EXAM 0 TRAINING FAULTEDJPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED B 7 0 Perform 0 Plant Site 0 AnnualRequalExam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 NRc 0 Classroom 0 OJT/TPE 0 Other:

0 Training 0 Other: .-

tI Performer Name:

EVALUATION RESULTS I Performer SSN:

Actual 15 Minutes minutes zritical: No Time: Time:

JPM RESULTS:

0 SAT 0 mSAT (Comments required for UNSAT evaluation)

Comments: ~.

Name/SSN: Name/SSN:

Name/SSN: I Name/SSN:

EVALUATOR -

Evaluator (Print): Date:

Evaluator Signature:

1/2-ADM-1301.F( t Page 4 of 3 Revision I EVALUATOR DIRECTION SHEET TASK STANDARD: All steps of 20ST-6.6 that relate specifically to 2RCS*MOV537 are omitted or marked N/A. (Answer Key provided to assist in this evaluation)

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to perform the task Prepare a Partial OST for Performance.

INITIAL CONDITIONS: Unit 2 is at 100% power. 20ST-6.6, PORV Isolation Valve Test and Position Check is on the Work Implementation Schedule (WIS) and I S scheduled to be performed on your shift. PRZR PORV 2RCS*PCV455D is INOPERABLE but CAPABLE of being manually cycled. Technical Specification 3.4.1 1 required action A.l has been completed and PORV 455D Motor Operated Is01 Vlv 2MOV*MOV537 is CLOSED. All PORV Motor Operated Is01 Vlvs were last stroked 70 days ago. The last ASME Valve remote positioI:

indication verification was performed 90 days ago on ALL PORV Motor Operated Is01 Vlv.

INITIATING CUE: As the Shift manager, IAW the guidance provided in NOP-LP-2601.

Procedure Use And Adherence, Prepare 20ST-6.6, PORV Isolation Valve Test and Position Check for a Partial OST Performance. PORJ 455D Motor Operated Is01 Vlv 2MOV*MOV537 will NOT be tested Return the marked-up OST to the evaluator. (Assume the evaluator will perform the second licensed SRO concurrence of your mark-ups).

REFERENCES:

NOP-LP-2601, Procedure Use And Adherence (Rev. 1) 20ST-6.6, PORV Isolation Valve Test and Position Check (Rev. 18)

TOOLS: None HANDOUT: NOP-LP-2601, Procedure Use And Adherence (Rev. 1) 20ST-6.6, PORV Isolation Valve Test and Position Check (Rev. 181

1/2-ADM-1301 .FO 1 Page 5 of i Revision CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task Prepare a Partial OST for Performance.

INITIAL CONDITIONS: Unit 2 is at 100% power. 20ST-6.6, PORV Isolation Valve Test and Position Check is on the Work Imulementation Schedule (WIS) and is scheduled to be performed on your shift. PRZR PORV 2RCS*PCV455D is INOPERABLE but CAPABLE of being manual ly cycled. Technical Specification 3.4.11 required action A.l has been completed and PORV 4551) Motor Operated Isol Vlv 2MOV*MOV537 is CLOSED. All PORV Motor Operated Isol Vlvs were last stroked 70 days ago. The last ASME Valve remote position indication verification was performed 90 days ago on ALL PORV Motor Operated Isol Vlv.

INITIATING CUE: As the Shift manager, IAW the guidance provided in NOP-LP-2601, Procedure Use And Adherence, Prepare 20ST-6.6, PORV Isolation Valve Test and Position Check for a Partial OST Performance. POR'J 455D Motor Operated Isol Vlv 2MOV*MOV537 will NOT be teste1 .

Return the marked-up OST to the evaluator. (Assume the evaluator will perform the second licensed SRO concurrence of your mark-ups).

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

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

Simulate performance or perform as directed the required task.

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".

0 Then hand this sheet to the evaluator.

RTL#A5.64OU 112-ADM-1301.FO 1 Page 6 of :

Revision OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-025 JPM TITLE: Prepare Partial OST [20ST-6.6] for Performance (SRO L

( L.*'Denotes CRITICAL SIFP )

I (Indicate "S" FOR SAT or "U" FOR U N S A T p IS d START TIME:

I. The Shift Manager or designated 1.1 Determines based on initial conditions that, All steps related SRO shall determine if the section specifically to PORV 455D Motor Operated Is01 Vlv or step will be designated as N/A 2MOV*MOV537 shall be omitted or marked N/A or whether the section or step shall be performed.

Documents the following on page 3 of the OST under test results:

The Shift Manager or designated SRO shall document the decision Circles Partial OST in the official record copy of the Writes an explanation documenting why PORV 455D procedure. Motor Operated Is01 Vlv 2MOV*MOV537 will NOT be performed EVALIJTOR NOTE:

Completing Test Results section may be deferred until test completion; therefore candidate may NOT perform this step as part of the JPM. This is acceptable.

COMMENTS:

JPM NUMBER 2AD-025 JPM TITLE: Prepare Partial OST [20ST-6.6] for Performance (SRO iTEP STANDARD "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)-

!.C If the Shift Manager or designated 2.1 Candidate performs the following:

SRO has granted approval, the performer or responsible

. On Page 9 item VII.A.l- places 70 days ago and initials in the space provided.

supervisor shall ensure that the procedure section or step is . initialsPagein theitemspace On 9 VII.A.2- places days ago and provided.

90 designated as N/A, initialed and dated. . Page item VII.A.3.a- places NIA.

On 9 2.2c On Page 10 item VII.A.3.c- places NIA.

2.3 On Page 13 item VII.C.l.b.1 places N/A.

2.4 On Page 14 places N/A on ALL items.

2.5 On Page 15 items g and h places N/A.

2.6 On Page 16 items 2, 3 , 4 , 5, and 2.b.l places N/A.

2.1 On Page 17 places N/A on ALL items.

2.8 On Page 18 items g and h places NIA.

2.9 On Page 19 items 2,3,4, and 5, places N/A.

COMMENTS:

RTL#A5.640U 112-ADM-1301.FO 1 Page 8 of <

Revision OPERATIONS JOB PERFORMANCE MEASURE IPM NUMBER: 2AD-025 I JPM TITLE: Prepare Partial OST r20ST-6.61 for Performance (SRO 1 I JPM REVISION: 0 I ONLY) I STEP STANDARD

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

3.1C On pages 19 through 22 places NIA for all of step 3, initials and dates.

30MMENTS:

EVALUTOR NOTE:

Grader discretion may he required. The "critical" portions of this P M are to clearly document the steps that are to he performed and the steps that are NOT to be performed. An answer key is provided to assist in evaluating this JPM.

EVALUTOR CUE:

That completes this JPM.

STOP TIME:

lI2-ADM-1301 .FO1 Page 1 of I Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Review/Approve Completed Surveillance of RHS Pump (SRO ONL TRAINING MATERIAL NUMBER 2AD-026 -

PROGRAM TITLE: Licensed Operator Training -

COMPUTER CODE: 2AD-026 -

REVISION NUMBER: 0 -

TECHNICAL

REFERENCES:

' T T - 1 0 . 2 Residual Heat Removal Pump [2RHS*P21B] Performance Test Rev. 10 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 10 Minutes

+++ '\

PREPARED BY: R. J. Brooks PEER REVIEW BY: -.

Date APPROVED FOR USE: .- .-

Training Supervisor Date

112-ADM-1301 .F04 Page 2 of 9 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-026 Type of Change:

0Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision 0Y e s No 0Changes Not The Change Does Not Impact Learning Existing Rev. #

Requiring Revision Objectives or Material Quality.

New Change #

ListDescription of Change(s):

New JPM Reason for Change (s):

APPROVALS:

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

("Changes Not Requiring Revision only)

" 1

RTLffA5.640U 112-ADM-1301 .FO Page 3 of Revision OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2AD-026 JPM REVISION: 0 1 JPM TITLE: Review/Approve Completed Surveillance of RHS Pump W A

REFERENCE:

2.2.37 4.6 TASK ID: 1320-01 1-03-023 EVALUATION METHOD: LOCATION: TYPE:

0 Perform c] Plant Site AnnualRequalExam 0 BVT 0 Simulate 0 Initial Exam OJTITPE 0 Other:

Training Performer Name: Performer SSN:

Time Critical:

0 Yes NO I Time:

I 10 Minutes Actual Time:

minutes JPM RESULTS:

0 SAT 0 WSAT (Comments required for UNSAT evaluation)

Comments: -

I Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

I Evaluator Signature:

1R-ADM- 1301.FO.

Page 4 o f '

Revision OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: 2RHS*P21B is declared inoperable based on unacceptable A P and vibrations.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to perform the task Review/Approve completed Surveillance of RHR Pump 2FCHS*P21B to determine operability as defined by thc acceptance criteria.

INITIAL CONDITIONS: Unit 2 is in Mode 5 with RCS core exit thermocouple temperatures at 110°F. Surveillance 20ST-10.2 Residual Heat Removal Pump

[2RHS*P21B] Performance Test has been completed by the RO and reviewed by the STA.

'NITIATING CUE: ReviewiApprove completed Surveillance of RHR Pump 2RHS*P2 1B to determine operability as defined by the acceptance criteria.

Document the results of your review in the comments section of the cover page.

REFERENCES:

20ST-10.2 Residual Heat Removal Pump [2FWS*P21B] Perfomanci.

Test. Rev. 10 TOOLS: None HANDOUT: 20ST-10.2 Residual Heat Removal Pump [2RHS*P21B] Performanct Test (Rev. 10) completed With unacceptable A P and vibrations.

1/2-ADM-1301.F( 1 Page 5 of ?

Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task Review/Approve completed Surveillance of RHR Pump 2RHS*P21B to determine operability as defined by thl acceptance criteria.

INITIAL CONDITIONS: Unit 2 is in Mode 5 with RCS core exit thermocouple temperatures ai 110'F. Surveillance 20ST-10.2 Residual Heat Removal Pump

[2RHS*P21B] Performance Test has been completed by the RO and reviewed by the STA.

INITIATING CUE: Review/Approve completed Surveillance of RHR Pump 2RHS*P21B to determine operability as defined by the acceptance criteria.

Document the results of your review in the comments section of the cover page.

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

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

Simulate performance or perform as directed the required task.

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 J P M .

Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.FI 4 Page 6 01 9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-026 I JPM REVISION: 0 I JPM TITLE: Review/Approve Completed Surveillance of RHS Pump 7

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)a START TIME:

1. Refers to appropriate procedure I.1 Consult the Acceptance Criteria for acceptable step. performance.

ZOMMENTS:

2.C [2RHS*P21B], Residual Heat 2.1 Compares Actual Motor Vibrations on Data Sheet 1 to Removal Pump: Operates within Acceptable and Alert range.

the limits of ASME XI IST 2.2C Determines Motor Inboard (2) Axial is GREATER Program ([ITS] T.S.5.5.4) as THAN Acceptable and Alert Range I follows: Motor Vibration (Data Sheet 1)

COMMENTS:

3.C [2RHS*P21B], Residual Heat 3.1. Compares Actual Pump Vibrations on Data Sheet 1 to Removal Pump: Operates within Acceptable and Alert range.

the limits of ASME XI IST 3.2C Determines Pump Inboard ( 3 ) Horizontal and Vertical are Program ([ITS] T.S.5.5.4) as BOTH greater than Acceptable and Alert Range.

follows: Pump Vibration (Data Sheet 1)

COMMENTS:

112-ADM-1301.FI 4 Page I of 9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-026 I JPM REVISION: 0 I JPM TITLE: Review/Approve Completed Surveillance of RHS Pump I STEP STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)a 4.C [2RHS*P21B], Residual Heat 3.1 Compares calculated Delta P on Data Sheet 2 to Removal Pump: Operates within Acceptable Range.

the limits of ASME XI IST 1.2C Determines calculated Delta P is LESS THAN Program ([ITSITS. 5.5.4) as Acceptable Range.

follows: Delta-P (Data Sheet 2)

ZOMMENTS:

5 . [2RHS*4], Residual Heat 5.1 Reviews step VII.B.9 of OST to determine if 4000 gpm Removal Pump 21B Disch was achieved.

Check Vlv, operates within the 5.2 Determines step was completed satisfactorily.

requirements of ASME XI IST Program ([ITS] T.S. 5.5.4) for forward flow (full-stroke) at a flowrate of 4000 gpm (Step COMMENTS:

VII.B.9).

6.C [2SIS*141], SI Accum Tank 21C 6.1C Determines DOES NOT MEET Acceptance criteria Check to Loop C Cold Leg, partial based on unacceptable A P and vibrations.

stroke forward flow test. (Check valve operation is acceptable IF IU.A.1 above is met.) ([ITS] T.S.

5.5.4)

COMMENTS:

RTLffA5.640U IR-ADM-1301 .Fl 4 Page 8 of 9 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I

JPM NUMBER 2AD-026 JPM REVISION: 0 I STEP JPM TITLE: ReviewiApprove Completed Surveillance of RHS Pump I STANDAIU) 7 1.-( "C" Denoles CRITICAL STEP..) L . - 1-Indicate "S" FOR SAT

. ~ ~

or "U".~

FOR UN

~

S,== . ..

7. RHR heat exchanger outlet '.I Compares the Data from Data sheet 3 to initial conditions temperature indication conforms ofcore exit thermocouples of 110°F.

with the expected temperature based on current plant conditions. 7.2 Determines that these are as expected.

(Data Sheet 3) 2OMMENTS:

8. RHR heat exchanger outlet 3.1 Compares Data from Data sheet 3; and, determines that temperatures and RCS cold leg RHR heat exchanger outlet temperatures and RCS cold temperature are within 25°F of leg temperature are within 25°F of each other.

each other. (Data Sheet 3).

COMMENTS:

RTL#AS.@OU 1/2-ADM-1301.FC I Page 9 of Revision '.

OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2AD-026 JPM REVISION: 0 I JPM TITLE: Review/Approve Completed Surveillance of RHS Pump 1

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)a 1.C Complete the front cover 3.1 Places a checkmark in the Problems encountered block of sheet. cover page.

9.2C Lists the following uroblems on OST nroblem sheet:

Motor Inboard (2) Axial vibration is GREATER THAN Acceptable and Alert Range Pump Inboard (3) Horizontal and Vertical vibrations are BOTH greater than Acceptable and Alert Range.

Calculated Delta P is LESS THAN Acceptable Range.

[2SIS*141], SI Accum Tank 21C Check to Loop C Cold Leg, partial stroke forward flow test. (Check valve operation is unacceptable (Due to problems listed above).

COMMENTS:

EXAMINER CUE:

That completes this JPM STOP TIME:

112-ADM-1301 .FI 4 Page 101 8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Review/Approve LW Discharge (SRO ONLY)

TRAINING MATERIAL NUMBER: 2AD-023 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2AD-023 REVISION NUMBER: 0 TECHNICAL

REFERENCES:

20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Conttmts To Cooling Tower Blowdown. Rev. 24 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 15 Minutes

/ )

  1. 0 PREPARED BY: R. J. Brooks \ # * )

PEER REVIEW BY: r 0 -

rC - -J- Datc

/

APPROVED FOR USE: 1-4

, y --I&

Training Supervisor *I -&ignee Date 4

112-ADM-1301.F I4 Page 2 o 8 Revisioi 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-023 Type of Change:

0Changes Requiring

~

Learning Objective Related Change? New Rev. # 0 Revision 0Y e s 0 No 0Changes Not The Change Does Not Impact Learning Existing Rev. #

Requiring Revision Objectives or Material Quality.

New Change #

ListlDescription of Chani s) :

Reason for Change (s):

APPROVALS:

~ ~~

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

NOBP-TR-I 104.

I

112-ADM-1301.F I4 Page 3 o 8 Revisioi 1 JPM NUMBER: 2AD-023 JPM TITLE: ReviewiApprove LW Discharge (SRO ONLY)

JPM REVISION: 0 K/A

REFERENCE:

2.3.1 1 4.3 TASK ID: 1300-009-03-023 JPM APPLICATION: [XI REQUALIFICATION INITIAL EXAM TRAINING El FAULTED JPM ADMINISTRATIVE JPM LOCATION: TYPE: ADMINISTERED B ?

0 plant Site AnnualRequalExam 0 BVT 0 Simulate 0 Simulator Initial EX^ NRc Classroom 0 OJT/TPE Other:

Iu I

Training I I Other: -

Performer Name: Performer SSN:

I Time kitical:

0 Yes No 1 Time:

15 Minutes Actual Time:

minutes JPM RESULTS:

0 SAT 0 WSAT (Comments required for UNSAT evaluation)

Comments:

NameiSSN: NameISSN:

Name/SSN: NameiSSN:

Evaluator (Print): Date:

Evaluator Signature:

IR-ADM- 1301.F04 Page 4 off Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: RWDA-L-99999T is NOT approved for the following reasons:

Wrong tank volume and Wrong alternate radiation monitor alarm setpoint calculation.

RECOMMENDED Classroom STARTTNG LOCATION:

DIRECTIONS: You are to perform the task ReviewiApprove LW Discharge.

INITIAL. CONDITIONS: Unit 2 is at 100% power. RWDA-L-99999T has been prepared for discharging Steam Generator Blowdown Evaporator Test Tank 2SG( '-

TK23B. Steam Generator Blowdown Evaporator Test Tank 2SGC-TK23B level is 130 inches. Procedure 20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(!)]

Contents To Cooling Tower Blowdown has been completed through step IV.A.ll.

INITIATING CUE: Approve RWDA-L-99999T IAW procedure 20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(ll)]

Contents To Cooling Tower Blowdown step IV.A.12.

Document the results of your approval in appropriate steps of 2 0 M -

25.4.L AND in the block below. (Located on candidate direction sheet)

REFERENCES:

20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Contents To Cooling Tower Blowdown Rev. 24 Curve Book for 2SGC-TK23B TOOLS: Calculator HANDOUT: RWDA-L-99999T filled out with the following errors:

18,000 gal volume for the tank instead of 17,705 gals.

Wrong alternate radiation monitor alarm setpoint calculation. ( I .88E instead of 1.X8E 20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)] Contents To Cooling Tower Blowdo,vn filled out up to step 1V.A.12

RTL#AS .640U 1/2-ADM-1301 .F '4 Page 5 o 8 Revisior 1 CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

TASK: You are to perform the task Review/Approve LW Discharge.

INITIAL CONDITIONS: Unit 2 is at 100% power. RWDA-L-99999T has been prepared for discharging Steam Generator Blowdown Evaporator Test Tank 2SG( :-

TK23B. Steam Generator Blowdown Evaporator Test Tank 2SGC-TK23B level is 130 inches. Procedure 20M-25.4.L, Discharging Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(H )]

Contents To Cooling Tower Blowdown has been completed through step 1V.A.1 1 .

INITIATING CUE: Approve RWDA-L-99999T IAW procedure 20M-25.4.L, DischargiIig Steam Generator Blowdown Evaporator Test Tank [2SGC-TK23A(B)]

Contents To Cooling Tower Blowdown step IV.A.12.

Document the results of your approval in appropriate steps of 20M-25.4.L AND in the block below. -

RESULTS:

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

When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

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".

0 Then hand this sheet to the evaluator.

112-ADM-I301 .F04 Page 6 of E Revision 1 OPERATIONS JOB PERFORMANCE MEASURE NUMBER: 2AD-023 I JPMREVISION: 0 1 JPM TITLE: Review/Approve LW Discharge (SRO ONLY) 1 STEP STANDARD

( "C" Denotes CRITICAL STEP )

START TIME:

1. After the RWDA-L is approved .1 Verifies Unit 1 Shift Manager has signed the appropriate by Radiation Protection AND block on the RWDA-L Chemistry, have the SM or US review the RWDA-L to confirm the following: :OMMENTS:

Verify that the Unit 1 SM OR US has signed the RWDA-L at "Approved By".

2.C The tank data is correct  !.1C Refers to Tank Curve book and determines that the tank data is INCORRECT. The correct volume for 130 inches should be 17,705 gals. NOT 18,000 gals.

EVALUTOR NOTE:

Candidate may also refer to recirculation time of the tank. The recirculation time is more than the minimum required.

ZOMMENTS:

3. Verify Chemistry has authorized 3.1 Verifies Chemistry has signed the appropriate block on the the RWDA-L. RWDA-L IOMMENTS:

RTL#A5.640U 1/2-ADM-1301 .F14 Page70 8 Revisior 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2m-023 I JPMREVISION: 0 1 JPM TITLE: Re\iew/Approve LW Discharge (SRO ONLY) 1 STEP STANDARD

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

Verify Radiation Protection has 4.1 Verifies Rad Pro has signed the appropriate block on the authorized the RWDA-L. RWDA-L ZOMMENTS:

5.C All hand calculations are 5.1C Determines that the alternate radiation Alarm setpoint correct. calculation is INCORRECT.

EVALUTOR NOTE:

4000/85 X 4.0B6should equal 1.88E-4NOT 1.88B 3

A N D this also makes 1 .88B4 X .7 INCORRECT.

COMMENTS:

Verify the effective period for 6.1 Determines RWDA-L is still effective the RWDA-L has NOT expirec EVALUTOR NOTE:

IAW P&L I on page 3 the RWDA-L is effective for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time the sample was drawn COMMENTS:

RTL#A5.640U 1I2-ADM- 130 1.FOL Page 8 oft Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2AD-023 JPMREVISION: 0 I JPM TITLE: Review/Approve LW Discharge (SRO ONLY) 1 STEP ;TANDARD

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

In the remarks section places the following information:

7.C If the tank is NOT acceptable for discharge, an approval signature is NOT required.

'.IC

.. Mark the RWDA-L VOID Tank volume is incorrect.

Mark the RWDA-L VOID, state Radiation monitor alarm setpoint calculations are reason, initial, AND Return the incorrect RWDA-L to Radiation Protection. Candidate initials (Otherwise N/A this step).

EVALUTOR NOTE:

Some discretion is required when grading this step of the JF'M. It is NOT required to place the exact words listed here for the tank volume and radiation monitor alarm setpoint. However, it is critical the candidate documents all the emors on the form.

ZOMMENTS:

EVALUTOR CUE:

That completes this JPM.

STOP TIME:

porn 1/2-ENV-05.04.POl, Rev 0 (Page 1 of 5) RTI&A9 - 52Oj RWA-L: Part 1 Summary of Discharge Data RWDA-I -99999T Beaver Valley hower station-2 This tank w a s recirculated from Yesterday 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to Y e s ~ ~ d ~ y _ 2 0 0 1 ~ h p y y s (at which time it was sampled) for a total of 1200 minutes.

I Cooling Tower Plow Set Unit 1Y\C~Ul&U2 Ini;t Y[ft Monitor Check nit mo dy yr hr mn levl ini mo dy y r hr mn levl ini gal. TOTAL 1- -I-- - 1- -I --

-I-I--I----I-I--I---

-I-I-I--I-I-I--

_Discharge

_-__---_ Time,

_ _ - -min

- - - -=- - - - - - - - _Discharged

- _- - _ _ _ _ _ - _ Volume,

_ _ - _ _ _ _ _gal

_ _ _=_ _ _ _ _ _ _ _ _ _ _ _ _

ALERT htA Init HIGH NA

_ _ _ _ _ _ _ _ _ _ _ _ _Init x t Release Review I

- - - - - - - U1 -_-_- _ _Mgr

- - -Shift - - _ Sig

- - _ - Date

- _ _ _ _ U2 - - - Shift

- Mgr Sig Date gpmt C.T. Plow x ( min) = (

Discharge Time Dilution Vo ume qal1

Porn 1/2-gpP-05.04.P01, Rev.0 [page 2 of 51 kTLh9.52011 BIIDB-I;: Part 2, Tank Aualysis RWDA-L-99999T Beaver Valley Poser Station-2 IAKK: 2S6C-m3B 7'11BI VOLDIIB: 17705.3 gal, 6.708t01 II LEVEL: 13b.D in

'BWLU ID!LETIFICATIOU: 20080422005 TOTAL C.I. PLOR: 4000.0 9pn Concentration OBC cout PA-?@

WCLID1 CP-51 nCi/rl 5.321-06 Fraction*

1.061-03 Pate 1.078102 Fraction 3.56B-07 co-5s 3.961-05 1.988-01 7.2lB+03 2.65B-04 CO-60 l.49B-06 1.908-02 1.50Bt02 9.861-06 F8-59 1,45846 1.453142 1.83Bt02 9.728-06 A6-1101 5.20B-07 8.668-03 2.22Bt02 3.IBB-06 SB-124 8.82B-D6 1.268-01 2.37B103 5.91%-05 SB-125 1.llB-05 3.108-02 1.68Bt03 7.448-05

P a n 1/2-Bllv-05.04.P01 Rev 0 [pa e 3 of 51 1

KRDA-L: Part 3 Pre-Beiease Dose jrojections PTLtA9.52 01 Beaver Valley borer Station-2 RWDA-L-99999 (All Dose Values in &ern)

RICLIDB COACKBTUTIOH BORB LIVER TOTAL BODY THYBOID KIDHEY LW6 CP-51 5.328-06 0.008+00 0.00Bt00 1.67B-07 GI-LLI CO-58 3.968-05 0.008tOO 9.96848 3.67B:718 2.21B47 4.m-05 8.718-05 1.958- 04 O.OOE+OO O.OOB+OO 0.00Bt00 1.778-03 CO-60 1.478-06 O.OOE+OO 9.318-06 2.05B-05 O.OOE+OO 0.008t00 0.008+00 FE-59 1.458-06 3.718-05 8.73B-05 3.348-05 1.748-04 AG-11011 0.00Bt00 0. OO8+OO 1.988-05 2.91E-04 5.20B- 07 1.218-08 1.128-08 6.658-09 0. OOBtOO 2.208-08 0.00B+00 SB-124 8.828-06 1.718-06 3.238-08 6.751-07 4.58B-06 SB-125 1.1l.B-05 1.378-06 4.14E-09 0.00Bt00 1.33B-06 4.848-05 1.538-08 3.288-07 l.4OB-09 0.008tOO 1.068-06 1.51B-05 PB-55 O.OOB+OO 0.00Bt00 O.OOBtO0 0.00Bt00 0.008+00 0.00~t00 0.0OKiOO O.OBB+OQ SB-89 0.008+00 o.ooBtoo 0 .OOBtOO 0.008+00 0.008t00 0. OOBtOO O.OOB+OO 0.0DBt00 SI-90 0.00Bt00 0.00B+00 0. OOBtOO O.OOB+OO 0.00Bt00 0. OOE+OO 0.008t00 E- 3 1.401-02 0.00B+00 9.308-05 9.308-05 0.OOBt00 G.ALPHA 9.308-05 9.308-05 9.308-05 9.30B-05 O.OOB+OO 0.00Bt00 O.OOEtO0 O.OOE+OO O.OOE+OO 0.00Bt00 0 . OOB+OO 0.00Bt00 PPOJBCW) PBLBBSB DOSB = 4.02B-05 2.77B-04 3.438-04 9.318-05 9.308-05 1.158-04 2.448-03 WIT 112 PPOJKCTED PBLEASB DOSE = 2.018-05 1.3lB-04 1.718-04 4.658-05 4.65B-05 5.718-05 1.22B-03 Unit 1 Current Nonth Dose = 6.31B-04 4.738-03 3.828-03 2.778-03 3.94B-03 2.808-03 6.288-03 WII.1 PPOJBCTlD WHIT DOSE = 6.518-04 4.868-03 3.991-03 2.g1~-03 3.99E-03 2.868-03 7.508-03 hit 2 Current Nontb Dose = 6.318-04 4.738-03 3.828-03 2.778-03 3.948-03 2.808-03 WIT 2 PPOJKCTBD N om DOSE = 6.518-01 4.868-03 3.998-03 2.81B-03 3.998-03 2.86B-03 6.288-03 7.508-03 4.73B-03 3.82B-03 2.178-03 3.948-03 2.8OB-03 6.288-03 4.868-03 3.998-03 2.818-03 3.998-03 2.868-03 7.508-03 4.73143 3.828-03 2.178-03 3.948-03 2. R O W 3 6.288-03 4.86B-03 3.998-03 2.818-03 3.99B-03 2.868-03 7.508-03 5.95B-02 3.82B-02 8.848-03 3.23K-02 1.26E-01 2.92B-02 5.968-02 3.848-02 8.898-03 3.238-02 1.268-02 3.058-02 5.958-02 3.828-02 8.848-03 3.238-02 1.26B-02 2.928-02 5.968-02 3.848-02 8.89B-03 3.238-02 1.268-02 3.058-02 ma of the PQs is c 1; this is not considered a Reportable Quantity.

BXEBCISB MODE OBLP

Form In-ENV-05 04 FOi, Rev 0 (Page 4 of 5 ) RTL A9.520P RWDA-L: Part 4, Checklist, Pre-Release Data and Alternate Alarm Setpoint Determination Beaver Valley Power station - 1 I2 IBWDA-L-gg999T -

- RWDA-L Pre-Release Data: Complete this portion of the form PRIOR to entrance inlo the LICIDIS Computer Code Source ofDischarge: [ 1 <Ut> Unii 1 HCUP Unit 2 Tank [ ] cl> for 1LW-TK-6A. or 1 1 <2, IDT 68 [ 1 e l > for2LWsTK214 or [ J for 218 Identification: [ ] c3> for lLW-TK-3A. nr I 1 +lor 38 [ ]<PItorZSGC-TK21A. or[ ]&bar218

[ ] cs> for ILW-TK-SA. or [ J <6, for 58 [ 1 c 9 fm 2SGGTK23A. or [ q c 6 > for 238 I [ 1CPfor iLW-TK-7A. or [ I for 78 I I J <7r lor Not Applicable, or l 1 for NIA Note: Use [ J <-I>lor Other Releases (e&: Chemical Waste Sump)] 1 Note: Use [ 1clr for Other Rekas- (e.9.: Fire Sump) 17705-3 ]Tank Level: 1%. 0 I I feet or f4nches Isampk TankVolume: qalbns Recirculation Start YESTERDAY 0001 to YESTERDAY 2001 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.613805e-4 months <br /> nme:YESTERDAY 2o01 hours Sample ID: I 1 Unit 1 Sample ID No. , o r r y O n ~ 2S a n p i e I ~ ~ oacogoqaaoog Minimum CT Flow from Unit 1 and Unit 2. Yo00 g D m (Asa Guide. O ~ e r a t i o n win~ pmYide this MIWbased on w I W aarm Setwinr min~,.i MO -

Discharge Pam: [.Fur, Send Liquid Waste to Unit 1 CT Blowdown, orl 1 <U2> Send tiquid waste IO Unit 2 CT Blowdown

. ~..:.: . . . , . : . ~ . . . . I . . ... . . .:. ..... . ~..: .:.~. . ... ... . .: . . ... . . ... . . . . . ~ ,

. ~.~..: . ~ I Icdependlml t RepkatPSample Cornpuisga:

1 I ho r m a w n rnonilor ava iaok lor the dlscnarge p irtntiw Guide nrh, quancr(rl. am' year.

Alternate Alarm Setpoint Determination: Complete this portion of the form AFTER exit from the LIQDIS Computer Code 1RM-lLW-v34: lsTotal Patiiulate '3.14E-3 UCdml? [ 1YES [ NO 1 1IF YES. THEN Altemale Alarm Setpoints SHALL NOT be used

[ 1 RM-1LW-116: IS Total Paniculate '7.33E-3 Uclhl ? [ ] YES J NO & IF NO. THEN Alternate Alarm Sapointr M A Y be used

Form l/Z-ENV45.04.FOl, Rev 0 (page 5 of 5) RTLt A9 520A RWDA-L: Part 5, Effluent Radiation Monitor Tracking IRWDA-L-99999T 7 Beaver Valley Power Station - 1 / 2 Effluent Radiation Monitor & Determination ofAcceptable Range of Readings During Discharge: J

[ ] Unit 1 Liquid Waste Tank Discharge via IRM-1LW-3041: 'IM-ILW-I04 DKgd = - :pm RWDA-: Comt Rale Form 1Q.ENV-05 04 FO1 (Page 2 01 5) i net cpm RMlLW-IO4 Gross HSP = Qrn NOTE: MDCR = Minirnm Deleclab e Count Rate RM-ILW.104 Grass HHSP = pm

[ ]Eb e RWDA-L Count Rate .s 51 141 net cpm (MDCR). THEN m e discnarge IS control ed by the m r m Selpo nts (ho funner ca.culabons reqirea)

I

[ ] E lne RWOA-L Count Rate IS >1,141 net cpm. THEN aete:mme I l e Acceptable Range of Readings lor c m t m 01 !ne discharge. e5 folious M a x m m = (RWDA-L Couit Rate I M,nimdm i (RWDA-L C o ~ nRale l cpm) x (21

~ (okga.

c p m ) l l l . (okgd cpml =

cpm =

cpm cpm 1 [ ] Unit 1 Laundry 8 Shower Drain Tank Discharge via [RM-1LW-1161: QMlLW.116Dkgo 9 3m RWDA-L Count Rate: Form In-ENV-0504 FOt (page 2 of 5) i I net c?m RM-1LW-llt Gross H S P 5 I 1

,11 NOTE. M@CR= Minimdm 3ele-b e Comt R a e RM-ILh.116 Gross HHSP= <m

[ 111(ne RWOA-L count ~ s t $5 e 52% net cpn (MDCR). me oemaxga 1s conno:!ed by me aiaim setpol~ts(NOlucher c a i c ~ a on0 t reqired).

[ ]Eme RWDA-L Count Rate 8s ,236 ne1 cpm. THEN aetennme :ne Acceptable Range of Readings for contra of Ine Oischarge, as foIIows' Maximum = (RWDA-L C o ~ nRate l cpm) x (21 * (brgd cml - c m Minunun = (RWDA.L Court Rale cpm)l (21' (brgd cpm) = cum

[ ]Unit 2 Liquid Waste Tank Discharge via [ZSGC-RQlOO]: ZSSC-ROlOO orgd = uC ml RWnA-L Cam1 Rale F3rm IR.ENV-05 M.FO1 (page Z 01 5) = net cpm 2SGC-RO100 Gross ASP = "C 111 NOTE: MDCR = M wmum Delectaooe C o m l Rate 25GC.RO100 Gross HSP = LC,.rnl

[ ]E the RWDA-L C o ~ lRate t 1s 5257 "el cpm (MDCR) THEN !ne 0 SCh3rge 5 Con1,O r d 09 me alarm selpo 71s (ho lumer calcuial~~ns i e q d rod)

[ ]E !he RWDA-L CO~TI Rate IE ,247 ne1 cpm. THEN oelerm.ne the Acceptable Range of Reaoingr lor conlrai of me aischarge. as l d m Max.rn.m = (RWDA-L Couil Rate cpm) x (5 6 t E - 9 uCiJmkpml x 12, * (Dkgd UCI ml) = uC;lml Minimum i(RWDA-L Court Pale cpm) x (5 6 1 i - 9 uCYmucpm) l ( 2 ) (okgo f "C Iml) = "Cilml

~ ~~~

Gross Effluent Radiation Monitor Readings:

Date I lime I -: Reading NQTE Recwd actual reaaing CR, Obtain AtttsaQ 2 Effluent HonltarReadings PPI Dlscharge.AND At Least 1 P o r n h r S h m Forti-e Apphcable Momtor

Is reading within range? Yes[ ] NO[1: RT Initial?-:

Do Not Round 00v.n)

SAP No.

1 Date Ilime 1-  : Reading  : Is reading withii range? Yesl] Nor]: RT Initials -  : SAP NO.

Date I Time -I  : Reading  : 1s reading within range? Yes[ ] No[ 1: RT Initials -: SAP NO.

Date ITime -1  : Reading  : Is reading within range? Yes[ ] No[ 1: RT Initials __ :SAP No.

Dala ITime I-: Reading  : Is reading within range? Yes[ ] No[ I: RT Initials -: SAP NO.

Date ITime I-: Reading  : Is reading wiltin range? Yes[ ] No[ 1: RT lnitiais -: SAP No.

[ ] EffluentMonitor Readings are not within the Acceptable Range of Readings. THEN contact Chemistw Supervision

[ ] Chernisby Supervision has determined that the discharge should be terminated, and Operations has been notified io terminate the discharge.

1 ] Chemistry Supervision has determined that the discharge may continue. Reasoninq: ~

Final Review of all Monitor Readmgs by Chemistry Supervision:

1

RTL#AS .640U 112-ADM-1301.FO Page 1 of Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

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

TRAINING MATERIAL NUMBER: 2AD-021 ~

PROGRAM TITLE: Licensed Operator Training ~

COMPUTER CODE: 2AD-021 REVISION NUMBER: 0 TECHNICAL

REFERENCES:

EPPiI-la, Recognition and Classification of Emergency Conditions, Rev. 10 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes PREPARED BY: R. J. Brooks PEER REVIEW BY: -

Date 4

APPROVED FOR USE:

Training Superviscj &<esignee Date

112-ADM-1301 .FO Page 2 of Revision TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2AD-02 1 Type of Change:

0Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision 0Yes 0No Changes Not The Change DoesNot Impact Learning Existing Rev. #

Requiring Revision .

Objectives or Material Quality.

1 New Change #

ListlDescription of Chang S) :

Reason for Change (s):

APPROVALS:

R. J. Brooks Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Training Superintendent/Superisor/Peer Date Qualification Matrix. See Incumbent Impact Review, (Changes Not Requiring Revision only)

NOBP-TR-1104.

112-ADM-1301.FO Page 3 of Revision JPM TPM REVISION: 0 2AD-021 I JPM TITLE: Classify an Emergency Event (Scenario Specific) 1 WA

REFERENCE:

2.4.41 (4.1) TASK ID: 1350-004-03-023 JPM APPLICATION: [XI REQUALIFICATION [XI INITIAL EXAM TRAINING 0 FAULTEDJPM ADMINISTRATIVE JPM EVALUATION -

~~~~ ~ ~~

METHOD: LOCATION: TYPE: ADMINISTERED BY:

Perform 0 Plant Site 0 AnnualRequalExam 0 BVT Simulate EyIator 0 Initial Exam 0 NRc assroom OJTiTPE Other:

Training 17 Other: -

I EVALUATION RESULTS -

Perfomier Name: Performer SSN:

Time 0 Yes Allotted 10 Minutes Actual minutes P . '

,ntical: No Time: Time: -

JPM RESULTS:

SAT mSAT (Comments required for UNSAT evaluation)

Comments: -

NameiSSN: NameISSN:

Name/SSN: NameiSSN:

1R-ADM-I 301.FO.

Page 4 of Revision EVALUATOR DIRECTION SHEET TASK STANDARD: The correct EPP classification is made for the associated scenario AND all critical steps of the initial notification form are correotly completed.

RECOMMENDED Simulator STARTING LOCATION:

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

INITIAL CONDITIONS: The simulator scenario just completed.(2LOT6 NRC Exam)

INITIATING CUE: As the Unit Supervisor, you are to classify the events in the scenario just completed in accordance with EPP/I-1 a, Recognition and Classification of Emergency Conditions AND complete the initial notification form.

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

The code word is TANGO Unit 1 is at 100% steady state power

. Wind direction at 150 is 65

. Wind speed at 35 is 7 mph

REFERENCES:

EPP/I-la, Recognition and Classification of Emergency Conditions, Rev. 10 TOOLS: None HANDOUT: EPPII-la, Recognition and Classification of Emergency Conditions, Rev. 10

1R-ADM-1301 .FO' Page 5 of 1 Revision CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • 0 Read:

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

INITIAL CONDITIONS: The simulator scenario just compIeted.(2LOT6 NRC Exam)

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

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

. The code word is "TANGO"

. Unit 1 is at 100% steady state power

. Wind direction at 150' is 65"

. Wind speed at 35' is 7 mph At this time, ask the evaluator any questions you have on this JPM.

0 When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

0 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" 0 Then hand this sheet to the evaluator.

1/2-EPP-IP-l.I.F01 Rev. 2 A SW ERK RTL# A5.715i)P 5 C f N A R 10 .l;t' I NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM

1. Call Status h( THIS IS A DRILL THIS IS A N ACTUAL E VENT
2. Thisis: At: Beaver Valley Power Station My Number is:

724-643-8000 The Code Word is: DM Go Notification Time is:

3. Emergency Classification:

'b' # Unusual Event 0 Site Area Emergency Alert General Emergency This event has been terminated Unit(s): 2 Declaration Time: 3me Date: brQrE-All Units Power Level at time of Notification ut\) iT I loa%. llA/;724%

.I

'&*H This represents &an: Initial Declaration Escalation 0 NoChange 1

J In Classification Status "c"4. The Emergency Action Level (EAL) number is:

4 ~q 4 .d k R e w #;;E.&

Brief non-technical description of the event below:

O M1 t A 0~ 4 The M b U*&I15.lr+c*l 1

-It-i~t p 8 p A flCS co*&ulN 2)hlb SAF&Y IU Icc+wN Hc4UR.h'66 .~

"c"5. There:% 0 No Radiological Release in Progress due 96 AnAirbome Radiological Release 0 A Liquid Radiological Release in Progress due tr the I

to the event in Progress due to the event event

'k" 6. Wind Direction is from:

50 degrees at 150' Wind Speed is: mph ;it 35'

7. Protective Action Recommendation (PAR): e, 8.

Conclusion:

Is A THIS IS AN ACTUAL EVENT APPROVED: DATE: b1)7e

1/2-EPP-IP-1.1 .F01 RTL# A5.715 )P NUCLEARPOWER PLANT INITIAL NOTIFICATION FORM I. Call Status p4 THIS IS A DRILL THIS IS ANACTUAL EVENT

2. Thisis:

At: Beaver Valley Power Station My Telephone Number is:

724-643-8000 The Code Word is: TANGO Notification Time is:

'3' 3. Emergency Classification:

0 Unusual Event $1 Site Area Emergency 0 Alert 0 General Emergency 0 This event has been terminated Unit(s): 2 Declaration Time: r/m@. Date: a All Units Power Level at time of Notification UhiT'I J de% eDv;?z 03

  • kofpd This represents dan: Initial Declaration 0 Escalation 0 NoChange 1

1 In Classification Status

  • a c 4. The Emergency Action Level (EAL) number is: B 7.3

'c*' 5. There is: 0 No Radiological Release in Progress due fl Anebome Radiological Release 0 A Liquid Radiological Release in Progress due 1'3 the to the event in Progress due to the event event

'b "6. Wind Direction is from: 45 e degrees at 150' Wind Speed is: 7 mph at 35'

7. Protective Action Recommendation (PAR):

APPROVED: h)fi mQ DATE: D&z

lI2-EPP-IP-1.1.FOl RTL# A5.715 DP NUCLEAR POWER PLANT INITIAL NOTIFICATION FOPM

1. Call Status $I THIS IS A DRILL THIS IS ANACTUAL EVEN7
2. This is:

At: Beaver Valley Power Station My Number is:

724-643-8000 The Code Word is: 7ArJGo Notification Time is:

3. Emergency Classification:

0 Unusual Event plf Site Area Emergency 0 Alert General Emergency 0 This event has been terminated Unit(s): 2 Declaration Time: Ti Me Date: b&Ez All Units Power Level at time of Notification 4

UNfT 1 ~ pa c

\\

This represents a/an: Initial Declaration 0 Escalation 0 NoChange 1

_I In Classification Status c 4. The Emergency Action Level (EAL) number is: B 2.2 Brief non-technical description of the event below:

Lsrs e$ 6Jdc+-8n needad Q :eve, rj :fiw4.-

ha+ Shu+dawt) .~

b 5. There is: 0 No Radiological Release in Progress due AnFbome RadloloDcal Release 0 A Liquid Radiological Release in Progress due t3the to the event in Progress due to the event event C

  • 6. Wind Direction is from: degrees at 150 Wind Speed is: 7 mphat35
7. Protective Action Recommendation (PAR): k.)dh)E .~

8.

Conclusion:

Is A THIS IS AN ACTUAL E VENT

Rev.2 scAIQwEK 1I2-EPP-IP-1.l .F01 ~

A \ 0 #4 RTL#A5.715L)P NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM I. Call Status pd THIS IS A DRILL a THIS IS AN ACTUAL EVENT

2. Thisis: - At: Beaver Valley Power Station My Number is:

724-643-8000 The Code Word is: r-lq60 Notification Time is:

  • L3. Emergency Classification:

0 Unusual Event (3 Site Area Emergency Alert 0 General Emergency This event has been terminated Unit(s): 2 Declaration Time: Lrr\eDate:

All Units Power Level at time of Notification w I T I I 60%: UKT-2 4k c pb This represents aian: Initial Declaration 0 Escalation 0 NoChange 1

J In Classification Status 2.3 OR. 1.

\t I@

4. The Emergency Action Level (EAL) number is:

e5. There is: 0 No Radiological Ant\irbome 0 A Liquid Radiological Release in Progress due Radiological Release Release in Progress due to the to the event in Progress due to the event event

>

  • 6 . Wind Direction is from: degrees at 150 Wind Speed is:
7. Protective Action Recommendation (PAR): UonC 8.

Conclusion:

@ Is Is A THIS IS AN A CTUAL E VEN:f APPROVED: _b,#J WpA DATE: DME

RTL#A5.64OU 112-ADM-1301.F04 Page 6 of 8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE

, IPM NUMBER: 2AD-021 JPM REVISION: 0 1 JPM TITLE: Classify an Emergency Event (Scenario Specific) 1 lTEP STANDARD "C" Denotes CNTICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=

EVALUATOR NOTE: The Candidate is being evaluated on classifying the events in the scenario just completed. (2LOT6 NRC Exam) It may be necessary to review the events before beginning the JPM.

.C Classify the event in accordance 1.1C Candidate correctly classifies the event with the Emergency Plan.

Scenario #1: Unusual Event, Tab 2.10 S t e a d e e d Lint Break Scenario #2: Site Area Emergency, Tab 2.3, Failure of Reactor Protection Scenario #3: Site Area Emergency, Tab 2.2, CSF Red Path on Heat Sink Scenario #4: Alert, Tab 2.3, Failure of Reactor Protection OR Alert, Tab 1.2.4Loss of RCS Barrier COMMENTS:

112-ADM-1301.F04 Page 7 of 8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE

,jPM

'PM NUMBER: 2AD-021 REVISION: 0 1 JPM TITLE: Classlfy an Emergency Event (Scenario Specific) 1 STEP STANDAH)

( "C" Denotes CRITICAL STEP )

2.C Completes the initial 2.1 Places the following information on the space provided on the notification form. initial notification fonn.

. Item 1 places a checkmark in the this is a drill box

. Item 2 leaves name and notification time blank (this is for the communicator) places the word TANGO in the code space.

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

. Item 3 places a 2 in the Unit space, places current time in the declaration time space, places the date in the date space, places Unit 1 at 1005 and Unit 2 at 0% in the all units power level space.

. C Item 4 places the appropriate EAL tab number in the EAI~.number space (as identified in step 1 of the JPM above).

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

. C Item 5 places a checkmark in the an airborne radiological release in progress due to this event box.

. C Item 6 places 65' direction spaces and mph in the wind speed and 7

Item 7 is left blank or NONE

. Item 8 places a checkmark in the this is a drill box

RTL#A5.640U 1R-ADM- 1301.F04 Page 8 of 8 Revision I OPERATIONS JOB PERFORMANCE MEASURE

, rpM NUMBER: 2AL-021 JPM REVISION: 0 I JPM TITLE: Classify an Emergency Event (Scenario Specific) 1 jTEP ;TANDARD "C" Denotes CRITICAL STEP )

!.2 Places candidate name and current date in the approved space and date.

EVALUATOR NOTE:

Refer to Answer Key for initial notification form critical steps.

TERMINATING CUE:

That completes this JPM 30MMENTS:

STOP TIME:

112-ADM-1301.FO :

Page 1 of 1 Revis~on OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Perfom Partial Movement Test (CB-D)

TRAINING MATERIAL NUMBER: 2CR-647 -_

PROGRAM TITLE: Licensed Operator Training (Retraining)

COMPUTER CODE: 2CR-647 -~

REVISION NUMBER: 0 TECHNICAL

REFERENCES:

20ST-1.1, Control Rod Assembly Partial Movement Test Rev 10 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 10 Minutes PREPARED BY: R. J. Brooks PEER REVIEW BY:

APPROVED FOR USE: -- -

Training Supervisor jr'dsignee Date

I/Z-ADM-1301 .FO Page 2 of ~

Revision TRAINING MATERIAL CHANGE FORM iffected Training Materials: 2CR-647 rype of Change:

a Changes Requiring Revision 1 Learning Object& Related Change? I New Rev. # 0 1 New Change #

,ist/Description of Cbange(s):

Iriginal issue ieason for Change (s):

UPROVALS:

R. J. Brooks NOTE: Additions, deletions or '

Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See rraining Superintendent/Superisor/Peer Date Incumbent Impact Review,

'"Changes Not Requiring Revision" only) NOBP-TR-I 104.

112-ADM-1301.FO !

Page 3 of 1 Revision

' JPM NUMBER: 2CR-647 JPM REVISION: 0

~ JPM TITLE: Perform Partial Movement Test (CB-D) 1 WA

REFERENCE:

001 A3.05 3.5/3.5 TASK ID: 0010010201 001 1-002-06-013 JPM APPLICATION: REQUALIFICATION INITIAL EXAM 0 TRAINING FAULTEDJPM 0 ADMTNISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE:

0 Perform 0 Plant Site 0 AnnnalRequalExam BVT Simulate 0 Simulator 0 Initial Exam 0 Classroom 0 OJTiTPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS -

I Performer Name: I Performer SSN:

'Time Critical:

0 Yes No 1 Allotted Time:

10 minutes Actual Time:

minutes JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

Name/SSN. KameiSSN:

Name/SSN: Name/SSN:

Evaluator (Print): Date:

I Evaluator Signature:

RTL#AS .640U 112-ADM-1301.FOP Page 4 of 5 Revision EVALUATOR DIRECTION SHEET TASK STANDARD: Control Bank D is verified operable (moved 10 steps) AND Rod H:

is identified as NOT aligned by 2 12 steps.

RECOMMENDED CONTROL ROOM STARTING LOCATION:

DIRECTIONS: You are to perfom the task of Control Rod Assembly Partial Movement Test.

INITIAL CONDITIONS: The reactor is in Mode 1, 100% power. All procedural Initial Conditions are satisfied.

INITIATING CUE: Your supervisor directs you to verify Control Bank D is operable hy performing Section V1I.B of 20ST-1.1, Control Rod Assembly Part a1 Movement Test, and report your results to your supervisor.

REFERENCES:

20ST-1 . I , Control Rod Assembly Partial Movement Test Rev. 10 TOOLS: NONE HANDOUT: 20ST-1 .I filled out up to step V1I.B

RTL#AS .640U IR-ADM-I 301.FOf.

Page 5 of!

Revision CANDIDATE DIRECTION SHEET

  • THIS SHEET T O BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task of Control Rod Assembly Partial Movement Test.

MITIAL CONDITIONS: The reactor is in Mode 1, 100% power. All procedural Initial Conditions are satisfied.

INITIATING CUE: Your supervisor directs you to verify Control Bank 'D' is operable by performing Section VI1.B of 20ST-1.1, Control Rod Assembly Partial Movement Test, and report your results to your supervisor.

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

0 When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

2LOIT-OS-NRC-JPMs SI & S2 Iage 1 of 1 2LOIT-08-NRC JPMs S I & S2 I

s/simulator setup Initialize Run LRTIC file commands Horns, Printers, Sounds ready Trg 1 to actuate dropped rod Dropped rod Trg 2 to clear dropped rod Dropped rod cleared file:/lE:\U2%20LOIT%2020OS%2ONRC\LOIT%2OO8%2ONRC%~OJPMs%2OS 1%20&%20S2 htm ioiwmn~

RTL#AS 640U 112-ADM-1301 FO' Page 6 of Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2CR-647 JPM REVISION: 0 1 JPM TITLE: Perform Partial Movement Test (CB-D) 1

TEP STANDARD "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR U N S A E START TIME

SIMULATOR SET-UP: Initialize IC-10 Turn on all PRZR hcaters Stick rod El2 such that it ratchets down when outward rod niotion is attempted Rods in Auto Record the Rod Step Counter Control I.1 Logs Control Bank 'D' Group 1 and 2 Readings Bank 'D' Group 1 and 2 readings.

JOMMENTS :

Using the DRPI, Record the rod 2.1 Records the rod height ofthe Control Bank D rods height of the Control Bank D rods listed below:

Rod H2- Rod F6- EVALUATOR NOTE:

Although the Rods are at 229 steps, DRPI will only Rod B8- Rod F 10- indicate 228 steps Rod HI4- Rod K 10-COMMENTS:

Rod P8- Rod K6-l.C Place the Control Rod Bank Sel SW 3.1C Places thc Control Rod Bank Sel SW to MAN position to MAN position.

COMMENTS:

RTL#A5.640U II2-ADM-1301 .FO Page 7 of J Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2CR-647 JPM REVISION: 0 1 JPM TITLE: Perform Partial Movement Test (CB-D)

.I STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)= 17SW 1.C Using the IN-HOLD-OUT lever, 4.1C Places the IN-HOLD-OUT lever to IN and Inserts rods 10 steps drive CB 'D' 10 steps into the core in 5 step increments as indicated by the Group Step Demand until verification of individual rod counters, and verifies individual rod motion on DRPI.

movement is obtained by observation of the DRPls. EVALUATOR NOTE:

Annuciator A4-9G, Computer Monitored Alarm is expected each time rod motion is demanded.

COMMENTS:

j. Record the Control Bank 'D' step 5.1 Records the Control Bank 'D' step counter position for Group 1 counter position. and 2.

COMMEKTS:

5. Record the Control Bank 'D' rod 6.1 Candidate locates each individual rod DRPI indication and records position as indicated by DRPI. the rod height.

COMMEKTS:

7. Compare the step counter indication 7.1 Candidate compares the Group Step Demand counters against the for each rod group (from Step DRI'Is for Control Bank 'D'. Determines all rods are within f 12 VlI.B.5) with the DRPI indication for steps.

each RCCA (from Step VII.B.6).

Verify the step counter and DRPI indications are within f 12 steps as COMMENTS:

stated in T.S. 3.1.4.

I

RTL#AS 640U 1/2-ADM-1301.F0*

Page E of Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM JPM REVISION: 0 2CR-647 I JPM TITLE: Perform Partial Movement Test (CB-D)

STANDARD CRITICAL STEP ) (Indicate S FOR SAT or UFOR FAULT STATEMENT:

The next step of the JPM is Faulted. When the candidate begins to withdraw the control rods, Rod H2 I

will ratchet inward such that it will be misaligned by more than 12 steps from the rest of the bank.

EVALUATOR NOTE:

Candidate may immediately STOP rod motion before achieving 229 steps.

8.C Return Control Bank D rods (in 5 3.1 Candidate locates the IN-HOLD-OUT lever.

step increments) to the group positions recorded in Step VII.B.1 3.2C Candidate places it to the OUT direction AND attempts to withdraw thc Group Step Demand counters to 229 steps.

3.3C Candidate recognizes Rod H2 is ratcheting inward and stops rod motion EVALUATOR NOTE:

Candidate may refer to Annuciator A4-8G, Rod Position Deviation COMMENTS:

EVALUA rOR CUE:

If necessary Role-play the Unit Supervisor and inshuct the candidate to STOP rod withdrawal AND remain here until further instmctions It may alsri be necessary to ask the candidate to re-perform step 7 of the JPM to verify rod alignment

112-ADM-I 301.FO Page 9 of '

Revision O P E M I ' I O N S JOB PERFORMANCE MEASURE IJPM REVISION: 0 JPM NUMBER: 2CR-647 I JPM TITLE: Perform Partial Movement Test (CB-D) 1 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)a 9.C Compare the step counter indication 9.1C Candidate compares the Group Step Demand counters against the for each rod group (from Step DRPIs for Control Bank 'D'. Determines rod H2 is NOT within i VII.B.5) with the DRPI indication for 12 steps of the other rods in the bank.

each RCCA (from Step VII.B.6).

Verify the step counter and DRPI indications are within -t 12 steps as COMMENTS:

statedinTS. 3.1.4.

I E\'ALUATOR CUE: Termnate JPM at this point.

STOP TIME: -

. ~ _ _

1/2-ADM-l301 .F04 Page 1 of 8 Revision 1 OPERATINS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Perform a Hot Bus Transfer -

TRAINING MATERIAL NUMBER: 2CR-023 - -

PROGRAM TITLE: Licensed Operator Retraining -

COMPUTER CODE: 2CR-023 -

REVISION NUMBER: 9 -

TECHNICAL

REFERENCES:

~M-36.4.C,Transferring 4KV System from US SERV TFMR to SS SERV TFMR, Rev 9 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes

112-ADM-I301.F04 Page 2 of 8 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-023 Changes Requiring Learning Objective Related Change? New Rev. #9 Revision 0Y e s ?J No 0Changes Not The Change Does Not Impact Learning Existing Rev. # 8 Requiring Revision Objectives or Material Quality.

I New Change #

List/Description of Change(s):

1. Updated to reflect actual control room mark numbers and nomenclature
2. Update to current procedure revision, Rev 9 Reason for Change (s):
1. Improve JPM accuracy.

APPROVALS:

I NOTE: Additions, deletions or I R. J. Brooks changes to training materials must be reviewed for their Prepared by Date possible impact to the Training Qualification Matrix. See Incumbent Impact Review, Training Superintendent/Superisor/Peer Date NOBP-TR-I 104.

("Changes Not Requiring Revision" only)

112-ADM-1301 FOd.

Page 3 off Rev is1on OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2CR-023 JPM REVISION: 9

~ JPM TITLE: Perform a Hot Bus Transfer WA

REFERENCE:

062K1.04 3.714.2 TASK ID: 0361-013-01-013 062A4.01 3.313.1 JPM APPLICATION: [XI REQUALIFICAT[ON [XI INITIAL EXAM 0 TRAINING FAULTEDJPM 0 ADMINISTRATIVE JPM

~ ~~~~

EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED B>':

Perform 0 Plant Site 0 AnnualRequalExam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 Classroom 0 OJT1TPE 0 Other:

0 Training 0 Other:

Performer Name: Performer SSN:

Time 0 Yes Allotted 15 minutes Actual minutes Critical: [XI NO Time: Time: -

0 SAT JPM RESULTS:

mSAT (Comments required for UNSAT evaluation)

Comments:

NameiSSN: NameiSSN:

~~

NameiSSN: NameiSSN:

Evaluator Signature:

I -

112-ADM-1301.FOf; Page 4 of :,

Revision I OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The 4kv Bus 2B is being supplied by the System Station Service Transformer.

RECOMMENDED Control Room STARTING LOCATION:

DIRECTIONS: You are to perform the task Perform a Hot Bus Transfer INITIAL. CONDITIONS: The plant is at 100% power with all systems in NSA. It is desired to place the 2B 4KV bus on offsite power to allow for a relay check on ACB- 142C.

INITIATING CUE: Your supervisor directs you to transfer the 2B 4KV bus to the 2A SSST, but do not set it up for auto transfer back to the 2C USST.

REFERENCES:

20M-36.4.C, Transferring 4KV system from USST to SSST, Rev 9 TOOLS: None HANDOUT: 20M-36.4.C

112-ADM-1301.FOl Page 5 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GWEN TO CANDIDATE
  • 0 Read:

TASK: Perform a Hot Bus Transfer INITIAL. CONDITIONS: The plant is at 100% power with all systems in NSA. It is desired to place the 2 8 4KV bus on offsite power to allow for a relay check on ACB-142C.

INITIATING CUE: Your supervisor directs you to transfer the 2B 4KV bus to the 2A SSST, but do not set it up for auto transfer back to the 2C USST.

0 At this time, ask the evaluator any questions you have on this JPM When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

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

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

Then hand this sheet to the evaluator.

2LOIT-08-NRC-JPMs S1 & S2 >age 1 of 1 2LOIT-08-NRC JPMs S I & S2 Indsimulator setup Initialize I

Run LRTIC file commands Horns, Printers, Sounds ready Trg 1 to actuate dropped rod Dropped rod Trg 2 to clear dropped rod Dropped rod cleared file://E:\U2%20LOITO2OO8%2O~C~OIT%2OO8%2O~C%2O~Ms%2OS 1 %20&%20S2.htm 10/3/2008

RTL#A5.640U 112-ADM-1301.FO Page 6 of I Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2CR-023 JPM REVISION: 9 I JPM TITLE: Perform a Hot Bus Transfer 1

STEP STANDARD

( C Denotes CRITICAL STEP ) (Indicate S FOR SAT or U FOR UNSAT)a START TIME:

SIMULATOR SETUP:

h i t in LRT 100% power IC set.

1. Obtain procedure 20M-36.4.C, 1.1 Candidate locates procedure, Transfemng 4kv system from USST to SSST.

COMMENTS:

2. Verify voltages on the 2B 4kv 2.1 Candidate locates the 4KV Common volts meter, 4:

bus are approximately tbe same Bus 2B Volts meter, and 2A SS Serv Tmr Voltmete on all phases as on SSST 2A. Phase selector switch.

2.2 Checks all phases and verifies 2B bus and 2A SSSl within 2.0 volts.

COMMENTS:

3.C Place Live Bus Transfer Switck 3.1 Candidate locates Live bus Transfer Switch to ON.

3.2C Turns switch to the ON position.

COMMENTS:

RTLifA5.640U 112-ADM-1301.FOi Page 7 of ;

Revision OPERATIONS JOB PERFORMANCE MEASURE JPM NUh4BER: 2CR-023 JPM REVISION: 9 1 JPM TITLE: Perfom a Hot Bus Transfer 1

SIW STANDARD

( "C" Denotes CRITICAL STEP ) .. - >?icaJc "S" FOK ..S .A T or . "C" FOK I 4.C Close ACB-142A. 4.1 Candidate locates control switch for 2A SS SE TFMR TO 4KV BUS 2B ACB-142A.

4.2C Turns switch to the CLOSE position 4.3 Verifies BOTH Red lights are LIT and the w

~

is S NOT LIT COMMENTS :

! 5. Verify that amps increase on Bus 2B Tfmr 2A ammeter.

5.1 Candidate locates 4KV BUS 2B TFMR 2A an 5.2 Verifies it indicates greater than ZERO amps.

COMMENTS:

6.1 Candidate locates control switch for 2C US SI TFMR TO 4KV BUS 2B ACB-142C.

6.2C Places it in the OPENKRIP position 6.3 Verities BOTH Red lights are -NOT LIT and light is - LIT COMMENTS:

112-ADM-130 I .F04 Page 8 of E Revision 1 OPERATIONS JOB PERFORMANCE MEASURE I NUMBER: 2CR-023 JPM REVISION: 9 I JPM TITLE: Perform a Hot Bus Transfer 1

STEP STANDARD

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

7. Place the Live Bus Transfer 1.1 Candidate locates Live Bus Transfer Switch.

Switch to OFF.

1.2 Places it in the OFF position.

OMMENTS:

3, Place Load Tap Changer in 1.1 NIA AUTO (only necessary if voltage adjusted earlier). 1.2 Places it in the AUTO position.

70MMENTS:

EVALUATOR CUE:

That completes this JPM STOP TIME:

1/2-ADM-l301.F@

Page 1 of',

Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Transfer to Cold Leg Recirculation (ES-1.3)

TRAINING MATERIAL NUMBER: 2CR-529 ~-

PROGRAM TITLE: Licensed Operator Retraining COMPUTER CODE: 2CR-529 REVISION NUMBER:

TECHNICAL

REFERENCES:

20M-53A.l.ES-1.3 (Issue lC), Revision 5 INSTRUCTIONAL SETTING: Control Room APPROXIMATE DURATION: 10 Minutes 0

' i

/

. 4 4

/ e PREPARED BY: R. J. Brooks - .-/*

Date PEER REVIEW BY: .-

\ -

&* Date

',. J

/

APPROVED FOR USE: c 8 r '

1- ~-

Training Supervisor -? &&nee Date

112-ADM-1301.FO:

Page 2 of 1 Revision TRAINING MATERIAL CHANGE FORM 4ffected Training Materials: 2CR-529 rype of Change:

Changes Requiring Learning Objective Related Change? 1 New Rev. # 3 Revision Yes E3 No Existing Rev. # 2 Changes Not The Change- Does Not Impact Learning Requiring Revision Objectives or Material Quality.

New Change #

List/Description of Chang S):

Updated procedure to current revision.

Updated JPM to reflect actual control room mark numbers and nomenclature.

4dded Evaluator Cue to step 5 of JPM (2LOT6 NRC exam validation comment)

Modified setup force a different procedural flowpath Reason for Change (s):

Improve JPM clarity and to reflect current procedure revision APPROVALS:

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

("Changes Not Requiring Revision" only) ~ NOBP-TR-I 104.

112-ADM-1301.FO I Page 3 of 1 Revision JPM NUMBER: 2CR-529 I JPM REVISION: 3 1 JPM TITLE: Transfer to Cold Leg Recirculation (ES-1.3) 1 WA

REFERENCE:

006K4.08 3.4/3.6 TASK ID: 01 11-019-01-013 006A4.02 4.0/3.8 006 A4.05 3.913.8 JPM APPLICATION:

EVALUATION METHOD:

0 0

Perform Simulate REQUALIFICATION FAULTEDJPM 0

0 0

LOCATION:

Plant Site Simulator Classroom 0

u 0

0 INITIAL EXAM ADMINISTRATIVE JPM TYPE:

AnnualRequalExam Initial Exam OJT/TPE 0

0 BVT TRAINING

~;TEREDB Other

7 fl Training Performer Name: Performer SSN:

Time 0 Yes Allotted 10 minutes Actual minutes Critical: No Time: Time: -

JPM RESULTS:

0 SAT mSAT (Comments required for UNSAT evaluation)

Comments: -

Name/SSN: Name/SSN:

I NameiSSN: I NameiSSN:

EVALUATOR -

Evaluator (Print): Date: .-

Evaluator Signature:

II2-ADM-I 301.FO' Page 4 o f '

Revision EVALUATOR DIRECTION SHEET TASK STANDARD: Parallel redundant Cold Leg Recirculation flowpaths are established according to Step 5 of 20M-53A, Procedure ES-1.3.

RECOMMENDED CONTROL ROOM STARTING LOCATION:

DIRECTIONS: You are to simulate (perform) the task Transfer to Cold Leg Recirculation (ES-1.3).

INITIAL CONDITIONS: The plant is recovering from a Loss of Coolant Accident. The Contr 11 Room Operators are now at step 5 of ES-1.3, Transfer to Cold Leg Recirc.

INITIATING CUE: Your supervisor directs you to perform Step 5 of ES-1.3 'Transfer t')

Cold Leg Recirc'.

REFERENCES:

20M-53A.l.ES-1.3 (Issue IC), Revision 5 TOOLS: 4 Shorting Bars HANDOUT: 20M-53A.1 .ES-I . 3

112-ADM-1301 .F04 Page 5 off Revision 1 CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: Transfer to Cold Leg Recirculation (ES-1.3)

NITIAL CONDITIONS: The plant is recovering from a Loss of Coolant Accident. The Control Room Operators are now at step 5 of ES-1.3, Transfer to Cold Leg Recirc.

INITIATING CUE: Your supervisor directs you to perform Step 5 of ES-1.3 'Transfer to Cold Leg Recirc'.

0 At this time, ask the evaluator any questions you have on this JPM When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

2LOIT-08-NRC-JPM S 3 lage 1 of 1 2LOIT-08-NRC JPM S3 LRTIC file commands Horns, Printers, Sounds ready 10/3/2008

RTL#A5.640U 112-ADM-1301.FO I Page6of J Revision OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2CR-529 JPM REVISION: 3 I JPM TITLE: Transfer to Cold Leg Recirculation (ES-1.3) 1 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR U N S A T p START TIME:

~ ~ _ _ _

SIMULATOR SETUP:

Malf RCS03C, Open 2CCS*AOVI 18 Start an Air compressor.

Reset SI both trains. Stop both EDG's.

Wait until RWST level <400 inches.

Reset CIA & CIB.

Ensure 2CHS*P21A/C running.

Place both LHSI pumps in PTL. Energize cbarging pump suction and discharge valves via LOA-LOV093 t h 096, and LOV102 t h 105, Insert following to trip [2RSS*P21D]

PMP-CSSO10 EVALUArOR NOTE: Have 4 shorting bars available for candidate to perform this JPM

1. Obtaina copyofprocedure ES-1.3 of 1.1 Candidate locates ES-1.3 of 20M-53A 20M-53A.

EVALUATOR NOTE: Procedure can be provided to Candidate. if provided, NIA this JPM step.

COMMENTS:

RTL#A5.640U 1/2-ADM-l301.FO, Page I o f '

Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2CR-529 JPM REVISION: 3 JPM TITLE: Transfer to Cold Leg Recirculation (ES-1.3) 1 STEP STANDARD I 1

( "C" Denotes CRITICAL STEP ) .-

(Indicate "S" FOR SAT or "U" FOR U N S A T ) a 1S

2. Verify TWO chargingiHHS1 pumps 2 1 Verifies Charging Pump High Head Safety InJ 2CHS*P21A and C NMing. Red lights are - LIT and the white lights are - NOT LIT COMMENTS

-~

3.C Insert shorting bar into 3.1C Candidate locates jack for High Head SI Cold Leg Is01 Vlv (2SIS*MOV836) High Head SI Cold 2SIS*MOV836 and inserts shorting bar.

Leg Isol. Valve Jack.

COMMENTS:

4.C Open 2SlS*MOV836 HHSI Cold Leg 4.1 Candidate locates control switch for High Head SI Cold Leg lsol lsol. Valve. Vlv ?SlS*MOV836.

4.2C Candidate places CS to OPEN 4.3 Candidate verifies Red light is - LIT and green light is - NOT LIT COMMENTS.

RTL#A5 640U 1/2-ADM-1301 FO, Page 8 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM REVISION:2CR-529 I JPM STEP 3

JPM TITLE: Transfer to Cold Leg Recirculation (ES-1.3)

STANDARD 1

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

5.1 Candidate verifies Recirc Spray Pump 2RSS*P21C red light i s -

LIT and white light is -NOT LIT 5.2. Candidate verifies Recirc Spray Pump 2RSS*P21D red light is NOT LIT and white light is - LIT EVALUArOR CUE:

If necessary inform the candidate that Recirc Spray Pump ZRSS'P2ID will NOT START.

5.3 Candidate verifies HHSI pumps 2CHS*P21 A and C red lights are LIT and white lights are NOT LIT

~

COMMENTS.

6.C Insert shorting bar into appropriate 6.1C Candidate locates jacks for Charging Pump Disch Is01 Vlv jacks and then close appropriate HHSI 2CHS*MOV8132A & B and inserts shorting bars.

pump discharge isolation valves 2CHS*MOV8132A & B. 6.2 Candidate locates control switches for Charging Pump Disch Is01 Vlv 2CHSXMOV8132A& B.

6.3C Candidate places Control switches to CLOSE 6.4 Candidate verifies green lights are ~ LIT and red lights are .- NOT Lrr COMMENTS:

112-ADM-1301.FO~

Page 9 of 1 Revision STEP STANDARD

( "C" Denotes CRITICAL STEP ) ~- (Indicate "S" FOR SAT or "U" FOR U N S A T p I. Verify 2SIS*F1945, (946) LHSI Train 7.1 Verifies 21A LHSI Pump Disch Flow 2SIS-F945 indicates greate A & B flow is indicated. than ZERO flow COMMENTS:

%.Verify [2SIS*F1940, 9431 Train A, B 8.1 Candidate locates HHSI TRN A 2SIS*FI940 indicates greater flow - indicated. than ZERO flow COMMENTS:

STOP TIME: -

1/2-ADM-l301 .FO, Page 1 of 11 Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Establish RCS Bleed and Feed per FR-H. 1 TRAINING MATERIAL NUMBER: 2CR-624 PROGRAM TITLE: Licensed Operator Training (Retraining)

COMPUTER CODE: 2CR-624 REVISION NUMBER: 5 TECHNICAL

REFERENCES:

?OM-53A.l.FR-H.I, Issue lC, Response To Loss Of Secondary Heat Sink, Rev. 7 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 10 minutes PREPARED BY: R. J. Brooks

\

PEER REVIEW BY:

Date APPROVED FOR USE: .-

Training Date

RTLffA5.640U 112-ADM-1301.FO.

Page 2 of 11 Revision TRAINING MATERIAL CHANGE FORM Affected Training Materials: JPM 2CR-624 Type of Change:

Changes Requiring Learning Objective Related Change? New Rev. # 5 Revision 0 Yes No Changes Not The Change Does Not Impact Learning Existing Rev. # 4 Requiring Revision Objectives or Material Quality.

New Change #

ListiDescription of Chang S):

Updated JPM to current JPM format.

Modified failure. (PCV455C and D will not open)

Reason for Change (s):

3PM Enhancement APPROVALS:

R. J. Brooks NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Training SuperintendentiSuperisoriPeer Date Incumbent Impact Review, (Changes Not Requiring Revision onlyl NOBP-TR-1104.

1/2-ADM-l301 .FOZa Page 3 of I (

Revision NUMBER: 2CR-624 I JPM REVISION:

IPM 5

1 JPM TITLE: Establish RCS Bleed and Feed per FR-H.1 1

WA

REFERENCE:

E05 EA1.l 4.114.0 TASK ID: 0533-006-05-013 JPM APPLICATION: [XI REQUALIFICATION INITIAL EXAM 0 TRAINING FAULTEDJPM ADMINISTRATIVE JPM fl Initial Exam I-n Simulate II -n Simulator Classroom 0 OJTiTPE

- Training 0

NRC Other:

1 Performer Name:

EVALUATION RESULTS I

Performer SSN:

I Time Yes Allotted Actual Critical: [XI NO Time:

10 minutes Time:

minutes I - I NameiSSN: Name1SSN:

Name/SSN: NameiSSN:

Evaluator (Print): Date:

-- I Evaluator Signature:

i

112-ADM-1301.FO, Page 4 of 1' Revision EVALUATOR DIRECTION SHEET TASK STANDARD: RCS Bleed and Feed are initiated (SI flow, one P U R PORV open, all RX vessel head vents open). At least one SG isolated and depressurizing for low pressure water injection.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform the task of Establishing RCS Bleed and Feed per FR-H.l, Response To Loss of Secondary Heat Sink.

INITIAL CONDITIONS: The plant has tripped from 100% power. FR-H.1, Response To Loss of Secondary Heat Sink has been entered. Steps 1 through 5 are complete. While performing step 6, the RCS bleed and feed criteria #tf continuous action Step 2 are met due to S/G WR levels dropping to less than 14%.

,NITIATING CUE: Your supervisor directs you to establish RCS bleed and feed by performing steps 13 through 16 of FR-H.1, Response To Loss of Secondary Heat Sink.

REFERENCES:

20M-53A.l.FR-H.1, Issue lC, Response To Loss of Secondary Hea?

Sink. Rev. 7 TOOLS: None HANDOUT: 20M-53A. 1.FR-H. 1, Issue 1C, Response To Loss of Secondary Heat Sink, Rev. 7

112-ADM-1301 .FO Page 5 of 1 Revision CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

TASK:

You are to perform the task of Establishing RCS Bleed and Feed per FR-H.1, Response To Loss of Secondary Heat Sink.

INITIAL CONDITIONS:

The plant has tripped from 100% power. FR-H.l, Response To Loss of Secondary Heat Sink has been entered. Steps 1 through 5 are complete. While performing step 6, the RCS bleed and feed criteria of continuous action Step 2 are met due to SIG WR levels dropping to less than 14%

INITIATING CUE:

Your supervisor directs you to establish RCS bleed and feed by performing steps 13 through 16 of FR-H.l, Response To Loss of Secondary Heat Sink.

0 At this time, ask the evaluator any questions you have on this JPM 0 When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

0 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".

cl Then hand this sheet to the evaluator.

2LOIT-08-NRC-JPM S4 l'age 1 of 1 2LOIT-08-NRC JPM S4 Initialize LRTIC file commands Horns, Printers, Sounds ready

[2FWS-P21B Trip]

[2FWS-P21A Trip]

[2FWE*P23A Trip]

[2FWE*P23A Trip]

Failure of AUTO reactor trip train A, manual successful Failure of AUTO reactor trip train B, manual successful

[2RCS*PCV455C] failed shut

[2RCStPCV455D] failed shut

[2FWE*P22] Trip t 0/3/2008

RTL#A5.640U 112-ADM-1301.FO Page 6 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE JPM IJPM REVISION:2CR-624 4 1 JPM TITLE: Establish RCS Bleed and Feed per FR-H. 1 1

I ~d C Denotes CNTICAL STEP

TANDARD I 1 START TIME

SIMULATOR SETUP:

Init IC-237 for 2LOT6 NRC Exam Defeat 2FWE-P22,23A, & 23B. Fail 2FWS-HW157A.

B, & C closed.

To establish conditions for JPM, trip 2FWS-P21A & B, place steam dumps in STM PRESS Mode at -1005 psig.

Stop 2RCS-P21A, B, & C. Allow SG levels to drop to <

13% and SNAP IC.

Fail P E R PORVs PCV455C and D from opening.

1. Obtain procedure. 1.1 Candidate locates procedure FR-H. 1 COMMENTS:

2.1C Candidate locates and actuates control switches for Train A and Train B Safety Injection.

2.2 Verifies alarm A12-1D Safety Injection Signal is -LIT COMMENTS:

112-ADM-1301 .FO Page 7 of 1 ,

Revision OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2CR-624 JPM REVISION: 4 1 JPM TITLE: Establish RCS Bleed and Feed per FR-H.1 1

TEP "C" Denotes CRITICAL SI'EP )

-~

TANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)a S W 11

!. Verify RCS Feed Path .I Candidate locates HHSI Train " B flow indicator ~

HHSI Flow Indicated, [2SIS-F1943] and verifies HHSI flow is greater than ZERO.

10MMENTS:

I FAULT STATEMENT:

The next steD begins the alternate uath for this P M .

There will only be ONE P E R PORV available as a I

bleed path. The candidate will be required to OPEN all RX Vessel head vents to obtain adequate bleed flow.

1. Establish RCS Bleed Path .I Candidate verifies the following indicating lights:

Power to P E R PORV 2KCS-MOV535,536 and 537 red lights - LIT block valves AVAILABL green lights - NOT LIT ZOMMENTS:

5. Establish RCS Bleed Path i.l NIA Previously verified Verify block valves - ALI OPEN.

ZOMMENTS:

RTL#A5.@0U 112-ADV-1301.FO<.

Page 8 of I (

Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM JPM NUMBER: 2CR-624 REVISION: 4 1 JPM TITLE: Establish RCS Bleed and Feed per FR-H.1 1

STEP STANDARD I1

( "C" Denotes CRITICAL STEP )

5.C Establish RCS Bleed Path Open all PORVs.

6. I i FAULT STATEMENT:

ONLY PRZR PORV, 2RCS-PCV456 will open in the next step. This will require the candidate to Open RCS vent paths.

Candidate locates PRZR PORV Control Switches, 6.2C Places CS for PRZR PORV, 2RCS-PCV455C, 455D and 456 to OPEN.

6.3 Verifies PRZR PORV, 2RCS-PCV456 red light - LIT green light -NOT LIT 6.4 Recognizesiverifies PRZR PORV, 2RCS-PCV455C and 4550 red lights -NOT LIT green lights - LIT COMMENTS :

7.C Verify Adequate RCS Bleed 7.1C Determines that ONLY ONE PRZR PORV and Path. associated block valve is open and Places all reactor

, PRZR PORV's and associated vessel head vent control switches to OPEN.

block valves -AT LEAST [2RCS-SOV200A, B]

TWO OPEN [2RCS-SOVZOlA, B]

7.2 Verifies red lights LIT green lights NOT LIT

~ ~

7.3C Depresses A PB for 2RCS-HCVC250A and B 7.4 Verifies 2RCS-HCVC250A and B at 100% demand.

COMMENTS:

STEP STANDARD

( "C" Denotes CRITICAL STEP )

8. Align any available low pressure 8.1 Attempts to align a low press. water source to an intact water source. SG.

No action needed.

EVALGATOR CUE: Another operator will work on a low pressure water source using Attachment A-1.10.

COMMENTS:

EVALUATOR CUE:

In the next step, Role-play the Unit Supervisor and direct the candidate to use SG 21A for depressurization.

9.C Isolate steam supply to Turbine 9.1C Places CS for 2MSS*SOVlOSA and D to CLOSE.

driven Aux feed pump from S/G selected for 9.2 Verifies red lights - NOT LIT green lights - LIT.

depressurization.

COMMENTS:

10.C Close MSIV on selected S/G. 10.1C Places CS for21A SG MSIV 2MSS-AOVlOIA to CLOSE.

10.2 Verifies red lights -NOT LIT green lights - LIT.

COMMENTS:

RTL#AS. 640U 1I2-ADM- 1301.FO.

Page 10 of 11 Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2CR-624 JPM REVISION: 4 1 JPM TITLE: Establish RCS Bleed and Feed per FR-H. 1 1

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U"FOR UNSAT)S 11.c Open Atm Steam dump valve 11.1C Places 21.4 SiG Atm Stm Dump Control on selected SG to depressurize. 2SVS*PCVIOlA to MAN and depresses the output A PB 11.2 Verifies red light - LIT green light -NOT LIT and 100%

demand on controller COMMENTS:

EVALUATOR CUE:

That completes this JPM STOP TIME:

1/2-ADM-I 301.FO I Page 1 of Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Respond to PRT Trouble -

TRAINING MATERIAL NUMBER: 2CR- 155 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: 2CR-155 -

REVISION NUMBER: 0 TECHNICAL

REFERENCES:

20M-6.4.AAY, Rev. 8 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes 0

F 0 r 4 /

PREPARED BY. R J Brooks -$:,,** Date r \'

PEER REVIEW BY: - *- J - A L -

\ -J+ Date

' r J

APPROVED FOR USE. e,'

Training Supervisoi >&signee Date

1 I2-ADM- 1301.FOs Page 2 of Revision TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2CR-155 Type of Change:

Changes Requiring Learning Objective Related Change? New Rev. # 0 Revision 0 Yes IXINo u Changes Not Requiring Revision The Change Does Not Impact Learning- Existing Rev. #

~

Objectives or Material Quality.

New Change #

ListiDescription of Changt S):

Original issue Zeason for Change (s):

WPROVALS:

Z. J. Brooks

'repared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See rraining Superintendent/Superisor/Peer Date Incumbent Impact Review,

"'Changes Not Requiring Revision" only) NOBP-TR-I 104.

I I

RTL#AS.640U 112-ADM-1301 .FO i Page 3 of 1 Revision JPM NUMBER: 2CR-155 JPM REVISION: 0 I JPM TITLE: Respond to PRT Trouble 1

EVALUATION METHOD: LOCATION: TYPE:

0 Perform 0 Plant Site 0 AnnualRequalExam BVT 0 Simulate 0 Simulator 0 Initial Exam IJ Classroom 0 OJTITPE 0 Other:

Training Other:

Performer Name: Performer SSN:

rime 0 Yes Critical: (XI No 1 Time:

I 15 Minutes Actual Time:

minutes JPM RESULTS:

0 SAT 0 mSAT (Comments required for UNSAT evaluation)

Comments:

NameISSN: NameISSN:

Name/SSN: Name/SSN:

112-ADM-1301.FO Page 4 of Revision EVALUATOR DIRECTION SHEET TASK STANDARD: PRT High Temperature alarm is cleared and PRT level is dropping RECOMMENDED Control Room STARTING LOCATION:

DIRECTIONS: You are to perform the task respond to Pressurizer Relief Tank Trouble.

INITIAL CONDITIONS:

The plant is operating at 25% power.

A PRZR PORV was leaking BUT is NOW NO LONGER LEAKING.

The Pressurizer Relief Tank Trouble annunciator [A4-3H] has just actuated as a result of this leakage.

INITIATING CUE: Your supervisor directs you to respond to Annunciator A4-3H Pressurizer Relief Tank Trouble and take action to clear the annunciator.

REFERENCES:

20M-6.4.AAY, Revision 8 TOOLS: NONE HANDOUT: 20M-6.4.AAY, Revision 8

RTL#AS .640U 112-ADM-I 301.FO Page 5 of 8 Revision CANDIDATE DIRECTION SHEET

  • THIS SHEET T O BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task respond to Pressurizer Relief Tank Trouble.

INITIAL CONDITIONS:

The plant is operating at 25% power.

0 A PRZR PORV was leaking BUT is NOW NO LONGER LEAKING.

0 The Pressurizer Relief Tank Trouble annunciator [A4-3H] has just actuated as a result of this leakage.

MITIATING CUE: Your supervisor directs you to respond to Annunciator A4-3H "Pressurizer Relief Tank Trouble" and take action to clear the annunciator.

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

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

Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

2LOIT-08-NRC-JFMs SI & S2 lage 1 of 1 2LOIT-08-NRC JPMs S5 & S6 I 1 Initialize Run LRTIC file commands Horns, Printers, Sounds ready s5 Trg 2 when [2RCS*AOV519] placed to open Reduce PRT temperature indication S6 Trg 1 when A BPFRV placed in AUTO Open [2FWS*FCV479]

RTL#A5.640U IR-ADM-I 301.FO, Page 6 of Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2CR-155 JPM REVISION: 0 I JPM TITLE: Respond to PRT Trouble 1

STEP STANDARD

( "C" Denotes CRITICAL STEP ) - (Indicate "S" FOR SAT or "U" FOR U N S A T p Simulator Setup: Initialize Simulator IC 238 for 2LOT6 NRC exam. Mode 1 25% power.

TRGSET 2 XAlI097P ==I' IMFXMT RCS078A (2 0) 110 120 Trg2 When 2RCSAOVS 19 is opened reduce PRT temperature indication START TIME:

1. Obtaincopy of 20M-6.4.AAY 1.I Candidate locates 20M-6.4.AAY, reviews and determines proper procedure section is PRT temperature is > 125°F and level is >

78%

1.2 Determines 20M-6.4.AAY Part A for High temp and Part D for High level are both applicable.

COMMENTS:

EVALUATOR NOTE: Candidate may address the actions in either order. The JPM is formatted to address High temperature first. Step 6 ofthe JPM begins to address the high level.

2.C Reduce PRZR Relief Tank Temperature 2.1C Places CS for P E R ReliefTank Spray Vlv 2RCS-MOV516 to c 125F as follows:

Open [2RCS-MOV516], P E R Relief Tank Spray Vlv. 2.2 OPEN Verifies red light - LIT and green light - NOT LIT COMMENTS:

STEP STANDARD

( "C" Denotes CRITICAL STEP )

3.C open [2RCS-AOV519], PRZR Relief 3.1C Places CS for P U R ReliefTank Pri Grade MiU Wtr InletZRCS-Tank Pri Grade MiU Wtr Inlet. AOVS 19 to OPEN 3.2 Verifies red light - LIT and green light NOT LIT COMMENrS:

I.C When the desired PRT temperature is 4.1C Monitors PRT temperature to verify it has decreased helow achieved, 12YF Close [2RCS-AOV519], PRZR Relief Tank Pri Grade MAJ Wtr EVALUATOR CUE: If necessary, inform candidate Inlet. that it is desired to reduce temperature below 120°F Close [2RCS-MOV516], PRZR Relief Tank Spray Vlv.

4.2C Places CS for P U R Relief Tank Pri Grade MiU Wtr Inlet2RCS-AOV5 19 to CLOSE 4.3 Verifies red light - NOT LIT and green light ~ LIT 4.4C Places CS for P E R Relief Tank Spray Vlv 2RCS-MOV516 to CLOSE 4.5 Verifies red light - NOT LIT and green light ~ LIT COMMENTS:

5. Independently verify [2RCS-AOVS19] 5.1 N/A closed and log in the Narrative Log.

EVALUATOR CUE: Inform the candidate that another operator will perform the independent verification.

COMMENTS:

RTL#AS ,640U 112-ADM-1301 .FO Page 8 of Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUM13ER: 2CR-155 JPM REVISION: 0 1 JPM TITLE: Respond to PRT Trouble 1

I y'g Denotes CRITICAL STEP )

STANDARD

- (Indicate "S" FOR SAT or "U" FOR UNSAT):

I 6.C Lower PRZR Relief Tank level to < 5.1C EVALUATOR NOTE: Candidate should proceed to 20M-6.4.AAY Part D to address the PRT High level.

Places CS for PRZR Relief Tank Drain Vlv 2RCS-MOV523 to I

72%, ([2RCS-L1470], VB-B): OPEN Open [2RCS-MOV523], PRZR Relief Tank Drain Vlv, (BB-A) 6.2 Verities red light - LIT and green light - NOT LI?

YOMMENTS:

7.1C Places CS for Primary Drains Tfr Pump. 2DGS-P21A(B) to START 7.2 Verities red light - LIT and green light -NOT LIT ZOMMENTS:

8.C When PRZR Relief Tank level to < 8.1 Monitors PRT level to verify level is dropping and has dropped 72%, Stop [2DGS-P21A(B)], Primary below 72%.

Drains Tfr Pump AND Return control switch to AUTO. 8.2C Places CS for Primary Drains Tfr Pump. 2DGS-P21A(B) to AIJTO 8.3 Verifies red light - NOT LIT and green light - LIT COMMENTS:

112-ADM-1301.FO Page 9 of Revision OPERATIONS JOB PERFORMANCE MEASURE 1 JPM NUMBER: 2CR-155 JPM REVISION: 0 I JPM TITLE: Respond to PRT Trouble "I

1 STEP STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=.

9.C Close [2RCS-MOV523], PRZR 9.1C Places CS for P E R Relief Tank Drain Vlv 2RCS-MOV523 to Relief Tank Drain Vlv. CLOSE 9.2 Verifies red light - NOT LIT and green light - LIT COMMENTS:

EVALIJATOR CUE:

That completes this JPM STOP TIME:

112-ADM-1301.FO.

Page 1 of 1 Revision OPERATIONS JOB PERFORM-TRAINING MATERIAL TITLE Shift From Main Feedwater Reg Valves to Bypasses TRAINING MATERIAL NUMBER 2CR-572 PROGRAM TITLE Licensed Operator Retraining COMPUTER CODE. 2CR-512 REVISION NUMBER: 1 TECHNICAL

REFERENCES:

20M-52.4.R.l.F, Station Shutdown From 100% Power To Mode 5 , Revision 9 INSTRUCTIONAL SETTING: Control Room APPROXIMATE DURATION: 15 Minutes c

c i i PREPARED BY: R. J. Brooks - - -

i' Date r

PEER REVIEW BY: -

Date

/

  • \ ' J'-

APPROVED FOR USE: - .-

Training Supemsoddesignee Date

112-ADM-1301.FOI Page 2 of I Revision TRAINING MATERIAL CHANGE FORM iffected Training Materials: 2CR-572 rype of Change:

Changes Requiring Learning Objective Related Change? New Rev. # 1 Revision 0Yes [XI NO 1Changes Not The Change Does Not Impact Learning Existing Rev. # 0 Requiring Revision Objectives or Material Quality.

New Change #

>ist/Descriptionof Changei Jpdated to reflect current procedure teason for Change (s):

Jpdated to reflect current procedure WPROVALS:

R. J. Brooks - NOTE: Additions, deletions or

'repared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See rraining SuperintendentlSupervisorPeer Date Incumbent Impact Review,

"'Changes Not Requiring Revision only)

NOBP-TR-1104.

I

RTL#AS .640U 112-ADM-I301.FO.

Page 3 of 1 Revision EVALUATION METHOD: LOCATION: TYPE:

0 Perform 0 Plant Site 0 AnnualRequalExam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 Classroom 0 OJTiTPE 0 Other:

0 Training Performer Name: Pcrformcr SSN.

0 Time Critical:

Yes NO I Time:

15 minutes Actual Time:

minures 0 SAT JPMRESULTS: uNsAT (Comments required for UNSAT evaluation)

Comments:

Name/SSN: NameiSSN:

NameISSN: NamelSSN:

1/2-ADM-1301 .F( 4 Page 4 of 1 I Revision I IJPM NUMBER: 2cR-072 JPMREVISION 1 I JPM TITLE: Shift From Main Feedwater Reg Valves to Bypasses 7

EVALUATOR DIRECTION SHEET TASK STANDARD: The A Bypass Feed Regulating Valve has been placed in service in automatic mode and then, after candidate recognizes failure of automatic control, returned to Manual mode with candidate controlling steam generat( r level.

RECOMMENDED CONTROL ROOM STARTING LOCATION:

DIRECTIONS: You are to perform the task Transfer from Main Feed Regulating Valve to Bypass.

INITIAL CONDITIONS. .. A plant shutdown is in progress

. 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 IV.D.5.

The 21B and C: SiG main Feed Reg Valves have been removed froni

. service.

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 2lA S/G Bypass Feed Reg Valve [2FWS-FCV479] in service in accordance with 20M-52.4.R.l.F, Station Shutdown From 100% Power To Mode 5

. Attachment IO step A.

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

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

REFERENCES:

20M-52.4.R.1 .F, Station Shutdown From 100% Power To Mode 5 , Revisior 9

TOOLS: None HANDOUT: 2OM-52.4.R.l.F, Station Shutdown From 100% Power To Mode 5, Attachment 10 Revision 9

RTL#AS .640U 1/2-ADM-1301 .FO I Page 5 of 1 Revision CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE G N E N TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task Transfer from Main Feed Regulating Valve to Bypass.

INITIAL CONDITIONS: A plant shutdown is in progress The plant is at approximately 25% power.

2OM-52.4.R.l.F, Station Shutdown From 100% Power To Mode 5 has been completed up to Step N.D.5.

The 21B and C S/G main Feed Reg Valves have been removed fror I service.

The 21A main Feed Reg Valve [2FWS-FCV478] operated erraticaly during the shutdown and is currently in "AUTO" for observation.

INITIATLNG CUE Your supervisor directs you to place 21A SIG Bypass Feed Reg Valve [2FWS-FCV479] in service in accordance with 20M-52.4.R.l.F, Station Shutdown From 100% Power To Mode 5 Attachment I O step A.

[2FWS-FCV4?9] is to be placed in automatic to control steam generator level.

You are to maintain 21A SiG NR level between 39% and 49%.

0 At this time, ask the evaluator any questions you have on this JPM 0 When satisfied that you understand the assigned task, announce "I am now beginning the JF""

Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

2LOIT-08-NRC-JPMs S5 & S6 Iage 1 of 1 2LOIT-08-NRC JPMs S5 & S6 Initialize RUn LRTIC file commands Horns, Printers, Sounds ready s5 Trg 2 when [2RCS*AOV519] placed to open Reduce PRT temperature indication S6 Trg 1 when A BPFRV placed in AUTO Open [2FWS*FCV479]

112-ADM-1301.FO~~

Page 6 of Revision OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2CR-572 REVISION: 1 I JPM TITLE: Transfer fiom Main Feedwater Reg Valves to Bypasses 1

STEP STANDARD I CDenotes CRITICAL STEP (Indicate S FOR SAT or U FOR START TIME:

EVALUATOR NOTE:

Initialize IC-238 for 2LOT6 NRC Exam, Set Bank D Control Rods to 126 steps. Put SGWIDI: trend up on BOPSPCS screen.

Open MFRV isolation valve 2FWS-MOV154A.

Place 2FWS-FCV478 in AUTO, place 2FWS-FCV479 in MANUAL and close valve.

To set up alternate path, set Trigger 1 to actuate when the Bypass controller AUTO pushbutton is depressed TRGSET 1 XClI064E Insert command to fail Bypass to full open over 60 seconds fiom Trigger 1, (PB in AUTO)

IMF CNII-CFWIIB (1 0) 100 60 ASIS

1. Obtain a copy of 20M-52.4.R.1 .F, Station Shutdown From 100%

Power To Mode 5, Attachment 10 -

EVALUATOR NOTE:

Procedure can be provided to candidate, if provided, N/A this JPM Step.

COMMENTS:

2.C Place controller in MANUAL 2.1C Intermittently depresses the Bypass Control Valve [2FWS-AND Slowly Open the 21A FCV4791 up pushbutton.

Bypass FCV.

2.2 Verifies feed flow increases COMMENTS:

RTL#A5.640U 112-ADM-1301 .FOL Page I of 5 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE iPM hWMBER: 2CR-572 IJPM REVISION: 1 I JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses 1

-~

STEP

( "C" Denotes CRITICAL STEP )

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)a I1 SU 3 . As the 21A Bypass FCV is being 3.1 Verifies 2 1A Main Feedwater Reg Valve 2FWS-FCV 471 opened, close [ZFWS-FCV 4781, demand signal is decreasing and feed flow is reducing.

21A Main Feedwater Reg Valve, in MANUAL OR AUTO to maintain 21A SG level WITHIN 39% to 49%. COMMENTS:

l.CContinue to Open the 21A Bypass 4.1C Intermittently depresses the Bypass Control Valve [2FW!

FCV UNTIL the 21A Main Feed FCV4791 up pushbutton.

Reg Valve is closed.

4.2 Verifies 21 A Main Feed Reg Valve green light LIT anc

~

red light -- NOT LIT COMMENTS:

5.C WHEN the 21A Main Feed Reg 5.1C Places 21A Main Feed Reg Valve controller to MAN Valve is fully closed, perform the following: 5.2 Verifies MAN light LIT and AUTO light is -NOT LI'I

~

Verify the 2 1A Main Feed Reg Valve controller in MAN. COMMENTS:

RTL#A5.640U 1/2-ADM-l301.FOL Page 8 of 5 Revision !

OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER:

REVISION: 1 2CR-572 I JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses 1

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR U N S A T p 6 . Observe Feedwater flow, steam 6.1 Verifies feed flow, steam flow, and NR level are stable flow and SG level for evidence leakage past the 21A Main Fee(

Reg Valve. COMMENTS:

7.C Close [2FWS-MOV154A], 21 7.1C Places CS for 21A SG Main Feedwater Is01 Vlv 2FWS-SG Main Feedwater Is01 Vlv. MOV154A to CLOSE 7.2 Verifies green light - LIT and red light NOT LIT

~

COMMENTS:

FAULT STATEMENT:

This is where the alternate Dath will begin;

- . valve will trend open to 100% over 60 seconds as soon as the controller PB is I

placed in AUTO.

8.C Place controller for the 21A 8.1C Places controller for the 21A Bypass FCV in AUTO Bypass FCV in AUTO AND Monitor SG level AND flow. 8.2 Verifies MAN light -NOT LIT and AUTO light is LIT ~

8.3 Determines valve is failing OPEN in Automatic.

COMMENTS:

RTL#A5.640U 112-ADM-I 301.FOa Page 9 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE I IPM NUMBER: 2CR-572 JPM REVISION: 1 I JPM TITLE: Transfer from Main Feedwater Reg Valves to Bypasses 1

STEP STANDARD 1 "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)= i. -U 3.C If level control is NOT stable, 9.1C Places controller for the 21A Bypass FCV in MAN restore the valve controller to MANUAL AND Maintain SG NR 9.2 Verifies MAN light - LIT and AUTO light is - NOT LIT level between 39% and 49%.

9.3C Intermittently depresses the Bypass Control Valve

[2FWS-FCV479] upidown pushbutton to regain manual control of SG level with NR level between 39% and 49%.

COMMENTS:

c

  • RTL#A5.640U IR-ADM- I301 .FO I Page 1 of 1 ~

Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM]

TRAINING MATERIAL TITLE: Perform Nuclear Intermediate Range Channel Functional Test TRAINING MATERIAL NUMBER: 2CR-646 PROGRAM TITLE: License Operator Training (Retraining)

COMPUTER CODE: 2CR-646 REVISION NUMBER: 0 TECHNICAL

REFERENCES:

20ST-2.2, Nuclear Intermediate Range Channel Functional Test INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 10 Minutes t

@ 4 c ' ,'

PREPARED BY: R. J. Brooks _ L 0  :,'

.4

/+ Date 4

t PEER REVIEW BY, - t t - J L Date 8 --J+

.4 APPROVED FOR USE. * , '- 4 Training Superv1s;- *d 6 e s i g n e e Date

1/2-ADM-l301.FO.

Page 2 of 1 Revision TRAINING MATERIAL CHANGE FORM

~~~

Affected Training Materials: 2CR-646

~. of Change:

Type -

0Changes Requiring Learning Objective Related Change? New Rev. # 0 Kcvision

.. .-. 0Yes 0No 0(tiangzi ~

~

o t The Change Does Not Impact Leaming Existing Rev. # N/A Rcyuiriny Re\ ision Objectives or Material Quality New Change #

List!Dcscription ofCliang S):

Initial issue of JPM Reason for Change (s):

APPROVALS:

R. J. Brooks NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Training Superintendent/Superisor/Peer Date Incumbent Impact Review, (Changes Not Requiring Revision onlyl NOBP-TR- 1 104.

112-ADM-I 301 .FO Page 3 of 1 Revision J P M REVISION: 0 Test EVALUATION METHOD: LOCATION: TYPE:

0 Perform 0 Plant Site 0 AnnualRequalExam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 Classroom 0 OJTiTPE 0 Other:

0 Training EVALUATIOX RESULTS -

I Performer Name: I Perfomier SSN:

Actual 10 minutes minutes Critical: No Time: Time:

JPM RESULTS:

0 SAT 0 mSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS I

NameiSSN: I NameiSSN:

NameiSSN: I I

Name/SSN:

EVALUATOR -

Evaluator (Print): Date:

Evaluator Signature:

RTL#AS.640U 112-ADM-1301.FO.

Page 4 of 1 Revision EVALUATOR DIRECTION SHEET TASK STANDARD: Hi level Rod stop is tested satisfactorily and the surveillance is STOPPED when the high level trip will not reset.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform the task of Nuclear Intermediate Range Channel Functional Test.

INITIAL CONDITIONS: -

The plant is in Mode 2 with reactor power 3%. 20ST-2.2, Nuclear Intermediate Range Channel Functional Test has been completed through step VII.B.9.

INITIATING CUE: Your supervisor directs you to complete 20ST-2.2, Nuclear Intermediate Range Channel Functional Test Beginning at step VILB.10.

REFERENCES:

20ST-2.2, Nuclear Intermediate Range Channel Functional Test Revision 7 TOOLS: None HANDOUT: 20ST-2.2, Nuclear Intermediate Range Channel Functional Test completed through step VII.B.9.

112-ADM-1301 .FOL Page 5 of 1:

Revision I CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task of Nuclear Intermediate Range Channel Functional Test.

INITIAL CONDITIONS: The plant is in Mode 2 with reactor power - 3%. 20ST-2.2, Nuclear Intermediate Range Channel Functional Test has been completed through step VII.B.9.

INITIATING CUE: Your supervisor directs you to complete 20ST-2.2, Nuclear Intermediate Range Channel Functional Test Beginning at step VII.B.10.

0 At this time, ask the evaluator any questions you have on this JPM, 0 When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

2LOIT-08-NRC-JPMs S7 & S8 P ige 1 of 1 2LOIT-08-NRC JPMs S7 & S8 I 1 Initialize RUn LRTIC file commands Horns, Printers, Sounds ready S7 Perform IRNl Functional Test Trg 1 to fail N35 Bistable (Rx trip) as is whei actuated Fails N35 (Rx trip) bistable as is AD Fail [2GS-HCV100] open Trg 5 to remove failure of [2GS-HCV100]

Clear malfunction of [2GS-HCV100]

High failure of liquid waste discharge rad monitor Close [2CHS*79]

Open [2chs*87]

file://E:\U2%20LOIT%2020O8%2ONRC\LOIT%2008%2Ms~02OS7~o2O&%2OS8.htm 0/3/2008

JPM NUMBER: 2CR-646 JPM TITLE: Perform Nuclear Intermediate Range Channel Functional JPM REVISION: 0 Test STEP

( "C" Denotes CRITICAL STEP )

1 STAYDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)> I1 SU START TIME:

SIMULATOR SETUP:

Initialize IC-Mode 2 -3% power FAULT by making Hi flux tnp NOT reset 1 .C Perform the test of the IRN-35 High I .IC Rotates the Test Mode Variable control switch Level Rod Stop as follows: clockwise to the VARIABLE position.

Place the Test Mode Switch in 1.2 Verifies N35 Drawer Status Light "HIGH LEVEL ROD VARIABLE. STOP" is NOT LIT.

Verify that the "HIGH LEVEL ROD S T O P Drawer Status Light is OFF. ZOMMENTS:

2.C Turn the Variable control h o b  !.1C SLOWLY rotates the Test Mode Variable control knob clockwise until the "HIGH LEVEL clockwise UNTIL the "HIGH LEVEL ROD STOP" ROD STOP" Drawer Status Light Drawer Status Light is LIT.

turns ON.

ZOMMENTS:

JPM NUMBER: 2CR-646 JPM TITLE: Perform Nuclear Intermediate Range Channel Functional JPM REVISION: 0 Test STEP STANDARD

( "C" Denotes CRITICAL STEP ) --__ (Indicate "S" FOR SAT or "U" FOR UNSAT)=.

3.C Record the neutron level indication on 3.1 Records, in the space provided the neutron level the NIS Drawer meter when the indication on the N35 Drawer meter when the Drawer Drawer Status Light turns ON: Status Light turns ON.

Verify the NIS Drawer indication 3.2C Verifies the value recorded is between the Low and satisfies the Acceptance criteria. High limits listed in the surveillance and initials the space provided.

4.C Record the neutron level indication on 4.1 Records, in the space provided the neutron level

[2NMI-N135B], Intermediate Range indication on [2NMI-N135B], Intermediate Range Current, when the Drawer Status Current when the Drawer Status Light turns ON.

Light turns ON: 4.2C Verifies the value recorded is between the Acceatance Verify the indication on [2NMI- Criteria Low and High limits listed in the surveillance NI35Bl is within the high and low and initials the space provided.

limits.

EVALUATOR CUE:

If necessary to avoid contact with other candidates, CUE candidate that Benchboard [2NMI-N135B],

Intermediate Range Current is the SAME AS the drawer meter.

COMMENTS:

JPM NUMBER: 2CR-646 JPM TITLE: Perform Nuclear Intermediate Range Channel Functional STEP

( "C" Denotes CRITICAL STEP )

STANDARD (Indicate "S" FOR SAT or "U" FOR IINSAT)* I1 S.U 5.C Turn the Variable control h o b 5.1C SLOWLY Rotates Variable control h o b counterclockwise until the "HIGH counterclockwise until the "HIGH LEVEL ROD LEVEL ROD STOP" Drawer Status STOP" Drawer Status Light is NOT LIT.

Light turns OFF.

COMMENTS:

I.C Record the neutron level indication on 6.1 Records, in the space provided the neutron level the NIS Drawer meter when the indication on the N35 Drawer meter when the Drawer Drawer Status Light turns OFF: Status Light is NOT LIT.

Verify the NIS Drawer indication is 6.2C Verifies the value recorded is between the Low and satisfies the Acceptance criteria. High limits listed in the surveillance and initials the space provided.

COMMENTS:

RTL#A5.64OU 1/2-ADM-1301 FO.

Page 9 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-646 JPM TITLE: Perform Nuclear Intermediate Range Channel Functional

~-

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR U N S A T p SU

7. Perform the test of the Intermediate 7.1 Verifies the following:

Range Neutron Flux High Reactor Trip Status Light C-9, "INT RNG N35 RX TRIP", is Setpoint as follows: NOT LIT.

Verify the following: PCS Point N0020D, "INT RNG CHAN 1 HIGH Status Light (2-9, "INT RNG N35 FLUX", indicates NORMAL.

RX TRIP", is OFF.

PCS Point N0020D, "INT RNG EVAIJJATOR CUE:

CHAN 1 HIGH FLUX", indicates If necessary to avoid contact with other candidates, NORMAL.

CUE candidate that Benchboard Status Light C-9, "INT RNG N35 RX TRIP", is NOT LIT.

AND PCS Point N0020D, "INT RNG CHAN 1 HIGH FLUX", indicates NORMAL.

COMMENTS:

8.C Turn the Variable control knob Y.1C SLOWLY Rotates Variable control knob clockwise clockwise until the "HIGH LEVEL until the "HIGH LEVEL TRIP" Drawer Status Light TRIP" Drawer Status Light turns ON. is LIT.

COMMENTS:

RTL#A5.640U 112-ADM-1301 FOL Page 10 of 1:

Revision ;

OPERATIONS JOB PERFOKMANCE MEASURE JPM m B E R : 2CR-646 JPM TITLE. Perform Nuclear Intermediate Range Channel Functional JPM REVISION: 0 Test STEP STANDARD "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR EVALUATOR NOTE:

In the next step, the E N - 3 5 Trip Setpoint (recorded in Instruction A.4) High Limit has already been recorded in the space provided as part of a previously performed step in the initial conditions.

9.c Record the neutron level indication Records, in the space provided the neutron level on the NIS Drawer meter when the indication on the N35 Drawer meter when the Drawer Drawer Status Light turns ON: Status Light is LIT.

Verify the NIS Drawer indication '.2C Verifies the value recorded below the High limit listed satisfies the Acceptance criteria. in the surveillance and initials the space provided.

ZOMMENTS:

10. If the NIS Drawer indication for the 0.1 Determines reference to Attachment A, "Measurement setpoint is NOT within the of the [ZNMI NM35A(36A)], Log Current Amplifier Acceptance Criteria, Refer to Output" is NIA based on values being within limits.

Attachment A, "Measurement of the

[2NMI NM35A(36A)], Log Current Amplifier Output". (Otherwise NIA)

ZOMMENTS:

JPM NUMBER: 2CR-646 JPM TITLE: Perform Nuclear Intermediate Range Channel Functional JPM REVISION: 0 Test STANDARD I ( "C" Denotes CRITICAL STEP ) ~~

~~

(Indicate "S" FOR SAT or "U" FOR UNSAT)a I 1 .C Record the neutron level indication I1.1C Records, in the space provided the neutron level on the [2NMI-N13SB], Intermediate indication on [2NMI-N13SB], Intermediate Range Range Current, when the Drawer Current when the Drawer Status Light turns ON.

Status Light turns ON: I 1.2 Verifies the value recorded is between the Acceptance Verify the indication on [2NMI- Criteria Low and High limits listed in the surveillance NI3SBI is within the high and low and initials the space provided limits.

EVALUATOR CUE:

If necesary to avoid contact with other candidates, CUE candidate that Benchboard [2NMI-N135B],

Intermediate Range Current is the SAME AS the rlrawpr metpr IOMMENTS:

12. If necessary, turn the Variable 12.1 Determines NIA control knob clockwise until the "HIGH LEVEL TRIP" Drawer Status Light remains ON AND does NOT reset. (Otherwise NIA) COMMENTS:

JPM NUMBER: 2CR-646 JPM TITLE: Perform Nuclear Intermediate Range Channel Functional JPM REVISION: 0 Test jTEP STANDARD "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)S

13. Verify Status Light C-9, "INT RNG 13.1 Verifies the following:

N35 Rx TRIP", is ON AND NOT Status Panel 308 -9, "INT RNG N35 RX TRIP",is flashing. (Status Panel 308) LIT AND NOT flashing.

Verify PCS Point N0020D, "MT PCS Point N0020D, "INT FWG CHAN 1 HIGH RNG CHAN 1 HIGH FLUX", FLUX", indicates T W .

indicates TRIP.

EVALUATOR CUE:

If necessary to avoid contact with other candidates, CUE candidate that Benchboard Status Panel 308 -

9, "INT RNG N35 RX TRIP", is LIT AND NOT flashing.

AND PCS Point N0020D, "INT RNG CHAN 1 HIGH FLUX", indicates TRIP.

COMMENTS:

FAULT STATEMENT:

The High level trip bistable WILL NOT reset in the next sten

~~~

14.C Turn the Variable control knob 14.1C SLOWLY Rotates Variable control knob fully count' counterclockwise until the "HIGH LEVEL clockwise.

rRP Drawer Status Light turns OFF. 14.2C Determines "HIGH LEVEL TRIP" Drawer Status LIE REMAINS LIT.

COMMENTS:

1I2-ADM- 1301.FO' Page 13 of I .

Revision OPERATIONS JOB PERFOKMANCE MEASURE JPM NUMBER: 2CR-646 JPM TITLE: Perform Nuclear Intermediate Range Channel Functional JPM REVISION: 0 Test STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)S E 'u EVALUATOR NOTE:

At this point the Surveillance CANNOT be completed without support from the I&C department. If the Level Trip Switch is returned to NORMAL, the reactor will tnp.

I I EVALUATOR NOTE:

The candidate SHOULD recognize the impact of returning the level tnp swltch to normal EVALUATOR CUE:

That completes this JPM.

STOP TIME:

RTL#AS .640U 112-ADM-I 301 .FOz' Page 1 of 1 :

Revision OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Batch To The Refueling Water Storage Tank TRAINING MATERIAL NUMBER: 2CR-531 PROGRAM TITLE: Licensed Operator Training (Retraining)

COMPUTER CODE: 2CR-531 REVISION NUMBER:

TECHNICAL

REFERENCES:

20M-7.4.0, Makeup To The Refueling Water Storage Tank,Rev. 13 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 minutes c

/

'e ' /

/

' . 1 PREPARED BY: R. J. Brooks - -',,e.

r - .* .-

i, /' Date c

PEER REVIEW BY: +e J' .-

Date

  1. '\,,
  • I ' J*

APPROVED FOR USE: ' A/

Training Supervisor 6;Designee Date

1/2-ADM-1301 .FOz Page 2 of 1 Revision TRAINING MATERIAL CHANGE FORM kffected Training Materials: 2CR-537 rype of Change:

8Changes Requiring I Learning Objective Related Change? New Rev. # I Revision Existing Rev. ## 0 I ___ New Change ##

ListiDescnption of Change(s):

Update JPM to current procedure and JPM format Reason for Change (s):

JPM Enhancement APPROVALS:

R. J. Brooks Prepared by Date changes to training materials must be reviewed for their uossible imuact to the Traininc!

Qualification Matrix. See Training Superintendent/Superisor/Peer Date Incumbent Impact Review, (Changes Not Requiring Revision only) NOBP-TR-1104.

I L A D M - 1301.F04 Page 3 of 1 1 Revision I I.IPM NUMBER: 2CR-537 JPM REVISION: 1 1 JPM TITLE: Batch To The Refueling Water Storage Tank WA

REFERENCE:

004 A4.01 (3.813.9) TASK ID: 0071-025-01-013 004 A4.04 (3.213.6) 004 A4.07 (3.9/3.7)

EVALUATION METHOD: LOCATION: TYPE:

0 Perform 0 Plant Site 0 AnnualRequalExam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 Classroom c] OJTITPE 0 Other:

0 Training c] Other:

Performer Name: Performer SSN:

Time 0 Yes Allotted 15 minutes Actual minutes Critical: [XI NO Time: Time: -

Name/SSN Name/SSN Name1SSN NameiSSN Evaluator (Print): Date:

' Evaluator Signature:

II2-ADM-I 301.F04 Page 4 of 11 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Makeup flow to the RWST is initiated AND terminated aAer discover i of no boric acid flow.

RECOMMENDED Control Room STARTING LOCATION:

DIRECTIONS: You are to perform the task Batch To The Refueling Water Storage Tank.

INITIAL CONDITIONS: -

The plant is in Mode 2 with reactor power at 3%. The Refueling Water Storage Tank level is currently at 717.5". RWST boron concentration is 2500 ppm and Boric Acid Storage Tank concentratio,l is 7500 ppm. The Spent Fuel Pool was being filled from the RWST.

This operation has been secured. Annunciator A6-1D, RWST LEVEI, OFF NORMAL has alarmed. Actual RWST level is just below the narrow range low level alarm setpoint.

INITIATING CUE: Your supervisor directs you to batch 300 gallons of borated water at current RWST boron concentration to the RWST by manual blender operation in accordance with 20M-7.4.0, Makeup To The Refueling Water Storage Tank, beginning at step IV.B.5.

REFERENCES:

20M-7.4.0, Makeup To The Refueling Water Storage Tank, Rev. 13 TOOLS: Calculator HANDOUT: 20M-7.4.0, Makeup To The Refueling Water Storage Tank

112-ADM-1301.FOL Page 5 of 1 1 Revision 1 CANDIDATE DIRECTION SHEET

  • THIS SHEET T O BE GIVEN TO CANDIDATE
  • 0 Read:

TASK: You are to perform the task Batch To The Refueling Water Storage Tank.

INITIAL CONDITIONS: The plant is in Mode 2 with reactor power at - 3%. The Refueling Water Storage Tank level is currently at 717.5". RWST boron concentration is 2500 ppm and Boric Acid Storage Tank concentration is 7500 ppm. The Spent Fuel Pool was being filled from the RWST.

This operation has been secured. Annunciator A6-1D, RWST LEVE: I OFF NORMAL has alarmed. Actual RWST level is just below the narrow range low level alarm setpoint.

INITIATING CUE: Your supervisor directs you to batch 300 gallons of borated water at current RWST boron concentration to the RWST by manual blender operation in accordance with 20M-7.4.0, Makeup To The Refueling Water Storage Tank, beginning at step IV.B.5.

0 At this time, ask the evaluator any questions you have on this JPM 0 When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

2LOIT-08-NRC-JPMs S7 & S8 Page 1 of 1 2LOIT-08-NRC JPMs S7 & S8 I 1 Initialize RUn LRTIC file commands Horns, Printers, Sounds ready Trg 1 to fail N35 Bistable (Rxtrip) as is whm actuated Fails N35 (Rx trip) bistable as is Fail [2GS-HCVlOO] open Trg 5 to remove failure of [2GS-HCV100]

Clear malfunction of [2GS-HCV100]

High failure of liquid waste discharge rad monitor Close [2CHS*79]

Open [2chs*87]

file:/lE:\U2%20LOIP/o202008%2O~C~OIP~2OO8%2O~C%2O~Ms%2OS7%2O&%2OS8.h~ I n/mnnR

RTL#A5.64OU 112-ADM-1301.FO Page 6 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE 1JPM NUMBER: 2CR-537 JPM REVISION: 1 1 JPM TITLE: Batch To The Refueling Water Storage Tank 1

STEP STANDARD I 1

( "C" Denotes CRITICAL STEP )

START TIME:

SIMULATOR SETUP: h i t IC--.

Verify RWST level set to 717' 5" (ASISRWST =

7.43E6). Update RWST boron concentration placard to 2500 ppm and BA Storage Tank concentration placard t(

7500 ppm. Verify LOA BAT6 to open 2CHS*87.

Verify 2CHS*79 is overridden in the closed position LOA BAT 004. Set BA & Total Flow totalizers to ZERO and reset.

1 EVALUATOR NOTE: This step is optional.

Evaluator may elect to provide procedure.

If urovided, N/A this JPM steu 2.

I 1.1 Candidate locates 20M-7.4.0, Makeup To The Refuelin:

Water Storage Tank.

EVALUATOR CUE: After candidate locates the procedure, provide a copy of 20M-7.4.0, Makeup To The Refueling Water Storage Tank.

COMMENTS:

2. Place the Boric Acid Makeup 2.1 Candidate locates and places Boric Acid Makeup Blende Blender Control Switch in STOP, Control Switch in Stop.

COMMENTS:

RTL#A5.640U 112-ADM-1301.FOa Page 7 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2CR-537 JPM REVISION: 1 1 JPM TITLE: Batch To The Refueling Water Storage Tank 1

STEP

( "C" Denotes CRITICAL STEP )

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)J 17S'U 3.C Place the Mode Selector Switch I 3.1C Candidate locates and places Mode Selector Switch in MAN. Manual.

COMMENTS :

4. Verify the following valves are in 4.1 Candidate locates and verifies valves closed.

the closed position. 4.2 Candidate verifies green closed light lit and red open light

a. [2CHS*FCV113B], Boric Acic not lit for each valve.

Blender Disch To Chg Pumps

b. [2CHS*FCVl14B], Blender COMMENTS:

Outlet To Volume Control

'Tank

c. [2CHS*SOV206], Alt Emergency Boration Vlv
d. [2CHS*MOV350], Emergencq Boration Is01 Vlv
5. If this section is being performed 5.1 Candidate NIA's step.

for testing of the blender, THEN EVALUATOR NOTE: If asked, inform the Candidate that no testing is being performed.

COMMENTS:

II2-ADM-I 301.FO 1 Page 8 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE

.lPM NUMBER: 2CR-537 JPM REVISION: 1 I JPM TITLE: Batch To The Refueling Water Storage Tank 1

STEP STANDARD EVALUATOR CUE: If asked, inform the Candidate that Desired flowrate is 75 gpm.

6. Determine Boric Acid Flow from 5.1. Candidate calculates boric acid flow:

the following calculation:

2500ppm x 75gpm axb = 25.0gpm (+ 1 gpm)

BoricAcidFlow = ~

7500 C

COMMENTS:

7.C Set [2CHS*FCV113A] as 7.1C Candidate calculates and adjusts 2CHS*FCV113A to follows: desired pot setting.

Boric Acid Flow 25.0 Pot Setting = 6.25 (* 0.25) = ~

4 gpm 4gpm COMMENTS:

3.C Adjust [2CHS*HIC168], Blender S.1C Candidate locates and adjusts 2CHS*HIC168 to desired Total Flow Auto Setpoint, to the pot setting.

blender total flow used in Step IV.A.9.

75 Total Makeup Flow 4.69 (4.6 - 4.8) =

Pot Setting = 16 gpm 16 gpm ZOMMENTS:

RTL#A5.64OU 112-ADM-I 301.FO Page 9 of 1 Revision OPERATIONS JOB PERFOKMANCE MEASURE IPMNUMBER: 2CR-537 I JPM REVISION: 1 I JPM TITLE: Batch To The Refueling Water Storage Tank 1

1 STEP 1 STANDARD 9.C Adjust [2CHS*FCVl14A] pot 9.1C Candidate locates and adjusts 2CHS*FCV114A to desired setting to the blender total flow pot setting.

used in Step IV.A.9.

75 4.69 (4.6 - 4.8) = _ _

16gpm COMMENTS:

10.C Set [2CHS-FQIS113], Boric Acid 10.1C Candidate locates and sets 2CHS-FQISl13for the desired Flow To Blender Flow Totalizer, total volume of boric acid.

to the total volume in gallons of boric acid to be added from the 25ir1 following equation: 100 (96 - 104) = x 300 75 gpm B.A Flow B.A.Vol= 10.2 Candidate locates and resets 2CHS-FQISI 13 Total Makeup Flow x Tutal Makeup Vol COMMENTS:

1 l.C Set [ZCHS-FQIS168], Total 11.1C Candidate locates and sets 2CHS-FQIS168 to 300 gallons.

Makeup From Blender Flow 11.2 Candidate locates and resets 2CHS-FQIS168.

Totalizer, to the desired total volume in gallons of makzup to COMMENFS:

be added.

RTLAfA5.640U 1/2-ADM-1301 .FOd Page 10 of I Revision OPERATIONS JOB PERFORMANCE MEASURE I

JPM NUMBER: 2CR-537 JPM REVISION: 1 STEP JPM TITLE: Batch To The Reheling Water Storage Tank STANDARD 1

( "C" Denotes CRITICAL STEP ) -~ (Indicate "S" FOR SAT or "U" FOR UNSAT)S

12. Record the following information 12.1 Candidate indicates the values to be recorded in the into the Narrative Log: Narrative Log.

Total Makeup + Total Makeup From Blender Flow Totalizer = EVALUATOR CUE: lnform the Candidate that Total another operator will make the log entry.

IOMMENTS:

13. Establish communications with an 13.1 Candidate uses page party to contact local operator in the operator at the blender room (Aux. blender room.

Bldg. 710') EVALUATOR CUE: Inform the Candidate that an operator is standing by in the blender room.

COMMENTS:

14.C Open the following valves: (Aux. 14.1C Candidate directs local operator to open 2CHS*87 and Bldg. Blender Rm,710') 2CHS*89.

a. [2CHS*87], Blender To EVALUATOR CUE: Report as local operator Refueling Cavity Isolation that 2CHS*87 and 2CHS*89 are open.
b. [2CHS*89], Blender To RWST Isolation COMMENTS:

RTL#A5 640U 1/2-ADM-1301.FO I Page I I of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2CR-537 JPM REVISION: 1 I JPM TITLE: Batch To The Refueling Water Storage Tank 7

lTANDARD s CRITICAL STEP )

15.C To initiate makeup, place the 5.1C Candidate locates and places Boric Acid Makeup Control Boric Acid Makeup Blender Switch in Start.

Control Switch to START. .5.2. Candidate verifies red makeup light lit.

ZOMMENTS:

FAULT STATEMENT: ZCHS*79 IS failed closed. In the next step Boric acid flow will be zero with total flow indicatine 75 mm.

,6.C Verify expected flows for the 16.1 Candidate locates 2CHS-FRI 13 and verifies boric acid following parameters are being flow and total makeup flow.

recorded at [2CHS-FRI 131, Boric 16.2C Candidate takes irnmkdiate action to terminate dilution b:

Acid To Blender Total M/U Flow placing Boric Acid Makeup Control Switch in STOP.

From Blender:

a. Boric Acid To Blender (red EVALUATOR NOTE: Stop the JF'M after the Pen) Candidate secures the dilution.
b. Total M/U Flow From Blender (green pen)

ZOMMENTS:

STOP TIME: ~

. RTL#Aj .640U 1R-ADM- I301 .F'M Page I of !3 Revisioi 1 OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Safeguards Test of FWI TRAINING MATERIAL NUMBER: 2PL-048 PROGRAM TITLE: Licensed Operator Training (Retraining)

COMPUTER CODE. 2PL-048 REVISION NUMBER: 11 TECHNICAL

REFERENCES:

20ST-l.IlA,Rev 15 20ST-1.12A, Rev 19 INSTRUCTIONAL SETTING: In-PI ant APPROXIMATE DURATION: 20 Minutes r

0@ )

@ /

c 0

PREPARED BY: R. .I.

Brooks \' 0 e

- - /P Date 4

c \\*

PEER REVIEW BY: -4 -JL Date 0

' -Je e

APPROVED FOR USE: *

'-/ 4 Training Supervisor c-- L,dgnee Date

112-ADM-1301.Fil4 Page 2 of !3 Revisioi I TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2PL-048

. - of Change:

Type -

Changes Requiring Learning Ohjectice Related Change? I New Rev. # 11 Revision 17 Yes El No Changes Not The Change Does Not Impact Learning Existing Rev. # 10 Requiring Revision Objectives or Material Quality.

New Change #

ListDescription of Chang :S):

Updated to current procedure revisions.

Added 2LOT6 NRC Exam Validation comments.

0 Split JPM into 2 separate sections for ease of performance Added Cabinet mark numbers to first evaluator note Added evaluator cue for annunciator A2-2H Reason for Change (s):

JPM Enhancement APPROVALS:

R. J. Brooks changes to training materials Prepared by Date must be reviewed for their possible impact to the Training Qualification Matrix. See Training Superintendent/Supervisor/Peer Date Incumbent Impact Review, (ChangesNot Requiring Revision only)

1/2-ADM-1301.F(I Page 3 of: 3 Revision 1 NUMBER: 2pL-048 JPM REVISION: 11 1 JPM TITLE: Safeguards Test of FWI 7

K/A

REFERENCE:

013A3.01 3.7/3.9 TASK ID: 001 1-024-06-013 2.1.23 3.9/4.0 JPM APPLICATION: REQUALIFICATION (xi INITIAL EXAM 0 TRAINING

[7 FAULTEDJPM 0 ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

Perform Plant Site AnnualRequalExam 0 BVT 0 Simulate 0 S' Initial Exam NRc assroom 0 OJT/TPE 0 Other:

0 Training Performer Name: Performer SSN:

rime 0 Yes Allotted 10 Minutes (TRN A) Actual minutes Critical: No Time: 20 Minutes (TRN B) Time:

JPM RESULTS:

SAT 0 mSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS I

Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

Evaluator (Print): Date:

Evaluator Signature:

1/2-ADM-1301.FC I Page 4 of 2 3 Revision !

EVALUATOR DIRECTION SHEET TASK STANDARD: Relay K622A (K601B and K620B) are tested IAW the surveillance procedure and determined to meet the acceptance criteria.

EVALUATOR NOTE: This JPM is formatted to use either SSPS Train.

During Protected Train A weeks, use 20ST 1.12A, Train B test ani1 JPM pages 12-23.

During Protected Train B weeks, use 20ST 1.1 lA, Train A test anG JPM pages 6- 11 RECOMMENDED In Plant STARTING LOCATION:

DIRECTIONS: You are to siniulate the Main Feedwater Isolation safeguards test.

Following completion of this portion of the OST, determine if the test results satisfy the acceptance criteria.

INITIAL CONDITIONS: The plant is operating under steady-state conditions at 100% power.

All plant systems are configured in their normal system arrangement.

2 0 S T 1.11A, Safeguards Protection System Train A Blockable Test, (or 2 0 S T 1.12A, Safeguards Protection System Train B Blockable Test) is in progress and has been completed up to the beginning of Section VI1.B. Communications have been established with the control room and the front panel of the Safeguards Test Cabinet is unlocked and open.

INITIATING CUE: Your supervisor directs you continue with the test by completing Section VII.B, and when complete, determine if the test results satisf) the acceptance criteria.

REFERENCES:

20ST-1.11A Revision 15 20ST-1.12A Revision 19 TOOLS: Key #79 Train A SSPS

-or-Key #126 Train B SSPS HANDOUT: 20ST-1.llA pages 1-16 (content) and 45-46 (table 1 &table 2)

-or-20ST-1.12A pages 1-21 (content) and 51-52 (table 1 & table 2)

1/2-ADM-1301.FC I Page 5 of 2 i Revision I CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

TASK: You are to simulate the Main Feedwater Isolation safeguards test.

Following completion of this portion of the OST, determine if the tes' results satisfy the acceptance criteria.

INITIAL CONDITIONS: The plant is operating under steady-state conditions at 100%power.

All plant systems are configured in their normal system arrangement.

20ST 1.1lA, Safeguards Protection System Train A Blockable Test, (or 2 0 S T l.l2A, Safeguards Protection System Train B Blockable Test) is in progress and has been completed up to the beginning of Section VI1.B Communications have been established with the control room and the front panel of the Safeguards Test Cabinet is unlocked and open.

INITIATING CUE: Your supervisor directs you continue with the test by completing Section V1I.B. and when complete, determine if the test results satisf.'

the acceptance criteria.

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

When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

RTL#AS 640U l/Z-ADM-1301 .FC I Page 6 of 2 %

Revision OPERATIONS JOB PERFORMANCE MEASURE IJpM NUMBER: 2pL-048 JPM REVISION: 11 1 JPM TlTLE: Safeguards Test of FWI 1

I STEP STANDARD (Indicate S FOR SAT or U FOR UNSAT)a EVALUATOR NOTE: EVALUATOR NOTE:

This JPM is formatted to use Normally two operators are assigned to perform this either SSPS Train. task. One is the performer and the other is the peer checker/placekeeper. It may be necessaly to clarify the During Protected Train A expectation that the candidate will be the performer, weeks, use 2 0 S T 1.12A, and the other operator will assist in placekeeping.

Train B test and JPM pages 12-23.

During Protected Train B EV.4LUATOR CUE:

weeks, use 2 0 S T 1.11A, Unlock and open the Safeguards Test Cabinet Train A test and JPM pages [2RK*2P-TST-A]. Provide cues as appropriate.

6-11 Provide a copy of 20ST-1.11A to the candidate.

1. Notify SMKJSto make a 1.1 Candidate notifies SMAJS to make a narrative log entry of narrative log entry of relay relay inoperability and entry into Tech Spec.

inoperability and Tech Spec entry.

i EVALUATOR CUE:

Role-play S W S and acknowledge the repon AND inform the candidate that the appropriate log entries have been made COMMENTS:

RTL#A5.64OU 1R-ADM- 1301.FOf Page 8 of 2:

Revision I OPERATIONS JOB PERFORMANCE MEASURE IJPM JPM NUMBER: 2pL-048 REVISION: 11 I JPM TITLE: Safeguards Test of FWI 1

STEP ;TANDARD "C" Denotes CRIlICAL STEP ) - "S" (Indicate F O R S:Z'I' or "U" FOR [INSAT)=

1. Verify red test lamp 081 is ON. 1.1. Candidate verities red test lamp 081 is ON.

EVALUATOR CUE:

Red test lamu is ON.

-0MMENTS:

5. Verify white test lamps are i.1. Candidate verifies white test lamps 040,041,042 are OFF.

OFF.

EVALUATOR CUE:

White test lamps are OFF.

SOMMENTS:

5.C Depress and release test switch. 5.lC Candidate depresses and then releases test switch TRN A S811.

EVALUATOR CUE:

Test switch has been depressed and released.

IOMMENTS:

RTL#AS 64OU 112-ADM-1301FO'l Page 9 of 2 Revision OPERATIONS JOB PERFORMANCE MEASURE IJpM NUMBER: 2pL-048 JPM REVISION: 11 I JPM TITLE: Safeguards Test of FWI 1

STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "SvFOR SAT or "U" FOR UNSAT)a 7.C Depress each white test lamp 7.1C Candidate depresses and then releases each lamp 040,041, individually and verify each is 042 and verifies each is ON when depressed and OFF ON as depressed and OFF when when released.

released.

EVALUATOR CUE:

Lamps ON when depressed and OFF when released.

COMMENTS:

8.C Place reset test switch to 8.1C Candidate places reset test switch TRN A S821 to RESET RESET and allow it to spring and allows it to spring return to NORMAL,.

return to NORMAL.

EVALUATOR CUE:

Test switch has been RESET and has spring returned to NORMAL.

COMMENTS:

9.C Verify white test lamps. 9.1C Candidate depresses and then releases each lamp 040,041, 042 and verifies each remains OFF when depressed.

L EVALUATOR CUE:

Lamps remain OFF when depressed.

COMMENTS:

RTL#AS .640U IR-ADM- 1301.FOl Page 10 of 2:

Revision OPERATIONS JOB PERFORMANCE MEASURE STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR U N S A T H LO. Check for stuck relays. LO. 1. Candidate determines that no stuck relays are indicated an3 proceeds to the next step.

ZOMMENTS:

ll.C Place test switch in NORMAL. 11.1C Candidate places test switch TRN A S811 in NORMAL EVALUATOR CUE:

Test switch is in NORMAL.

COMMENTS:

12. Verify testmlocking lamps. 12.1. Candidate verifies white test lamps 040, 041,042 ON EVALUATOR CUE:

White test lamps are ON.

COMMENTS:

RTL#A5.640U 112-ADM-1301.FO~

Page 11 of 2 Revision OPERATIONS JOB PERFORMANCE MEASURE I.lPM NUMBER: 2pL-048 JPM REVISION: 11 I JPM TITLE: Safeguards Test of FWI STANDARD I ( "C" Denotes CRITICAL STEP ) __ (Ind~cate"S" FOK SAT o r 'TI" FOR UNSAT)

13. Verify red test lamp 081 is 13.1. Candidate verifies red test lamp 081 is OFF.

OFF.

EVALUATOR CUE:

Red test lamp 081 is OFF 13.2. Candidate contacts the control room to verify annunciato A2-2H is OFF.

EVALUATOR CUE:

Role.-play control room operator and inform the candidate that Annunciator A2-2H is OFF.

COMMENTS:

14.C Evaluate results against 14.1C Candidate evaluates results against OST acceptance acceptance criteria. criteria and determines that this portion of the OST mee the acceptance criteria.

COMMENTS:

EVALUATOR CUE:

That completes this JPM.

STOP TIME:

RTL#A5.640U 112-ADM-1301.FO.

Page 12 of 2 Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NLTMBER: 2pL-048 JPM REVISION: 11 I JPM TITLE: Safeguards Test of FWI 1

STEP STANDARD

( C Denotes CRITICAL STEP ) (Indicate S FOR SAT or UFOR UNSAT)a EVALUATOR NOTE:

Normally two operators are assigned to perform this task. One is the performer and the other is the peer checkedplacekeeper. It may be necessary to clarify the expectation that the candidate will be the performer, and the other operator will assist in placekeeping.

EVALUATOR CUE:

Unlock and open the Safeguards Test Cabinet

[2RK*2P-TST-B]. Provide cues as appropriate.

Provide a copy of 20ST-1.12A to the candidate.

1. Notify S W S to make a narrative 1.1 Candidate notifies SM/US to make a narrative log entry of log entry of relay inoperability and relay inoperability and entry into Tech Spec.

Tech Spec entry.

EVALUATOR CUE:

Role-play SMKJS and acknowledge the report AND inform the candidate that the appropriate log entries have been made COMMENTS:

RTL#AS 640U 112-ADM-1301FO I Page 14 of 2 i Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2pL-048 JPM REVISION: 11 I JPM TITLE: Safeguards Test of FWI STEP :TANDARD

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

l.C Rotate test switch to the PUSH t.lC Candidate rotates test switch TRN B S801 to the PUSH TO TEST position. TO TEST position.

EVALUATOR CUE:

Test switch is in the PUSH TO TEST position. I 1.2 Candidate contacts the control room to verify annunciator A2-2H is in alarm.

EYALUATOR CUE:

Role-play control room operator and inform the candidate that Annunciator A2-2H is IN ALARM.

ZOMMENTS:

7. Verify red test lamp 081 is ON. j. 1. Candidate verifies red test lamp 08 1 is ON.

~

EV4LUATOR CUE: Red test lamp is ON.

ZOMMENTS:

112-ADM-1301.FO Page 15 of 2 Revision I OPERATIONS JOB PERFORMANCE MEASURE I JPM NUMBER: 2pL-048 JPM REVISION: 11 I JPM TITLE: Safeguards Test of F W I STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR U N S A T ) z

5. Verify green blocking lamps are 6.1. Candidate verities green blocking lamps 001,003,005 are ON. ON.

I EVALUATOR CUE: Green blocking lamps are ON. I COMMENTS:

7.C Depress and release test switch. 7.1C Candidate depresses then releases test switch TRN B SEO1.

EVALUATOR CUE:

Test switch has been depressed and released COMMENTS:

8. Verify white test lamps are OFF. 8.1. Candidate verifies white test lamps 002, 004, 006 are OFF.

EVALUATOR CUE:

White test lamps are OFF COMMENTS:

I

RTL#AS 640U 1/2-ADM-1301 FO i Page 16 of 2 i Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2pL-048 JPM REVISION: 11 I JPM TlTLE: Safeguards Test of F W I I

( "C" Iknotcs CRITICAI. STLP J (Indicate "S" FOR SAT or "U" FOR UNSAT)=,

9.C Depress each white test lamp ).1C Candidate depresses and then releases each lamp 002,004, individually and verify each is OC16 and verifies each is ON when depressed and OFF ON as depressed and OFF when when released.

released.

EVALUATOR CUE:

Lamps ON when depressed and OFF when released.

ZOMMENTS:

10.C Place reset test switch to L0.1C Candidate places reset test switch TRN B S821 to RESET and allow it to spring RESET and allows it to spring return to NORMAL return to NORMAL.

EVALUATOR CUE:

Test switch has been RESET and has spring returned to NORMAL.

ZOMMENTS:

~ ~~

1l.C Verify white test lamps. ll.1C Candidate verifies white test lamps 002, 004, 006 ON.

EVALUATOR CUE:

White test lamps are ON.

JOMMEISTS:

112-ADM-1301.FO 1 Page 17 of 2 i Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUhU3ER jPM REVISION: 1 1 2pL-048 I JPM TITLE: S a f e y a r d s Test of FWI 1

STEP ;TANDARD

( "C" Denotes CRITICAL STEP )

L2. Check for stuck relays. 12.1. Candidate determines that no stuck relays are indicated and proceeds to the next step.

-0MMENTS:

13.C Place test switch in NORMAL. 13.1C Candidate places test switch TRN B S801 in NORMAL,.

EVALUATOR CUE:

Test switch is in NORMAL.

30MMENTS:

14. Verify testmlocking lamps L4.1. Candidate verifies green blocking lamps 001, 003, 005 are OFF.

EVALUATOR CUE:

Green Blocking lamps are OFF.

IOMMEKTS :

112-ADM-1301.FCI Page18of21 Revision I OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2pL-048 JPM REVISION: 1 1 I JPM TITLE: Safeguards Test of F W I 1

STEP STANDARD

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

15.C Rotate test switch to the PUSH 15.1C Candidate rotates test switch TRN B S802 to the PUSH TO TEST position. TO TEST position E:VALUATOR CUE:

Test switch is in the PUSH TO TEST position.

~~

COMMENTS:

16. Verify red test lamp 081 is ON. 16.1. Candidate verifies red test lamp 081 is ON.

EVALUATOR CUE:

Red test lamp is ON.

COMMENTS:

17.1. Candidate verifies green blocking lamps 001,003,005 are ON.

EVALUATOR CUE:

Green blocking lamps are ON.

COMMENTS:

RTL#A5.640U 1/2-ADM-l301.FO, Page 19 of 2 Revision OPERATIONS JOB PERFORMANCE MEASURE I JPM

.IpM NUMBER: 2pL-048 REVISION: 1 1 1 P M TITLE: Safeguards Test of F W I STEP

( "C" Denotes CRITICAL STEP )

STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=. 17

!JU 18.C Depress and hold test switch 18.1C Candidate depresses and holds test switch TRN B S802 depressed.

EVALUATOR CUE:

Test switch is being held depressed.

COMMENTS:

I 19. Verify white test lamps are OFF.

19.1 Candidate verifies white test lamps 002,004, 006 are OFF.

EVALUATOR CUE:

White test lamps are OFF.

COMMENTS:

20.C While holding the test switch 20.1C Candidate holds test switch TRN B S802 depressed AND depressed, depress each white depresses and then releases each lamp 002,004,006 and test lamp individually and verifies each is ON when depressed and OFF when verify each is ON as depressed released.

and OFF when released.

EVALUATOR CUE:

Lamps ON when depressed and OFF when released.

COMMENTS:

1/2-ADM-1301.F0i Page 20 of 2 i Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER:

JPM REVISION: 11 2pL-048 I JPM TITLE: Safeguards Test of FWI I

I STEP I STANDARD I .

!I.IC Cindidatt? relcascs u t switch TRN B SXU2.

r EVAI.UAIOK CUE:

Test switch releascd.

ZOMMENTS:

22.C Place reset test switch to RESET 22.1C Candidate places reset test switch TRN B S821 to RESET and allow it to spring return to and allows it to spring return to NORMAL.

NORMAL.

EVALUATOR CUE:

Test switch has been RESET and has spring returned to NORMAL.

ZOMMENTS:

23.1. Candidate verifies white test lamps 002,004,006 ON.

LEVALUATOR CUE:

White test lamps are ON.

ZOMMENTS:

1/2-ADM-1301.FOI Page 21 of 2 Revision OPERATIONS JOB PERFORMANCE MEASURE IJPM JpM NUMBER: 2pL-048 REVISION: 11 I JPM TITLE: Safeguards Test of FWI 1

I ( "C" Denotes CRITICAL STEP ) STANDAPD I 1 (Indicalc "S" FOK SAT or "U" FOR UNSAT)=

I I'U I

24. Check for stuck relays 24.1 Candidate determines that no stuck relays are indicated, and proceeds to the next step.

COMMENTS:

25.C Place test switch in NORMAL,. 25.1C Candidate places test TRN B S802 in NORMAL EVALUATOR CUE:

Test switch is in NORMAL.

COMMENTS:

26. Verify green blocking lamps OFF. 26.1. Candidate verifies green blocking lamps 001,003,005 are OFF.

EVALUATOR CUE:

Green blocking lamps are OFF.

COMMENTS:

1/2-ADM-1301.FO Page 22 of 2 Revision OPERATIONS JOB PERFORMANCE MEASURE 1 JPM IPMNUMBER: 2pL-048 REVISION: 11 I JPM TITLE: Safeguards Test of F W I 1

I STEP I STANDARD 1 ( C Denotes CRITICAL STEP ) (Indicate S FOR SAT or UFOR UNSAT)=.

27. Verify red test lamp 081 is OFF. 27.1. Cnndidate verifies red test lamp 081 is OFF.

EVALUATOR CUE:

Red test lamp 081 is OFF.

27.2. Candidate contacts the control room to verify annunciator A2-2H is OFF.

EVALUATOR CUE:

Role-play control room operator and inform the candidate that Annunciator A2-2H is OFF.

COMMENTS:

28. Step 28 should be N/A. 28.1. Candidate determines step B.2 was not performed and documents step 28 N/A.

COMMENTS:

112-ADM-1301 FO I Page 1 of 1 !

Revision OPERATIONS JOB PEKFORMANCE MEASURE (JPM)

TRAINING MATERIAL TITLE: Local Shutdown of 2FWE*P22 (LAW 20ST-24.4A) ___

TRAINING MATERIAL NUMBER: 2PL-069 PROGRAM TITLE: Licensed Operator Training (Retraining)

COMPUTER CODE: 2PL-069 REVISION NUMBER: 4 __

TECHNICAL

REFERENCES:

20ST-24.4A, Steam Driven Auxiliary Feed Pump [2FWE*P22] Full Flow Test, Rev. 19 20M-24.4.R, Resetting And Opening TDAFW Pump Trip And Throttle Valve, Rev. 20 INSTRUCTIONAL SETTING: Plant (Auxiliary Feed Pump Room)

APPROXIMATE DURATION: 15 Minutes PREPARED BY: R. J. Brooks r

PEER REVIEW BY: - d i - -

0 J

iz Date APPROVED FOR USE:

Training

  • '-0 I

)

Date

4ffected Training Materials:

~.of Change:

rype -

Changes Requiring Revision Changes Not Requiring Revision LisVDescription of Chang S):

Yes TRAINING MATERIAL CHANGE FORM Learning Objective Related Change?

0 The Change Does Not Impact Learning Objectives or Material Quality.

LJpdated to current procedure revision and JPM format.

Revised initial conditions to address full flow testing of 2FWE*P22 Reason for Change (s):

Add critical steps Enhance JPM New Rev. # 4 Existing Rev. # 3 New Chan e #

II2-ADM-130I.FC 1 Page 2 of 11 Revision I APPROVALS:

R. J. Brooks NOTE: Additions, deletions or Prepared by Date changes to training materials must be reviewed for their possible impact to the Training Qualification Matrix. See Training SuperintendentlSuperisoriPeer Date Incumbent Impact Review, (Changes Not Requiring Revision only) NOBP-TR-I 104.

1/2-ADM-1301 .Fa<.

Page 3 of 1:

Revision

' IpM NUMBER: 2pL-069

, JPM REVISION: 4 JPM TITLE. Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A)

EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED B' ':

0 Perform 0 Plant Site 0 AmualRequalExam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 NRc 0 Classroom 0 OJTiTPE 0 Other:

0 Training 0 Other:

EVALUATION RESULTS -

Performer Name: I Performer SSN:

rime 0 Yes Critical: [XI NO I Time:

15 Minutes Actual Time:

minutes JPM RESULTS:

0 SAT 0 mSAT (Comments required for UNSAT evaluation)

Comments:

NameiSSN: NameiSSN:

NameiSSN: NameiSSN:

112-ADM-1301 .FOL Page 4 of 1 Revision EVALUATOR DIRECTION SHEET TASK STANDARD: 2FWE*P22 tripped and Reset RECOMMENDED Auxiliary Feed Pump Room STARTING LOCATION:

DIRECTIONS: You are to simulate the task Local Shutdown of [2FWE*P22].

INITIAL CONDITIONS:

- The Plant is in Mode 3 with SG pressures at 700 psig.

20ST-23.4A Steam Driven Auxiliary Feed Pump [2FWE*P22]

Full Flow Test, is in progress and completed satisfactory througsi Part V.F.(THE PUMP IS CURRENTLY RUNNING)

NO RWDA-G Discharge Authorization was required for this evolution.

INITIATING CUE: Your supervisor directs you to perform Part G Pump Shutdown step1 .a through step 1 .e of 20ST-24.4A Steam Driven Auxiliary Feed Pump

[2FWE*P22] Full Flow Test, to shutdown [2FWE*P22].

REFERENCES:

20ST-24.4A, Rev. 19 20M-24.4.R, Rev.20 TOOLS: Hardhat, safety glasses, gloves, and Dosimetry HANDOUT: 20ST-24.4A, Part G step 1.a through 1.e (Rev. 19) 20M-24.4.R, Rev.20

112-ADM-1301.FO I Page 5 of 1 !

Revision OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

  • THIS SHEET TO BE GIVEN TO CANDIDATE
  • Read:

TASK: You are to simulate the task Local Shutdown of [2FWE*P22].

INITIAL CONDITIONS: . The Plant is in Mode 3 with SG pressures at 700 psig.

20ST-24.4A Steam Driven Auxiliary Feed Pump [2FWE*P22]

Full Flow Test. is in progress and completed satisfactory throupi Part V.F.(THE PUMP IS CURRENTLY RUNNING)

. NO RWDA-G Discharge Authorization was required for this evolution.

INITLATING CUE: Your supervisor directs you to perform Part G Pump Shutdown step1 a through step 1 .e of 20ST-24.4A Steam Driven Auxiliary Feed Pump

[2FWE*P22] Full Flow Test, to shutdown [2FWE*P22].

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

When satisfied that you understand the assigned task, announce "I am now beginning the JPM" Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations, After determining the Task has been met announce " I have completed the JPM",

Then hand this sheet to the evaluator.

1R-ADM-1301.FO.

Page 6 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE I NUMBER: 2pL-069 JPM REVISION: 4 1 JPM TITLE: Locai Shutdown of 2FWE*P22 (IAW 20ST-24.4A)

STEP

( "C"Denotes CRITICAL STEP )

STANDAFD (Indicate "S" FOR SAT or "U" FOR IJNSAT)=, 17 SW START TIME:

EVALUATOR CUE:

For exam sequencing this step may be omitted, the

<:valuatormay provide a copy of the procedure.

1. Obtain procedure 20M-24.4.A. I. Candidate locates 20M-24.4.A ZOMMENTS:

l.C Stop [2FWE*P22] by pressing 1.1 Locates the Emergency Trip Manual Lever.

the Emergency Trip Manual Lever. 1.2C Presses the Emergency Trip Manual Lever.

1.3 Verifies that the pump shaft has stopped rotating.

EVALUATOR CUE:

The pump shaft has stopped rotating 30MMENTS:

2.C Close the following valves:  !. 1 C Contacts the control room and requests operator to clo:

(BB-C) [2MSS*SOV105A], Turb Driven AFW Pump Stm Hdr SlJPp~YIS01 VlV.

[2MSS*SOVIOSA], Turh Driven [2MSS*SOVIOSD], Turh Driven AFW Pump Stm Hdr AFW Pump Stm Hdr A Supply Isol Supply Is01 Vlv.

Vlv.

[2MSS*SOV105D], Turh Driven EVALUATOR CUE:

AFW Pump Stm Hdr A Supply Is01 Role-play the control room operator and inform the candidate that [2MSS*SOV105A], Turb Driven AFW Pump Stm Hdr A Supply Isol Vlv. AND

[2MSS*SOVlOSD], Turb Driven AFW Pump Stm Hdr A Supply Is01 Vlv. are CLOSED.

ZOMMENTS:

112-ADM-1301.FOI Page 7 of 1 !

Revision .

OPERATIONS JOB PERFORMANCE MEASURE IJPMNUMBER: 2pL-069 JPM REVISION: 4 1 JPM TITLE: Local Shutdown of 2FWE*P22 (IAW 20ST-24.4.4) 1 STEP STANDARD

( CDenotes CRITICAL STEP ) (Indicate S FOR SAT or U FOR UNSAT)a

3. Initiate Part I, Plant Restoration, concurrently with EVALIJATOR CUE:

the remaining steps in this part Role-play the Unit supervisor and inform the of the test (Part G) and Part H, candidate that another operator will complete (Part Remote Closed Position ( 3 ) and Part H, Remote Closed Position Verification of Verification of [2MSSfSOV105A, B and C].

[2MSS*SOVIO5A, B and C].

1. Record the necessary VIA NO RWDA-G in progress information for stopping the discharge on the RWDA-G, Discharge Authorization. (NIA if RWDA-G is NOT required)

ZOMMEUTS:

5. WHEN the pump shaft has NIA Pump previously verified to be stopped come to a complete stop, Reset

[2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, in accordance with 2 0 M -

24.4.R, Resetting and Opening COMMENTS:

TDAFW Pump Trip and Throttle Valve.

112-ADM-1301FO Page 8 of 1 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE!

JPM NUMBER: 2PL-069 JPM REVISION: 4 I JPM TITLE: Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A) 1 STEP STANDAFD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR U N S A T p

6. Locates procedure 20M- 6.1 Candidate locates 20M-24.4.R 24.4.R, "Resetting and Opening TDAFW Pump Trip and Throttle Valve" and reviews initial conditions, and P&Ls COMMENTS:
7. Verify closed 7.1 Candidate contacts Control Room to determine valve

[2MSS*SOVlOSA-F] positions.

EVALIJATOR CUE:

All of the steam supply SOV's, [2MSS*SOVlOSA, H. C. D. E. F1. are CLOSED.

COMMENTS:

112-ADM-I301 FO, Page 9 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2pL-069 JPM REVISION: 4 STEP JPM TITLE: Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A)

STANDARD 7 1

1

( "C" Denotes CRITICAL STEP )

8. Verify tripped or depress 8.1 NIA Previously performed Manual Emergency Trip Lever.

COMMENTS:

Verify [2FWEfTTV22] Trip 9.1 Candidate locates latch hook and verifies that the trip Throttle valve is unlatched. lever is not engaged.

EVALUATOR CUE:

Trip Throttle Valve is NOT ENGAGED. (Brass sleeve is full down)

COMMENTS:

112-ADM-1301.FOL Page 10 of 1:'

Revision ~

OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2pL-069 JPM REVISION: 4 I JPM TITLE: Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A) 1 STEP

( "C" Denotes CRITICAL STEP )

STANDARD (Indicate "S" FOR SAT or "U" FOR U N S A T p 11 SU 10.C Reset and latch the overspeed 1 EVALUATOR CUE:

The Turbine Driven Aux Feed pump will NOT be started within the next 15-20 minutes.

10.1C Candidate turns the handwheel CLOCKWISE until the trip device sliding nut and lever raise to the trip hook.

1 EVALUATOR CUE:

Brass Sliding nut and lever are all the way up.

10.2C Candidate locates and holds the overspeed trip connecting rod to the left, while ensuring the overspeed tappet washer f i t side directly faces the overspeed trip lever.

EVALUATOR CUE:

l r i p Lever is to the LEFT and ENGAGED in the trip hook with flat side tappet washer directly facing the Overspeed Trip Lever.

10.3C Candidate releases the connecting rod, allowing spring tension to maintain the reset condition.

CUE:

After candidate releases the connecting rod the Overmeed Trio remains RESET.

10.4 Candidate ensures the washer flat side is flush against the vertical side overspeed trip lever.

10.5 1 EVALUATOR CUE:

Washer flat side is flush against the overspeed trip lever vertical side.

Candidate verifies valve is latched by observing that the latch on the right side of the valve is fully engaged.

EVALUATOR CUE:

The latch is FULLY ENGAGED COMMENTS:

112-ADM-1301.FO' Page 11 of 1.

Revision OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2pL-069 JPM REVISION: 4 I JPM TITLE: Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A)

TEP STANDARD "C" Denotes CRITICAL STEP ) (Indicate '3"FOR SAT or "U" FOR UNSAT)a 1.C Reopen Trip Throttle Valve 1I .lC Candidate locates 12FWE*TTV221 and turns handwheel C(3W until it stops in the full open position.

EVALIJATOR CUE:

[2FWE*TTV22] is FULL OPEN.

11.2 Candidate verifies that the pump does not accelerate in an ur.controlled manner.

EVALUATOR CUE:

The pump slowly rotates as you open the Trip 1 I

EVALUATOR CUE:

Acknowledge request for concurrent verification of t.he valve, inform candidate that other operators will perform this function using step 11 of the procedure.

Direct candidate to continue with step 8.

11.3 Candidate adjusts the valve 1/4 turn off the backseat.

EVALUATOR CUE:

Valve is 114 Turn off its backseat.

11.4 Candidate verifies that the overspeed trip mechanism is reset by observing that the flat side of the washer remains engaged with the trip lever.

11.5 LEVALIJATOR CUE:

Hat side of the washer remains engaged with the trip lever Cmdidate contacts the control room to verify that computer point Y5 172D indicates OPER.

Role-play Control Room operator and inform the indicates OPER.

COMMENTS:

112-ADM-1301.FO Page 12 of 1 Revision OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2pL-069 JPM REVISION: 4 I JPM TITLE: Loca. Shutdown of 2FWE*P22 (IAW 20ST-24.4A)

~-

STEP ;TANDAFD

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

EVALUATOR CUE:

IF necessary, Role-play the Unit Supervisor and inform the candidate that the Governor Oil Pressure was NOT previously relieved.

12.C Relieve governor oil pressure. 12.1 Candidate removes access cover to [2FWE-2CSSOVIOl].

EVALUATOR CUE:

Cover is removed.

2.2C Candidate simultaneously . depresses

. both pushbuttons until governor linkage movement has ceased and pushbuttons have been held for 15 seconds.

All linkage movement has stopped, 15 seconds has elapsed.

12.3 Candidate replaces access cover to [2FWE-2CSSOV101].

EVALUATOR CUE:

is re-installed.

12.4 Candidate notifies Control Room that [2FWE*P22] is available EOMMEXTS:

EVALUATOR CUE:

That completes this JPM.

STOP TIME:

1/2-ADM-l301 .FDi Page 1 of 11 Revision i OPERATIONS JOB PERFORMANCE MEASURE (JPM)

TR WING TERIAL TITLE: Locally Start the No.1(2) Emergency Diesel Generator -

TRAINING MATERIAL NUMBER: 2PL-606 -

PROGRAM TITLE: Licensed Operator Training -

COMPUTER CODE: 2PL-606 -

REVISION NUMBER: 1 -

TECHNICAL

REFERENCES:

20M-53A.l.A-1.5, Local Action to Restore AC Power, Issue lC, Revision 5 INSTRUCTIONAL SE7TING: In Plant c

APPROXIMATE DURATION: 15 Minutes

/

0 . e, t PREPARED BY: R. J. Brooks -- 4

/ Date

/

+--

t --,

PEER REVIEW BY: -

rC - Date

-\t J

0 4 APPROVED FOR USE: ti-8 4 -

Training Supervisor -.fignee Date 4

LIZ-ADM- 1301.F04 Page 2 of 11 Revision 1 TRAINING MATERIAL CHANGE FORM Affected Training Materials: 2PL-606 Type of Change:

Changes Requiring I Learning Objective Related Change? New Rev. # 1 Revision Yes !xi No Changes Not The Change Does Not Impact Learning Existing Rev. # 0 Requiring Revision Objectives or Material Quality.

New Change #

Reason for Change (s):

JPM Enhancement changes to training materials R. J. Brooks must be reviewed for their Prepared by Date possible impact to the Training Qualification Matrix. See Incumbent Impact Review, NOBP-TR-1104.

Training Superintendent/Supervisormeer Date (Changes Not Requiring Revision only)

1/2-ADM-l301.FI 4 Page 3 of 1 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2pL-606 JPM REVISION: 1 I JPM TITLE: Locally Start the No. l(2) Emergency Diesel Generator 1

WA

REFERENCE:

064A4.01 4.0/4.3 TASK ID: 0362-003-01-043 055EA1.01 4.314.4 JPM APPLICATION: REQUALIFICATION INITIAL EXAM 0 TRAINING FAULTEDJPM 0 ADMINISTRATIVE JPM EVALUATION RESULTS 1 Performer Name: I I

Performer SSN:

Time Critical: [XI No Yes I ~llotted Time:

I 20 minutes Actual Time:

minutes JPM RESULTS:

0 SAT UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS 1 NameISSN: I Name/SSN:

I

~~ ~~ ~~~

NameISSN: NamelSSN:

1 I Evaluator (Print): Date:

'valuator Signature:

112-ADM-1301.FOi Page 4 of 1 Revision EVALUATOR DIRECTION SHEET TASK STANDARD: Locally start the No. l(2) Diesel Generator.

RECOMMENDED In Plant STARTING LOCATION:

EVALUATOR NOTE: This JPM is designed for either Train. Perform on Diesel Generator k 2 if Protected Train A and on Diesel Generator #1 if Protected Train B.

Train B equipment in parentheses.

DIRECTIONS: You are to simulate the task locally start the No. l(2) Emergency Diesel Generator.

INITIAL CONDITIONS: A station blackout has occurred. OM-53A Procedure ECA-0.0, Loss of All AC Power, has led the crew to the step which requires local action to restore power. 2SWS*P21A(B) control switch is in AUTO.

INITIATING CUE: Your supervisor directs you to use Attachment A-1.5 of ECA-0.0 to locally start the No. l(2) Diesel Generator and energize the 2AE(2DF) bus, but to not load equipment onto the bus. You are given the key for the Diesel Generator (use of keys will be simulated).

REFERENCES:

20M-53A.l.A-1.5, Local Actions to Restore AC Power, Issue IC, Revision 5 TOOLS: Key 138 for Excitation Panel will be provided when needed Key for Local Start will be simulated (SR 27/28)

HANDOUT: 20M-53A.l.A-1.5, Local Actions to Restore AC Power, Issue lC, Revision 5

1/2-ADM-1301.FI 4 Page 5 of 1 Revisior 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE: DIRECTION SHEET Use this sheet if Protected Train "A"

  • THIS SHEET TO RE GIVEN TO CANDIDATE
  • 0 Read:

TASK: Locally start No. 2 Diesel Generator INITIAL CONDITIONS: A station blackout has occurred. OM-53A Procedure ECA-0.0, "Loss of All AC Power," has led the crew to the step which requires local action to restore power. 2SWS*P21B control switch is in AUTO.

W I A T I N G CUE: Your supervisor directs you to use Attachment A-1.5 of ECA-0.0 to locally start the No. 2 Diesel Generator and energize the 2DF bus, but do not load equipment onto the bus. You are given the key for the Diesel Generator (use of keys will be simulated).

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

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

Simulate performance or perform as directed the required task.

0 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".

0 Then hand this sheet to the evaluator.

112-ADM-1301.F I4 Page 6 of 1 Revisioi 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET Use this sheet if Protected Train B

  • THIS SHEET TO 13E GIVEN TO CANDIDATE
  • Read:

TASK: Locally start No. 1 Diesel Generator INITIAL CONDITIONS: A station blackout has occurred. OM-53A Procedure ECA-0.0, Los,.

of All AC Power, has led the crew to the step which requires local action to restore power. 2SWS*P21A control switch is in AUTO.

INITIATING CUE: Your supervisor directs you to use Attachment A-1.5 of ECA-0.0 to locally start the No. 1 Diesel Generator and energize the 2AE bus, but do not load equipment onto the bus. You are given the key for the Diesel Generator (use of keys will be simulated).

c] At this time, ask the evaluator any questions you have on this JPM When satisfied that you understand the assigned task, announce Iam now beginning the J P M Simulate performance or perform as directed the required task.

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

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

Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F 14 Page 7 of 1 Revisior 1 OPERATIONS JOB PERFORMANCE MEASURE I JpM NUMBER: 2pL-606 TPMREVTSTON. 1 1 JPM TITLE: Locally Start the No. l(2) Emergency Diesel Generator 1

STEP STANDARD (Indicate "S" FOR SAT or "U" FOR U N S A T h I?

SILI START TIME:

EVALUATOR NOTE:

A copy of the procedure can be given to the candidate if starting in plant. Key #138 will be needed for the Excitation Panel. Provide key when candidate needs to get into the panel. Uses of AutoLocal key will be simulated.

1. Place Auto-Local Selector 1.1 Candidate locates Auto-Local Control key switch.

Switch in the LOCAL position.

1.2 Inserts key and places in the LOCAL. position.

EVALUATOR CUE:

Diesel Generator is in LOCAL.

COMMENTS:

l. Verify following alarms are not 2.1 Candidate locates Alarm Panel lit: Engine Overspeed and Start Failure. 2.2 Verifies Engine Overspeed and Start Failure alarms not lit.

EVALUATOR CUE:

No alarms present.

COMMENTS:

RTL#A5.640U 112-ADM-1301.F )4 Page 8 of 1 Revisioi 1 OPERATIONS JOB PERFORMANCE MEASURE IJPM REVISION: 1 2pL-606 1 JPM TITLE: Locally Start the No. l(2) Emergency Diesel Generator 7

STEP STANDARD

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

3. Depress one local start 3.1 Candidate locates Start Pushbutton, Start 1 or Start 2 pushbutton and maintain it depressed until the diesel starts 3.2 Depresses it until engine starts and is self-sustaining and and is self-sustaining and then then releases.

release pushbutton. EVALUATOR CUE:

Diesel starts and is self-sustaining at 525 rpm.

COMMENTS:

1.C Adjust Diesel Generator speed 4.1 Candidate locates Governor Raise-Lower control and using governor raise-lower speed indication.

control to establish an operating speed of approximately 5 14 4.2C Candidate simulates turning Governor Raise-Lower to rpm (510 to 520 rpm) "Lower" position to decrease speed to 514 rpm.

4.3 Verifies Engine speed at appx. 514 rpm.

EVALUATOR CUE:

Diesel speed is 514 rpm. (510-520).

COMMENTS:

RTL#A5.640U 112-ADM-1301.F 14 Page 9 of 1 Revisior 1 OPERATIONS JOB PERFORMANCE MEASURE lJpM NUMBER: 2pL-606 JPM REVISION: 1 1 JPM TITLE: Locidly Start the No. l(2) Emergency Diesel Generator STEP STANDARD

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

i. Verify Diesel Generator Volts i.1 Candidate locates Diesel Generator Voltmeter.

greater than 4160 VAC.

i.2 Verifies Engine voltage greater than 4160 VAC.

EVALUATOR CUE:

Diesel Generator Voltage is ZERO.

30MMENTS:

5.C Response to failure of 5.1 Candidate calls control room.

Automatic Field Flash 5.2. Candidate has operator flash generator field from bench hoard

~

EVALUATOR CUE:

Role-play Control room operator and inform the candidate the control room has attempted to flash the field, HOWEVER, Diesel Generator Voltage is still ZERO.

5.3 Candidate locates the K2 field flash contactor inside cab.

[PNL-2DIGEN-IA (2A)]

5.4c Candidate simulates DEPRESSING the White Stabs on the K2 Field Flash Contactor until the voltmeter shows a rapid rise.

EVALUATOR CUE:

Diesel Generator Voltage is now indicating -4160 VAC and stable.

COMMENTS:

1/2-ADM-1301.F 14 Page 10 of 1 Revisior 1 OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2pL-606 J P M REVISION: 1 I J P M TITLE: Locally Start the No. l(2) Emergency Diesel Generator 7

STEP STANDARD

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

7. Attempt to Restore Diesel '. 1 Candidate locates Auto-Local key switch.

Generator Control to the Control Room. '.2 VerifiesPlaces it to AUTO.

EVALUATOR CUE:

Auto-Local key switch is in AUTO.

IF necessary, Role-play the Control Room and confirm control of Diesel Generator in the control room.

I 30MMENTS:

8. Request Control Room 3. 1 Candidate contacts Control Room.

Operator verify open or open emergency bus tie breaker. 3.2 Has operator open or verify open 2E7(2F7) and 2.4lO(2D 10)

EVALUATOR CUE:

Control Room reports both breakers open.

IOMMENTS:

I

RTL#A5.640U 112-ADM-1301.F 14 Page 11 of 1 Revisior 1 OPERATIONS JOB PERFORMANCE MEASURE IJPM NUMBER: 2pL-606 JPM REVISION: 1 1 JPM TITLE: Locally Start the No. l(2) Emergency Diesel Generator 7

iTEP STANDARD "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)a

).C Request Control Room operator 9.1 Candidate contacts Control Room.

close Diesel Generator Output Breaker 2E10(2F10). 9.2C Candidate has operator close Diesel Generator Output breaker.

EVALUATOR CUE:

ACB 2E10(2F10) is closed.

COMMENTS:

STOP TIME:

Appendix D Scenario

______ Outline Form ES-D-1 Tacility: BVPS 2 Scenario No.: 1 Op Test No.: NRC Sxaminers: Candidates: SRO ATC

- BOP

nitial BOL, -5% power following Xe free SIU, CB D = 104, 2003 PPM IC-165 Zonditions

rumover: Continue plant startup 1.4W 20M-52.4.A. [2SAS-C21B] Station Air Compressor OOS, will not be returned this shift lritical Tasks: 1. E-0.1 Crew establishes flow from at least one high head ECCS pump before transition out of E-0.

2. E-O.P Crew manually actwtes main steam line isolation before a Severe (orange path) challenye develops to either the Sub-criticality or Integrity CSF or before transition to ECA-2.1, whichever occurs first.
3. E-2.A Crew isolates the faulted SG and directs operator to close isolation valve(s) operated from outside of the control room before transition out of E-2.

Event Malf. No. Event Type Event Description Crew raises power IAW procedure (Must raise power above 10% before N-36 failure) 2 NIS07B SRO T S . IRNl N-36 Intermediate Range Nuclear Instrument Inst Pwr fuse blows 3 XMT-RCS019A I(RO/SRO) [2RCS*LT459] Controlling P E R Level Channel fails low, LID isolates SRO T S .

4 N(RO/SRO) Alternate channel selected and L/D restored 5 CNH-CFW 15B C(B0PISROi C BPFRV fails open in auto, manual control required 6 MSSOlC M(ALL) Steam leak inside CNMT slowly progresses to Steam line RUPTURE inside CNMT, SI, CIA, ClB 7 PMP-CHS002 C(ROISR0) [2CHS*P21B] HHSI Pump trips on SI

[2CHS*P21A] HHSI pump Fails to AUTO, PPL07A requires manual start on SI 8 PPLl OA C(BOP/SRO) AUTO MSLI failure BOTH Trains, requires manual actuation PPLl OB (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1

Scenario Summary Scenario 1 The crew will assume the shift at approximately 5% power BOL, with station air compressor 2SAS-C21B 00s. Crew instructions are to continue the plant start-up. The crew will perform a Normal Power Increase to > 10%. When power is greater than IO%,

the instrument power fuse will fail on lntermediate Range Channel N-36. The crew will respond to the annunciators and implem,mt the actions of AOP 2.2.1B, Intermediate Range Channel Malfunction. After the t J S implements the required Technical Specification actions, the controlling channel of P E R level [2RCS*LT459] will FAIL LOW causing letdown isolation. The crew will respond to the annunciators and implement the actions of instrument failire procedure OM 2.6.4.IF ATT # l . After stabilizing the plant, letdown will be resrored IAW normal operating procedure 2 0 M -

7.4.AB, Restoring Charging and Letdown. After the US implements the required Technical Specification actions C BPFRV will FAIL OPEN in automatic. The crew will be required to take manual control of C BPFRV to restore and maintain SG level.

After SG levels are stabilized, a steam leak will develop inside containment. The leak will slowly progress to a full steam line RUPTURE causing RX TRIP, SI, CIA and CIB.

The crew will respond by implementing the actions of E-0, Reactor Trip or Safety Injection. The actions of E-0, Reactor Trip or Safety Injection will be complicated by HHSI pump 21B tripping after the SI start signal and HHSI pump 21A failing to atitomatically start on the receipt ofthe SI signal. The crew must identify these failures and manually start the 21 A HHSI pump. The crew must then diagnosis the faulted SG and transition into E-2, Faulted SG Isolation. The actions of E-2, Faulted SG Isolation will be complicated by a failure of SLI. The crew must identify this failure and manually initiate SLI. After completing the actions of E-2, Faulted SG Isolation the crew must determine that the SI termination criteria have been met and transition into ES-1.1, SI Tennination. After the crew has termina:ed HHSI flow the scenario will be terminated.

EOP Flow Path:

E-0, Reactor Trip or Safety Injection + E-2, Faulted Steam Generator Isolation -z ES-1.1, SI Tennination.

BVPS - 2 Scenario 1 2 of 26 Rev. 1 (45 day submittal)

BEAVER VALLE .OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: Approx 5% Power, CBD = 104, XE increasing from XE frec S / U , BOL, 2003 PPM Boron, IC-165 ADDITIONAL LINEUP CHANGES STlCKERS VOND MARKINGS ~

[2SAS-C21B] - PTL DANGER EQUIPMENT STATUS DATEITIME 00s TECHNICAL SPECIFICATION(S1 .

[2SAS-C21B] 1 week ago NIA SHIFT TURNOVER INFORMATION

1. Protected Train is Train B
2. [2SAS-C21B] undergoing a compressor overhaul, will not be returned until 3 days from now
3. [2FWS-P21 A] operating, SG levels maintained via BPFRVs operating in AUTO
4. Continue plant SiLT IAW 20M-52.4.A step 6
5. Reactor Engineering has provided the reactivity plan Tor the continuation of the startup SCENARIO SUPPORT MATERIAL REOUIRED Reactivity plan placard for BOL 20M-52.4.A signed-off through step 5 .

Placard for [2FWE*P22] position stating [2FWE*P22] is aligned to A header Place plaque on wall for Protected Train B BVPS - 2 Scenario 1 3 of 26 Rev. 1 (45 day submittal)

BEAVER VALLE , .OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina Initialire IC Set 165, and establish Reactor plant at approx 5% power, BOL, initial plant conditions. equilibrium conditions. RCS boron 2003 PPM, CBD = 104 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this drill drill:

IMF PMP-CAS004 (0 0) 1 [2SAS-C21B] 00s IMFPPl.IOA(O0) Prevent auto MSLI Tm A IMF PPI .I nB (0 0) Prevent auto MSLI Tm B TRGSET 1 JPPLSI(1) == 1 Set trigger 1 on SI actuation IMF PMP-CHS002 (1 0) 1 [2CHS*P?I B] trips on SI initiation IMF PPL07A (0 0) 0 [2CHS*P21A] fails to auto start on SI initiation, manual start required TRG 1 IMFMSSOlC 1E7 C Steam line rupture inside CNMT on SI actuation TRGSET 2 MCRFNS(3) <= 225 Set trigger 2 on reactor trip TRG 2 IMF MSSOlC 1E7 C Steam line rupture inside CNMT on reactor trip TRGSET 3 TPCSTAAU <= 547 Set trigger 3 on Tavg < 547F TRG 3 IMF MSSOlC 1E7 C Steam line rupture inside CNMT when Tavg decreases below 547F BAT STUFFON.DAT Horns, Printers, Sounds ready BVPS - 2 Scenario 1 4 of 26 Rev. 1 (45 day submittal)

BEAVER VALLE. .'OWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE Assign shift positions SM:

us:

RO:

BOP:

STA:

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

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

place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 1 5 Of 26 Rev. 1 (45 day submittal)

BEAVER VALLE. ,'OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina EVENT #1:

Normal Power Increase to > 10% US directs crew to conduct power increase IAW 20M-52.4.A and the reactivity plan provided by Reactor Engineering BOP Raises turbine reference and setter to raise turbine power.

RO dilutesiwithdraws rods to raise reactor Dower.

Continue with next event AFTER IRNI High Flux Trip has been blocked above 10% AND LE discretion EVENT #2:

IRNI N-36 Instrument power fuse blows IMF NIS07B (0 0) 0 lMMEDlATE PLANT RESPONSE: RO verifies alarms, diagnose failure of N-36 A4-4E NIS DETECTOR IRNI COMPENSATOR TROUBLE (V0139D, V0132D)

[2NMI-NI36B] Intermediate range current indicates low (BB B) Crew identities blown fuse N-36 meter at NIS racks indicates low h i . 7 ~l n c + PIIIrf,lro fnA-,-.+.x hI-7. -

BVPS - 2 Scenario 1 6 of 26 Rev. 1 (45 day submittal)

LOSS OF DETECTOR VOLTS LIT ~

Crew refers to ARP and AOP 2.2.1B LOSS OF COMP VOLTS LIT ~

BB B Status panel 308 LIGHT C- I O

~

LIT NO PLANT TRANSIENT Operable recorders selected on VB B RO verifies operable recorders selected to VB B recorders MODE 1 operation US refers to TS 3.3.3 for post acc monitoring (when time permits)

Plant is above P10 US directs actions IAW step 6 based on current plant operating conditions Both IRNIS block switches to BLOCK RO blocks both IRNIS Rod Stop and position Reactor Trip functions (previously performed)

BVPS - 2 Scenario 1 7 of 26 Rev. 1 (45 day submittal)

BEAVER VALLE .TOWERSTATION I

112-ADM-1357 Conduct of Simulator Trainina Caution tags in place to prompt MANUAL RO places caution tags on both SRNl Unblock of S R N l on plant SID BlocWReset switches US directs continued plant operations and continue power increase Ann A4-5F NIS INT RANGE HIGH Crew bypasses reactor trip function by FLUX ROD WTTHDRAWL STOP placing LEVEL TRIP switch of inoperable actuates channel in BYPASS position Ann A4-5E NIS SOURCEIINT RANGE HIGH FLUX TRIP BYPASS LIT ~

(N0096D) TRIPPED

~

Status light LEVEL TRIP BYPASS -

LIT Caution tag in place BOP places Caution Tag on Level Trip switch for N-35 Power increase continues Crew continues power increase IAW 2 0 M -

52.4.A and reactivity plan EVENT #3:

Power increase continues Continue with next event at LE discretion BVPS - 2 Scenario 1 8 of 26 Rev. 1 (45 day submittal)

BEAVER VALLE. ,,OWER STATION 112 - ADM - 1357 Conduct of Simulator Training EVENT #4:

PZR level Xmitter [2RCS*LT459] fails low IMF XMT RCS019A (0 0) 0 PZR level transmitter [2RCS*LT459] fails RO recognizes problem with PZR lcvel low. channel, informs US that [2RCS*LT459]

IMMEDIATE PLANT RESPONSE: failed low.

A4-1C PZR CONTROL LEVEL DEVIATION LOW (L0493D)

A+lD PZR CONTROL LEVEL LO%' KO p l x e s jiTiS"FCVii2j in manual to (LO491D) reduce charging flow and control PZR level

[2CHS*LCV460A],

[2CHS*AOV200A,B,C]close PZR heaters off.

Crew refers to AFS' and OM 2.6.4.IF ATT

  1. 1, US directs operator to defeat level control input with PZR level channel and recorder selector switches.

Level alarms clear, charging flow reduces, RO places Channels 460 and 461 in service.

high flow alarm clears.

Adequate M/U to VCT exists RO verities MIU to VCT BVPS - 2 Scenario 1 9 Of 26 Rev. 1 (45 day submittal)

BEAVER VALLk , :OWER STATION 112 - ADM - 1357 Conduct of Simulator Training PZR heaters energized as desired RO places PZR heaters in operation as necessary to restore normal PZR pressure control US directs operators to restore Letdown flow IAW 20M-7.4.AB

[2CHS*FCV122] - CLOSED RO places [2CHS*FCV122] in manual and closes the valve

[2CHS*MOV289] - OPEN RO verifies [2CHS*MOV289] open 12CHS*MOV3 101 - OPEN RO verifies [2CHS*MOV3101 open

[2CHS*FCVI 221 throttled to ohtain 311 ~

RO throttles charging pump discharge flow 50 gpm on [2CHS*FIl22] (VB A) control valve open to provide 30 - 50 gpm flow as indicated on [2CHS*FI122] (VB A)

[2CHS*AOV200A, B, C] - CLOSED RO verifies 3 L/D isolation valves are closed

[2CHS*AOV204] - OPEN RO verifies the NRHX L/D inlet valve is open (BB A)

[2CHS*PCV145] IN MANUAL AND RO place NRHX Disch Pres control valve ADJUSTED TO 50% OPEN DEMAND in MANUAL and adjusts for 50% output SIGNAL (BB A) demand BVPS - 2 Scenario 1 10 of 26 Rev. 1 (45 day submittal)

[2CHS*MOVlOOA] OPEN RO verifies positions of

[2CHS*MOVIOOB] CLOSED ~

[2CHS*MOVlOOA], [2CHS*MOVl OOB]

[2CHS*LCV460A, B] - OPEN RO verifies Regen HX LID Inlet valves open

[2CHS*AOV200A, B] - OPEN RO opens LID isol valves to establish LID flow at previous value

[2CHS*PCV145] adjusted to maintain 260 RO establishes automatic control of letdown psig as indicated on [2CHS*P!145] flO\V SETPOINT of [2CHS*PCV145] SET ~

FOR ~ ~ P S I G

[2CHS*PCV145] PLACED IN AUTO

~

[2CHS*FCV122] S PLACED IN AUTO PZR level trending to normal RO monitors PZR level for proper response US refers to TS. 3.3.1 Table 3.3.1-1 Function 9, Condition K: Place channel in trip Wl16 hrs Reduce THERMAL POWER to <P7 WII 12 hrs TS 3.3.4 and Bases Table B3.3.4 Function 4.a: Remote S/D Indication and Controls requires 1 channel nfP7R !eve1 operable BVPS - 2 Scenario 1 11 of26 Rev. 1 (45 day submittal)

BEAVER VALLE, , .OWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE TS 3.3.3 Table 3.3.3-1 Function 1 1 Condition E: As required by Action D.l and referenced in Table 3.3.1-1 Condition E.l: Be in MODE 3 - 6 hrs AND Condition E.2: Be in MODE 4 ~ 12 hrs RO informs the US that letdown has been reestablished.

IF DESIRED use the following to tnp US directs operators to trip appropriate histable per 2MSP-6.23-1: histahle.

IRF LOA-PCS001 (0 0) 1 Protection rack C1 door open.

IMF BST-PCS097 (0 0) 0 2LS/459A-1 (442, BS-1) hi level trip US notifies I&C of problem.

IRF LOA-PCS001 (0 0) 0 Protection rack C1 door closed.

Infonn crew that bistable is tripped US is informed that bistable is tripped Continue next event when letdown is reestablished OR at LE discretion BVPS - 2 Scenario 1 12 of 26 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE EVENT #5:

C BPFRV Controller fails to 100%

IMF CNH-CFWISB (0 0) 100 C BPFRV Controller fails to 100%

IMMEDIATE PLANT RESPONSE: BOP identifies problem with C SG level

[2FWS*FCV499] travels to the fully open control, reports to the crew position Ab-l1F LOOP C FEEDWATER FLOW >

STEGM FLOW (F0477D)

CSC NR LEVEL ( 3 klicatui> VR C) increases rapidly RCS Tavg bcgins to rcducc (3 indicators, 1 recorder VB B)

A6-I 1E SG 21C LEVEL DEVIATION FROM SETPOINT (L0479D)

[2FWS*FCV499] in manual & throttled US directs BOP to take manual control of closed C BPFRV and restore level C SG level returning to normal Crew refers to ARPs Continue with next event at LE discrction BVPS - 2 Scenario 1 13 of 26 Rev. 1 (45 day submittal)

BEAVER VALLE . :OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Trainina INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTEDSTUDENTRESPONSE EVENT #6:

Steam leak develops in CNMT on C SG over a ten minute period IMF MSSOlC (0 0) 1 E6 600 Steam leak develops on C SG IMMEDIATE PLANT RESPONSE:

CNMT Temp, Pres and Humidity slowly Crew notes alarms, diagnose steam leak increase (indicators VB A) inside CNMT AI-1E CONTAINMENT AIR PRESSURE HIGHILOW (Y5023D, GCP031)

A2-2B UNIDENTIFIED LEAKAGE SYSTEM TROUBLE A 1- 1 F CONTAINMENT AIR AVERAGE TEMP HIGH/LOW (Y5022D)

AI-2G INCORE INST ROOMICNMT SUMP LEVEL HIGHiVALVE N O 1 RESET (L0002D)

CNMT condition continue to degrade US directs manual reactor trip manual SI due to degrading plantiCNMT conditions Crew enters E-0, performs immediate Crew performs IMAs of E-0.

operator actions.

BVPS - 2 Scenario 1 14 of 26 Rev. 1 (45day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - BOTH BOP verifies power to AC Emergency ENERGIZED Buses.

Check SI .- ACTUATED RO checks SI status CNMT Pressure - > 5PSIG PZR Pressure - < 1860 PSIG SG Steam Pressure - < 500 PSIG Crew continues E-0 Manually actuate SI (both trains) RO manually actuates SI both trains Alert Plant Personnel RO/BOP sound Standby Alarm, announce reactor trip and safety in;ectioc BVPS - 2 Scenario 1 15 of 26 Rev. 1 (45 day submittal)

BEAVER VALLE , . .OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTEDSTUDENTRESPONSE Check [2HVS*FN204A(B)], Leak BOP checks Leak Collection Exhaust Fan Collection Filtered Exhaust Fan - AT status LEAST ONE RUNNING CRITICAL TASK Charging Pumps NONE RUNNING

~ RO verifies SI System status Crew establishes flow from at least one [2CHShP21B] TRIPPED ON SI RO reports trip of [2CHS*P21B]

high head ECCS pump bcforc transition [2CHS*P21A] - REQUIRED MANUAL RO reports manual start of [2CHS*P21A]

out of E-0. START required Charging Pumps ONE RUNNING

~

HHSI Flow INDICATED

~

LHSI Pumps TWO RUNNING

~

Motor-driven AFW Pumps RUNNING BOP verifies AFW System status Turb driven AFW Pump Stm Supply lsol Valves OPEN

~

AFW Throttle Vlvs - FULL OPEN Total AFW Flow GREATER THAN 340

~

GPM Perform Attachment A-0.11 Verification US directs performance of Attachment A-Of Automatic Actions in a timely manner 0.1 I when timelmanpower permit Attachment A-0.11 included with scenario beginning on Pg 2 1 RCPs OPERATING -.- MONITOR Tavg ROIBOP check RCS Tavg stable at or RCPs STOPPED - MONITOR Tcold trending to 547°F BVPS - 2 Scenario 1 16 of 26 Rev. 1 (45 day submittal)

Check CIB ACTUATED RO checks Recirc Spray Pump status Recirc Spray HXs SERVICE WATER

~

FLOW TO ALL 4 HXs Check Recirc Spray Pumps - ANY RUNNING Check Recirc Spray Pumps ALL ~

RUNNING Check Recirc Spray Pumps NOT ~

CAVITATNG All RCPs - STOPPED RO Slops all RCPs due to CIB PORVs CLOSED

~ RO verifies PZR isolated Spray Valves CLOSED

~~

Safety relief valves (PSMS Detailed Data

~

Page 1) CLOSED

~

Check PRT conditions ~- CONSISTENT WITH EXPECTED VALUES Power to at least one block valve -

AVAILABLE Block valves AT LEAST ONE OPEN

~

RCPs PREVIOUSLY STOPPED RO checks if RCPs should be stopped BVPS - 2 Scenario 1 17 of 26 Rev. 1 (45 day submittal)

BEAVER VALLE . ,OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training Rnvisinn 7 Pressures in all SGs ANY DROPPING BOP checks if any SGs are faulted.

IN AN UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURlZED CREW DETERMINES 1 OR MORE SGs ARE FAULTED, TRANSITIONS TO E-2 STEP 1 Crew transitions to E-2 step 1 US directs STA to monitor status trees.

As U-l operator, when requested, Check CREVS actuated: BOP verifies CREVS actuated, requests report proper CREVS actuation. Control room air intake and exhaust Unit 1 CREVS vcrification.

dampers CLOSED

~

[2HVC*FN241A(B)] AT LEAST ONE

~

RUNNING Request U1 operator to verify CREVS actuation Commence Control Room ventilation actions IAW ATT A-2.4 BVPS - 2 Scenario 1 18 of 26 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTEDSTUDENTRESPONSE CRITICAL TASK AUTO MSLI FAILURE - BOTH Crew verifies steam line isolation.

Crew manually actuates main steam TRAlNS line isolation before a Severe (orange path) challenge develops to either the MSLl MANUALLY ACTUATED Crew identifies failure of AUTO MSLI, Sub-criticality or Integrity

- . CSF or MANUALLY actuates MSLI Both Trains before transition to ECA-2. I , whichever occurs first. Check All yellow SLI marks ~ LIT Check all SG pressures ~ ANY STABLE BOP checks for any non-faulted SG, OR RISING Check all SGs pressure ANY SG

~

BOP identities "C" SG as faulted.

PRESSURE DROPPING IN AN UNCONTROLLED MANOR OR ANY SG COMPLETELY DEPRESSURIZED "C" SG pressure dropping uncontrollably.

CRITICAL TASK Check FWI PREVIOUSLY VERIFIED

~ Crew verifies faulted SG (C) isolated Crew isolates the faulted SG and directs operator to close isolation valve(s) operated from outside of the control room before transition out of E-2.

[2FWS*HYV-l57C] closed BOP verifies "C" SG CNMT isolation vlv closed.

BVPS - 2 Scenario 1 19 of 26 Rev. 1 (45 day submittal)

[2FWS*FCV498] closed. BOP verifies "C" MFRV closed.

[2FW S* F W4991 closed BOP verifies "C" BPFRV closed.

[2FWE*HCVlOOA, B] closed. BOP closes [2FWE*HCVlOOA, B]

Check Residual Heat Release valve BOP closes [2SVS*HCV104].

CLOSED IRF I,OA-MSSOll (0 0) 0 Check Residual Heat Release Valve from Crew dispatch operator to close [2SVS*29]

rauitc:cl SG PREVIOUSLY ISOLATED.

~

SG 21C [2SVS*29]

Close Turbine driven AFW pump steam BOP closes [2MSS*SOVlOSC,F]

supply isolation valves from faulted SG:

[2MSS*SOVlOSC,F]

IF REQUESTED: Close atmospheric steam dump on faulted BOP closes "C" SG atmospheric steam SG [2SVS*PCV1 OlC] dump [2SVS*PCVlOlC]

IRF LOA-MSS018 (0 0) 0 To close [2SVS*25]

Verify SG blowdown isolation valve from BOP verities SG blowdown isolated from faulted SG CLOSED: "C" SG.

[2BDG*AOV100CI] OR

[2BDG*AOVlOlCl]

BVPS - 2 Scenario 1 20 of 26 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE Closc [2SSR*AOV117C] SG blowdown BOP isolates SG blowdown sample from sample outside CNMT isolation valves C SG Check [2FWE-TK210] PPDWST level - Crew checks PPDWST level > 85 inches 85 inches Or Refer to Attachment A-1.8 for makeup.

Check all SG levels NONE RISING IN Crew checks if SG tubes are intact AN UNCONTROLLED MANNER Check Secondary Radiation ~

CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQl00] Air Ejector Discharge

( 1007)

[2SSR-RQl00] SGBD sample BVPS - 2 Scenario 1 21 Of 26 Rev. 1 (45 day submittal)

RCS pressure STABLE OR RISING

~

P E R level GREATER THAN 17%

~

Crew determines SI Termination criteria 138% ADVERSE CNMT] met, transitions to ES-1.1 Crew transitions to ES-1.1 Step 1 US directs STA to monitor status trces SI, CIA & CIB - RESET RO resets SI, CIA & CIB All but one charging pump - STOPPED RO stops all but one Charging Pump RCS Pressure ~ STABLE OR RISING RO checksireports RCS Pressure status BVPS - 2 Scenario 1 22 of 26 Rev. 1 (45 day submittal)

HHSI Cold Leg Is01 VLVs ~ CLOSED: RO isolates HHSI injection path Drill may be terminated after HHSI flow i s isolated CLASSIFY EVENT UE TAB 2.10 BVPS - 2 Scenario 1 23 of 26 Rev. 1 (45 day submittal)

x 50 m

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BEAVER VALLE . OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE

[2NME-NR45] Nuclear Recorder selected Align neutron flux monitoring for shutdown to operable source and intermediate range displays CNMT pressure ~ HAS REMAIND LESS Check CIB status THAN 11 PSIG IF NOT Actuate CIB if required Manually initiate CIB BOTH SWITCHES FOR BOTH TRAINS Manually a l i g equipment as required All RCPs STOPPED

~

Stop ALL RCPs BV-1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps 2 RUNNING

~

Verify Service Water System in service Service Water Header Pressure ~

GREATER THAN 5 5 PSIG SWS Seal Water Pressure NOT LOW

~

[2HCS*SOVlOOAl, BI] ~ CNMT Sample Verify both CNMT hydrogen analyzers amber light - LIT running BVPS - 2 Scenario 1 25 of 26 Rev. 1 (45 day submittal)

All Red SIS Marks LIT

~

Verify ESF Equipment status Stadalign

~

All Orange CIA Marks LIT ~

equipment as required All Green FWI Marks LIT ~

Power available to both Emergency AC Verify power to both AC Emergency busses Busses Restore power as required Attachment A-0.11 ~ COMPLETE Report any discrepancies to SMmS BVPS - 2 Scenario 1 26 of 26 Rev. 1 (45 day submittal)

Appendix D Scenario Outline Form ES-D-1

acility
BVPS 2 Scenario No.: 2 Op Test No.: NRC
xaminers: Candidates: - SRO

- ATC

- BOP nitial MOL, 75 %power Equ Xe, CB = 188, 1116 PPM IC-166 Zonditions:

urnover: Maintain current plant cmditions ritical Tasks: 1. ~ - 1 . c Crew trips all RCPs when KCS to highest SG DIP criteria is exceeded and SI flow verified prior to exiting procedure E-I 2 . FR-S.l .C Crew insertr. negative reactivity into the core by inserting RCCAs before completing the immediate action steps of FR-S.1.

3

~

~

!vent Malf. No. Event Type Event Description No.

1 XMT-MSS022A I(BOPISR0) [2MSS*FT485] B SG Selected Steam Flow SRO T.S. Channel drifts HIGH XMT-LDSOO3A I(ROlSR0) VCT 1,evel control channel failure LOW 3 XMT-RCS032A SRO T.S. [2RCS*PT455] PRZR Pressure Protection Channel fails HIGH 4 Power reduction due to TS 3.0.3 requirement (No TS Action addressing two channels of OTA1 being inoperable) 5 RCPOlA C(ROlSR0) RCP # I seal leakoff excessive (requires Rx trip) 6 PPLOlA M(ALL) ATWS ~ Failure of auto/manual Rx trip PPLO 1 B 7 LOA-AFW022 C(BOPISR0) [2FWE*P22], Turbine driven AFW pump trips PPL07B during S/U, [2FWE-P23B] Motor Driven AFW Pump requires manual start VLV-RCS032A M(ALL) PORV [2RCS*PCV455C] sticks open after auto open and its block valve [2RCS*MOV535] cannot be closed from CR ( P E R Vapor space leak)

(K)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev 1

Scenario Summary Scenario 2 The crew will assume the shift at approximately 75% power BOL equilibrium Xenon.

Power Range Channel N-42 is 00s and remove from service IAW AOP 2.2.1C, Pow8:r Range Channel Malfunction. Motor driven AFW pump 2FWE*P23A is also 00s. Crew instructions are to maintain the plant at 75% power. After the crew assumes the shift, the controlling channel of steam flow on the B steam generator [2MSS*FT485] will drift HIGH. The crew will respond to the alarms and implement the actions of instrument failure procedure OM 2.24.4.1F ATT #3 and take manual control of SGWLC on the 73 SG. The crew will swap controlling channels and return SGWLC to automatic. After the US implements the required Technical Specification actions, VCT level transmitter 2CHS*LT115 will FAIL LOW causing automatic make-up to VCT to begin. The crew will STOP the automatic make-up to VCT and respond to the alarms and implement the actions of instrument failure procedure OM 2.7.4.1F ATT k l . From this point on in the scenario, all VCT make-ups will need to be initiated manually. After stabilizing the plant, P E R Pressure Protection channel 2RCS*PT455 will FAIL HIGH. The crew will respond to the annunciators and implement the actions of instrument failure procedure:

OM 2.6.4.IF ATT #2. While performing the actions of the procedure and Technical Specifications, the crew MUST recognize that there are NOW 2 channels of OTAT 00s and Technical Specification 3.0.3 is app.icable. Plant management instructs the crew to begin an immediate power reduction to comply with Technical Specification 3.0.3 actions. The crew begins a power reduction IAW 20M-52.4.B, Load Follow. During the power reduction, # 1 seal on the B RCP will degrade. The crew will respond to the alarms and implement the actions o f AOP 2.6.8, RCP Malfunction. The seal degradation will worsen to the point where the AOP 2.6.8, RCP Malfunction will require the crew to initiate a manual reactor trip. The crew will enter E-0, Reactor Trip or Safety Injection only to find that manual and automatic rzactor trips will not function. The crew will transition to FR-S.1, Response to Nuclear Power generation - ATWS. The actions of FR-S.l, Response to Nuclear Power generation ATWS will be complicated by the steam

~

driven AFW pump tripping during start-up and motor driven AFW pump 2FWE*P23B failing to automatically start. This will require the crew to manually start motor driven AFW pump 2FWE*P23B. The actions cf FR-S.1, Response to Nuclear Power generation

-- ATWS will be further complicated by PRZR PORV failing to close, after automatically opening, and its associated block valve cannot be fully closed. (PRZR VAPOR SPACE LEAK). The reactor will be tripped locally by the operator dispatched during FR-S.l, Response to Nuclear Power generation ATWS performance. The crew will transition

~~

back to E-0, Reactor Trip or Safety Injection and perform the actions to verify ECCS equipment operating and diagnose the vapor space leak. The crew will then transition into E-1, Loss o f Reactor or Secondary Coolant and perform the actions to stabilize the plant.

The scenario is terminated when the crew transitions into ES-1.2, Post LOCA Cooldown and Depressurization.

EOP Flow Path:

E-0, Reactor Trip or Safety Injection + FR-S. 1, Response to Nuclear Power generation ~

ATWS + E-0, Reactor Trip or Safety Iujection + E-1, Loss of Reactor or Secondary Coolant + ES-I .2, Post LOCA Cooldown and Depressurization BVPS - 2 Scenario 2 2 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE , OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 75 % Power, CBD = 188, EQU XE MOL, 11 16 PPM Boron, IC-166 N-42 Control Pwr fuses REMOVED

~ N-42 meters (2)

N-42 Rod Stop BP sw to BP Chan 2 OTDT Meter Channel Comparator Defeat sw to N-42 Ann OTDT TnpiRod stop NR-45 NOT selected to N-42

[2FWE*P23A] - PTL DANGER - [2FWE*P23A]

switch DATEITIME 00s ~~~ ~ TECHNICAL SrECIFICATION(S) 2 Hrs. ago 1 [2FWE*P23A] 3 Hrs ago SHIFT TURNOVER INFORMATION

1. Protected Train is Train B
2. N-42 removed from service per AOP 2.2.1C,
3. [2FWE*P23A] Motor ground, repair estimate is 8 10 Hrs.
4. Maintain current plant conditions.

SCENARIO SUPPORT MATERIAL REQUIRED Reactivity plan placard for MOL Placard for [2FWE*P22] position stating [2FWE*P22] is aligned to A header Place plaque on wall for Protected Train B BVPS - 2 Scenario 2 3 of 29 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE Initialize IC Set 166, and establish Reactor plant at 75% power, MOL, initial plant conditions. equilibrium conditions. RCS boron 1 1 16 PPM, CBD = 188 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this drill drill:

I R F LOA-HIV055 (0 0) 1 [2FW*P23A] breaker racked out I M F PPL02A (30 120) Train A trip BKR open I M F PPL02B (30 130) Train B trip BKR open IRF LOA-CRF007 (30 140) 1 Trip A rod drive MG set IRF LOA-CRF008 (30 150) 1 TI ip B ivd dt i v c MG hcl I M F PPLOlA (0 0) 1 Set ATWS condition TRN A I M F PPLOlB (0 0) 1 Set ATWS condition TRN B IMF VLV-RCSOI 1 (0 0) 1 [2RCS*MOVS3S] cannot be closed from control room TRGSET 1 RRCH455C >= 0.1 Set trigger 1 on [2RCS*PCV455C]

position I M F VLV-RCS032A (1 0) 50 [2RCS*PCV45SC] sticks open after auto open TRGSET 2 OAFWT22 >= 1000 Set trigger 2 on [2FWE*P22] speed IRF LOA-AFW022 (2 0) 1 [2FWE*P22] trips during startup I M F PPL07B (0 0) 5 [2FWE*P23B] fails to auto start, manual successful I M F NIS03B (0 0) 0 PRNI N-42 00s I M F BST-PCS158 (0 0) 0 CH I1 OTDT Reactor trip B/S I M F BST-PCS159 (0 0) 0 CH I1 OTDT Rod StopiTurbine Runback Bf S BVPS - 2 Scenario 2 4 of 29 Rev. 1 (45 day submittal)

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BEAVER VALLE :OWER STATION I

112 - ADM - 1357 Conduct of Simulator Trainina INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #1:

[2MSS-FT485] drifts high IMF XMT-MSS022A (0 0) 5 30 IMMEDIATE PLANT RESPONSE: BOP notesherifies alarms, informs

[2MSS-F1485] begins to drift high USiCrew of apparent instrument failure of

[2MSS*FT485]

[2FWS*FCV488] begins to open B SG level begins to increase A6-IOF LOOP B FEEDWATERFLOW >

STEAM FLOW (FG476D)

A6-10E (possible) SG21B LEVEL DEVIATION FROM SETPOINT (L0477D)

US/Crew refer to ARPs & Procedure 2 0 M -

24.4.1F ATT 3

[2FWS-FCV488] - MANUAL BOP places MFRV for B SG to manual and restores level

[2FWS-FR488] - Position FT 487 BOP selects position FT 487 on [2FWS-FR4881 BVPS - 2 Scenario 2 6 of 29 Rev. 1 (45 day submittal)

a, K

m N

c 0

P-I v) a m

US refers to TS 3.3.2, Table 3.3.2-1 Functions 5.b and 6.b:

5.b & 6.b Condition D D.l: Place channel in TRIP W/I 6 hrs OR D.2: Be in MODE 3 WII 12 hrs AND D.2.2: Be in MODE 4 WII 18 hrs When directed to trip bistables: US refers to ATT 1 to trip bistables for the failed channel, contacts I&C IRF LOA-PCS003 (0 0) 1 Protection rack C3 door open Crew monitors tripping of B/S IMF BST-PCS041 (0 0) 0 2LS/486A (BS-1) low-low trip IMF BST-PCS032 (0 0) 0 2LS/486C (BS-2) high-high FWI IRF LOA-PCS003 (0 0) 0 Protection rack C3 door closed US directs BOP to place [2FWS-FCV488]

to auto when SG level returned to normal and stable THEN report actions to CR BVPS - 2 Scenario 2 8 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE'Y fOWER STATION 112 - ADM - 1357 Conduct of Simulator Training INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE Proceed with next event at LE discretion EVENT #2:

[2CHS*LT115] fails LOW IMMEDIATE PLANT RESPONSE:

IMF XMT-LDS003A (0 0) 0 A2-2G VOLUME CONTROL TANK TROUBLE (L0145D)

[2CHS*LT115] VCT Level indicates 0, VB A Auto M/U initiates (blender station BB A) RO diagnoses LOW failure of L2CHS*L I I 151, reports to USiCrew Crew refers to ARPs or 20M-7.4.IF ATT

  1. 1 Actual VCT level is well W/I normal level RO confirms failure by comparing VB A range and rising as indicated by [2CHS*LI115] to PCS point (L2704A)

[2CHS*LT112] (L2704A) on plant PCS Auto MiLT in progress RO reports auto M/U in progress US directs RO to place M/U control switch to OFF after rising VCT level is confirmed.

Auto MIU stopped, VCT level rise stopped RO places M/U switch to OFF BVPS - 2 Scenario 2 9 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE , OWER STATION I

112 - ADM - 1357 Conduct of Simulator Trainina Crew monitors Tavg for inadvertent boron change US directs I&C to investigate problem with

[2CHS*LT115]

[2CHS*LTl12]indication SAT, blender Crew controls VCT level in manual control controls remain in OFF Continue with next event at LE discretion BVPS - 2 Scenario 2 10 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE , OWER STATION 112 - ADM - 1357 Conduct of Simulator Training EVENT #3:

[2RCS+PT455] fails high IMF XMT-RCS032A (0 0) 2500 [2RCS*PI455] indicates pegged high RO diagnose high failure of

[2RCS*PT455], reports to USKrew IMMEDIATE PLANT RESPONSE:

A4-2D PRESSURIZER PRESSURE HIGHiLOW ACTUATES (P0480D)

[2RCS*PI455] (CH I) indicates pegged high (2500 psig) on BB B

[2RCS*TI412C] Loop I OTDT Setpoint indicates pegged high (1 50%) BB B US ensures plant is stable US directs crew to ARP A4-2D and IF procedure 2.6.4.IF Att 2 OPERABLE OT/OPDT channel selected RO selects OPERABLE channel on [2RCS-on recorder [2RCS-TR412] TR4121 BVPS - 2 Scenario 2 11 of 29 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE TS 3.3.1, Table 3.3.1-1: (RTS) 2TSi412C-I, OTDT trip - CANNOT BE Function 6: OTDT Condition E. 1 Place TRIPPED

~

in TRIPPED Condition (6 hrs) 2TW412C-2, OTDT rod stop CANNOT

~

E.2 be in MODE 3 (12 hrs)

BE TRIPPED US refers to TS, determines that OTDT B/S cannot be tripped WiO causing a reactor trip US determines that TS 3.0.3 applies US identifies PZR Pressure instrument related TS and MAY trip B/S associated with PZR Pres Function 8.a: PZR Press LOW Condition K.l Place in TRLF'PED Condition (6 hrs)

~

OR K.2 Reduce THERMAL POWER to < P-I

~

( 12 hrs)

BVPS - 2 Scenario 2 12 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE 1 OWER STATION I

112-ADM-1357 Conduct of Simulator Training INSTRUCTIONAL GUIDELINES PLANTSTATUSORRESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Function 8.b: PZR Press HIGH Condition E.l Place in TRIPPED Condition (6 hrs)

OR E.2 Be in MODE 3 (1 2 hrs)

US refers to ESFAS TS associated with PZR Pres and MAY trip BIS associated with PZR Pres TS 3.3.2, Table 3.3.2-1: (ESFAS)

Function 1.d: PZR Press LOW Condition D.l - Place channel in TRIP (6 hrs) Q F J

D.2.1 - B e i n M O D E 3 ( 1 2 h r s ) D D.2.2 - Be in MODE 4 ( 1 8 hrs)

Function 8.b: PZR Press P-11 Condition K.l - Verify interlock is in required state for existing Unit condition ( 1 hr)

K.2.1 -Be in MODE 3 (7 hrs) AND K.2.2 - B e in MODE 4 (13 hrs)

As Plant Management, direct US to US informs Plant Management that a plant commence an immediate plant SID to SID is required by TS MODE 3 BVPS - 2 Scenario 2 1 3 of 29 Rev. 1 (45 day submittal)

IF requested to trip PZR Pres bistables US may decide to trip only the BIS THEN: associated with SI, HIGHILOW press Rx Trip, P-1 1 and PORV Block IRF LOA-PCS001 (0 0) 1 Protection rack 1 door open.

IMF BST-PCS117 (0 0) 0 2PS/4SSA, high prcssurc trip.

IMF BST-PCS118 (0 0) 0 2PSl4SSB, P-l 1.

I M F BST-PCS125 (0 0) 0 2PS/4SSC, low pressure trip.

IMF BST-PCS126 (0 0) 0 2PSl4SSD, low pressure SI.

IMF BST-PCSl27 (0 0) 0 2PSl4SSG, PORV block.

IRF LOA-PCS001 (0 0) 0 Protection rack 1 door closed.

Report actions to CR NOTE: IF the US insists on tripping the B/S associated with OTDT THEN:

IMF BST-PCS151 (0 0) 0 2TS/412C-1, OTDT trip.

IMF BST-PCS152 (0 0) 0 2TS/412C-2, OTDT rod stop.

Report actions to CR Event #S will be inserted upon trip, Reactor trip SHOULD HAVE RO announce 1 out reactor trip AND that advance to page 15 for E-0 actions OCCURRED the reactor DID NOT TRIP BVPS - 2 Scenario 2 14 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE . .OWER STATION I

1/2-ADM- 1357 Conduct of Simulator Trainina INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE US directs entry into E-0 EVENT #4:

Normal power reduction Crew commences power reduction IAW 20M-52.4.B Load Follow Reactor Engineering is currently Crew develops reactivity plan for 12% Hr.

unavailable. Plant Management directs power reduction to MODE 3 immediate power reduction to MODE 3 SM recommends 12%/Hr.

BOP prepares EHC for load reduction, presses GO when ordered BOP maintains VPL 5% above turbine load RO maintains axial flux WiI target band, rods above RIL and Tavg +/- 2F of Tref during transient BOP maintains Generator Lagging power factor and Base Adjuster at Null Continue with next event at LE discretion:

BVPS - 2 Scenario 2 15 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE . OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE EVENT #5:

[2RCS*P21A] # 1 seal degrades IMMEDIATE PLANT RESPONSE:

IMF RCPOlA (0 0) 8 A2-4D REACTOR COOLANT PUMP RO checks alarms, reports indications of $1 SEAL TROUBLE (F0125D) for the A seal failure on [2RCS*P21A] to US/Crew RCP US refers to ARPs, AOP 2.6.8 Step 2.g

[2CIIS-rRl53A\;R E 3 PEN iiidiiatcs 6 p,o--

LLpVILa

-A- th;; A RCP $! sca! !&off is gpm (off scale high for XRCP) >6gpm US direct manual reactor trip, Directs RO to trip [2RCS*P21A] after completion of IMAs of E-0, Directs Crew to isolate [2RCS*P21A] seal leakoff W/I 3 5 min after tripping RCP

~

Crew enters E-0, performs Crew performs IMAs of E-0.

immediate operator actions.

Annunciator A5-6D TURBINE TRIP DUE RO verifies reactor tripped TO REACTOR TRIP NOT LIT~

Power range indication NOT LESS

~

RO Attempts manual reactor trip from BB B THAN 5 % and BB A, rcports reactor has NOT tripped Neutron flux NOT DROPPING

~

BVPS - 2 Scenario 2 16 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE I . OWER STATION 112 - ADM - 1357 Conduct of Simulator Traininq US transitions to FR-S.1 Reactor IS NOT tripped LISiCrew deternine FR-S.l entry conditions met, transition to FR-S.1 Step 1 When directed to locally trip the Crew performs lMAs of FR-S.1 reactor:

TRG! 30 Time delays are built in.

Turbine is tripped BOP manually trips the turbine CRITICAL TASK Control Rods are inserting RO inserts control rods, AUTO at first, Crew insens negative reactivity into the THEN MANUAL when required core by inserting RCCAs before completing the immediate action steps of FR-S I

[2FWE*P23A] on clearance Crew verifies AFW status

[2FWE*P23B] REQUIRE MANUAL START BOP reports AFW status, manually starts

[2FWEXP22]TRIPPED during S/U [2FWE*P23B], verifies flow to SGs AFW Throttle V h s FULL OPEN

~

SI may not have actuated at this time Charging Pumps AT LEAST 1

~ Crew initiates Emergency Bordtion RUNNING SI ACTUATED (possibly not at this

~

time)

HHSI flow INDICATED

~~

BVPS - 2 Scenario 2 17 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE . .OWER STATION I

112 - ADM - 1357 Conduct of Simulator Trainina Step 3.e [2CHS*MOV350] - OPEN Crew aligns boration path In service boric acid Xfer pump STARTED Emergency Boration Flow - > 30 GPM

[2CHS*FCVl22] adjusted for > 40 GPM PZR Pressure < 2330 PSIG RO checks PZR pres < 2330 PSIG Plant personnel alerted of ATWS Crew alerts plant personnel, sounds STBY alarm and announces U2 reactor trip W/O SCR4M Turbinc TRIPPED

~

BOP vcrifics turbine tripped and reheat

[2MSS-MOVlOOA,B] CLOSED steam isolated Reheater Controller RESET

~

IF SI ACTUATED THEN:

~ Crew checks SI Status First NTNE steps of E-0 performed when time and manpower permit Power range channels - <5% Crew checks if reactor is subcritical IRNI channels NEGATIVE SUR

~

Boration continues for SDM considerations Crew continues boration as necessary BVPS - 2 Scenario 2 18 of 29 Rev. 1 (45day submittal)

BEAVER VALLE I , OWER STATION 112 - ADM 1357

~

Scenario assumes the reactor has been LIS directs return to E-0 step I locally tripped by this time Crew enters E-0, performs immediate Crew perfoms IMAs of E-0.

operator actions.

Annunciator A5-6D TURBINE TRIP DUE RO verifies reactor tripped TO REACTOR TRIP - LIT Power range indication - LESS THAN 5%

Neutron flux - DROPPMG Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - BOTH BOP verifies power to AC Emergency ENERGIZED Buses.

Check SI ACTUATED

~

RO checks SI status CNMT Pressure - > SPSIG PZR Pressure - < 1860 PSIG SG Steam Pressure - < 500 PSIG CREW DETERMINES SI REQUIRED Crew continues E-0 Manually actuate SI (both trains) RO manually actuates SI both trains BVPS - 2 Scenario 2 19 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE . OWER STATION I

112-ADM-1357 Conduct of Simulator Trainina INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE Alert Plant Personnel ROIBOP sound Standby Alarm, announce reactor trip and safety injection Check [2HVS*FN204A(B)], Leak BOP checks Leak Collection Exhaust Fan Collection Filtered Exhaust Fan AT~ status LEAST ONE RUNNING Charging Pumps - TWO RUNNWG RO verifies SI System status HHSI Flow - INDICATED LHSl Pumps TWO RUNNING

~

Motor-driven AFW Pumps ONE ~

BOP verifies AFW System status R(JNNING Turb driven AFW Pump TRIPPED DURING S/U AFW Throttle Vlvs FULL OPEN

~

Total AFW Flow - GREATER THAN 340 GPM Perform Attachment A-0.11 Verification US directs performance of Attachment A-Of Automatic Actions in a timely manner 0.1 1 when tiineimanpower permit Attachment A-0.11 included with LIST ATT A-0.11 DISCREPANCIES scenario beginning on Pg 27 AS APPLICABLE:

[2FWE*P23B] required manual start

[2FWE*P22] tripped during S/u BVPS - 2 Scenario 2 20 of 29 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE EXPECTEDSTUDENTRESPONSE RCPs OPERATING - MONITOR Tavg ROiROP check RCS Tavg stable at or RCPs STOPPED MONITOR Tcold

~

trending to 547°F Check CIB NOT ACTUATED

~ RO checks Recirc Spray Pump status PORVs NOT ALL CLOSED RO verifies PZR isolated

[2RCS*PCV455C] STUCK OPEN

~

[2RCS*MOV535] -CANNOT BE RO reports status of [2RCS*PCV455C]

CLOSED AND its block valve [2RCS*MOV535]

Transition to E-1 US directs transition tu E-1 due iu PORVIBlock Valve status Control Room radiation monitor Crew checks if CREVS should be actuated

[2RMC*RQ201,202] (1069, 1072)-

NOT IN HIGH ALARM CIB - HAS NOT OCCURRED CRlTICAL TASK DIP between RCS pressure and highest SG RO checks if RCPs should be stopped Crew tnps all RCPs when RCS to highest pressure LESS THAN 205

~ [220 SG DIP criteria IS exceeded and SI flow PSID ADVERSE CNMT]

verified prior to exiting procedure E-I. AND HHSI Flow INDICATED

~

RCPs - STOPPED RO stops RCPs BVPS - 2 Scenario 2 21 of29 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTEDSTUDENTRESPONSE Pressures in all SGs ANY DROPPlNG

~ BOP checks if any SGs are faulted IN AN UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED SGs are NOT faulted Xarrow Range Levels GREATER T l A N

~

12% [31% ADVERSE CNMT]

BOP controls feed flow to intact SGs to maintain NR level between 12% [31%

ADVERSE CNMT] and 50%

BVPS - 2 Scenario 2 22 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE . OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES OBJECTIVE EXPECTEDSTUDENTRESPONSE Check all SG levels NONE RISING IN

~

Crcu, chccks if SG tubes are intact AN UNCONTROLLED MANNER Check Secondary Radiation ~

CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQ100] ( 1 007) Air ejector discharge

[2SSR-RQl00] (1062) SGBD sample

[2MSS*RQlOlA,B,C] Main Steamline discharge (1005,3005,5005)

SG Tubes are intact Power to the Block Vlvs AVAILABLE

~ RO checks P E R PORVs and Block Valves PORVs [2RCS*PCV455C] STUCK

~ ~

OPEN Block Vlvs [2RCS*MOV535] -

~

CANNOT BE CLOSED RCS Subcooling based on core exit TCs ROiBOP check if SI flow can be reduced LESS THAN 41F [59F ADVERSE CNMT]

BVPS - 2 Scenario 2 23 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE, . OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina Secondary heat sink:

Total feed flow to intact SGs GREATER THAN 340 GPM OR Narrow range level in at least one intact SG-GREATERTHAN 12% [31-%

ADVERSE CNMT]

RCS pressure REDUCING PRZR level GREATER THAN 17%

- RO/BOP check if SI flow can be reduced

[38% ADVERSE CNMT] (continued)

SI FLOW CANNOT BE REDUCED Any Quench spray or recirc spray pump RO/BOP check if CNMT Spray should be NONE RUNNING stopped SI & CIA - RESET RO resets SI and CIA RCS Pressure - > 225 PSIG [250 PSIG RO checks if LHSI Pmps should be stopped ADVERSE CNMT]

NOTE: RCS pressure MAY appear to RCS Pressure REDUCING

- IF STABLE, RO stops LHSI pumps and be stable and RO will stop LHSI pumps places them in auto Check pressures in all SGs STABLE OR

- RO/BOP check RCS and SG Pressures RISING Check RCS Pressure STABLE OR DROPPING BVPS - 2 Scenario 2 24 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE :OWER STATION I

112 - ADM - 1357 Conduct of Simulator Trainina Verify AC emergency busses energized BOP checks if EDGs should be stopped from offsite Stop any unloaded EDG by performing Crew stops EDGs 20M-36.4.AF(AG)

Recirc capability exists US directs operators to perfom Att A-0.6 and verify cold leg recirculation capability Check AUXbuilding and Safeguards Crew tries to identify and isolate the leakage radiation CONSISTENT WITH PRE-

~

EVENT SM consults with TSC Staff to determine whether samples can be obtained Sample: US directs Chemistry and HP to obtain CNMT atmosphere for radioactivity and pertinent samples hydrogcn CNMT sump for pH and boron RCS liquid Crew performs ATT A-1.1 US directs crew to perform additional actions as required to aid in plant recovery per ATT A-1.1 BVPS - 2 Scenario 2 25 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE . OWER STATION I

112 - ADM - 1357 Conduct of Simulator Traininq RCS Pressure - > 225 PSIG [250 PSIG RO checks if cooldown and ADVERSE CNMT] depressurization is required US directs crew transition to ES-1.2 Terminate drill when crew transitions to ES-1.2 Classify Event Site Area Emergency Tab 2.3 BVPS - 2 Scenario 2 26 of 29 Rev. 1 (45day submittal)

BEAVER VALLE, , OWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Attachment A-0.1 1 Verification of US directs operator to perform Attachment Automatic Actions performed as time A-0.11 as time & manpower permit

& manpower permit Diesel generators ~ BOTH RUNNING Check both EDGs running CNMT pressure ~ GREATER THAN 7 Check if MSLI is required PSlG OR !fnot rcquircd, go to ,,ep 1

-+

SG Steam Pressure LESS THAN 500

~

PSlG OR Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIT Verify steamline isolation STEP 4 Open [2CCS-AOV118] Domestic Water to Establish Domestic Water System Cooling Station Air Compressor to Station Air Compressors At least one Station Air Compressor Start 1 Station Air Compressor as required RUNNING CCP pumps ~ AT LEAST 1 RUNNING Check CCP Pump status BVPS - 2 Scenario 2 27 of 29 Rev. 1 (45 day submittal)

BEAVER VALLE) ,-OWER STATION 112-ADM-1357 Conduct of Simulator Traininq INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE

[?NME-NR45] Nuclear Recorder selected Align neutmn flux monitoring for shutdown to operable source and intermediate range displays CNMT pressure ~ HAS REMAIND LESS Check CIB status THAN 11 PSIG IF NOT Actuate ClB if required Manually initiate CIB BOTH

~

SWITCHES FOR BOTH TRAINS Manually align equipment as required All RCPs STOPPED

~

Stop ALL RCPs BV-1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps 2 RUNNWG

~

Verify Service Water System in service Service Water Header Pressure ~

GREATER THAN 55 PSIG SWS Seal Water Pressure NOT LOW

~

[2HCS*SOVlOOAl, BI] ~ CNMT Sample Verify both CNMT hydrogen analyzers amber light LIT

~

running BVPS - 2 Scenario 2 Rev. 1 (45 day submittal)

BEAVER VALLE) ,-OWER STATION 112 - ADM - 1357 Conduct of Simulator Training All Red SIS Marks LIT

~ Verify ESF Equipment status ~ Start/align All Orange CIA Marks LIT~

equipment as required All Green FWI Marks LIT

~

Power available to both Emergency AC Verify power to both AC Emergency busses Busses Restore power as required Attachment A-0.11 COMPLETE Report any discrepancies to SMKJS BVPS - 2 Scenario 2 29 of 29 Rev. 1 (45 day submittal)

~~

Appendix D Scenario Outline Form ES-D-1

'acility: BVPS 2 Scenario No.: 3 Op Test No.: NRC Zxaminers: Candidates: - SRO

- ATC BOP

nitial MOL, 75 % power Equ Xe, CB = 188, 11 16 PPM 1C-167 londitions:

rumover: Plant has been at 7S% for hree days at system request. Crew is to return the unit ti full power at 12%0/HrIAW 20M-52.4.B, Load Follow, and the reactivity plan provided by Reactor Engineering. [2FWE*P23A] Motor Driven AFW Pump is on clearance for motor replacement and is due to be returned tomorrow. [2SAS-C21 E I Station Air Compressor is on clearance for bearing replacement and due to be returned 2 days from now.

%tical Tasks: 1. E-0.Q Crew manually trips the main turbine before a Severe (orange path) challenge develops to either the Sub-criticality or the Integrity CSF 0 '

before transitimm to ECA-2.1, whichever occurs first.

2. FR-H.l .ACrew establishes feedwater flow into at least one SG before RCS feet1

__ and bleed is r pired. -

Event Event Description

~

No.

I PRNl N-44 fails HIGH causing automatic control rod insertion SRO T S .

2 CRF03-HI4 SRO T.S. Misaligned rod. During control rod motion, Control R id H-14 will drop to some position below the group and then remain stuck at that position 3 Normal power reduction 1 N(BOP/SRO) 4 [2FWS-P21B], Main Feedwater Pump trips 5 [2FWS-P21A], 2"d Main Feedwater Pump trips 6 Main Turbine fails to auto trip, manual trip successful 7 LOA-AFW022 M (ALL) [2FWE*P22] Turbine driven AFW Pump trips during startup [2FWE*P23B] Motor driven AFW Pump Trip PMP-AFW002 resulting in Entry into FR-H.1 Loss of Secondary Hea' Sink.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1

Scenario Summary Scenario 3 The crew will assume the shift at approximately 75% power BOL equilibrium Xenon.

Motor driven AFW pump 2FWE*P23A is 00s. Station air compressor 2SAS-C21B i s also 00s. Crew is to raise power at 12%-/hrIAW 20M-52.4.B, Load Follow. Before the crew can begin raising power, Power range channel N-44 FAILS HIGH which causes automatic control rod insertion at 72 SPPA. During the rapid rod insertion, rod H-14 drops to a position below the group and becomes stuck at this position. The crew responds to the alarms and implements the actions ofAOP 2.2.1C, Power Range channel Malfunction and AOP 2.1.3, RCCA Control Bank Inappropriate Continuous Movement. The crew will manually stop the inward rod motion and stabilize the plant. After the plant is stable, the US will then implement AOP 2.1.8, Rod Inoperability and implement the required Technical Specification actions for both the failed N44 and stuck rod. After the Technical Specifications have been addressed, reactor engineering/plant management directs an immediate power reduction to 50% to gather data and assess the impact ofthe stuck control rod. The crew begins the power reduction. During the power reduction, Main feed pump 2FWS-21B trips. The crew responds to the alarms and implements the actions of AOP 2.24.1, Loss of Feedwater. When the crew attempts to start the startup feed pump 2FWS-P24 it will NOT start. The crew will be required to commence a rapid load reduction to 50% power as part of the loss of feedwater AOP. During the load reduction, the 2"" main feed pump trips. This will require the crew to manually trip the reactor and enter E-0, Reactor Trip or Safety Injection. The actions of E-0, Reactor Trip or Safety Injection will be complicated by a failure ofthe turbine to automatically trip. The crew will be required to manually trip the turbine. The actions of E-0, Reactor Trip or Safety Injection will be further complicated by .a failure of the steam driven and only operable motor driven AFW pumps. The crew will transition into ES-0.1, Reactor Trip Response.

While in ES-0.1, a RED PATH will be identificd on Heat sink No AFW flow and NR levels less than 12%. This will require the crew to transition into FR-H.1, Loss of Heat Sink (RED PATH). The crew will remain in FR-H.1 and restore the heat sink by depressurizing the steam generators and establishing condensate flow to the steam generators. After establishing condensate flow, the crew will transition back to ES-0.1, Reactor Trip Response The scenario is tmninated when condensate flow is established and a transition has been made back to ES-0.1.

EOP Flow Path:

E-0, Reactor Trip or Safety Injection + ES-0.1, Reactor Trip Response + FR-H.l, Loss of Heat Sink + ES-0.1, Reactor Trip Response BVPS - 2 Scenario 3 2 of 28 Rev. 1 (45 day submittal)

BEAVER VALLEi OWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision 7

[2FWE*P23A] PTL DANGER

[2SAS-C21B] PTL DANGER I

[2FWE*P23A] 12 hrs ago

[2SAS-C21B] 1week ago BVPS - 2 Scenario 3 3 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE . OWER STATION I

112 - ADM - 1357 Conduct of Simulator Trainina Initialize IC - 167. and establish initial Reactor plant at 75 % power, MOL, plant conditions. equilibrium conditions. RCS boron 1116 PPM, CBD = 188 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this drill drill IRF LOA-HIV055 (0 0) 1 [2FW*P23A] breaker racked out IMF PMP-CAS004 (0 0) 1 [2SAS-C21B] 00s IMF EHCOSA (0 0) Turbine fails to auto trip, manual successful TRGSET 1 'FNISPR(4) >= 120' Set triggri i uti X-44 i i d i d i u i i IMF CRFOS-H14 (0 0) 0 Control rod H14 remains stuck at 188 steps during rod motion TRGSET 2 'OAFWT22 50' Set trigger 2 on [2FWE*P22] start IRF LOA-AFW022 (2 0) 1 [2FWE*P22] trips during startupkquencing IMF VLV-CFW027 (0 0) 0 [2FWS-P24] will not start, set up FR-H.1 conditions TRGSET 3 'MCRFNS(3) <= 225' Set trigger 3 on reactor trip IMF PMP-AFW002 (3 90) 1 [2FWE*23B] trips 90 seconds after reactor trip BVPS - 2 Scenario 3 4 of 28 Rev. 1 (45 day submittal)

Assign shift positions SM:

us:

RO:

BOP:

STA:

Conduct a shift turnover with oncoming Simulator Frozen until after shift turnover operators. unless 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 drill.

BVPS - 2 Scenario 3 5 of 28 Rev. 1 (45day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE EVENT #I & 2 N-44 fails high AND Rod H-14 drops to a position below the group and then remains stuck at that position (Pre-load)

IMF NIS03D (0 0) 200 N-44 fails high AND Rod H-14 drops to a RO diagnose & reports high failure o f PRNI IMF CRFOS-H14 (5 0) 0 position below the group and then remains N-44 TRGSET 4 FNISPR(4) = SO stuck at that position TRG 4 SET MCRFNS(44) = 168 TRGSET 5 XB21040H == 1 IMMEDIATE PLANT RESPONSE:

Annunciators actuate:

A4-4F NIS POWER RANGE COMPARATOR DEVIATION (YO130D)

A4-4H NIS POWER RANGE HIGH SETPOlNT OVERPOWER ROD STOP BLOCK ROD WD (Y0131D)

A4-5G NIS POWERRANGE HIGHILOW SP NEUTRON FLUX HIGH(N0004D)

BVPS - 2 Scenario 3 6 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE. . OWER STATION 112-ADM-1357 Conduct of Simulator Trainina Control bank D begins to step IN at FAST SPEED

[2NMP-N144B] pegs high (BB B)

N-44 indication at NI rack pegs high RCS Temperature and Pressure begin to reduce PZR Level begins to reduce US directs RO to place Control Rods in manual upon determining an instniment failure has caused rod motion AOP 2.1.3 STARTS HERE T JS directs crew actions for AOP 2.1.3 ADDITIONAL ANNUNCIATORS:

A4-8G ROD POSITION DEVIATION (C5680D)

A4-1D PRESSURIZER CONTROL PRESSURE HIGH/LOW A4-1E PRESSURIZER CONTROL PRESSURE DEVIATION HIGH/LOW (P0501D)

PRESSURE RELIEF BLOCK (P0496D)

PRESSURIZER BACKUP HEATER GROUP AUTO ON/OFF (P0503D)

TAVG DEVIATION FROM TREF (T0508D)

BVPS - 2 Scenario 3 7 of 28 Rev. 1 (45 day submittal)

BEAVER VALLEI OWER STATION I

112 - ADM - 1357 Conduct of Simulator Trainina NO LOAD REJECTION Crew rcpoi-ts no load rejection in progress Rod Motion - STOPPED US directs RO to place Control Rods in MANUAL Tavg REDUCING

~

US directs preparation for load reduction to Restore Tavg by load reduction match TavgiTref OPERABLE PRNIS ~ WII 2% OF Crew checks core power distribution EACH OTHER NORMAL CHANNEL DEVIATION light - LIT (due to failed inst)

A4-4F NIS POWER RANGE

~

COMPARATOR - LIT (due to failed inst)

Delta Flux Indicators ~ WII TARGET BAND Control Rod Positions ~ GREATER RO reports Rods above RIL THAN FUL Reactor Power 2 50% RO reports power level QPTR in progress STA previously directed to perform QPTR BVPS - 2 Scenario 3 8 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE, . OWER STATION 112-ADM- 1357 Conduct of Simulator Trainina INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE A4-3C TAVG DEVIATION FROM TREF Crew refers to A M s as required

- may/may not be lit depending on progress of load reduction at this time Power operation continues US directs recovery efforts to restore Minimize turbine load changes TavgiTref Adjust boron to control Tavg Crew completes actions of AOP 2.1.3 AOP 2.2.1C STARTS HERE ONLY N-44 has failed Crew checks only ONE PRNI has failed US refers to TS when time permits W/I 1 hr verify P-8 and P-9 interlocks are SAT for current plant conditions (TS 3.3.1 Function 17.c & 17.d: Be in MODE 2 W/I I hrs.)

Crew verifies P-8 and P-9 interlocks are SAT (power > 50%)

BVPS - 2 Scenario 3 9 of 28 Rev. 1 (45day submittal)

BEAVER VALLE . OWER STATION I

112 - ADM - 1357 Conduct of Simulator Trainina Crew verifies P-10 interlock is SAT (power

> 10%)

W/I 1 hr verify P-10 interlocks are SAT for current plant conditions (TS 3.3.1 Function 17.e: Be in MODE 3 W/I 7 hrs.)

BOP removes N-44 Control Power fuses A4-4G actuates when fuses pulled WiI 6 hrs trip nuclear BIS by removing the Control Power fuses from drawer A for the failed channel (TS 3.3.1 Function 2.a, 2.b and 3: Be in MODE 3 W/I 12 hrs.)

N-44 has failed high RO ensures Control Rod group Selector Switch i s in MANUAL (previously performed)

At NIS Rack SO - Detector Current BOP operates switches as directed Comparator Rod Stop Bypass Switch

~

to BYPASS for N-44 Panel 308 status light D-14 Overpower Rod Stop Bypass -LIT A4-4 clears Power > SO% RO reports power > 50%

BVPS - 2 Scenario 3 10 of 28 Rev. 1 (45 day submittal)

BEAVER VALLEi OWER STATION I

112 - ADM - 1357 Conduct of Simulator Traininq INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE US directs STA to perform QPTR ALL PRNI Upper and Lower channel Crew determines all inputs to QPTR are inputs to QPTR OPERABLE

~ OPERABLE At NIS Rack N37N46 - Comparator and BOP operates switches as directed Rate - Comparator Channel Defeat Switch to N-44 A4-4F clears Vertical board A recorders selected to RO selects OPERABLE channels to N-45 monitor OPERABLE channels recorder Crew completes AOP 2.2.1C for N-44 US directs crew actions for AOP 2.1.8 NO Control Rods Have Dropped RO reports No Dropped Rods ROD H Stuck at a position > 12 RO reports Rod H-14 is at a position > 12 steps below its respective group steps below its respective group Control Rods MANUAL

~ US directs RO to place Control Rods in Control Rod motion STOPPED

~

MANUAL (PREVIOUS)

BVPS - 2 Scenario 3 11 of28 Rev. 1 (45 day submittal)

BEAVER VALLEI , OWER STATION 112-ADM-1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE Reactor IS critical Tavg - > 541F Tavg NOT W/I 5 4F of Tref

~

Tavg Stable (after rods placed in

~

MANUAL)

US refers to TS 3.1.4 (Rod Group Alignment Limits) when time permits:

MODES 1&2:

All SD and CR shall be operable AND 1ndividi.ial indicated rnd pnsitinns shall he W/I 12 steps of their group step counter demand position.

Condition B:

B.l Restore rod to WII alignment limit (1Hr)

OR B.2.1.1 Verify SDM to be WII the limits specified in the COLR (1Hr)

OR B.2.1.2 Initiate boration to restore SDM to WII limits (1Hr) AND B2.2.2 Reduce THERMAL POWER to <=

75% RTP (2Hrs) AND B.2.3 Verify SDM is WII the limits specified in the COLR (once112 Hrs) AND BVPS - 2 Scenario 3 12 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE I . OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina B.2.4Perfom SR 3.2.1.1 andSR3.2.1.2 (72 Hrs) AND TS 3.1.4 (continued)

B.2.5 Perform SR 3.2.2.1 (72 Hrs) AN9 B.2.6 Re-evaluate safety analysis and confirm results remain valid for duration of n p r a t i n n nnrlrr these cnnditions ( 5 days)

OPERABLE rwIs ~ W/J 2 2% OF Crew checks core power distribution EACH OTHER NORMAL CHANNEL DEVIATION light - LIT (due to failed inst)

A4-4F - NIS POWER RANGE COMPARATOR - LIT (due to failed inst)

Delta Flux Indicators -~WII TARGET BAND Control Rod Positions GREATER

~

RO reports Rods above RIL THAN RIL BVPS - 2 Scenario 3 13 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE I OWER STATION I

112-ADM-1357 Conduct of Simulator Traininq INSTRUCTIONALGUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE Reactor Power 350% RO reports power level QPTR in progress STA previously directed to perform QPTR A4-3C TAVG DEVIATION FROM TREF Crew refers to ARPs as required

- mayimay not be lit depending on progress of load reduction at this time Crew completes actions of AOP 2.1.8 EVENT #3:

Normal Power reduction US contacts Reactor Engineering for a complete reactivity plan to complete the load reduction After appropriate delay, provide the Crew refers to 20M-52.4.B Load Follow crew with a reactivity plan that will for the load reduction allow the continued power reduction Power < 100% AND load change will be GREATER than 2%

Turbine control ~ 1"STG IN BOP transfcrs turbine control in 1" STG IN mode BVPS - 2 Scenario 3 14 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE I I OWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision 7 Setter - SET TO LOWER VALUE BOP sets the EHC SETTER to a lower value as directed by the US 1%Imin selected BOP selects l%Imin load rate on EHC panel Turbine load - REDUCING BOP depresses the GO pushbutton on the EHC control panel when directed Blender controls set as desired per the RO sets the blender controls for the desired reactivity plan boration rateiamount as determined by the reactivity plan MAINTAIN : Crew maintains planthrbine & generator TavgITref WII i 2F parameters as specified by 20M-52.4.B during the load reduction AFD WII limits of CB-14 (TS 3.2.3 AXIAL FLUX DIFFERENCE)

Control Rods ABOVE RIL as defined by COLR Fig 4.1-1 VPL at 5% above turbine load Generator parameters W/I limit of Calculated Capability Curve 2 0 M -

52.5.A.5 (Figure 52-5) between a power factor of 0.90 lagging and 1.0

[2GSS-MOV204] - . ADJUSTED as necessary to maintain gland steam pressure BVPS - 2 Scenario 3 15 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE I . OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina Continue with next set of events at LE discretion:

EVENT #4 Loss of 1 Main Feedwater Pump IMF PMP-CFWOOS (0 0) 1 [2FWS-P21B] trips BOP reports [2FWS-P21B] has tripped IMMEDIATE PLANT RESPONSE:

A6-IUA h b kkkD P U M P 21 A B AUTO-STOP (Y0438D)

SG levels begin to reduce 3 Main Feed Reg Valves begin to open SG Levels recover in automatic control BOP monitors SG levels, reports levels recovering Crew refers to AOP 2.24.1 and ARPs for loss of Main Feedwater Pump

[2CNM-P21 B,C] Condensate Pumps - BOP checks status of Condensate & Drains RUNNJNG pumps

[2HDH-P21A,B] Heater Drain Pumps -

RUNNING

[2HDH-P22A,B] Separator Drains Pumps NOT RUNNJNG BVPS - 2 Scenario 3 16 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE) OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training-Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE BOP starts pumps as ncccssary NOTE: When crew discovers that Reactor Power > 52% BOP reports [2FWS-P21A] is Running

[2FWS-P24] is unavailable, they may conservatively trip the reactor and go to ONLY ONE MFP RUNNING Crew attempts use of [2FWS-P24] , Startup E-0. If so, go to page of this scenario Feed Pump

[2CNM-DCV100] - OPEN BOP opens [2CNM-DCV100] Condensate Demin Diff Control Vlv IMF-VLVCFW027 (0 0) 0 [2FWR-FCV15.S] DOES NOT OPEN

~

BOP attcmpts start of [2F\VS-P24] by Prevent opening of [2FWR-FCV155] placing pump start switch to START and holding until [2FWR-FCV155] opens (PRE-LOAD)

[2FWS-P24] -DOES NOT START BOP reports [2FWS-P24] did not start Rx power < 80% - TRIP NOT REQUIRED RO reports reactor power -c 80%

Crew begins Emergency S/D to 50% power IAW AOP 2.51.1 Emergency Shutdown NOTE: The Emergency S/D is scripted Standby Alarm sounded Crew alerts plant personnel of emergency for a reduction to an end point of Emergency S/D announced SID approximately SO% power and 4KV EPP busses WILL NOT be transferred to offsite power.

BVPS - 2 Scenario 3 17 of 28 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE 3 PORVs - AVAILABLE (3 block vlvs RO reports PORVs available open, 3 PORVs in auto)

NOTE: Proceed to the next event at For 2%/min - USE 20M-7.4.AR RO begins boration at directed rate any time during the Emergency S/D at BLENDER OPERATION TN MODE 1 the LE discretion For 5%/min - USE 20M-7.4.Q EMERGENCY BORATION Turbine Control 1STG IN MODE

~ BOP starts power reduction at directed rate Load reduction rate thumbwheel set as directed GO Pushbutton PRESSED

~

Governor valves function properly BOP monitors turbine operation during transient Control rods in AUTO or Manual as RO maintains Tavg/Tref within +/- 5F with desired autoimanual rods as directed PZR HTRS ~ ALL ON RO places all PZR heaters to ON VPL at 5% above GV position BOP maintains VPL at proper position during transient 4KV BUSSES NOT TRANSFERRED

~

Crew does not transfer 4KV busses to TO OFFSITE offsite BVPS - 2 Scenario 3 18 of 28 Rev. 1 (45 day submittal)

NOTE: If crew tripped the reactor Crew notifies SYSTEM CONTROL of earlier, DO NOT trip [2FWS-P21B] emergency power reduction until after transition to ES-0.1 Reactor Power approximately 50% Crew stops power reduction Turbine Control HOLD

~

EVENT #5 Loss of the 2dMain Feedwater Pump IhlF PhlP-CFb00.1(0 0) 1 [2I%S-P2:A] trips, no &fain Fcc&Gatcr BOP reports trip of only running Main Pumps operating Feedwater Pump US directs RO to manually trip the reactoi Reactor Tripped RO manually trips the reactor Crew enters E-0, performs immediate Crew perfoms IMAs of E-0.

operator actions.

Annunciator A5-6D TURBlNE TRIP DUE RO verifies reactor tripped TO REACTOR TRIP - LIT Power range indication - LESS THAN 5%

Neutron flux - DROPPING BVPS - 2 Scenario 3 19 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE I OWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision 7 EVENT #6 Auto Turbine trip failure, manual BOP verifies turbine tripped REPORTS successful AUTO TRIP FAILURE and manually trips the Main Turbine Main turbine fails to auto trip, manual successful (PRE-LOAD) Throttle Valves - ALL CLOSED OR IMF EHCOSA (0 0) Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN CRITICAL TASK Exciter Circuit Bkr - OPEN Crew manually trips the main turbine hefore a Severe (orange path) challenge develops to either the Sub-criticality or the Integrity CSF or before transition to ECA-2.1, whichever occurs first.

AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency ENERGIZED Buses.

Check SI ACTUATED

~

RO checks SI status CNMT Pressure - 5PSIG PZR Pressure - < 1860 PSIG CREW DETERMINES SI IS NOT SG Steam Pressure - < 500 PSIG REQUIRED, TRANSITIONS TO ES-0.1 STEP 1 Crew transitions to ES-0.1 Step 1 US directs STA to monitor status trees.

BVPS - 2 Scenario 3 20 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE . OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training SOUND Standby Alarm Crew alerts plant personnel of reactor trip U2 Rx Trip . - ANNOUNCED

~

RCS Temp STABLE AT OR

~ Crew monitors RCS temperature for proper TRENDING TO 547F: response Tavg - RCPs RUNNING Tcold - RCPs NOT RUNNING RCS temperature maintained by Condenser Crew sets Condenser Steam Dumps to Stm Dmps: maintain RCS temperature in .4VTO MSIVs AT LEAST 1 OPEN

~ OR Condenser AVAILABLE

~'

Stni Dmps adjusted to slightly above Stm Crew uses SG Atmospheric Stm Dmp Vlvs HDR Pres Stm Dmps Controller MANUAL

~

OR Output Demand ZERO~

Stm Dmps STM PRESS MODE

~

RHR Vlv Tavg Interlock DEFEATED (if req)

~

Stm Dmps Controller - AUTO Controller Setpoint -ADJUST AS NECESSARY BVPS ~ 2 Scenario 3 21 Of28 Rev. 1 (45 day submittal)

BEAVER VALLEI CWER STATION I

112-ADM-1357 Conduct of Simulator Traininq IF NOT previously performed trip

[2FWS-P21B] at this time Loss of the 2dMain Feedwater Pump

[2FWS-P21A] trips, no Main Feedwater BOP reports trip of only running Main IMF PMP-CFW004 (0 0) 1 Pumps operating Feedwater Pump EVENT #7 & 8 Complete loss of all feedwater ~ FR-H.l conditions (PRE-LOAD)

IRF LOA-AFWO22 (2 0) 1 [2FWE*P22] trips during startup IMF PMP-CFW008 (0 0) 2 [2FWS-P24] cannot be started IMF PMP-AFW002 (3 180) 1 [2FWE*P23B] trips 180 seconds after startup All feedwater pumps - STOPPED Crew checks Feedwater Status Annunciators A5-2C(3C)(4C) SG 21 A(21B)(21C) LEVEL LOW-LOW REACTOR TRIP - ANY LIT AS FIRST OUT NO AFW Pumps RUNNING NO AFW Flow to SGs STA rcports FR-11.1 m t r y conditions arc met BVPS - 2 Scenario 3 22 of 28 Rev. 1 (45 day submittal)

RCS Pressure is > SG pressure Crew checks if Secondary Heat Sink is RCS Hot Leg Temperature > 350F required WR level in at least 2 SGs is above 14% Crew checks ifRCS Bleed and Feed should

[32% ADVERSE CNMT] be initiated PZR pressure is <2330 psig PPDWST > 85 inches BOP checks PPDWST level >. 85 inches

[2BDG*AOV 1OOAl ,B1,C 11 SGBD BOP try to establish AFW flow to at least 1SOLATION VALVES CLOSED ~

onc SG

[2SSR*AOV117A,B,C] BLOWDOWN SAMPLE OUTSIDE CNMT S O L VLVS

~ CLOSED No Motor Driven AFW pumps available BVPS - 2 Scenario 3 23 of 28 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE [ OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE Turbine Driven AFW Pump Steam Supply Valves OPEN

~

SG 21A [2MSS*SOVIOSA,D]

SG 21B [2MSS*SOVIOSB,E]

SG 21C [2MSS*SOVlOSC,F]

AFW throttle valves - OPEN Computer point YS 172D Turb DR AFW PP Tripped FWE*P22 Inop IN ALARM

~

STATE FW-P-2 Tripped/mechanical damage Crew continues to try to restore AFW Total Flow - LESS THAN 340 GPM USiCrew continues with FR-H.l RCPs ~ Stopped RO stop RCPs CRITICAL TASK Condensate system AVAILABLE, IN

~ BOP try to establish MFW flow to at least 1 Crew establishes feedwater flow into at SG least one SG before RCS feed and blecd [2FWS*HYVlS7A,B,C] OPEN is required.

[2FWS-P24] Startup Feed Pump ~ BOP reports Both Main feed pumps and the UNAVAILABLE Startup Feed Pump are unavailable

[2FWS-P21A,B] UNAVAII,ART,E

~

BVPS - 2 Scenario 3 24 of 28 Rev. 1 (45 day submittal)

All SGNR Levels LESS THAN 12%

~ BOP reports status of SGNR levels

[31% ADVERSE CNMT]

Letdown ~ NOT IN SERVICE Crew prepares for RCS depressurization to less than 2000 psig ONE PORV - OPEN RO opens ONE PORV to perform the depressurization RCS pressure - < 2000 psig RO closcs PORV and stops the depressiirimtinn PORV - CLOSED

[2CHS*MOV310] -OPEN RO restores normal charging flow

[2CHS*FCV122] - ADJUSTED TO MAINTAIN PZR LEVEL Low Steamlinc Press SI - BLOCKED RO blocks SI Signals Low PZR Pressure SI BLOCKED

~

BVPS - 2 Scenario 3 25 of 28 Rev. 1 (45 day submittal)

BEAVER VALLE , OWER STATION 112 - ADM - 1357 Conduct of Simulator Traininq-Revision 7 INSTRUCTIONAL GUIDELINES OBJECTIVE EXPECTEDSTUDENTRESPONSE MSIVs I OPEN

~

Crew begins SG depressurization to less CONDENSER AVAILABLE

~

than 440 psig to establish condensate flow by dumping steam to the condenser at the STEAM DMPS MANUAL

~

max rate DEMAND - ZERO STEAM DUMPS IN STM PRES MODE Crew uses SC Atmospheric Steam Dumps

~

TAVG - > 541F IF MSLI occurs A12-3F NOT LIT Steam Dump Rate GRADUALLY

~

RAISED Tavg approaches 541 F (A12-3F lit) BOP blocks low Tavg interlock when Tavg IN I'MLOCK BLOCKbD rcquircd FOLLOWING CONDITIONS Crew cstablishcs condensate flow to at least ESTABLISHED: one SG per Attachment A-1.10

[2FWE*P23A,B] PTL ~

[2FWS-P21A,B] PTL ~

[2FWS-P24] - PTL

[2FWS*FCV478,488,498] CLOSED ~

[2FWS-MOV154A,B,C] - CLOSED

[2FWS*FCV479,489,499] CLOSED ~

[2FWS-MOV155A,B,C] - OPEN US dispatches operators to MCCs to assist in establishing conditions per Att. A-1.10 BVPS - 2 Scenario 3 26 of 28 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTEDSTUDENTRESPONSE IMF VLV-CFW043 (0 0) 0 [2FWS-MOVlSOA] OPEN BOP opens [2FWS-MOV150A]

IMF VLV-CFW044 (0 0) 0 [2FWS-MOV150B] OPEN BOP opens [2FWS-MOVISOB]

IMF VLV-CFW045 (0 0) 0 [2FWS-MOVIS2] OPEN BOP opens [2FWS-MOVlS2]

When directed to locally close [2FWS-HCV2001:

IRF LOA-CFW037 (0 0) 2 [2FWS-HCV200] - CLOSED US dispatches operator to locally close

[2FWS-HCV200]

Then report valve is closed

[2CNWDCV100] OPEN ~ BOP checks [2CNM-DCV100] open

[2CNM-P2IB,C] -RUNNING BOP checks condensatc pumps operating SI - HAS NOT OCCURRED Crew checks SI Status

[2FWS*HYV157A,B,C] OPEN ~ Crcw checks FWI valves open

[2~WS-~CV47Y,4t;Y,4YY]Ihrottled open

~ BOP operates [2FWS-FCV479,489,499] as to establish feed flow to each SG directed to establish feed flow to each SG BVPS - 2 Scenario 3 Rev. 1 (45 day submittal)

BEAVER VALLE . OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE Level rising on [2FWS-LR477] Crew checks SG level rising Crew continues with FR-H.1 Feed Flow verified to at least one SG Crew verifies feed flow established IF ON SCALE SGNR Level rising in

~

Crew checks SGNR levels SG/SGs selected for feeding BOP maintains feed flow to SGs until SGNR level > 12% [31% ADVERSE CN\4T] in at lezst one SG Core Exit TCs DROPPING

~

SG Wide Range Level RISING IN AT

~

LEAST ONE SG Heat Sink Restored US/Crew returns to Procedurektep in effect, returns to ES-0.1 Scenario may be terminated when Condensate flow is established Classify Event at the end of the SAE Tab 2.2 ~ CSF RED PATH on HEAT scenario SINK BVPS - 2 Scenario 3 28 of 28 Rev. 1 (45day submittal)

Appendix D Scenario Outline Form ES-D-1 Facility: BVPS 2 Scenario No.: 4 Op Test No.: NRC Examiners: Candidates: SRO

- ATC

~ BOP

[nitial BOL, 100% power Equ Xe, CB 229, 1459 PPM IC-168 Conditions:

Turnover: Maintain current plant csnditions 2CHS*P21C HHSI Purrp 00s. Will be returned in approximately 1 week Critical Tasks: 1 . E-O.A Crew manually trips the reactor from the control room before performing the mitigation strategy of FR-S.1.

2. E-0.D Crew manually actuates at least one train of SIS-actuated safeguards before transition to any OW.
3. ECA-3. I .B Crew initiates cool down of the RCS to cold shutdown conditions at the h hest rate achievable but less than IOOF per hour in all

~

~

RCS c( 1 legs.

Event Malf. No. Event Event Description No.

_______ Type*

1 XMT-MSSO42A I(ALL) 2MSS*PT446 Selected First Stage Pressure Transmitter fails LOW SRO T.S.

7 L PMP-CHS002 C(RO/SRO) 2CHS*P21B HHSI Pump trips SRO T.S.

N/A R(RO) Crew begins power reduction V(BOPISR0)

A XMT-RCSO30A I(RO/SRO) 2RCS-PT444 P E R Pressure Control Channel fails HIGH 5 VLV-RCS032 C(ROISR0) [2RCS*PCV455C] PRZR PORV sticks open after lifting. block valve closure required 6 IMF PPLOl A I(RO/SRO) Automatic reactor trip failure Manual Rx trip from IMFPPLOlB BB B UNSUCCESSFUL, Manual RX trip from BB A SUCCESSFUL IOR XBI IO21 T 7

RCS04C M(ALL) 350 GPM SGTR on C SG with all MSZV. stuck open VL v-MSSOO3 VL V-MSSOO4 VL V-MSSOOS 8 PPLOSA C(RO/SRO) Auto SI failure, both trains, manual actuation required PPLOSB (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021. Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 1

Scenario Summary Scenario 4 The crew will assume the shift at 100% power BOL equilibrium xenon. HHSI pump 2CHS*P21C is 00s. The crew is instruzted maintain current plant conditions. After the crew assumes the shift, Selected first stage pressure transmitter 2MSS*PT446 will FAIL LOW. Control rods will begin stepping ,nward. The crew will verify no load rejection and then place rod control to manual. The crew will then implement the actions of instrument failure procedure OM-24.4.117 Att.# 5 and stabilize the plant. The crew will swap controlling first stage pressure transmitters. After the US implements the required Technical Specification actions, HHSI pump 2CHS*P21B will trip. The crew will implement the actions of AOP 2.7.1, L O S S of ChargingiLetdown. Crew will isolate letdown and start the standby HHSI pump 2CHS*P21A. After the standby HHSI pump is started and letdown restoration is underway, and the US has implemented the appropriate Technical Specification actions, plant management will direct a power reduction to comply with the Technical Specification actions for only one operable HHSI pump.

During the power reduction PRZR pressure control channel 2RCS-PT444 will FAIL HIGH. This will cause P U R PORV 2RCS*PCV455C to open. PRZR PORV 2RCS*PCV455C will stick open forcing the crew to manually close the block valve.

When the crew stabilizes the plant, a 353 GPM tube rupture will occur. The reactor will fail to trip automatically but can be tripped from the control room BB-A switch ONLY (BB-B switch will not work). The crew will enter E-0, Reactor Trip or Safety Injection.

The actions of E-0 will be complicated hy the failure of SI to automatically actuate, this will require the crew to manually actuate SI. The crew will verify ECCS equipment operating and diagnose a SGTR. The cr,:w will transition into E-3, SGTR. The actions of E-3 will be complicated by the failure ofall MSIVs to CLOSE. This will require the crew to transition into ECA-3.1, SGTR With Loss Of Reactor Coolant Subcooled Recovery

~

Desired. The scenario is terminated when a cooldown to mode 5 has commenced in ECA-3.1.

EOP Flow Path:

E-0, Reactor Trip or Safety Injection + E-3, SGTR Reactor Coolant Subcooled Recovery Desired.

~

- ECA-3.1, SGTR With Loss Of BVPS - 2 Scenario 4 2 Of 33 Rev. 1 (45 day submittal)

BEAVER VALLE , OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training Revision 7 CONDITIO S: - 00% Power, BOL, CB D = 229, 1459 PPM Boron IC-I 68 ADDITIONAL LINEUP CHANGES 1 STICKERS 1 VOND MARKINGS EQUIPMENT STATUS DATE/TIME 00s TECHNICAL SPECIFICATION(S)

[2CHS*P2 1C] Yesterday 1300 SHIFT TURNOVER INFORMATION

1. Protected Train i s Train B
2. (2CHS*P21C] is 00s for motor replacement and will not be retumcd until next week
3. Maintain current plant conditions 4.

SCENARIO SUPPORT MATERIAL REQUIRED Reactivity plan placard for BOL Placard for [2FWE*P22] position stating [2FWE*P22] is aligned to A hcadcr Place plaque on wall for Protected Train B BVPS - 2 Scenario 4 3 of 33 Rev. 1 (45 day submittal)

Initialize IC Set 168, and establish Reactor plant at 100% power, BOL, initial plant conditions. equilibrium conditions. RCS boron 1459 PPM, CBD = 229 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the Setup section of the HTML File for this drill drill:

IMF PLPOSA (0 0) 0 Auto SI failure (both trains)

IMF PLP05B (0 0) 0 IMF VLV-MSS003 (0 0) 1 3 MSIVs fail open and cannot be closed IMF VLV-MSS004 (0 0) 1 IMF VLV-MSS005 (0 0) 1 IMF PPLOlA (0 0) 0 batlure of auto Kx trip TRN "A" IMF PPLOlB (0 0) 0 Failure of auto Rx trip TRN "B" IMF RCS04C (30 0) 350 'C' SGTR 350 gpm IMF VLV-RCS032 (30 0) 1 [2RCS*PCV455C] sticks open IMF XMT-RCS030A (30 0) 2500 [2RCS-PT444] fails high IOR XBlI021T (0 0) 0 Prevent manual trip from BB B TRGSET 1 'RRCH535 <= 0.899' Trigger 1 on [2RCS*MOV535] position IMF VLV-RCSOll(1 0) 3 [2RCS*MOV535] sticks partially open until a reactor trip occurs TRGSET 2 'MCRFNS(3) <=225' Trigger 2 on reactor trip TRG 2 'DMF VLV-RCSO11' Trigger 2 allows closure of

[2RCS*MOV535]

TRGSET 3 'XB11042C == 1' Trigger 3 on [2RCS*MOV535] switch position to close BVPS - 2 Scenario 4 4 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE . OWER STATION 112 -ADM - 1357 Conduct of Simulator Trainina IOR XBI0042R (3 0) 1 Trigger 3 fails RED light on for

[2RCS*MOV535]

TRGSET 4 'RRCH535 <= 0.1' Trlgger 4 on [2RCS*MOV535] position TRG 4 'DOR XB10042R' Trlgger 4 allows RED light to go out for

[2RCS*MOV535]

Assign shift positions SM:

US:

RO:

BOP:

STA:

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

When the shift turnover is completed, Simulator running Crew assumes control ofthe Unit place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 4 5 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE , . OWER STATION 112-ADM- 1357 Conduct of Simulator Trainina EVENT #1:

[2MSS*PT446] fails low IMF XMT-MSS042A (0 0) 0 IMMEDIATE PLANT RESPONSE: Crew reports no load rejection, diagnose 1A FIRST STAGE STM PRESS failure of [2MSS*PT446]

[2MSS*PI446] Ch I11 indicates low (VB C)

(P2840D) TURB ISTSTAGE PRESS Ttd"(g:l p e ~ iiidiates

~) 5 3 T 011 recorder [2RCS-TR408] (VB B)

Control rods begin to step in at fast speed Ann A4-3C TAVG DEVIATION FROM TREF actuates (T0507D)

Ann A6-12G AMSAC TROUBLE actuates (Y2522D)

Panel 18 Status light D- 10 STM DUMP TRIP OPEN actuates Control rod motion stops US directs RO to place control; rods in manual AOP 2.1.3 STARTS HERE US directs crew actions for AOP 2.1.3 NO LOAD REJECTION Crew reports no load rejection in progress BVPS - 2 Scenario 4 6 O f 33 Rev. 1 (45 day submittal)

BEAVER VALLE, . OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina INSTRUCTIONAL GUIDEL~NES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE Rod Motion - STOPPED US directs RO to place Control Rods in MANUAL Tavg REDUClNG

- US directs preparation for load reduction to Restore Tavg by load reduction match Tavg/Tref OPERABLE PRNIS - WII + 2% OF Crew checks core power distribution EACH OTHER NORMAL CHANNEL DEVIATION light - NOT 1.1T

.44-4F NIS POWER RANGE COMPARATOR N O T LIT Delta Flux Indicators - WII TARGET BAND Control Rod Positions - GREATER RO reports Rods above RIL THAN RIL Reactor Power > 50% RO reports power level QPTR in progress STA previously directed to perfom QPTR A4-3C TAVG DEVIATION FROM TREF Crew refers to A R P s as required

- LIT (due to failed inst.)

BVPS - 2 Scenario 4 7 of 33 Rev. 1 (45 day submittal)

Power operation continues US directs recovery efforts to restore Minimize turbine load changes TavgiTref Adjust boron to control Tavg Crew completes actions of AOP 2.1.3 180 SECONDS after the transmitter Crew refers to appropriate ARPs failure Ann A12-1E AMSAC BYPASSED BY C-20 PERMISSIVE actuates Crew refers to IF procedure 24.4.IF ATT 5

[2MSS*PT446] has failed low BOP reports [2MSS*PT446] failed low Control Rods previously placed in Manual RO reports Control Rods in Manual, rod motion stopped

[2MSS*PT447] selected BOP selects redundant channel A4-3C Clears (possible) [2MSS*PT447] on BB C BVPS - 2 Scenario 4 a of 33 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE Crew refers to 20M-1.4.ACJ for AMSAC restoration Control Rods MAY be returned to AUTO RO places Control Rods to AUTO IF if desired Directed US refers to TS 3.3.1 and Table 3.3.1-1 Function 17.f TS 3.3.1 W!I 1 Hr: Verify interlock is in required state for existing plant conditions BVPS - 2 Scenario 4 9 Of 33 Rev. 1 (45 day submittal)

BEAVER VALLEk ,*OWER STATION 112-ADM-1357 Conduct of Simulator Traininq When dircctcd to locally rcarm US directs additional personnel to rearm AMSAC: AMSAC IAW 20M-1.4.ACJ IMF BST-PCS014 (0 0) 0 Test switch [TPSDMSS 4461 in test (up) position Then report actions to the Control Following test lights are ON:

Room [TL/2MSS446]

[TL/2MSS447]

[TL/2MSS440A] (212 impulse pres 1 4 0 % )

[TL/2MSS440B] (C-20 permissive)

Ann A12-1E AMSAC BYPASSED BY C-20 PERMISSIVE clears Proceed with the next event at LE discretion BVPS - 2 Scenario 4 10 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE. . OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina EVENT #2:

IMMEDIATE PLANT RESPONSE:

2CHS*P21B Trips [2CHS*P21B] bright white LIT (BB A)

[2CHS*II21B] 21B CHG Pump Amps IMF PMP-CHSOOZ (0 0) 1 indicates 0 (VB A) Crew diagnose trip of [2CHS*P21B]

[2CHS*FI122A] charging flow indicates 0 (VB A)

[2CHS*FII 30A, FI127A, FI124A1,RCPs US dispatch personnel to investigate the Seal injection indicates 0 (VB A)

Role-play field operator and report loss of [2CHS*P21B]

Annunciators Actuate:

motor ground.

A 2 - l D CHARGING P l ~ i M PAI-ITO-STARTIAUTO-STOP (YO1 16D)

A2-3E CHARGING FLOW PATH TROUBLE (FOlOID)

A2-4D REACTOR COOLANT PUMP SEAL TROUBLE(F0112D, F0116D, F0118D)

[2CHS*TI140] Regen HX Letdown Temp begins to increase (VB A)

[2CHS*TI144] Letdown Temp begins to increase (VB A)

[2RCS*LI459A, LI461, LI4601 PZR level CH I, 111, I1 begin to decrease (BB B)

DELAYED RESPONSE:

Ann A2-3F LETDOWN FLOW PATH TROUBLE actuates (T0127D)

BVPS - 2 Scenario 4 11 of 33 Rev. 1 (45 day submittal)

[2CHS*AOV200A,B,C] - CLOSED RO closes LID orifice isolation valves

[2CHS*LCVl15C,E] - OPEN RO verities CHP suction valves from VCT open VCT Level - NORMAL Crew verifies CHP did not triplstop due to VCT Pressure NORMAL

~

cavitation

[2CHS*FCV122] - CLOSED RO closes charging pumps discharge flow control v-alve

[2CHS-HCV186] - CLOSED RO closes RCP seal injection flow controller

[2CHS*P21A] -RUNNING RO starts the standby charging pump

[2CHS*P21B] PTL ~ RO places tripped charging pump in PTL

[2CHS-HCV186] adjusted to obtain 6 to 9 RO adjusts RCP seal injection flow to 6 to 9 gpm on [2CHS-F1130A, 127A, 124Al gpm for each RCP

[2CHS*FCV122] adjusted as required to RO adjusts charging pump discharge flow restore PZR level AND THEN placed in control valve to restore lcvcl as required and AUTO then places valve in auto BVPS - 2 Scenario 4 12 of 33 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE After appropriate delay report that [2CHS*P21A] operating properly US dispatch operator to ensure proper

[2CHS*P2 1A] is operating properly operation of [2CHS*P21A]

US directs operators to restore Letdown flow IAW 20M-7.4.AB

[2CHS*FCV122] - CLOSED RO places [2CHS*FCV122] in manual and closes the valve

[2CHS*MOV289] - OPEN RO verifies [2CHS*MOV289] open

[2(-HS*MOVllO] -OPEN

[2CHS*FCV122] throttled to obtain 30 RO throttlcs charging pump discharge flow 50 gpm on [2CHS*FI122] (VB A) control valve open to provide 30 50 gpm

~

flow as indicated on [2CHS*F1122] (VB A)

[2CHS*AOV200A, B, C] - CLOSED RO verifies 3 L/D isolation valves are closed

[2CHS*AOV204] - OPEN RO verifies the NRHX L/D inlet valve is open (BB A)

[2CHS*PCV145] IN MANUAL AND RO place NRHX Disch Pres control valve ADJUSTED TO 50% OPEN DEMAND in MANUAL and adjusts for 50% output SIGNAL (BB A) demand BVPS - 2 Scenario 4 13 of 33 Rev. 1 (45 day submittal)

BEAVER VALLEi ,-OWER STATION 112-ADM-1357 Conduct of Simulator Training

[2CHS*MOVIOOA] OPEN RO verities positions of

[2CHS*MOVlOOB] ~ CLOSED [2CHS*MOV 1OOA], [2CHS*MOVI OOB]

[2CHS*LCV46OA, B ] - OPEN RO verifies Regen HX LID Inlet valves open

[2CHS*AOV20OA, B] - OPEN RO opens LID isol valves to establish LID flow at previous value

[2CHS*PCVI45] adjusted to maintain 260 RO establishes automatic control of letdown psig as indicated on [2CHS*PIl45] flow SETPOINT of [2CHS*PCV145] -SET FOR 260 PSIG

[2CHS*PCV145] PLACED IN AUTO US directs personnel to perform 20ST-6.4

[2CHS*FCV122] PLACED IN AUTO PZR level trending to normal RO monitors PZR level for proper response BVPS - 2 Scenario 4 14 of 33 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE US refers to TS 3.5.2, 3.5.3 and LRM 3.1.3, 3.1.4 TS 3.5.2: 2 ECCS TRAINS SHALL BE OPERABLE: Restore 2 Trains W/I 72 Hrs OR MODE 3 W/I 6 Hrs OR MODE 4 WII 12 Hrs TS 3.5.3. a;Fp!icahle MODE 4 ONLY LR\%3.1.3: Applicable MODE 5 ONLY LRM 3.1.4: 2 Charging Pumps SHALL be OPERABLE MODE 1 - 4: Restore two pumps to OPERABLE status W/I 72 Hrs OR MODE 3 WiI 6.0 Hrs AND borated to SDM of 1% D K K at 200F AND restore the required charging pump to OPERABLE status WiI 174 Hrs When informed as plant management, US informs plant management of the loss of direct the US to begin power reduction [2CHS*P21B] and the requirement to S/D at 12 % hr due to the status of [2CHS*P21C]

BVPS - 2 Scenario 4 15 of 33 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #3: Crew develops a reactivity plan for power reduction of 12%/hr Normal Power reduction US contacts Reactor Engineering for a complete reactivity plan to complete the load reduction After appropriate delay, provide the Crew refers to 20M-52.4.B Load Follow crew with a reactivity plan that will for the load reduction allow the continued power reduction Turbine control - lsTSTG OUT BOP verities turbine control in Is' STG OUT modc Setter - SET TO LOWER VALUE BOP sets the EHC SETTER to a lower value as directed by the US 1%/min selected BOP selects l%/min load rate on EHC panel Turbine load ~ REDUCING BOP depresses the GO pushbutton on the EHC control panel when directed Blender controls set as desired per the RO sets the blender controls for the desired reactivity plan bordtion rate/amount as determined by the reactivity plan BVPS - 2 Scenario 4 16 of 33 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE MAINTAIN: Crew maintains plant/turbine & generator TavgiTref WII 2 2F parameters as specified by 20M-S2.4.B during the load reduction AFD WII limits ofCB-14 (TS 3.2.3

'AXIAL FLUX DIFFERENCE')

Control Rods ABOVE RIL as defined by COLRFig4.1-1 VPL at 5% above turbine load Generator parameters WII limit of

'Calculated Capability Curve' 20M-52.S.A.5 (Figure 52-5) between a power factor of 0.90 lagging and 1.0

[2GSS-MOV204] ADJUSTED as

~

necessary to maintain gland steam pressure Power - LESS THAN 98% BOP stops load reduction by pushing HOLD PB on EHC control panel Turbine Control - Transferred to 1 STG BOP transfers turbine control to 1"STG IN IN mode mode by pushing the 1 STG IN PB on EHC control panel Turbine Load - REDUCING BOP pushes GO PB on EHC control panel When Directed to resume load reduction Continue with next set of events at 1.E discretion:

BVPS - 2 Scenario 4 17 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE :OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Trainrna NOTE: the following Events #4 through 7 will occur simultaneously.

All commands are PRE-LOADED and w i l l actuate when Trigger 30 is fired EVENTS#4,5,6 7 IMMEDIATE PLANT RESPONSE:

Annunciators actuate:

(4) A4-1D PRESSURIZER CONTROL

[2RCS-PT444] Fails high PRESSURE HIGHiLOW (P0501D)

IMF XMT-RCS030A (30 0) 2500 A4-1E PRESSURIZER CONTROL PRESSURE DEVIATION (5) HIGH/LOW(P0503D)

[2RCS*PCV455C] Sticks open A4-2F PRESSURE RELIEF BLOCK IMF VLV-RCS032 (30 0) 1 (P0496D)

(6) A4-1A PRESSURIZER POWEWSAFETY Automatic reactor trip failure RELIEF TROUBLE (T0480D)

IMF PPLOlA (0 0) 0 A4-1F PRESSURIZER PORV OPEN

~

PERMISSIVE (Y6672D) (immediate IMF PPLOlB (0 0) 0 reset)

Manual trip from BB B unsuccessful A2-4B REACTOR COOLANT SYSTEM IOR XBlI021T (0 0) 0 SUBCOOLING OFF NORMAL (TO761D)

(7) A4-5A RADIATION MONITORING 350 GPM SGTR on C SG SYSTEM TROUBLE (R0003D)

IMF RCSO4C (30 0) 350 A4-5C RADIATION MONITORING LEVEL HIGH (R0004D)

BVPS - 2 Scenario 4 18 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE , , .OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina WHEN DIRECTED:

TRG! 30

[2RCS*LI459A, L1461, LI4601 PZR level CH I, III,11 begin to decrease (BB B)

[2RCS*P1455, PI456, PI4571 PZR pres CH I, 11, TIT begin to decrease (BB B)

[2RCS-P1445] PZR control prcs indicator begins to decrease (VB R)

[?RCS-PR441] RCS Wide rangc pressure recorder redigrcen pens begin to decrease (VB A)

RCS pressure rapidly reducing RO verifies alarms, diagnose [2RCS-PT4441 has failed high

[2RCS*PCV455A,B] CLOSED ~

RO closes Spray Valves, reduces MPC output to 0 EVENT #5 [2RCS*PCV455C] ~ STUCK OPEN RO attempts to close [2RCS*PCV455C]

reports it does not close

[ZRCS*MOV535] ~ TRAVELING RO cluscs [2RCS*MOV535]

CLOSED BVPS - 2 Scenario 4 19 of 33 Rev. 1 (45 day submittal)

BEAVER VALLEk ,-OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina IST OUT ANNUNCIATOR: A5-4H RO Reports 1 OUT Annunciator A5-4H PRESSURIZER PRESSURE LOW REACTOR T R P (P0488D)

EVENT #6 Reactor ~ NOT TRIPPED RO reports failure of automatic trip CRITICAL TASK Crew manually trips the reactor from the control room before performing the mitigation strategy of FR-S.1.

EVENT #6 Reactor ~ NOT TRIPPED Ro attempts manual trip from BB B, reports UNSUCCESSFUL EVENT #6 Reactor ~ TRIPPED Ro attempts manual trip from BB A, reports SUCCESSFUL

[2RCS*MOV535] -CLOSED RO reports [2RCS*MOV535] closed after reactor trip EVENT #I RCS Pressure APPEARS to recover until RO monitors RCS pressure and MAY the effects of the SGTR are seen report that it is recovering until the SGTR effects are seen Crew enters E-0, performs immediate Crew performs IMAs of E-0.

operator actions.

BVPS - 2 Scenario 4 20 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE /OWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision 7 Annunciator A5-6D TURBINE TRIP DUE RO verifies reactor tripped.

TO REACTOR TRLP - LIT Power range indication - LESS THAN 5%

Neutron flux - DROPPING Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - BOTH BOP verifies power to AC Emergency ENERGIZED Buses.

Check SI ACTUATED RO checks SI status CNMT Pressure - > 5PSIG PZR Pressure - < 1860 PSIG SG Steam Pressure - < 500 PSIG CREW DETERMINES SI REQUIRED Crew continues E-0 Manually actuate SI (both trains) RO manually actuates SI both trains Alert Plant Personnel ROIBOP sound Standby Alarm, announce reactor trip and safety injection EVPS - 2 Scenario 4 21 of 33 Rev. 1 (45 day submittal)

BEAVER VALLEk POWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE Check [2HVS*FN204A(B)], Leak BOP checks Leak Collcction Exhaust Fan Collection Filtered Exhaust Fan AT

~

status LEAST ONE RUNNING EVENT #8: Charging Pumps - ONE RUNNING RO verifies SI System status, reports auto HHSI Flow TNDICATED

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SI failure on BOTH Trains, MANUALLY actuates both trains of SI (PRE-LOADED) LHSI Pumps - TWO RUNNING Both trains of auto SI fail to actuate, BOTH TRAINS OF AUTO SI manual actuation successful FAILURE IMF PLPOSA (0 0) 0 ONLY ONE HHSl PUMP IMF PLPOSB (0 0) 0 OPERATING CRITICAL TASK Crew manually actuates at least one train of SIS-actuated yakguards before transition to any O W .

Motor-driven AFW Pumps - RUNNING BOP verifies AFW System status Turb driven AFW Pump Stm Supply Is01 Valves OPEN

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AFW Throttle Vlvs FULL OPEN

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Total AFW Flow GREATER THAN 340

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GPM BVPS - 2 Scenario 4 22 of 33 Rev. 1 (45 day submittal)

Perform Attachment A-0.1 1 Verification US directs performance of Attachment A-Of Automatic Actions in a timely manner 0.1 1 when timeimanpower permit Attachment A-0.11 is included and LIST ATT A-0.11 DISCREPANCIES begins on page 3 1 of scenario AS APPLICABLE:

Manual SI required -BOTH TRAINS ONLY ONE HHSI PUMP RUNNING RCPs OPERATING - MONITOR Tavg RO/BOP check RCS Tavg stable at or RCPs STOPPED ?vIOXITORTcold trcnding to 547°F Check CIB - HAS NOT ACTUATED RO checks Kecirc Spray Pump status PORVs 2 CLOSED -

~ RO verifies PZR isolated

[2RCS*PCV455C] Stuck OPEN, ISOL by

[2RCS*MOV535]

Spray Valves - CLOSED Safety relief valves - (PSMS Detailed Data Page 1) CLOSED Check PRT conditions - CONSISTENT WITH EXPECTED VALUES Power to at least one block valve ~

AVAILABLE Block valves AT LEAST ONE OPEN

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BVPS - 2 Scenario 4 23 of 33 Rev. 1 (45 day submittal)

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE D/P between RCS pressure and highest SG RO checks if RCPs should be stopped pressure -- LESS THAN 205 PSID [220 PSID ADVERSE CNMT] RO DOES NOT STOP RCPs AND HHSI Flow INDICATED Pressures in all SGs - ANY DROPPING BOP checks if any SGs are faulted.

IN AN UNCONTROLLED MANNER OR BOP REPORTS SGs NOT FAULTED ANY SG COMPLETELY DEPRESSURIZED Check all SG levels - C IS RISING IN Crew checks if SG tubes are intact AN UNCONTROLLED MANNER Check Secondary Radiation -

CONSISTENT WITH PRE-EVENT CREW REPORTS INDICATION OF VALUES SGTR ON C SG

[2ARC-RQ100] Air Ejector Discharge

( 1007)

[2SSR-RQl00] SG Blowdown Sample (1062)

[2MSS*RQI 01A,B,C] Main Steamline Discharge (1005,3005,5005)

Crew transitions to E-3 STEP 1 US directs transition to E-3 US directs STA to monitor status trees BVPS - 2 Scenario 4 24 of 33 Rev. 1 (45 day submittal)

CR radiation not in high alarm CIB has not occurred Crew commences control room ventilation action per Attachment A-2.5 D/P between RCS pressure and highest SG RO checks if RCPs should be stopped pressure LESS THAN 205 PSID [220

~

P S D ADVERSE CNMT]

2hJ HHSl Flow ~ INDICATED RO does not stop RCPs C SG ruptured US identifies C SG as the ruptured SG Unexpected rise in NR level Rad survey results:

ANY SAMPLE

[2MSS*RQl02A,B,C] SG N-16 monitors (1075,2075, 3075)

[2MSS*RQlOlA,B,C] Main Stm Monitors (1005, 3005, 5005)

High Radiation from any SG BD rad monitor BVPS - 2 Scenario 4 25 of 33 Rev. 1 (45 day submittal)

BEAVER VALLt ,?OWER STATION 112 - ADM - 1357 Conduct of Simulator Training US directs crew to isolate flow from the ruptured SG IF REQUESTED: Close atmospheric steam dump on ruptured BOP closes C SG atmospheric steam SG [2SVS*PCVlOIC] dump [2SVS*PCVlOlC]

IRF LOA-MSS018 (0 0) 0 Setpoint raised to 100%

To close [2SVS*25]

Check Residual Heat Release valve BOP closes [2SVS*HCV104].

CLOSED IRF 1,OA-MSSOll (0 0) 0 Check Residua! Hcat Rclcasc \ahC f i ~ i i i Crew dispatch operator to close [2SVS*29]

faulted SG CLOSED:

To close [2SVS*29] SG 21A [2SVS*29]

2 RUNNING BOP checks motor driven AFW pumps

[2MSS*SOVl05C & F] CLOSED BOP closes [2MSS*SOVIOSC & F]

SG-21C blowdown isol valve BOP closes SG 21C blowdown isol vlv

[2BDG*AOVl OOCl ] CLOSED SG-21C Main Stm Line drain BOP closes SG 21C main steamline drain

[2SDS*AOVlllCl]CLOSED vlv RHR Piping Drain [2SDS*AOVI29A] BOP closes RHR Piping drain vlv CLOSED BVPS - 2 Scenario 4 26 of 33 Rev. 1 (45 day submittal)

(PRE-LOADED) 3 MSIVs Stuck open NO MSIVs can be closed BOP reports that all 3 MSIVs are stuck open and cannot bc closed IMF VLV-MSS003 IMF VLV-MSS004 RUPTURED SG CANNOT BE ISOLATED FROM 1 INSTACT SG, GO IMF VLV-MSSOOS TO ECA-3.1 Crew transitions to ECA-3.1 Step 1 SI, CIA & CIB - RESET RO resets S1, CIA & CIB Open [2CCS-AOVl18]Domestic Water to Establish Domestic Water System Cooling Station Air Compressor to Station Air Compressors US directs additional personnel to perform Att A-1.20 as manpower pcrmits At least one Station Air Compressor Start 1 Station Air Compressor as required RUNNTNG BVPS - 2 Scenario 4 27 of 33 Rev. 1 (45 day submittal)

BEAVER VALLk. ,-OWER STATION 112 - ADM - 1357 Conduct of Simulator Trainina INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTEDSTUDENTRESPONSE

[2IAC-MOV131] & [21AC*MOV130] Crew establishes Inst Air to CNMT OPEN CNMT Inst Air Press > 85 PSIG All AC Busses ENERGIZED BY

~

BOP checks 4KV electrical status OFFSITE POWER All PZR HTRS - PULL TO LOCK RO places PZR HTRS in PTL Quench/Recirc Spray Pumps - NONE Crew checks if CNMT spray should be RUNNING stopped C SG level > 12% [ 3 1% ADVERSE BOP checks ruptured SG level CNMT]

[ZFWE*HCVlOOA,B] - CLOSED Crew isolates feed flow to C SG

[2FWS*HYVl57C] CLOSED Check FWI previously verified BVPS - 2 Scenario 4 2a of 33 Rev. 1 (45 day submittal)

BEAVER VALLE'f POWER STATION 112-ADM- 1357 Conduct of Simulator Training Revisinn 7 RCS Pressure - i225 PSIG [250 PSIG KO checks if LHSI Pmps should be stopped ADVERSE CNMT]

Pressure STABLE OR RISING

~

LHSI Pmps stopped and in auto RO stops LHSI Pmps and places them in auto Aux Bldg/Safeguards radiation ~ Crew evaluates plant status CONSIS'IENT WITH PKE-EVENT LEVELS Obtain Pertinent samples Pressures in all SGs ANY DROPPING

~ BOP checks if any SGs are faulted.

IN AN UNCONTROLLED MANNER OK Crew checks faulted SGs previously ANY SG COMPLETELY isolated unless needed or C/D DEPRESSURIZED SGs ARE NOT FAULTED Total AFW flow maintained >340 GPM BOP checks intact SG levels, controls AFW until SG level > 12% [31% adverse flow to intact SGs CNMT] THEN CONTROL AFW flow to maintain level between 26% [33% adverse CNMT] and 50%

BVPS - 2 Scenario 4 29 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE 8OWER STATION I

112 - ADM - 1357 Conduct of Simulator Training INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE Shutdown margin requirements arc US directs chemistry to sample as required, satisfied for cooldown Crew maintains SDM during CID CRITICAL TASK CID sate - < 1OOFIHT Crew initiates cooldown to MODE 5 at <

Crew initiates cool down of the RCS to Trend initiatedlinitialed at % hr interval 1OOF/hr cold shutdown conditions at the highest RHR used if in servicc rate achievable but less than 100°F per hour in all RCS cold legs. SI blocked when PZR Pres < 2000 PSIG Condenser Stni Dmps operated in BOP operates Condenser Stm Dmps as MANUAL control to cooldown required to maintain C/D rate W/1 limits Tavg interlock blocked < S41F Terminate drill after proper CID rate RWST Level - > 600 inches Crew checks if subcooled recovery desired cstablished 01-at LE discretion Ruptured (C) SG levcl - < 95% [79%

ADVERSE CNMT] IF NOT TRANSITION TO ECA 3.2 STEP 1

Classify event at the end of the scenario ALERT based on TAB 2.3 entry into E-3 BVPS - 2 Scenario 4 30 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE I r'OWER STATION 112 - ADM - 1357 Conduct of Simulator Training Revision

~. 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTEDSTUDENTRESPONSE Attachment A-0.1 1 'Verification of US directs operator to perform Attachment Automatic Actions' performed as time A-0. I 1 as time & manpower permit

&manpower permit Diesel generators - BOTH RUNNING Check both EDGs running CNMT pressure GREATER THAN 7

~

Check if MSLI is required PSIG OR If not required, go to step 4 SG Stcam Prcssure LESS THAN 500

~

PSIG OR Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIl Verify stearnline isolation STEP 4 Open [2CCS-AOVl18] Domestic Water to Establish Domestic Water System Cooling Station Air Compressor to Station Air Compressors At least one Station Air Compressor Start 1 Station Air Compressor as required RUNNlNG CCP pumps - A T LEAST 1 RUNNING Check CCP Pump status BVPS - 2 Scenario 4 31 of 33 Rev. 1 (45 day submittal)

BEAVER VALLEk r'OWER STATION 112-ADM-1357

[2NME-NR45] Nuclear Recorder selected Align neutron flux monitoring for shutdown to operable source and intermediate range displays CNMT pressure ~ HAS REMAIND LESS Check CIB status THAN 11 PSIG IF NOT Actuate CIB if required Manually initiate CIB -BOTH SLZ'ITCIIES FOR BOT11 TRAINS Manually align equipment as required All RCPs STOPPED

~

Stop ALL RCPs BV-1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps 2 RUNNING

~

Verify Service Water System in service Service Water Header Pressure ~

GREATER THAN 55 PSIG SWS Seal Water Pressure -NOT LOW

[2HCS*SOVlOOAl, BI] - CNMT Sample Verify both CNMT hydrogen analyzers amber light LIT

~

running BVPS - 2 Scenario 4 32 of 33 Rev. 1 (45 day submittal)

BEAVER VALLE ,'OWER STATION I

112 -ADM - 1357 Conduct of Simulator Training INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1 OBJECTIVE EXPECTEDSTUDENTRESPONSE MANUAL SI REQUIRED All Red SIS Marks LIT Verify ESF Equipment status - Startialign ONLY ONE HHSI PMP RUNNING All Orange CIA Marks LIT

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equipment as required All Green FWI Marks - LIT Power available to both Emergency AC Verify power to both AC Emergency busses Busses Restore power as required Attachment A-0.1 1 COMPLETE

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Report any discrepancies to SMiUS BVPS - 2 Scenario 4 33 of 33 Rev. 1 (45 day submittal)