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Exam Folder 3, Final Operating Examination
	ML16342C521
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Site:	Beaver Valley
Issue date:	09/28/2016
From:	; NRC Region 1
To:	;
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ML16076A416	List: IR 05000334/2016302; ML16089A007; ML16292A483; ML16342C521; ML17003A276; ML17003A277; ML17003A278; ML17003A280; ML17003A281; ML17003A282; ML17003A283; ML17003A284; ML17003A285;
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BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Calculating a Shutdown Margin Following a Stuck Rod TRAINING MATERIAL NUMBER: 1AD-001

~~~~~~~~~~~~~~~~~~~~~~~

PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lAD-001 REVISION NUMBER: 4 TECHNICAL

REFERENCES:

lOST-49.1, Shutdown Margin Calculation (Plant Critical), Rev. 23 Unit 1 Curve Book Cycle 24 Unit 1 LRM and Technical Specifications INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 25 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE

SUMMARY

Affected JPM: lAD-001 New Revision: 4 Description of Change(s):

1. Updated for current JPM format.

2. Updated for procedure and Curve book revisions.

3. Removed reference to curve book CB-13 in JPM step 9.

4. Updated values used for calculations throughout the JPM.

5. Changed task number to 0011-006-06-013 from 0011-006-01-013.

6. Task Standard: Add wording that the Surveillance is determined to be Satisfactory. Step 21.1 C:

Typo - change Block "B.4.f' to "B.5 Step 21.3 add wording "and initials Data Sheet 1 Answer Key: type in "Initials" on the form in line (1)

Reason for Change (s):

1. Changed format to the new JPM procedure (BVPS-TR-0026).

2. lOST-49.1 and Ul Curve book have been updated for Fuel Cycle 24.

3. CB-13 is not required. Core bumup is given in the initial conditions.

4. Values used for SDM calculations change with fuel cycles.

5. Task list update.

6. NRC comments

BVPS-TR-0026 Page 1of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-001 JPM TITLE: Calculating a Shutdown Margin Following a Stuck Rod JPM REVISION: 4 KlA

REFERENCE:

2.1.25 3.9/4.2 TASK ID: 0011-006-06-013 001 A4.11 3.5/4.1 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D SRO ONLY 0 ALTERNATEPATHJPM ~ ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC

~ Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The Shutdown Margin calculation is determined to be 2.5272 (+/-

0.100). Surveillance is determined to be satisfactory.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS:

The Unit is in Mode 1, 100% power

All rods are at 228 steps on the group demand counters

Annunciator [A4-46], TAVG DEVIATION FROM TREF is "Off'

A single Bank "D" Control Rod is stuck and indicates 228 steps

Current RCS boron concentration is 1620 ppm

Current core burnup is 100 MWD/MTU INITIATING CUE: Your Supervisor directs you to perform a shutdown margin calculation for the present plant conditions using 1OST-49 .1, Shutdown Margin Calculation (Plant Critical), and report your results in the COMMENT section of the OST cover sheet.

REFERENCES:

lOST-49.1, Shutdown Margin Calculation (Plant Critical), Rev. 23 Unit 1 Curve Book Cycle 24 TOOLS: Calculator HANDOUT: lOST-49.1, Shutdown Margin Calculation (Plant Critical), Rev. 23 with SM authorization signature.

Unit 1 Curve Book Cycle 24 Unit 1 LRM and Technical Specifications (as available reference)

BVPS-TR-0026 Page 3 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-001 JPM TITLE: Calculating a Shutdown Margin Following a Stuck Rod JPM REVISION: 4 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT):::>

EVALUATOR NOTE: Provide the Candidate with a copy of the attached lOST-49.1, Cycle 24 Curves, LRM, Tech Specs and a calculator.

START TIME: _ _ _ _ _ __

1. If the plant is in Mode 1, 1.1 Initials Step VII.A.1, (Plant in Mode 1, Tavg < 5°F Verify that Tavg is less than above Tref (Annunciator A4-46 OFF) from Initial 5°F above Tref (Annunciator Conditions.

A4-46, TAVG DEVIATION FROM TREF is OFF) COMMENTS:

(Otherwise NIA).

(Ste Vll.A.1

2. If the plant is in Mode 2, 2.1 Places NI A in Step VII.A.2, (Plant not in Mode 2).

Verify that Tavg is less than 8°F above Program Tavg as COMMENTS:

follows: (Otherwise NI A)

(Step VIl.A.2)

3. Request Chemistry to 3.1 Determines current boron concentration is 1620 ppm determine current RCS from initial conditions.

Boron concentration in ppm.

COMMENTS:

(Step VIl.A.3)

4. Record the number of steps 4.1 Records Control Bank D as 228 steps withdrawn on withdrawn for Control Bank Data Sheet 1 from initial conditions.

D from the group demand counters, (BB-B) on Data COMMENTS:

Sheet 1.

(Step VIl.A.4)

BVPS-TR-0026 Page 4of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-001 JPM TITLE: Calculating a Shutdown Margin Following a Stuck Rod JPM REVISION: 4 STEP STANDARD

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

5. Record the current reactor 5.1 Records reactor power as 100% on Data Sheet 1.

power level in percent of full power from initial COMMENTS:

conditions, on Data Sheet 1.

(Step Vll.A.5) 6.C Record the number of 6.lC Records number of inoperable (untrippable) OR inoperable (untrippable) OR dropped control rods as "1" on Data sheet 1 (given in dropped control rods on Data Initial Conditions).

Sheet 1.

COMMENTS:

(Step VIl.A.6)

7. If the number of inoperable 7.1 Places NIA in Step VII.A.7.

(untrippable) OR dropped control Rods is greater than COMMENTS:

1, Use Attachment 1 to determine the required boron concentration with greater than one struck rod and Record below. (Otherwise NIA)

(Step VII.A. 7)

8. With the number of 8.1 Places NIA in Step VII.A.8.

inoperable (untrippable) OR dropped rods greater than COMMENTS:

one, the shutdown margin is

< 1. 77% k/k. Perform Step VII.C.2 UNTIL the required boron concentration of Attachment 1 is reached.

(Step VIl.A.8)

BVPS-TR-0026 Page 5 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: IAD-001 JPM TITLE: Calculating a Shutdown Margin Following a Stuck Rod JPM REVISION: 4 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU 9.C Determine control bank 9.1 Recognizes initial plant core bumup is 100 reactivity worth per the MWD/MTU, based on initial plant conditions.

following:

9.2 Refers to ARO Total Bank Worth table on Data Sheet Using the ARO Total Bank 1 AND determines ARO Total Bank Worth to be Worth table on Data Sheet 1, 7.218.

Enter the total bank worth for the current core bumup 9.3C Records 7.218 on Data Sheet 1 (Block B.1.a).

range, in the space provided on Data Sheet 1. COMMENTS:

(Step VII.B.1.a) 10.C Using Curve Book Figures IO.IC Using Curve Book Figure CB-24A, determines CB24A, 24B OR 24C, integral rod worth to be ZERO and records on Data Determine integral rod worth Sheet 1 (Blocks B.1.b.l) and (B.1.b).

for the current bank position AND Enter this value on COMMENTS:

Data Sheet 1.

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

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

(Step VII.B.1.b)

11. Subtract the integral rod 11.1 Determines TBW-IRW is 7.218 %b.k/k and records worth from the Total Bank on Data Sheet 1 (Block B.1.c ).

Worth AND Enter the result on Data Sheet 1. COMMENTS:

(Step VII.B.1.c)

BVPS-TR-0026 Page 6 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-001 JPM TITLE: Calculating a Shutdown Margin Following a Stuck Rod JPM REVISION: 4 STEP STANDARD

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

12. Multiply this result by 0.9 to 12.1 Determines 90% ofTBW to be 6.4962 %~k:/k and apply a 10% uncertainty records on Data Sheet 1 (Block B.1.d).

AND Enter the result on Data Sheet 1.

COMMENTS:

(Step VII.B.1.d) 13.C If ONE rod is inoperable 13.IC Determines stuck rod worth to be 1.999 %~k:/k and (untrippable) OR dropped, records on Data Sheet 1 (Block B.2).

Record "Worst Case Rod with Inoperable Rod" worth COMMENTS:

on Data Sheet 1. Value is determined from Column "B" on Attachment 2 for the appropriate Cycle Burnup.

(Step VII.B.2.b)

14. Subtract Stuck Rod Worth 14.1 Determines 90% Total Bank Worth minus Stuck from the 90% Total Bank Rod(s) Worth to be 4.4972 %~k:/k and records on Worth value AND Enter the Data Sheet 1 (Block B.3).

result on Data Sheet 1.

COMMENTS:

(Step VII.B.3)

15. Determine Power Defect as 15.1 Record RCS Boron Concentration of 1620 ppm on follows: Data Sheet 1 (Block B.4.a).

Record RCS Boron COMMENTS:

Concentration results from Chemistry on Data Sheet 1.

(Step VIl.B.4.a)

BVPS-TR-0026 Page 7of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-001 JPM TITLE: Calculating a Shutdown Margin Following a Stuck Rod JPM REVISION: 4 STEP STANDARD

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

16. Using Curve Book Figure 29, 16.l Determines B-10 Correction Factor to be 0.989 and Determine the B-10 records on Data Sheet 1 (Block B.4.b).

Correction Factor for the present Burnup (If between COMMENTS:

two Burnup values, Use the B-10 Correction Factor for the greater MWD/MTU Burnup entry) AND Record on Data Sheet 1.

(Step VII.B.4.b)

17. Determine Corrected Boron 17.1 Determines Corrected Boron Concentration to be Concentration by multiplying 1602 ppm and records on Data Sheet 1 (Block B.4.c).

the RCS Boron Concentration and the B-10 COMMENTS:

Correction Factor AND Record on Data Sheet 1.

(Step VII.B.4.c)

18. Using Curve Book Figure 21, 18.1 Determines ABSOLUTE VALUE of the Power Determine the ABSOLUTE Defect to be 1720 pcm and records on Data Sheet 1 VALUE of the Power Defect (Block B.4.d).

for the current power level and the Corrected Boron COMMENTS:

Concentration AND Enter this value on Data Sheet 1.

(Step VII.B.4.d)

BVPS-TR-0026 Page 8of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-001 JPM TITLE: Calculating a Shutdown Margin Following a Stuck Rod JPM REVISION: 4 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => S/U 19.C Divide value from curve (in 19.lC Converts ABSOLUTE VALUE of the Power Defect pcm) by 1000 to convert to of 1720 pcm to 1. 72 %~k/k and records on Data

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

Sheet 1.

COMMENTS:

(Step VII.B.4.e)

20. Add 0.250% ~k/k for 20.1 Determines Power Defect plus operating temperature operating temperature band band margin to be 1. 97 % ~k/k and records on Data margin to the Power Defect Sheet 1 (Block B.4.f).

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

1.

(Ste VII.B.4.f) 21.C Determine SHUTDOWN 21.lC Determines SDM to be 2.5272 % (+/- 0.100) ~k/k, MARGIN by subtracting and records on Data Sheet 1 (Block B.5) AND space Power Defect (Step (Step provided on candidate direction sheet.

VII.B.4.f) from the value determined in Step B.3 AND 21.2C Compares calculated SDM to Tech Spec and Core Record on Data Sheet 1. Operating Limits Report requirement of 1. 77% ~ K/K and determines that it is acceptable.

(Step VII.B.5) 21.3 Records on OST cover sheet and initials Data Sheet 1.

COMMENTS:

EVALUATOR CUE: When the candidate hands in the OST cover sheet, the evaluation for this JPM is complete.

STOP TIME: - - - - - - - -

BVPS - SSS Unit 1 10ST-49.1 Revision 23 Operating Surveillance Test Page 1 of 1 Shutdown Margin Calculation (Plant Critical)

(Updated For Cycle 24)

- - - - ANSWER KEY *****

DATA SHEET 1 SHUTDOWN MARGIN CALCULATION A 4. CBD Steps Withdrawn 228 STEPS

5. Reactor Power 100 %

6. Number of Inoperable (untrippable) OR dropped Rods -~--ROD(s)

ARO TOTAL BANK WORTH (%Ak/k) 0 to 10000 MWD/MTU 10001 MWD/MTU to EOL I 7.218 I 7.746 B 1. a. ARO Total Bank Worth (See Table above) (TBW} 7.218 %L:.k/k

b. Integral Rod Worth (CB Figures 24A, 24B OR 24C) (IRW} 0 pcm 1 -~0~_%L:.k/k

1) 0 (pcmfromB.1.b)x %i'lk/k

--~---- 1000 pcm

c. TBW (B.1 .a) - IRW (B.1.b.1) 7.218 %L:.k/k

'----7~*=21~8~-~>-<'----~o~--*

d. 90% Current Total Bank Worth 0.9 x 7.218 (B.1.c) 6.4962 %L:.k/k

2. Inoperable (untrippable) OR Dropped Rod(s} Worth 1.999 %L:.k/k

3. (90% Total Bank Worth) - (Inoperable (Untrippable) OR Dropped Rod(s) Worth)

'-----6=.4~9'""6..._2_ __,) - (__1...,..9=9..,.9_ __ , 4.4972 %L:.k/k (B.1.d) (B2)

4. a. RCS Boron Concentration 1620 ppm

b. B-10 Correction Factor (CB Figure 29} 0.989

c. RCS Boron Concentration X B-10 Correction Factor

'----~1~62=0~-~l x '~-~o=.9=89~--- 1602 ppm (4.a) (4.b)

d. ABSOLUTE VALUE of Power Defect (CB Figure 21) 1720 pcm 1

e 1720 (pcmfromB.4.d)x %i'lk/k 1.72 %L:.k/k

--"""-=~----- 1000

f. Power Defect+ Operating temperature band margin

1. 72 (B.4.e) + 0.250% L:.k/k 1.97 %L:.k/k

5. SHUTDOWN MARGIN Acceptance Criteria - Within Limits Specified in COLR)

'----~4~.4~9~72~-~> - ( 1.97 2.5272 %L:.k/k (B.3) (B.4.f) (Acceptable Range is 2.4272 to 2.6272 l 111 'l""'414 ';¥'eu Initial (2) _ _ _ __

Initial

- - - - ANSWER KEY *****

SOM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SOM)

LCO 3.1.1 SOM shall be within the limits specified in the COLR.

APPLICABILITY: MODE 2 With kett < 1.0, MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SOM not within limits. A.1 Initiate boration to restore 15 minutes SOM to within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SOM to be within the limits specified in the In accordance COLR. with the Surveillance Frequency Control Program Beaver Valley Units 1 and 2 3.1.1 - 1 Amendments 292 /179

Licensing Requirements Manual Core Operating Limits Report 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Core Operating Limits Report This Core Operating Limits Report provides the cycle specific parameter limits developed in accordance with the NRC approved methodologies specified in Technical Specification Administrative Control 5.6.3.

5.1.1 SL 2.1.1 Reactor Core Safety Limits See Figure 5.1-1.

5.1.2 SHUTDOWN MARGIN (SOM}

a. In MODES 1, 2, 3, and 4, SHUTDOWN MARGIN shall be;?; 1.77% t-.k/k.< 1J

b. Prior to manually blocking the Low Pressurizer Pressure Safety Injection Signal, the Reactor Coolant System shall be borated to 2 the MODE 5 boron concentration and shall remain 2 this boron concentration at all times when this signal is blocked.

c. In MODE 5, SHUTDOWN MARGIN shall be 2 1.0% t-.k/k.

5.1.3 LCO 3.1.3 Moderator Temperature Coefficient (MTC)

a. Upper Limit - MTC shall be maintained within the acceptable operation limit specified in Technical Specification Figure 3 .1.3-1.

b. Lower Limit - MTC shall be maintained less negative than - 4.4 x 10-4 t-.k/k/°F at RATED THERMAL POWER.

c. 300 ppm Surveillance Limit: (- 37 pcm/°F)

d. The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 5.1-5 and the following algorithm from Reference 11 :

Revised Predicted MTC =Predicted MTC* + AFD Correction**+ Predictive Correction***

where,

Predicted MTC is calculated from Figure 5.1-5 at the burnup corresponding to the measurement of 300 ppm at RTP conditions,

- AFD Correction is the more negative value of:

{O pcm/°F or (MFD

AFD Sensitivity)}

where: MFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burn up corresponding to 300 ppm.

and AFD Sensitivity =0.05 pcm/°F I t-.AFD

- - Predictive Correction is -3 pcm/°F.

(1) The MODE 1 and MODE 2 with kett 2 1.0 SOM requirements are included to address SOM requirements (e.g., MODE 1 Required Actions to verify SOM) that are not within the applicability of LCO 3.1.1, SHUTDOWN MARGIN (SOM).

COLR Cycle 24 Beaver Valley Unit 1 5.1 - 1 LRM Revision 89

CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

INITIAL CONDITIONS:

The Unit is in Mode 1, 100% power

All rods are at 228 steps on the group demand counters

Annunciator [A4-46], TAVG DEVIATION FROM TREF is "Off'

A single Bank "D" Control Rod is stuck and indicates 228 steps

Current RCS boron concentration is 1620 ppm

Current core burnup is 100 MWD/MTU INITIATING CUE: Your Supervisor directs you to perform a shutdown margin calculation for the present plant conditions using 1OST-49 .1, Shutdown Margin Calculation (Plant Critical), and report your results in the COMMENT section of the OST cover sheet.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

B VPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Perform a Quadrant Power Tilt Ratio Calculation TRAINING MATERIAL NUMBER: 1AD-003

~~~~~~~~~~~~~~~~~~~~~~~

PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lAD-003 REVISION NUMBER: 3 TECHNICAL

REFERENCES:

10ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation", Rev. 6 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 25 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

BVPS-TR-0026 Revision 0 OPERA TIONS JOB PERFORMANCE MEASURE JPM CHANGE

SUMMARY

Affected JPM: lAD-003 New Revision: 3 Description of Change(s):

1. Updated JPM to new format.

2. Updated expected performance time to 25 minutes.

3. Added KIA 2.1.7

4. Added step 3 .5 to initial and date Data Sheet 1. Reworded Step 4.1 to specify procedure step 5.

Removed data from Data Sheet 1 and provided separate handout sheets with this information, reworded directions to use this information.

Reason for Change (s):

1. Format Change

2. Completion time update

3. Kl A review and update.

4. NRC Walkthrough comments.

BVPS-TR-0026 Page 1 of 7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-003 JPM TITLE p ~ Q d p T"l R

c 1 1

JPM REVISION: 3 : er1orm a ua rant ower It at10 a cu at10n KIA

REFERENCE:

015Al.04 3.5/3.7 TASK ID: 0021-005-06-013 2.2.12 3.7/4.1 2.1.7 4.4/4.7 JPM APPLICATION: ~ REQUALIFICA TION ~ INITIAL EXAM D TRAINING D SRO ONLY D ALTERNATE p ATH JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC

~ Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

I

BVPS-TR-0026 Page 2of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The QPTR calculation is completed and compared to Technical Specification limits, as specified in the OST Acceptance Criteria.

Reports UNSAT performance of OST.

RECOMMENDED Classroom STARTING LOCATION:

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

INITIATING CUE:

The Unit Supervisor directs you to perform a QPTR manual calculation in accordance with 10ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation" beginning at step VIl.B.3.

Report your results on the OST Cover Sheet.

Normalization factors have been verified by Reactor Engineering and are included on the attached Data Sheet 3 of lRST-2.9.

The NIS Meter readings are included on the NIS Data Handout.

REFERENCES:

10ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation", Rev. 6.

TOOLS: Calculator HANDOUT: 10ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation", Rev. 6, place kept up to Step VII.B.3, including normalization values and uncorrected currents provided on supplemental data sheets.

BVPS-TR-0026 Page 3of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION: 3 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT =>

EVALUATOR NOTE: This JPM is designed to use an accompanying Data Sheet Set and is to be performed in a classroom setting. For any of the following data cues, refer to the accompanying Data Sheet Set.

START TIME: _ _ _ _ _ __

EVALUATOR CUE: Provide a copy of 1OST-2.4A completed up to step VII.B.3. This includes normalization factors and uncorrected current filled out on Data Sheet 1.

1. Review procedure. 1.1 Candidate reviews procedure provided.

COMMENTS:

BVPS-TR-0026 Page 4of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: IAD-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION: 3 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 2.C Determine QPTR for each 2.IC Determines corrected current by multiplying each upper detector by performing detectors Current (Uncor.) value by the associated the following on Data Sheet 1: normalization factor and records the result in the appropriate Data Sheet 1 Current (Cor.) column.

a. Multiply each upper detector current value by 2.2C Add values in "Current (Cor.)" column AND records its associated result in "SUM".

normalization factor AND Record result in "Current 2.3C All power range high neutron flux channel inputs to (Cor.)" column. QPTR are OPERABLE, therefore divide value in "SUM" by 4 AND Record result in "AVG".

b. Add values in "Current (Cor.)" column AND 2.4C Determines QPTR for each upper detector by dividing Record result in "SUM". each value in the "Current (Cor.)" column by the "AVG" AND Record results in "Tilt Ratio" column.

c. IF all power range high neutron flux channel inputs to QPTR are OPERABLE Divide value COMMENTS:

in "SUM" by 4 AND Record result in "AVG".

(Otherwise NIA)

d. IF one power range high neutron flux channel input to QPTR is inoperable Divide value in "SUM" by 3 AND Record result in "AVG". (Otherwise NIA)

e. Determine QPTR for each upper detector by dividing each value in the "Current (Cor.)" column by the "AVG" AND Record results in "Tilt Ratio" column.

BVPS-TR-0026 Page5of7 Revision 0 OPERA TIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION: 3 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 3.C Determine QPTR for each 3.lC Determines corrected current by multiplying each lower detector by performing detectors Current (Uncor.) value by the associated the following on Data Sheet 1: normalization factor and records the result in the appropriate Data Sheet 1 Current (Cor.) column.

a. Multiply each lower detector current value by 3.2C Add values in "Current (Cor.)" column AND records its associated result in "SUM".

normalization factor AND Record result in "Current 3.3C All power range high neutron flux channel inputs to (Cor.)" column. QPTR are OPERABLE, therefore divide value in "SUM" by 4 AND Record result in "AVG".

b. Add values in "Current (Cor.)" column AND 3.4C Determines QPTR for each lower detector by dividing Record result in "SUM". each value in the "Current (Cor.)" column by the "AVG" AND Record results in "Tilt Ratio" column.

c. IF all power range high neutron flux channel 3.5 Initials and Dates Data Sheet 1.

inputs to QPTR are OPERABLE Divide value in "SUM" by 4 AND COMMENTS:

Record result in "AVG".

(Otherwise NIA)

d. IF one power range high neutron flux channel input to QPTR is inoperable Divide value in "SUM" by 3 AND Record result in "AVG". (Otherwise NIA)

e. Determine QPTR for each lower detector by dividing each value in the "Current (Cor.)" column by the "AVG" AND Record results in "Tilt Ratio" column.

BVPS-TR-0026 Page 6of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: IAD-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION: 3 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU EVALUATOR NOTE: Initial conditions stated plant computer was NOT available.

4. IF uncertain of the calculated 4.1 Procedure Step 5 is NIA based on initial conditions tilt values, Compare the results provided.

with the following computer points: (Otherwise NIA)

COMMENTS:

5.C Consult the Acceptance 5.1 Compares test data with Acceptance Criteria to Criteria for acceptable determine if QPTR exceeds 1.02.

performance. Verify Steamline Isolation. 5.2C Determines N43 is> 1.02 and is therefore UNSAT.

COMMENTS:

BVPS-TR-0026 Page7of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-003 JPM TITLE: Perform a Quadrant Power Tilt Ratio Calculation JPM REVISION: 3 STEP STANDARD

( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 6.C Inform the SM/US of the 6.1 C Informs the SM/US that QPTR performance is completion of this test UNSA T or documents UNSAT completion on front cover sheet of OST.

EVALUATOR CUE: When the candidate completes the QPTR calculation and reports or records completion, This JPM is COMPLETE.

EVALUATOR NOTE: After candidate determines tilt is either within OR out of specification, compare candidates data sheet with the Answer Key to ensure calculation method is correct. Grader Discretion Required.

COMMENTS:

EVALUATOR CUE: State "This JPM is complete" STOP TIME: - - - - - - - -

CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

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

INITIATING CUE:

The Unit Supervisor directs you to perform a QPTR manual calculation in accordance with 10ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation" beginning at step VII.B.3.

Report your results on the OST Cover Sheet.

Normalization factors have been verified by Reactor Engineering and are included on the attached Data Sheet 3 of lRST-2.9.

The NIS Meter readings are included on the NIS Data Handout.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

1AD-003 REACTOR ENGINEERING DATA HANDOUT BVPS-SBS Unit 1 1RST-2.9 Issue 1 Revision 11 NIS SINGLE POINT CALIBRATION Page 29 of 39 DATA SHEET 3 Nuclear Power Range Calibration Data DATE: TODAY INITIALS:

~-=------~----~~

CYCLE: CURRENT REVIEWED BY:

SM INITIALS/DATE: _____ S....,.M._. _ _ _ _ _ _l ____ T___

O_D.._A.......Y_____

Quadrant Power Tilt Ratio Delta Flux Normalization Factors Conversion Factors Computer Top Detectors Bottom Detectors Factor Point N-41 KDF014 20.596 N-41 0.0484 0.0401 N-42 KDF012 17.655 N-42 0.0489 0.0452 N-43 KDF011 19.082 N-43 0.0533 0.0520 N-44 KDF013 18.972 N-44 0.0431 0.0471 Calibration Map Identifications: Simulator DATE: Today EFPD Current BU Monthly Surveillance Check Performance (SR 3.3.1.3)

EFPD Next Surveillance Check Performance Acceptable Check (Above Data Effective Until EFPD Next Check Due)

Due Date of Most Recent Check Map l.D. Most Recent Check EFPD Initials

1AD-003 NIS DATA HANDOUT Quadrant Power Tilt Ratio NIS Readings Meter Reading NIS Channel Current - Uncorrected N-41A 148 N-42A 148 N-43A 139 N-44A 165 Meter Reading NIS Channel Current - Uncorrected N-418 183 N-428 162 N-438 140 N-448 157

BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Identify Isolation Boundary Points on Plant VOND TRAINING MATERIAL NUMBER: lAD-040

~~~~~~~~~~~~~~~~~~~~~~~

PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lAD-040 REVISION NUMBER: 0 TECHNICAL

REFERENCES:

1OM-36, 4KV Station Service System Unit 1 EDG Air Start System Vond, RM-0436-001 Rev. 11 Unit 1 Vond Graphics Symbology Sheets 1and2, RM-0400-001Rev.1 and RM-0400-002 Rev. 2 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 10 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE

SUMMARY

Affected JPM: IAD-040 New Revision: 0 Description of Change(s):

1. Developed new JPM for exam bank.

2. Modified step 7 to state should versus must for the air compressor as it will auto stop once the valves are closed. Step 8.1 modified to report answer in the answer box on the candidate direction sheet, added answer box. Reworded cue to clarify wording and to write actions in answer box.

Reason for Change (s):

1. Exam bank development

2. NRC comments.

BVPS-TR-0026 Page 1of5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-040 JPMTITLE: Identify Isolation Boundary Points on Plant VOND JPM REVISION: 0 KIA

REFERENCE:

2.2.41 3.5 TASK ID: 0481-007-03-013 JPM APPLICATION: C8J REQUALIFICATION C8J INITIAL EXAM D TRAINING D SROONLY 0 ALTERNATE PATH JPM C8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

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

D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 10 Minutes Actual minutes Critical: C8J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

IEvaluator Signature:

BVPS-TR-0026 Page 2 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Identifies boundary isolations for ruptured Diesel Air System Expansion Joint MFH-IEE-3, and correctly marks up the VOND.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS:

The plant is currently at 75% power

The Outside Tour Operator reports that there is an air rupture on Expansion Joint MFH-IEE-3, on the DGI Air Start System

Air compressor IEE-C-IA is running

The operator recommends that the rupture be isolated INITIATING CUE: You are to identify the isolation points to stop the air release and isolate the rupture, by marking them on the VOND, and inform your supervisor of the isolation points.

Report your results in the answer box below.

REFERENCES:

1OM-36, 4KV Station Service System Unit 1 EDG Air Start System Vond, RM-0436-001 Rev. 11 Unit 1 Vond Graphics Symbology Sheets 1 and 2, RM-0400-001 Rev.

1 and RM-0400-002 Rev. 2 TOOLS: None HANDOUT: Unit 1 EDG Air Start System Vond, RM-0436-001 Rev. 11 VONDs RM-0436-002, 003 and 004, other EDG system piping Unit 1 Vond Graphics Symbology Sheets 1 and 2, RM-0400-001 Rev.

1 and RM-0400-002 Rev. 2

BVPS-TR-0026 Page 3 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: I AD-040 JPMTITLE: Identify Isolation Boundary Points on Plant VOND JPM REVISION: 0 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT ~

EVALUATOR CUE: Provide the Candidate with a copy of Unit I DG Air Start System Vond RM-0436-00I, VONDs RM-0436-002, 003, 004 and Vond Symbology sheets OOI and 002.

EVALUATOR NOTE: The sequence of identifying the isolation points is not critical for this JPM, steps may be done in any order.

START TIME: - - - - - - - -

1. Reviews VOND 36-I to I.I Locates the ruptured expansion joint, MFH-IEE-3 on locate the ruptured expansion the VOND at grid location D-2.

joint, MFH- I EE-3 at grid location D-2.

EVALUATOR NOTE: If the candidate decides to only secure the compressor and allow the air tanks to bleed off, Cue them as their Supervisor to stop the air leak by determining the isolation valves necessary to stop the air release.

COMMENTS:

2.C Determines that IA Air Comp 2.IC Identifies that valve IDA-102, IA Air Comp Disch Disch Isol valve must be Isol valve must be CLOSED.

closed.

2.2 Marks the valve on the VOND with an "X".

COMMENTS:

BVPS-TR-0026 Page 4of5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-040 JPMTITLE: Identify Isolation Boundary Points on Plant VOND JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU I EVALUATOR NOTE: The valve is normally closed. I

3. Determines NO. 1 DG Air 3.1 Identifies that valve IDA-104, NO. 1 DG Air Supply Supply Hdr Cross Connect Hdr Cross Connect valve must remain closed.

valve must remain closed.

3.2 May mark the valve on the VOND with an "X" to identify that it must remain closed.

COMMENTS:

4.C Determines that 3A Air Tank 4.lC Identifies that lDA-105, 3A Air Tank Isol valve must lsol valve must be closed. be CLOSED.

4.2 Marks the valve on the VOND with an "X".

COMMENTS:

5.C Determines that 3B Air Tank 5.lC Identifies that lDA-106, 3B Air Tank Isol valve must lsol valve must be closed. be CLOSED.

5.2 Marks the valve on the VOND with an "X".

COMMENTS:

I

BVPS-TR-0026 Page 5 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-040 JPMTITLE: Identify Isolation Boundary Points on Plant VOND JPM REVISION: 0 STEP STANDARD

( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU 6.C Determines that 3C Air Tank 6.lC Identifies that lDA-107, 3C Air Tank Isol valve must Isol valve must be closed. be CLOSED.

6.2 Marks the valve on the VOND with an "X".

COMMENTS:

7. Determines that Motor Driven 7.1 Identifies that the control switch for lEE-C-lA, Air Compressor, lEE-C-lA Diesel Generator Start Air Compressor, is taken to should be secured. OFF EVALUATOR NOTE: This action is not required since closing lDA-102 isolates the compressor pressure switch, the compressor would stop automatically.

COMMENTS:

8. Checks Vond is marked up, 8 .1 Checks Vond is marked up with the isolation and reports to the supervisor. boundaries, and provides a summary report in the answer box.

COMMENTS:

EVALUATOR CUE: Once the Air Start System Vond is marked up with the isolation boundaries, and the actions taken have been reported, state "This JPM is complete".

STOP TIME: - - - - - - - -

CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

INITIAL CONDITIONS:

The plant is currently at 75% power

The Outside Tour Operator reports that there is an air rupture on Expansion Joint MFH-IEE-3, on the DGI Air Start System

Air compressor 1EE-C-1 A is running

The operator recommends that the rupture be isolated INITIATING CUE: You are to identify the isolation points to stop the air release and isolate the rupture, by marking them on the VOND, and inform your supervisor of the isolation points.

Report your results in the answer box below.

Answer:

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Select R WP and Determine Maximum Allowable Stay Time TRAINING MATERIAL NUMBER: lAD-012

~~~~~~~~~~~~~~~~~~~~~~~

PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lAD-012 REVISION NUMBER: 1 TECHNICAL

REFERENCES:

NOP-OP-4107, "Radiation Work Permit (RWP)", Rev 15 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 20 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE

SUMMARY

Affected JPM: lAD-012 New Revision: 1 Description of Change(s):

1. Updated for current JPM format.

2. Updated for NOP-OP-4107 revision.

3. Updated RWPs and survey maps (current year) required to perform the JPM.

4. Added step to calculate BVPS administrative limit.

5. Modified allotted time to 20 minutes. Remove the word Candidate prior to Answer Box throughout the JPM and label the box as Answer box. Reword the Initial Conditions to clarify where the drain hose is to be routed. Reprint Radpro Maps to make the lettering the same. Reword the Task Standard to match the Answer box. Reword step 2.1 to identify where the numbers are from. Step 3.1 reword for clarity. Add the words "STAY TIME" after the BV Administrative Limit in the Answer Box.

Reason for Change (s):

1. Changed format to the new JPM procedure (BVPS-TR-0026).

2. NOP-OP-4107 was revised.

3. JPM realism and accuracy.

4. Validator feedback

5. NRC Comments.

BVPS-TR-0026 Page 1of4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-012 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 1 Time K/A

REFERENCE:

2.3.7 3.5/3.6 TASK ID: 0481-005-03-043 JPM APPLICATION: ~ REQUALIFICA TION ~ INITIAL EXAM 0 TRAINING D SROONLY D ALTERNATE PATH JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

~ Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC

~ Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

l Evaluator Signature:

BVPS-TR-0026 Page 2of4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Select the correct RWP and associated Task Number AND determine the maximum stay time according to survey map dose rates.

Determines that the job cannot be completed within limits.

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS:

A clearance is being prepared to work on RCP seal injection isolation valve MOV-1CH-308C located in "A" Penetrations

You are assigned to connect a drain hose to RCP 1C Seal Supply Drain, lCH-324, located directly below MOV-1CH-308C, to support the clearance

The floor drain is located directly below the valve

Your task to connect the drain hose will take 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to perform INITIATING CUE: You are to SELECT the correct R WP and associated task number to perform the task from the R WPs provided, AND calculate your MAXIMUM stay time using the appropriate survey map and R WP.

Also calculate the Beaver Valley ADMINISTRATIVE limit for this job. Report your results in the Answer Box, including whether job can be completed based on calculated stay time.

REFERENCES:

NOP-OP-4107, "Radiation Work Permit (RWP)", Rev 15 TOOLS: Calculator HANDOUT: Set of 3 RWPs (216-2001, 116-1001, 116-1023)

Radiation Survey Maps (Multiple maps, ensure dose near MOV-1CH-308C is reflective of calculated numbers used for JPM)

BVPS-TR-0026 Page 3 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-012 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 1 Time STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT ~

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

START TIME: _ _ _ _ _ __

l.C Review set of three (3) RWPs 1.1 C Selects R WP 116-1001 based on Operations provided and select correct clearance activities and records RWP #in the Answer RWP and task number. box.

l.2C Selects Task# 3 (clearance activities).

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

COMMENTS:

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

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

(From RWP 116-1001) (From Survey Map 112105) 2.2C Determines Administrative time is 80% of the maximum [(1.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months s* 0.80) =1 hour] and records this time in the answer box.

COMMENTS:

BVPS-TR-0026 Page 4 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-012 JPM TITLE: Select RWP and Determine Maximum Allowable Stay JPM REVISION: 1 Time STEP STANDARD

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

3.C Determines allowable stay 3 .1 C Determines that the maximum stay time is 1.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , time does NOT allow (adminsitrative limits is 1.0 hour0 days 0 hours 0 weeks 0 months ) and the Initial completion of the work. Conditions stated the task will take 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , then records that the job CANNOT be completed in the answer box by circling NO.

COMMENTS:

EVALUATOR CUE: When the Candidate reports the results in the answer box, the evaluation for this JPM is complete. Grader Discretion is required.

STOP TIME: - - - - - - - -

ANSWER NAME: ANSWER KEY RWP# 116-1001 TASK# #3 (Clearance Activities)

MAXIMUM STAY TIME: 1 Hour 15 Minutes (75 minutes)

BV ADMINISTRATIVE LIMIT STAY TIME: 1 Hour (60 Minutes)

Can the Job be completed within limits? (circle one) YES

CANDIDA TE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

INITIAL CONDITIONS:

A clearance is being prepared to work on RCP seal injection isolation valve MOV-1CH-308C located in "A" Penetrations

You are assigned to connect a drain hose to RCP 1C Seal Supply Drain, 1CH-324, located directly below MOV-1 CH-308C, to support the clearance

The floor drain is located directly below the valve

Your task to connect the drain hose will take 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to perform INITIATING CUE: You are to SELECT the correct R WP and associated task number to perform the task from the R WPs provided, AND calculate your MAXIMUM stay time using the appropriate survey map and R WP.

Also calculate the Beaver Valley ADMINISTRATIVE limit for this job. Report your results in the Answer Box, including whether job can

. be completed based on calculated stay time .

ANSWER NAME:

RWP#

TASK#

MAXIMUM STAY TIME:

BV ADMINISTRATIVE LIMIT STAY TIME:

Can the Job be completed within limits? (circle one) YES NO D At this time, ask the evaluator any questions you have on this JPM.

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

I FUI # M8000.1 RADIOLOGICAL SURVEY FORM SURVEY NUMBER MAP RWP NUMBER 102138 102138 //(;.-1000 NOP-OP-4701-01 Rev. 00 BUILDING ELEVATION AREA/ROOM/SYSTEM DATE TIME 1 P.A.B. 722' BLENDER CUBICLE /0 -JO-/b C>'l30 PURPOSE % POWER R ....... ~ ...... c:.... ~ .......~\.....\ 5...,r--v <:... \ {) t:> 7o Legend: Unless otherwise noted, all radiation readings are In mrern/h and alls ears are In net dpm/100cm2. HS - Hot Spots, N .. Neutron, a -Alpha,~ - Beta. y -

Gamma, A - Air Sample, 0 - Smear, *1 - Contact/30cm, XXXX - Boundary, !§fl- Step Off Pad, Bkgd - Background, MDA - Minimum Detectable Activity, ND -

Non Detectable, CA - Contamination Area, HCA - Highly Contaminated Area, DPZ - Discrete Particle Zone, ARA - Airborne Radiation Area, RA - Radiation Area, HRA - High Radiation Area, LHRA - Locked High Radiation Area, RCA - Radlologlcal Controlled Area, VHRA - Very High Radiation Area, RMA - Radioactive Material Area, LOA - Low Doae Area, LAS - Large Area Smear,# - Direct Frisk.

0 P-i 0 0 FCV-1CH-12 L.f.3

/MOV-1C~

-30

. 1CH-171 1cH-11

~~o~ HCV-1CH-18~'-'

"*S'Q~ ...

ullP Q) 'i' ~ 3. b MO&H-373-t"~

n)

<fJ FCV-1CH-113a....~

ov V-1 CH-115J'l

~-3"--"---..J l:r' ~~

MOV-1CH-115 3.0 0 0

'f.& 0

..=l.i FCV-1CH-114a?

~ 0 FCV*1 CH-114A

,/"'Post*d

.* RA MOV'-1 CH-350 Smear Smear No. No.

5 2 6 3 7 4 8 INSTRUMENTS USED MODEL INSTRUMENT CAL DUE DATE NUMBER NUMBER MDA/BKGD DATE

/ 0-10-1 <./.

RM-14 o c:.."""'

-r--Pok. '-C.ol/-OS-1 0.3 ""'ii.......... APPROVED BY*

- SAP NUMBER SIGNATURE DATE

/1*/ 11..

'l*

~~

0 M ;;;> ::z. :z...0 7 I PAGE _ __ OF Footer

FUI # M8000.1 RADIOLOGICAL SURVEY FORM SURVEY NUMBER ,MAP# RWPNUMBER 112105 112105 1 1 t.-1 oo_o NOP-OP-4701-01 Rev. 00 BUILDING ELEVATION AREA/ROOM/SYSTEM DATE TIME c-Safe uards 722' Safe uarde "A" Penetratlo Area /u-.:10-1 (. Ir$()

PURPOSE %POWER 1oo°lo L*g*nd: un1eaa otherwtse noted, all radiation readings are In mrem/h and all smears are In net dp 1oocm2. HS- Hot Spots, N *Neutron, a* Alpha, 13 *Beta, y

Gamma, A* Air Sample, O - Smear, *1

Contaet/3ocm, XXXX. Boundary, l§QEI'. Step Off Pad, kgd

Background, MDA. Minimum Detectable Activity, ND -

Non Detectable, CA

Contamination Area, HCA. Highly Contaminated Area, DPZ. Discrete Parti e Zone, AAA. Airborne Radiation Area, AA* Radiation Area, HRA

High Radiation Area, LHAA

Locked High Radiation Area, RCA - Radlologlcal Controlled rea, VHAA- Very High Radiation Area, RMA - Radioactive Material Area, LOA - Low Dose Area, LAS - Large Area Smear, # - Direct Frisk.

Hot Spot: 1-2

Contact:

3<oo 30crn: °\O Smear Smear No. Smear Location No.

5 2 6 3 7 8

MODEL INSTRUMENT CAL DUE DATE MOA/BKGD NUMBER NUMBER DATE IC> -;;io-1

-r- ~ \c.. (.~o -'l3 SIGNATURE DATE

.s6 I" * .,;,1. 1(,.

Footer

FUI # M8000.1 RADIOLOGICAL SURVEY FORM SURVEY NUMBER RWP NUMBER 102110 11 b - I o,;ttf NOP-OP-4701-01 Rev. 00 BUILDING ELEVATION DATE , TIME Auxlllary Bldg. 717' ltf-21-11.o. I oo PURPOSE %POWER (OO~

Legend: Unless otherwise noted, all radiation readings are In mremlh and aH smears are In net 100em2. HS- Hot Spots, N. Neutron, a. Alpha,~. Beta, y.

Gamma, 6

Air Sample, 0 - Smear, */

Contaet/30cm, XXXX

Boundary, !Qfl - Step Off Pad, Bkgd

Background, MDA

Minimum Detectable Activity, ND -

Non Detectable, CA* Contamination Area, HCA* Highly Cof\1amlnated Area, DPZ

Discrete Pa Zone, ARA* Airborne Radiation Area, RA* Radiation Area, HRA *High Radiation Area, LHRA *Locked High Radiation Area, RCA- Rldlologleal Controlled , VHRA- Very High Radiation Area, RMA- Radioactive Matenal Area, LOA - Low Do8e Area, LAS - Large Area Smear, #

Direct Fr11k.

~

~ '-I -flcJ... -g -

2 ~ ..-. rL...J....;. -e, -

3 "( . . . . tl-.J..... '8-Smear No. Smear Location Smear Location 9

10 11 MCA=

INSTRUMENTS USED MODEL INSTRUMENT CAL DUE SIGNATURE MDA/BKGD NUMBER NUMBER DATE Ro--.;z.. '-f \ 8.'a

~-°\ _;20&0 DATE sf>-_;;J._ \-Z.-Z.~

f'.':**

1- NIA -- ,,

OF I I

Footer

FUI # MS000.1 RADIOLOGICAL SURVEY FORM SURVEY NUMBER MAP# RWP NUMBER 102110 102110 )1£-/tJ::J.'-/

NOP-OP-4701-01 Rev. 00 BUILDING Auxiliary Bldg.

ELEVATION 717' ~,

TIME I ~ao PURPOSE %POWER

.:S Legend: Unless otherwise noted, all radiation 198dinos ara In mremlh and au smears are In net d m1100cm2. HS- Hot Spots, N - Neutron, a-Alpha, 13 - Beta, r.

Gamma, A *Air Sample, 0 - Smear, */

Contac:t/30cm, XXXX - Boundary, !Qfl- Step Off Pad, Bkgd - Background, MDA - Minimum Detectable Activity, ND -

Non Detectable, CA* Contamination Area, HCA - Highly Contaminated Area, DPZ. Discrete Pa Zone, ARA - Airborne Radiation Area, RA - Radiation Area, HRA

High Radiation Area, LHRA

Locked High Radiation Area, RCA- Radiological Controlled rea, VHRA - Very High Radiation Area, RMA - Radioactive Material Area, LOA - Low Dose Area, LAS - Large Area Smear, # - Direct Frisk.

p.. rCJ1o. , s "' , '""-*"

... " po).s~ I.. I>."-""' ~C.A.

Ve.\--.. \

c,.e..l. ....... ...

c..\o\- *~.:t~

'.11 Smear Smear No. Smear Location No. Smear Location 5

6 7

3 .... '"" 8 INSTRUMENTS USED MODEL INSTRUMENT CAL DUE DATE NUMBER NUMBER DATE MDAIBKGD

/0-1-1/p PAGE - - - OF Footer

FUI # M8000.1 RADIOLOGICAL SURVEY FORM SURVEY NUMBER MAP# RWPNUMBER 102110 102110 JI~-; ooD NOP-OP-4701-01 Rev. 00 Legend: Unless otllerwlSe noted, all radiation raadlnos ara In mremlh and all tn'161rs are In net d 100cm2. HS - Hot Spots, N

Neutron, a

Alpha, 15

Beta, y

Gamma, A *Air Sample, 0 - Smear, */

Contact/30crn, XXXX

Boundary, iQfl. Step Of'f Pad, Bkgd. Background, MDA. Minimum Detectable Activity, ND -

Non Detectable, CA

Contamination Area, HCA

Highly Contaminated Area; DPZ

Discrete Pa e Zone, ARA

Alrbome Radiation Area, RA

Radiation Area, HAA

High Radiation Area, LHRA

Locked High Radiation Area, RCA- Radiological Controlled , VHRA - Very High Radiation Area, RMA - Radioactive Material Area, LOA - Low Dose Area, LAS - Large Area Smear, #. Direct Frisk.

"*\

'*,\

\

' ... ...... ...... . \) 'k.. r ...~ *... -k...,s

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Smear Smear No. No. Smear Location 5

2 6 3 7 4 8 INSTRUMENTS USED MODEL INSTRUMENT CAL DUE SIGNATURE DATE MDA/BKGD NUMBER NUMBER DATE

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PAGE OF t

Footer

FUI # M8000.1 RADIOLOGICAL SURVEY FORM SURVEY NUMBER MAP# RWPNUMBER 102113 102113 llb-1~

NOP-OP-4701-01 Rev. 00 BUILDING ELEVATION AREA/ROOM/SYSTEM DATE TIME Auxiliary Bldg. 727' VALVE OPERATING AREA TOP FLOOR Cf-IS--I b , 0 S"~<J PURPOSE % POWER I

...,...c.'~ .,\ -r'"' ~-- * .... c. ~ - .::1. \(\.( s c Legend~ Unless otherwise noted, all radiation readings are in mrem/h and all smears are in net dpm/100cm2. HS - Hot Spots, N - Neutron, a -Alpha, 13 - Beta, y- Gamma,£\ -Air Sample, 0 - Smear,*/ - Contact/30cm, XXXX - Boundary,~ -

Step Off Pad, Bkgd - Background, MDA- Minimum Detectable Activity, NO- Non Detectable, CA- Contamination Area, HCA

- Highly Contaminated Area, DPZ - Discrete Particle Zone, ARA - Airborne Radiation Area, RA - Radiation Area, HRA - High Radiation Area, LHRA - Locked High Radiation Area, RCA - Rad!ological Controlled Area, VHRA - Very High Radiation Area, RMA - Radioactive Material Area, LOA - Lo Dose Area, LAS - Large Area Smear, # - Direct Frisk.

SW-~~* \4 A. l..r- SI.Al ..~4 flf L'ill..)1..r .sw _~.:4 o1K I'!. ....-/\o\,..

,,_,7..._,.. ,,,,_,,..Jw- ~-r/V:. AREAPOSTED LHRA/HCA.

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3 _,.Jw-- .... ...... ..... .. ..... .--

J ....... .

Smear Smear No. Smear Location No. Smear Location 5 9 2 6 10 3 7 11 4 8 NA INSTRUMENTS USED MODEL INSTRUMENT CAL DUE SIGNATURE DATE MDA/BKGD NUMBER NUMBER DATE

..,.-c.le..P*C.. Ob;L NIA

~ ....... _,~ '\ \C\ ya c..p-. APPROVED BY*

~"" SAP NUMBER SIGNATURE DATE ft.)

r A. //Z.>7 .elei. . ~

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PAGE_\_ _ OF Footer

SURVEY No.

RADIOLOGICAL SURVEY FORM (Continued) .

NOP-OP-4701-02 Rev. 00

~lA Smear Smear dpm/100cm 2 No. Location BY a

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,, .A'S"T -nz..E..t.lc:..*"

INSTRUMENTS USED PREPARED BY:

MODEL INSTRUMENT CAL DUE SAP NUMBER SIGNATURE MOmf<GO NUMBER NUMBER DATE "I"&.\c.. P*\c... 0'94 tJIA. 6 ~.;Jo f c.J~

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SAP NUMBER

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FUI # M8000.1 1*

RADIOLOGICAL SURVl;V f!O~M SURV~ NUMQI;~ MA~ill ~WP NUM~i;R 102101 102101 -_/(,.-/ooo NOP-OP-4701-01 Rev. 00 8UILDING ELEVATION AREA/ROOM/SYSTEM DATE TIME

.~PAB 722 PRIMARY AUXILIARY BLDG /t> -10 -lb C}..o/S-PURPOSE % POWER ROUTINE MONTHLY SURVEY /00 Legend: Unless otherwise noted, all radiation readings are In mrern/h and all ameara are In net dpm/100cm2. HS- Hot Spota, N - Neutron, a -Alpha, 13 *Beta, r -

Gamma, t;. - Air Sample, 0 - Smear, */ - Contact/3ocm, XXXX - Boundary, !Qfl- Step Off Pad, Bkgd - Background, MDA - Minimum Detectable Activity, ND -

Non Detectable, CA - Contamination Area, HCA - Highly Contaminated Area, DPZ - Discrete Particia Zone, ARA - Airborne Radiation Area, RA - Radiation Area, HRA

High Radiation Area, LHRA - Locked High Radiation Area, RCA - Radlologlcal Controlled Area, VHRA - Very High Radiation Area, RMA - Radioactive Material Area, LOA - Low Dose Area, LAS - Large Area Smear, # - Direct Frtsk.

AREA IS POSTED RCA n n MAP 10212*

MAP 102123 I I MAP 102120 LJ u u

o. -:a.

O..I 1=--1 o..i O.'i o.s CJ

\.O l"M!t""

I i Smear No. Smear Location 2 6 3 7 4 8 INSTRUMENTS USED PREPARED BY:

MODEL INSTRUMENT CAL DUE SAP NUMBER MDA/BKGD NUMBER NUMBER DATE 1-P'>\c.... '(.o~ - o "{3 tJ/A (2..n-i - -I ilf'~ Bl> 41,,.....

tJ

}\

APPROVED BY*

SAP NUMBER

'-joq IJ SIGNATURE C, ~A*

DATE

/0. /0-1(,

- PAGE _ __

OF Footer

FUI # M8000.1 RADIOLOGICAL SURVEY FORM *SURVEY NUMBER MAP# RWP NUMBER 102186 102186 I~- o.2~

NOP-OP-4701-01 Rev. 00 8UILDING ELEVATION AREA/ROOM/SYSTEM DATE TIME _

P.A.B. 722' CHARGING PUMP "C" /0 /2. 1<o /ovs PURPOSE %POWER ROUTINE MONTHLY SURVEY loo '7o Legend: Unlen otherwlee noted, all radiation reacllng1 are In mremlh and 111 smeara are In net dpm/100cm2. HS - Hot Spots, N - Neutron, a -Alpha, 13 - Beta, y

Gamma, c. *Air Sample, O - Smear, *t - Contact/30Cm, XXXX. Boundary,~. Step Off Pad, Bkgd

Background, MDA

Minimum Detectable ActlVlty, ND -

Non Detectable, CA

Contamlnauon Area, HCA

Highly Contaminated Area, DPZ

Discrete Particle Z9ne, ARA

Alrbome Radiation Area, RA

Radiation Area, HRA *High Radiation Area, LHRA *Locked High Radiation Area, RCA- Radlologlcal Controlled Area, VHRA-Very High Radiation Area, RMA- Radioactive Material Area, LOA - Low Dose Area, LAS - Large Area Smear, #

Direct Frisk.

AREA POSTED "RA" 3P

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o.11-Smear Smear Smear No. No. Smear Location No.

5 N/A 9 N/A 2 6 NIA 10 NIA 3 7 NIA 11 NIA 4 8 NIA 12 NIA PREPARED BY*

MODEL INSTRUMENT CAL DUE SAP NUMBER SIGNATURE DATE MOA/BKGO NUMBER NUMBER DATE 3131..1.s- /.-r~nr ,

Jo /rz.jI<.

APPROVED BY*

SAP NUMBER SIGNATURE DATE "ICP/ /J £. c., -- --- /o-1z-!"-

'PAGE __J__ OF Footer

BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Prepare Partial OST [lOST-1.1] for Performance (SRO ONLY)

TRAINING MATERIAL NUMBER: lAD-029 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lAD-029 REVISION NUMBER: 1 TECHNICAL

REFERENCES:

NOP-LP-2601, "Procedure Use And Adherence" (Rev. 5) lOST-1.1, "Control Rod Assembly Partial Movement Test" (Rev. 20)

INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 30 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:

Date APPROVED FOR USE:

Training Supervisor or Designee Date

BVPS-TR-0026 Revision 0 OPERA TIONS JOB PERFORMANCE MEASURE JPM CHANGE

SUMMARY

Affected JPM: lAD-029 New Revision: 1 Description of Change(s):

1. Updated to latest format.

2. Updated for latest procedure revisions

3. Updated allotted time.

4. Added evaluator note that it is acceptable to use a line to designate a series of steps that are "N/A" or remove the pages from the procedure.

5. Initial Conditions: Change ARO to "All Rods Out" and add "Bank "C" between the words Control Rod. Initiating Cue: in parenthetical statement add the word "JPM" prior to the word evaluator.

Step 1.2: Change first bullet to "Checks or Circles" Add a third bullet to Initial and Date the Comments section Step 2.lC: add wording "with NIA or removal" after the word performed.

Answer Sheet cover page: Circle the word "partial" (Have available the rubber stamp OPS uses to sign off as preparer and reviewer)

Reason for Change (s):

1. JPM format update

2. Both referenced procedures were revised

3. Validation time was 30 minutes.

4. Validation comments.

5. NRC Comments

BVPS-TR-0026 Page 1of4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-029 JPM TITLE: Prepare Partial OST [lOST-1.1] for Performance (SRO JPM REVISION: 1 ONLY)

KlA

REFERENCE:

2.1.20 4.6 TASK ID: 1320-006-03-023 JPM APPLICATION: ~ REQUALIFICA TION ~ INITIAL EXAM D TRAINING cg) SRO ONLY 0 ALTERNATE PATH JPM cg) ADMINISTRATIVE JPM EV ALDA TION METHOD: LOCATION: TYPE: ADMINISTERED BY:

[8] Perform D Plant Site D AnnualRequalExam D BVT D Simulate D Simulator D Initial Exam D NRC

[8] Classroom D Training D Other:

D Other:

EVALUATION RESULTS Performer Name: Performer SAP:

Time D Yes Allotted 30 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

~**

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

BVPS-TR-0026 Page 2 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: All steps of 1OST-1.1 that are related specifically to movement of Shutdown Banks and Control Banks A, B & D are omitted or marked NIA. (Answer Key provided to assist in this evaluation)

RECOMMENDED Classroom STARTING LOCATION:

INITIAL CONDITIONS: Unit 1 is at 100% power with All Rods Out at 228 steps. Control Bank "C" Rod D 12 had a blown moveable gripper coil fuse. The fuse has been replaced, and it is REQUIRED to perform 1OST-1.1, "Control Rod Assembly Partial Movement Test" to verify the rod is still operable. Senior management has directed that a "Partial" performance of 1OST-1.1, "Control Rod Assembly Partial Movement Test" be

,} performed for Control Bank C ONLY.

INITIATING CUE: As the Unit Supervisor, IAW the guidance provided in NOP-LP-2601, "Procedure Use And Adherence" Step 4.1.11, Prepare 1OST-1.1, "Control Rod Assembly Partial Movement Test" for a Partial OST Performance. The Partial performance shall be for control Bank C ONLY. (Assume the JPM evaluator will perform the second licensed SRO concurrence of your mark-ups).

REFERENCES:

NOP-LP-2601, "Procedure Use And Adherence" (Rev. 5) 1OST-1.1, "Control Rod Assembly Partial Movement Test" (Rev. 20)

TOOLS: None HANDOUT: NOP-LP-2601, "Procedure Use And Adherence" (Rev. 5) 1OST-1.1, "Control Rod Assembly Partial Movement Test" (Rev. 20)

BVPS-TR-0026 Page 3 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1AD-029 JPMTITLE: Prepare Partial OST [lOST-1.1] for Performance (SRO JPM REVISION: 1 ONLY)

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

START TIME: _ _ _ _ _ __

1. The Unit Supervisor or 1.1 Determines based on initial conditions, All steps designated SRO shall determine related specifically to movement of Shutdown Banks if the section or step will be and Control Banks A, B & D shall be omitted or designated as NIA or whether the marked NIA.

section or step shall be performed.

1.2 Documents the following on page 3 of the OST under The Unit Supervisor or test results:

designated SRO shall document

Checks or Circles Partial OST the decision in the official record

Writes an explanation documenting why steps copy of the procedure related specifically to movement of Shutdown Banks and Control Banks A, B & D are being omitted or marked NIA.

Initials and Dates the comments EVALUATOR 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:

BVPS-TR-0026 Page 4of4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-029 JPM TITLE: Prepare Partial OST [lOST-1.1] for Performance (SRO JPM REVISION: 1 ONLY)

STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU 2-.C - If the Unit Supervisor or 2.IC Documents the steps that are to be performed and the

- designated SRO has granted steps that are NOT to be performed with NIA or approval, the performer or removal on procedure 1OST-1.1, "Control Rod responsible supervisor shall Assembly Partial Movement Test". Refer to the ensure that the procedure Answer Key.

section or step is designated as NIA, initialed and dated.

COMMENTS:

EVALUATOR NOTE: Per section 4.1.11 ofNOP-LP-2601, it is acceptable to mark a series of Steps NIA by drawing a vertical line from the first and last step not performed or by removing the pages that are not to be performed EVALUATOR NOTE: Grader discretion will be required. The "critical" portions of this JPM are to clearly document the steps that are to be performed and the steps that are NOT to be performed. An answer key is provided to assist in evaluating this JPM. Each step that MUST be performed and each step that MUST be marked NIA are identified in this key and are "CRITICAL" steps for the JPM. All other steps are optional.

EVALUATOR CUE: That completes this JPM.

CANDIDA TE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

INITIAL CONDITIONS: Unit 1 is at 100% power with All Rods Out at 228 steps. Control Bank "C" Rod D 12 had a blown moveable gripper coil fuse. The fuse has been replaced, and it is REQUIRED to perform lOST-1.1, "Control Rod Assembly Partial Movement Test" to verify the rod is still operable. Senior management has directed that a "Partial" performance of lOST-1.1, "Control Rod Assembly Partial Movement Test" be performed for Control Bank C ONLY.

INITIATING CUE: As the Unit Supervisor, IA W the guidance provided in NOP-LP-2601, "Procedure Use And Adherence" Step 4.1.11, Prepare lOST-1.1, "Control Rod Assembly Partial Movement Test" for a Partial OST Performance. The Partial performance shall be for control Bank C ONLY. (Assume the JPM evaluator will perform the second licensed SRO concurrence of your mark-ups).

D

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

BVPS-SBS Unit 1 10ST-1.1 Revision 20 Operating Surveillance Test Page 3 of 46 Control Rod Assembly Partial Movement Test Frequency: 31D*, 92D ISurveillance Requirements: SR 3.1.4.2, LRS 3.1.9.1 Required for MODE(s): 1, 2, 3*, 4*, 5* Date I Time Completed: I Performed in MODE(s): 1, 2, 3, 4, 5 Total Manhours: -*

TEST RESULTS: (Completed by Performer) PERFORMED BY:

Name (Print} Initial

('1 or NIA)

D _ _ Test Completed SATISFACTORY D - - (See Problems Encountered Problem Sheet)

D V Unscheduled~ST (explain) e~\ CoNT./lo" ({oo 1)12.

V"\O\Jtl\Bt...a 6-Rt~f~ f()Se Re fc..~ { t.""' tA..,. A-FT~ 2 ik.~ f\Jse Reviewer Signature/Date STA Review I SM Approval I COMMENTS: (Include Date and Initials) t),., ""

c.'C) A> 'Ta.~ l... 8AAJ\( C. wlL.L. BE 7 ES 7 rQ f:.on.. PMf '!;,

St-toTfJouJN GJ\Al\<C 'A"°"'~ ' aI 1

Co .u T"l o" i3Ma SIU EVALUATOR CUE: Provide the completed copy of 10ST-2.4A which contains errors.

START TIME: - - - - - - - -

1. Review 10ST-2.4A, "QPTR 1.1 Reviews 1OST-2.4A, "QPTR Manual Calculation" Manual Calculation" procedure procedure which is provided by the evaluator.
provided.
COMMENTS:
2.C Identifies N43A & N44A math 2.1 C Determines N43A Tilt Ratio was miscalculated errors contained on Data Sheet (should be 1.0247 versus 0.9759).
1.
2.2C Determines N44A Tilt Ratio was miscalculated (should be 0.9836 versus 1.0166).
2.3 Records these errors in the comments section of the OST Cover Sheet.
COMMENTS:
B VPS-TR-0026 Page 4of4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: IAD-009 JPM TITLE: Review a Quadrant Power Tilt Ratio Calculation JPM REVISION: 4 (SRO Only)
STEP STANDARD
( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT :::> SIU 3.C Identifies QPTR exceeds 1.02 3.1 C Identifies N43A when properly calculated exceeds on N43A. 1.02 which does NOT meet the OST Acceptance Criteria.
3.2 Records OST Acceptance Criteria is NOT met in the comments section of the OST Cover Sheet.
3.3C Does NOT approve the Surveillance.
COMMENTS:
4.C References T.S 3.2.4 is 4.1 C Identifies TS 3 .2.4 Condition A is applicable (N43A
. applicable and records the > 1.02).
-condition in the comments section of the OST Cover 4.2 Records TS 3.2.4 Condition A is applicable in the Sheet. comments section of the OST Cover Sheet.
COMMENTS:
EVALUATOR CUE: When the candidate documents findings in the comments section of OST Cover Sheet, state "This JPM is COMPLETE".
EVALUATOR NOTE: Grader discretion may be required.
STOP TIME: - - - - - - - -
CANDIDA TE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
Mode 1 at 100% Power.
The plant computers are unavailable.
The QPTR Alarm is Out Of Service, this is the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months surveillance.
INITIATING CUE:
You are to review the completed 1OST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation" for accuracy AND determine if any TS action statements are applicable.
Any identified discrepancy will be recorded in the Comments section of the OST Cover Sheet.
If no discrepancy is identified, list NONE and sign the SM approval of the OST Cover Sheet.
If it is determined that TS action statement(s) apply, list the specific TS condition in the Comments section of the OST Cover Sheet and reason why.
Normalization factors have been verified by Reactor Engineering.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
1AD-009 HANDOUT REACTOR ENGINEERING DATA BVPS - SSS Unit 1 1RST-2.9 Issue 1 Revision 11 NIS SINGLE POINT CALIBRATION Page 29 of 39 DATA SHEET 3 Nuclear Power Range Calibration Data DATE: TODAY
~~~~~~~~~~~~
INITIALS:
CYCLE: CURRENT REVIEWED BY:
SM INITIALS/DATE: S.M. I
~~----------~~~~~~~--=-----------~~~
TODAY Quadrant Power Tilt Ratio Delta Flux Normalization Factors Conversion Factors Computer Top Detectors Bottom Detectors Factor Point N-41 KDF014 20.596 N-41 0.0484 0.0401 N-42 KDF012 17.655 N-42 0.0489 0.0452 N-43 KDF011 19.082 N-43 0.0533 0.0520 N-44 KDF013 18.972 N-44 0.0431 0.0471 Calibration Map Identifications: Simulator DATE: Today EFPD Current BU Monthly Surveillance Check Performance (SR 3.3.1.3)
EFPD Next Surveillance Check Performance Acceptable Check (Above Data Effective Until EFPD Next Check Due)
Due Date of Most Recent Check Map l.D. Most Recent Check EFPD Initials
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Identify Isolation Boundary Points on Plant VOND, then determine diesel operability. (SRO Only)
TRAINING MATERIAL NUMBER: lAD-039
~~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lAD-039 REVISION NUMBER: 0 TECHNICAL
REFERENCES:
1OM-36, 4KV Station Service System BVPS Technical Specifications and Bases TTnit 1 EDG Air Start System Vond, RM-0436-001 Rev. 11 Jnit 1 Vond Graphics Symbology Sheets 1and2, RM-0400-001 Rev. 1 and RM-0400-002 Rev. 2 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 15 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIO NS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: lAD-039 New Revision: 0 Description of Change(s):
1. Developed new JPM for exam bank.
2. Initiating Cue: change wording to ... rupture by marking them" (from RO JPM Comment). Step 7:
Change "must" to "should" in left hand column. The Air compressor will Auto stop once the valves are closed to isolate the leak as the pressure switch is upstream of the isolation points. (from RO JPM Comment) Step 8.4: Change wording to read ... "Direction Sheet in the Answer Box" Step 8 Evaluator Cue: remove the word "Candidate" prior to Answer Box Reason for Change (s):
1. Exam bank development
2. NRC comments
BVPS-TR-0026 Page I of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-039 JPM TITLE: Identify Isolation Boundary Points on Plant VOND, then JPM REVISION: 0 determine diesel operability. (SRO Only)
KIA
REFERENCE:
2.2.41 3.9 TASK ID: 0481-007-03-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM 0 TRAINING
~ SRO ONLY 0 ALTERNATE PATH JPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
i:gJ Perform D Plant Site D Annual Requa! Exam D BVT D Simulate D Simulator D Initial Exam D NRC i:gJ Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SSN:
Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
Evaluator Signature:
1
BVPS-TR-0026 Page 2of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Identifies boundary isolations for ruptured Diesel Air System Expansion Joint MFH-lEE-3, marks up the VOND, and determines that isolating the air rupture will not make DG 1 inoperable.
RECOMMENDED Classroom STARTING LOCATION:
INITIAL CONDITIONS:
The plant is currently at 75% power
The Outside Tour Operator reports that there is an air rupture on Expansion Joint MFH-lEE-3, on the DGl Air Start System
Air compressor 1EE-C-1 A is running
DG Air Systems are NOT cross connected
PI-EE-201, Starting Air Right Bank Pressure is 105 psig and lowering
PI-EE-202, Starting Air Left Bank Pressure is 190 psig and stable
The operator recommends that the rupture be isolated INITIATING CUE: You are to identify the isolation points to stop the air release and isolate the rupture, by marking them on the VOND and inform your supervisor of the isolation points.
Then determine if DG 1 is Operable, and state the reason for your operability determination in the Answer box below.
REFERENCES:
lOM-36, 4KV Station Service System Unit 1 EDG Air Start System Vond, RM-0436-001 Rev. 11 VONDs RM-0436-002, 003 and 004, other EDG system piping BVPS Technical Specifications and Bases Unit 1 Vond Graphics Symbology Sheets 1 and 2, RM-0400-001 Rev.
1 and RM-0400-002 Rev. 2 TOOLS: None HANDOUT: Unit 1 EDG Air Start System Vond, RM-0436-001 Rev. 11 VONDs RM-0436-002, 003 and 004, other EDG system piping BVPS Technical Specifications and Bases Unit 1 Vond Graphics Symbology Sheets 1 and 2, RM-0400-001 Rev.
1 and RM-0400-002 Rev. 2
BVPS-TR-0026 Page 3of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-039 JPM TITLE: Identify Isolation Boundary Points on Plant VOND, then JPM REVISION: 0 determine diesel operability. (SRO Only)
STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)~
EVALUATOR CUE: Provide the Candidate with a copy of Unit 1 DG Air Start System Vond RM-0436-001, VONDs RM-0436-002, 003, 004 and Vond Symbology sheets 001 and 002 and Tech Specs.
EVALUATOR NOTE: The sequence of identifying the isolation points is not critical for this JPM, steps may be done in any order.
START TIME: - - - - - - - -
1. Reviews VOND 36-1 to 1.1 Locates the ruptured expansion joint, MFH-IEE-3 on locate the ruptured expansion the VOND at grid location D-2.
joint, MFH-lEE-3 at grid location D-2.
EVALUATOR NOTE: If the candidate decides to only secure the compressor and allow the air tanks to bleed off, Cue them as their Supervisor to stop the air leak by determining the isolation valves necessary to stop the air release.
COMMENTS:
2.C Determines that IA Air Comp 2.lC Identifies that valve IDA-102, lA Air Comp Disch Disch Isol valve must be Isol valve must be CLOSED.
closed.
2.2 Marks the valve on the VOND with an "X".
COMMENTS:
BVPS-TR-0026 Page 4of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-039 JPM TITLE: Identify Isolation Boundary Points on Plant VOND, then JPM REVISION: 0 determine diesel operability. (SRO Only)
STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU I EVALUATOR NOTE: The valve is normally closed. I
3. Determines NO. 1 DG Air 3.1 Identifies that valve lDA-104, NO. 1 DG Air Supply Supply Hdr Cross Connect Hdr Cross Connect valve must remain closed.
valve must remain closed.
3.2 May mark the valve on the VOND with an "X" to identify that it must remain closed.
COMMENTS:
4.C Determines that 3A Air Tank 4.IC Identifies that lDA-105, 3A Air Tank Isol valve must Isol valve must be closed. be CLOSED.
4.2 Marks the valve on the VOND with an "X".
COMMENTS:
5.C Determines that 3B Air Tank 5.IC Identifies that lDA-106, 3B Air Tank Isol valve must Isol valve must be closed. be CLOSED.
5.2 Marks the valve on the VOND with an "X".
COMMENTS:
I
BVPS-TR-0026 Page 5of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-039 JPM TITLE: Identify Isolation Boundary Points on Plant VOND, then JPM REVISION: 0 determine diesel operability. (SRO Only)
STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR UNSAT =:> SIU 6.C Determines that 3C Air Tank 6.lC Identifies that IDA-107, 3C Air Tank Isol valve must Isol valve must be closed. be CLOSED.
6.2 Marks the valve on the VOND with an "X".
COMMENTS:
7. Determines that Motor Driven 7.1 Identifies that the control switch for lEE-C-lA, Air Compressor, lEE-C-lA Diesel Generator Start Air Compressor, is taken to should be secured. OFF EVALU ATOR NOTE: This action is not required since closing lDA-102 isolates the compressor pressure switch, the compressor would stop automatically.
COMMENTS:
BVPS-TR-0026 Page 6of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-039 JPM TITLE: Identify Isolation Boundary Points on Plant VOND, then JPM REVISION: 0 determine diesel operability. (SRO Only)
STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 8.C Refers to Technical 8.1 Refers to TS 3.8.3 Cond. E to determine if starting Specifications to make Air Pressure < 125 psig will make DG 1 inoperable.
Operability determination.
8.2 Refers to TS 3.8.3 Bases to determine if one starting Air Receiver Bank pressure> 125 psig is sufficient to maintain the DG operable.
8.3C Determines that the required air start capacity for DG 1 is met with two out of three air tanks in one of the two air banks at the specified air pressure of ~125 psig. DG 1 is Operable.
8.4 Documents the results on the Direction Sheet in the Answer box.
COMMENTS:
EVALUATOR CUE: Once the Air Start System Vond and Answer box is turned in, state "This JPM is complete".
STOP TIME: - - - - - - - -
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
The plant is currently at 75% power
The Outside Tour Operator reports that there is an air rupture on Expansion Joint MFH-IEE-3, on the DGI Air Start System
Air compressor 1EE-C-1 A is running
DG Air Systems are NOT cross connected
PI-EE-201, Starting Air Right Bank Pressure is 105 psig and lowering
PI-EE-202, Starting Air Left Bank Pressure is 190 psig and stable
The operator recommends that the rupture be isolated INITIATING CUE: You are to identify the isolation points to stop the air release and isolate the rupture, by marking them on the VOND and inform your supervisor of the isolation points.
Then determine if DG 1 is Operable, and state the reason for your operability determination in the Answer box below.
ANSWER:
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Determine Emergency Exposure Authorization Limits (SRO ONLY)
TRAINING MATERIAL NUMBER: lAD-038 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lAD-038 REVISION NUMBER:
TECHNICAL
REFERENCES:
112-EPP-IP 5.3, "Emergency Exposure Criteria and Control", Rev. 11 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 15 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: lAD-038 New Revision: 1 Description of Change(s):
1. Updated to match new format.
2. Modified the result to be different from 2AD-038.
3. Initial Conditions: Add the person's name "Mike Defulle has" to the beginning of the last bullet.
Step l .C Remove the "1" in the left hand column (typo)
Reason for Change (s):
1. Format has changed
2. Modified conditions per NRC request.
3. NRC comment
BVPS-TR-0026 Page I of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: IAD-038 JPM TITLE: Determine Emergency Exposure Authorization Limits JPM REVISION: 1 (SRO ONLY)
KIA
REFERENCE:
2.3.4 3.7 TASK ID: 1350-006-03-023 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING
~ SROONLY 0 ALTERNATEPATHJPM ~ ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
[8J Perform D Plant Site D Annual Requa! Exam D BVT D Simulate D Simulator D Initial Exam D NRC
[8J Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SSN:
Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSA T evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
IEvaluator Signature:
BVPS-TR-0026 Page 2 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determines Emergency Exposure Authorization Limits for stated conditions are 75 rem TEDE, 225 rem lens of eye, and 750 rem organ CDE. Determines acute radiation probable effects to be possible slight transient blood changes, serious delated effects improbable.
RECOMMENDED Classroom STARTING LOCATION:
INITIAL CONDITIONS:
A General Emergency has been declared at Unit 1.
An individual is trapped and bleeding in a High Radiation Area.
An immediate response is necessary to search and rescue this individual.
It has been clearly determined that actions establishing adequate or equivalent protection, with less dose are not readily available.
Mike Defulle, a qualified radiation worker has volunteered to perform the rescue activity and has been briefed on risks of projected radiation exposure.
The Senior Vice President is not available.
Mike Defulle has a year to date exposure of 880 mR (TEDE).
The area dose rate is 8820 mRJhr and there is no airborne radioactivity present.
The rescue activity could take up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .
Mike Defulle has No previous history of accident or emergency exposure.
INITIATING CUE: As the Emergency Director, you are to evaluate the listed conditions and determine ALL of the Emergency Exposure Authorization Limits.
Also determine the Acute Radiation Exposure Probable Effects to this worker based on a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months stay time. The Emergency Exposure Authorization Form will NOT be filled out at this time.
Document your determinations in the box below.
REFERENCES:
1/2-EPP-IP 5.3, "Emergency Exposure Criteria and Control", Rev. 11 TOOLS: None HANDOUT: 1/2-EPP-IP 5.3, "Emergency Exposure Criteria and Control", Rev. 11
B VPS-TR-0026 Page 3 of 4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: IAD-038 JPM TITLE: Determine Emergency Exposure Authorization Limits JPM REVISION: I (SRO ONLY)
STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT ::::>
START TIME: --------
EVALUATOR NOTE: Block 5 ONLY is Critical.
I .C Determines the appropriate I. IC Using Attachment A and conditions provided, Emergency Exposure determines the Emergency Exposure Authorization Authorization Limits using Limits:
Attachment A.
Block 1:
(Step 8.1.2)
Declared Emergency YES General Emergency Personnel are qualified YES No declared pregnant YES Male workers Block 2:
Exposure necessary to (1) save human life YES Block 3:
Personnel are volunteers and have been YES-has briefed on risks of projected radiation volunteered exposure Block 4:
Senior Vice President authorization for NO - VP not exposure> 75 Rem available Block SC:
Limit exposure to: 75 rem TEDE; 225 rem lens of eye, 750 rem organ CDE COMMENTS:
BVPS-TR-0026 Page 4of4 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-038 JPM TITLE: Determine Emergency Exposure Authorization Limits JPM REVISION: 1 (SRO ONLY)
STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT =:> SIU 2.C Determines the Acute 2.1 C Determines (3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ) x (8820 mr/hr) = 26.46 Rem Radiation Exposure and based on this determination, references probable effects (biological Attachment C and further determines the probable risk) using Attachment C. effects to the worker for a dose of 25-100 Rads are:
(Step 8.1.5)
Possible Slight transient blood changes .
Serious delayed effects improbable.
COMMENTS:
EVALUATOR CUE: Once determinations are documented, inform the candidate that this JPM is COMPLETE.
STOP TIME: - - - - - - - -
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
LJ Read:
INITIAL CONDITIONS:
A General Emergency has been declared at Unit 1.
An individual is trapped and bleeding in a High Radiation Area.
An immediate response is necessary to search and rescue this individual.
It has been clearly determined that actions establishing adequate or equivalent protection, with less dose are not readily available.
Mike Defulle, a qualified radiation worker has volunteered to perform the rescue activity and has been briefed on risks of projected radiation exposure.
The Senior Vice President is not available.
Mike Defulle has a year to date exposure of 880 mR (TEDE).
The area dose rate is 8820 mR/hr and there is no airborne radioactivity present.
The rescue activity could take up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .
Mike Defulle has No previous history of accident or emergency exposure.
T"~UTIATING CUE: As the Emergency Director, you are to evaluate the listed conditions and determine ALL of the Emergency Exposure Authorization Limits.
Also determine the Acute Radiation Exposure Probable Effects to this worker based on a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months stay time. The Emergency Exposure Authorization Form will NOT be filled out at this time.
Document your determinations in the box below.
ANSWER: NAME: _ _ _ _ _ _ _ _ _ _ __
1. Limit Exposure to:
2. Probable Effects:
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
L..] Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Determine Protective Action Recommendations (Part 1)
TRAINING MATERIAL NUMBER: lAD-037
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lAD-037 REVISION NUMBER: 1 TECHNICAL
REFERENCES:
l/2-EPP-IP-4.1, "Offsite Protective Actions", Rev. 31 l/2-EPP-IP-1.1.FOl Rev. 8 1/2-EPP-1-5 Rev 42 INSTRUCTIONAL SETTING: Classroom APPROXIMATE DURATION: 15 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: lAD-037 New Revision: 1 Description of Change(s):
1. Updated for format changes.
2. Lowered and adjusted dose rates to lower as the distance from the site increased.
3. Modified to select a different PAR than JPM 2AD-03 7.
4. Task Standard: Modify to resemble step 3 of the JPM, with the PAR bulleted items and state that it must be completed within 15 minutes. Initiating Cue: Reword second to last sentence to state "Assume the Peer Check on the form will be SAT." NOTE- We could type in the word Peer Check in the signature blank of the form to avoid any confusion. Step 5: Add Critical Step 5.3C to verify that the form is signed by the candidate.
Reason for Change (s):
1. New JPM format
2. The 5 mile dose was higher than then EAB and 2 mile dose, lowered dose to reflect background.
3. Per NRC feedback, different PAR than one used on exam at BV2.
4. NRC comments
BVPS-TR-0026 Page 1of5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: IAD-037 JPM TITLE: Determine Protective Action Recommendations (Part 1)
JPM REVISION: 1 KJA
REFERENCE:
2.4.44 4.4 TASK ID: 1350-007-03-023 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM 0 TRAINING
~ SROONLY 0 ALTERNATEPATHJPM ~ ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
~ Perform D Plant Site D Annual Requa! Exam D BVT D Simulate D Simulator D Initial Exam D NRC
~ Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SSN:
Time ~ Yes Allotted 15 Minutes Actual minutes Critical: D No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
I Evaluator Signature:
BVPS-TR-0026 Page 2 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determine Protective Action Recommendations in accordance with 112-EPP-IP-4.1within15 minutes. Determines and documents on l/2-EPP-IP-1.1.FOl, the following PARs: SHELTER in Place 0 to 5 miles, 360 degrees. All others monitor and prepare. KI per the State Plan.
RECOMMENDED Classroom STARTING LOCATION:
INITIAL CONDITIONS: A General Emergency has been declared at Unit 1 at 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months following a small break LOCA and the loss of all 4KV emergency power on EAL SG 1. A Core Cooling Red condition exists.
The General Emergency was declared due to a Prolonged Loss of all OFFSITE and ONSITE AC power to Emergency Busses (SG 1) due to a tornado.
Unit 2 is shutdown and in an outage.
The following plant conditions exist:
35' wind direction is from 270° at 4 MPH.
150' wind direction is from 290° at 11 MPH.
500' wind direction is from 110° at 15 MPH.
Beaver County 911 Call Center reports numerous road closures due to downed trees and the Shippingport Bridge is closed due to structural damage.
NO radioactive release has occurred or is imminent (within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ).
There is NO Hostile Action event in progress.
Health Physics has provided the following dose projections:
At the EAB: .0025 REM TEDE; .0008 REM CDE At 2 miles: .00015 REM TEDE; .0004 REM CDE At 5 miles: .00009 REM TEDE; .00025 REM CDE INITIATING CUE: You are the Emergency Director and the TSC/EOF has NOT yet been activated. You are to evaluate the above conditions and determine which, if any, offsite Protective Action Recommendations (PAR) are necessary. Provide PAR by completing l/2-EPP-IP-1.1.FOl Nuclear Power Plant Initial Notification Form. Assume all Peer Checks will be SAT. This JPM is TIME CRITICAL.
REFERENCES:
l/2-EPP-IP-4.1, "Offsite Protective Actions", Rev. 31 l/2-EPP-IP-1.1.FOl Rev. 8 and 1/2-EPP-I-5 Rev 42 TOOLS: NONE HANDOUT: l/2-EPP-IP-4.1, "Offsite Protective Actions", Rev. 31 l/2-EPP-IP-1.1.FOl Rev. 8 and 112-EPP-I-5 Rev 42 Emergency Plan Wallboard
BVPS-TR-0026 Page 3of5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: lAD-037 JPMTITLE: Determine Protective Action Recommendations (Part 1)
JPM REVISION: 1 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)~
START TIME: - - - - - - - -
1. Locate Offsite Protective 1.1 Refers to l/2-EPP-IP-4.1, Attachment A, Part 1 Action Recommendation Offsite Protective Action Recommendation Flowchart Flowchart.
COMMENTS:
2. Determine offsite protective 2.1 Navigates PAR flowchart as follows:
action.
General Emergency already declared ( t)
Met data provided in Initial Conditions (t)
The difference between the 150' and 500' wind directions is 180 degrees; ( ~) goes to page 2 2.2 Navigates to Page 2:
This is the initial PAR (t) AND
NO Loss of Containment Fission Product Barrier transitions to the right (~)
2.3 Navigates to second decision box:
NO Hostile Action (t) OR
There are impediments to evacuation - YES (t) 2.4 Navigates to the third decision box:
Projected Dose at or Beyond Site Boundary 2 5 REM TEDE-NO (t) 2.5 Navigates to the Protective Action Recommendation.
COMMENTS:
BVPS-TR-0026 Page 4of5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-037 JPMTITLE: Determine Protective Action Recommendations (Part 1)
JPM REVISION: 1 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT ~ SIU 3.C Determine Offsite Protective 3.1.C Determines and documents on l/2-EPP-IP-1.1.FOl, Action Recommendations. the following P ARs:
SHELTER in Place 0 to 5 miles, 360 degrees
All others monitor and prepare
KI per the State Plan COMMENTS:
4. Continues Assessment. 4.1 Indicates that metrological and radiological conditions would be monitored.
EVALUATOR CUE: If asked cue, "There has been no change in metrological or radiological conditions."
COMMENTS:
BVPS-TR-0026 Page 5of5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lAD-037 JPMTITLE: Determine Protective Action Recommendations (Part 1)
JPM REVISION: 1 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> S!U 5.C Completes the PAR within 15 5.lC Determines that form is completed within 15 minutes minutes. of the start time.
5 .2 Confirm the start and stop times are within 15 minutes.
5.3C Verify the form is signed with the Candidate's name.
COMMENTS:
EVALUATOR CUE: When the candidate completes the Protective Action Recommendation, the evaluation for this JPM is complete.
STOP TIME: _ _ _ _ _ __
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS: A General Emergency has been declared at Unit 1 at 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months following a small break LOCA and the loss of all 4KV emergency power on EAL SG 1. A Core Cooling Red condition exists.
The General Emergency was declared due to a Prolonged Loss of all OFFSITE and ONSITE AC power to Emergency Busses (SG 1) due to a tornado.
Unit 2 is shutdown and in an outage.
The following plant conditions exist:
35' wind direction is from 270° at 4 MPH.
150' wind direction is from 290° at 11 MPH.
500' wind direction is from 110° at 15 MPH.
Beaver County 911 Call Center reports numerous road closures due to downed trees and the Shippingport Bridge is closed due to structural damage.
NO radioactive release has occurred or is imminent (within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ).
There is NO Hostile Action event in progress.
Health Physics has provided the following dose projections:
At the EAB: .0025 REM TEDE; .0008 REM CDE At 2 miles: .00015 REM TEDE; .0004 REM CDE At 5 miles: .00009 REM TEDE; .00025 REM CDE INITIATING CUE: You are the Emergency Director and the TSC/EOF has NOT yet been activated. You are to evaluate the above conditions and determine which, if any, offsite Protective Action Recommendations (PAR) are necessary. Provide PAR by completing 112-EPP-IP-l.1.FOl Nuclear Power Plant Initial Notification Form. Assume all Peer Checks will be SAT. This JPM is TIME CRITICAL.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
FENOC NUCLEAR POWER PLANT USE FOR: STATE I COUNTY USE ONLY
INITIAL CLASSIFICATIONS, INITIAL NOTIFICATION FORM
CHANGES IN CLASSIFICATIONS DATE: TIME:
Beaver Valley Power Station (BVPS)
CHANGES IN PROTECTIVE ACTION MESSAGE NO:
1/2-EPP-IP-1.1.F01 Rev. 8 RECOMMENDATIONS
EVENT TERMINATION
1. This is applicable to :
BVPS Unit 1 OR D BVPS Unit2 OR D Both BVPS Units 1 & 2 Current Reactor Power Levels are: Unit 1:----%, Unit 2: I %. Code Word is: SIMULATOR
2. This is: 0 An Actual Emergency
A Drill
3.
a. A
GENERAL EMERGENCY 0 SITE AREA EMERGENCY 0 ALERT 0 UNUSUAL EVENT was declared at: on -- based on EAL: ---
(TIME) (DATE)
D b. The Emergency situation has been terminated at: on (TIME) (DATE)
D c. The Protective Action Recommendation is being modified at: on (TIME) (DATE)
4. Brief non-technical description of event:
5. The radiological conditions are:
D a. A non-routine release of radioactive material, as a result of this event, is in progress.
The release is: D Airborne D Liquid D b. The release of radioactive material associated with this event has been terminated.
c. NO Radiological Release is in progress as a result of this event.
J. Wind Direction is FROM: ___,_L--_ degrees at 150' Wind Speed is: I mph at 35'
7. Utility Protective Action Recommendations (PARs):
D a. None D b. EVACUATE D 2 Miles - 360° D 5 Miles - 360° D 10 Miles - 360° AND Downwind Wedge D NIA D 5 Miles (check applicable sectors) D 10 Miles (check applicable sectors)
DA DB oc DD DE OF OG DH OJ DK DL OM ON DP oa DR AND that potassium iodide (Kl) be administered to the general public in accordance with State procedures.
The general public in unaffected areas should be advised to monitor EAS and prepare for further protective actions .
c. SHELTER IN PLACE 0 2 Miles - 360° ~ 5 Miles - 360° 0 10 Miles - 360° AND Downwind Wedge* NIA D 5 Miles (check applicable sectors) 0 10 Miles (check applicable sectors)
DA OB De Do DE OF OG OH OJ OK OL OM ON OP oa OR AND that potassium iodide (Kl) be administered to the general public in accordance with State procedures.
The general public in unaffected areas should be advised to monitor EAS and prepare for further protective actions.
Callback number is 724-643-8000 For Utility Use Only PEER Check: Approved: ==:;:N::A:::::M:::E::=:==============----_J
ANSWER KEY *****
Yellow Highlight is required, Blue Highlight is not critical information for this JPM.
FENOC NUCLEAR POWER PLANT USE FOR: STATE I COUNTY USE ONLY
INITIAL CLASSIFICATIONS, INITIAL NOT/FICA TION FORM
CHANGES IN CLASSIFICATIONS DATE: TIME:
Beaver Valley Power Station (BVPS)
CHANGES IN PROTECTIVE ACTION MESSAGE NO:
1/2-EPP-IP-1.1.F01 Rev. 8 RECOMMENDATIONS
EVENT TERMINATION
1. This is applicable to : 0 BVPS Unit 1 OR D BVPS Unit2 OR D Both BVPS Units 1 & 2 Current Reactor Power Levels are: Unit 1: %, Unit 2: %. Code Word is: SIMULATOR
2. This is: D An Actual Emergency D ADrill
3. Da. A 0GENERALEMERGENCY 0 SITE AREA EMERGENCY 0 ALERT 0 UNUSUAL EVENT was declared at: on based on EAL:
(TIME) (DATE)
D b. The Emergency situation has been terminated at: on (TIME) (DATE)
D c. The Protective Action Recommendation is being modified at: on (TIME) (DATE)
4. Brief non-technical description of event:
5. The radiological conditions are:
D a. A non-routine release of radioactive material, as a result of this event, is in progress.
The release is: D Airborne D Liquid D b. The release of radioactive material associated with this event has been terminated.
D c. NO Radiological Release is in progress as a result of this event.
6. Wind Direction is FROM: degrees at 150' Wind Speed is: mph at 35'
7. Utility Protective Action Recommendations (PARs):
D a. None D b. EVACUATE D 2 Miles - 360° D 5 Miles - 360° D 10 Miles - 360° AND Downwind Wedge D N/A D 5 Miles (check applicable sectors) D 10 Miles (check applicable sectors)
DA DB De DD DE OF OG DH OJ DK DL OM ON DP oa DR AND that potassium iodide (Kl) be administered to the general public in accordance with State procedures.
The general public in unaffected areas should be advised to monitor EAS and prepare for further protective actions.
0 c. SHELTER IN PLACE D 2 Miles - 360° D 5 Miles - 360° D 1O Miles - 360° AND Downwind Wedge D N/A D 5 Miles (check applicable sectors) D 10 Miles (check applicable sectors)
DA DB De DD DE OF OG DH OJ DK DL OM ON DP oa DR AND that potassium iodide (Kl) be administered to the general public in accordance with State procedures.
The general public in unaffected areas should be advised to monitor EAS and prepare for further protective actions.
Callback number is 724-643-8000 For Utility Use Only PEER Check: Peer Check l fl'wt eliecli Approved:
INSTRUCTIONS FOR COMPLETION PLANT INITIAL NOTIFICATION FORM (INF) 1/2-EPP-IP-1.1.F01 Rev. 8 Boxes 1 through 7 always need completed.
1. : Check one box for the affected Unit(s) associated with Item 3 below.
If the event results in an emergency declaration for both Units, check the Unit box with the higher event classification and provide additional details on the other unit in the follow-up notification.
If the event results in the same emergency declaration for both Units, check the box for both Units.
Always include the power level for both Units (power level at time of declaration) regardless of which Unit is making the emergency declaration.
2. : Check the one appropriate box. [Check 'A Drill' if this event is a drill.]
3. : Check the one applicable box and complete other listed information within that box area.
4. : Explain the EAL(s) listed in Item 3a; or why 3b or 3c was checked.
5. : Check the one appropriate box. Check the appropriate release box within 5a if checked.
6. : Supply the appropriate meteorological data for both wind direction and speed.
7. : Check the appropriate boxes (a, b or c) per 1/2-EPP-IP-4.1 Attachment A. Check all appropriate boxes in 7b or ?c if applicable.
Peer Check: Print and sign name Approval: Must be performed by Emergency Director.
Print and sign name.
Page 2 of 2
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Withdraw Shutdown Bank "A" TRAINING MATERIAL NUMBER: 1CR-085
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training (Retraining)
COMPUTER CODE: ICR-085 REVISION NUMBER: 7 TECHNICAL
REFERENCES:
1OM-50.4.D2, Reactor Startup From Mode 3 To Mode 2 Rev. 0 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: lCR-085 New Revision: 7 Description of Change( s):
1. Updated to new format
2. Modified JPM from OM-1 procedure to OM-50 procedure that is now used for plant startup.
3. Updated to match current procedure revision.
4. Correct typo in Task number to 0011 versus 0111.
5. Changed Task Standard for board awareness of stuck rod N7 during rod withdrawal.
6. Added SBA full out rod position is 228 steps for the current cycle to the Initial Conditions.
7. Modified time to 15 minutes based upon validation.
8. Added critical step for monitoring rod motion by inserting stuck rod N7 during withdrawal. This will be the termination point of the JPM.
9. Bulleted the Initial Conditions.
10. Changed student handout to include pages 1-32of10M-50.4.D2.
Reason for Change (s):
1. Standard JPM format has been updated.
2. OM-1 procedure now only starts up Rod drive system, Shutdown Bank withdrawal is now performed as a part of the overall plant startup procedure.
3. Procedure was revised to be inclusive of all startup activities.
4. Task review and update.
5. Modified Task Standard for critical step alignment with JPM.
6. The full out rod position was added to the initial conditions based on NRC feedback.
7. Validation times were shorter due to validation.
8. Added stuck rod for board awareness and additional critical steps per NRC request.
9. Ease of evaluator/trainee reading.
10. Easier for pre-briefing prior to JPM performance.
BVPS-TR-0026 Page 1 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-085 JPM TITLE: Withdraw Shutdown Bank "A" JPM REVISION: 7 KJA
REFERENCE:
001A3.02 3.713.6 TASK ID: 0011-013-01-013 014A4.02 3.4/3.2 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D SROONLY D ALTERNATE PATH JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
[gJ Perform D Plant Site D Annual Requal Exam D BVT D Simulate [gJ Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SAP:
Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
I Evaluator Signature:
BVPS-TR-0026 Page 2of5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Shutdown Bank "A" has been withdrawn, source range counts were monitored, and SBA Rod N7 was identified as a stuck rod prior to the Shutdown Bank A Group Step Counters indicating 125 steps.
RECOMMENDED Simulator STARTING LOCATION:
INITIAL CONDITIONS:
The plant is in a normal startup evolution.
The reactor trip breakers are closed
All initial conditions are met to withdraw the Shutdown banks.
The Rod Control System has been started to the point of withdrawing the shutdown banks.
Full out position for Shutdown Bank 'A' rods this cycle is 228 steps.
10M-50.4.D2 has been completed through step IV.B.l.k.
INITIATING CUE: Your Supervisor directs you to withdraw Shutdown Bank 'A' in accordance with 10M-50.4.D2, "Reactor Startup From Mode 3 To Mode 2", Step IV.C.l.
REFERENCES:
10M-50.4.D2, "Reactor Startup From Mode 3 To Mode 2", Rev 0 TOOLS: None HANDOUT: 10M-50.4.D2, "Reactor Startup From Mode 3 To Mode 2", Rev 0, pages 1-32.
BVPS-TR-0026 Page 3of5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-085 JPM TITLE: Withdraw Shutdown Bank "A" JPM REVISION: 7 STANDARD SIMULATOR SETUP: Initialize into a Start-up IC with Shutdown Banks inserted. Ensure all step counters are set to zero. Ensure Audio Count Rate is audible. Identify the full out rod position in the following cue.
TRIGGER 5 = rncrfpa(l)>=lOO IMF CRFl lAD 1 START TIME: - - - - - - - -
1. Review procedure. 1.1 Candidate reviews procedure 10M-50.4.D2 as provided.
COMMENTS:
2. Record initial SR and IR 2.1 Records SR and IR levels before pulling rods.
levels before pulling shutdown banks. COMMENTS:
SR IR N31 _ _ cps N35 _ _arnps N32 _ _cps N36_ _arnps
BVPS-TR-0026 Page 4 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-085 JPM TITLE: Withdraw Shutdown Bank "A" JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU 3.C Place the bank selector switch 3 .1 C Places bank selector switch to SBA (Shutdown Bank in the SBA (Shutdown Bank A) position.
A) position.
COMMENTS:
4.C Place the spring return ROD 4.1 C Places rod motion lever in the OUT position.
MOTION lever to the OUT position. 4.2 Verifies the WHITE OUT ( i ) direction lamp is lit, while rod motion lever is held in the OUT position.
COMMENTS:
EVALUATOR NOTE: During the withdrawal of SBA, Rod N7 will stop moving at approximately 100 steps. After the stuck rod is identified, rod withdrawal is terminated, and the US/SM has been notified, the JPM may be terminated.
5. Observes that the Shutdown 5.1 Monitors SBA group step counters by observing Bank A, group 1 and group 2 increasing step indication.
step counters indicate the withdrawal steps. COMMENTS:
BVPS-TR-0026 Page 5 of 5 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-085 JPM TITLE: Withdraw Shutdown Bank "A" JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 6.C Verify by observing the Rod 6.1 Monitors SBA Rod Position indicators on the vertical Position Indicators (VB-B) board are increasing as rods are withdrawn.
and respective IPC computer points that the mechanisms in 6.2 Monitors IPC computer points for SBA Rods are Shutdown Bank A are increasing as rods are withdrawn.
movmg.
6.3 Acknowledges A4-76, Computer Alarm Rod Deviation/Seq NIS Power range Tilts. (A4-76 will alarm at approximately 111 steps).
6.4C Candidate identifies Stuck Rod N7 prior to the SBA group step counters indicating 125 steps.
COMMENTS:
7.C Withdraw the Shutdown Bank 7.1 Monitors the Source Range instruments N31 and N32 A rods to the all rods out as SBA rods are withdrawn.
position for the current cycle and monitor the Source Range 7.2C Releases the Rod Motion lever after SBA Rod N7 is instrumentation during the rod identified as a Stuck Rod, and informs the US/SM of movement. the condition.
EVALUATOR CUE: As US/SM, acknowledge report of Stuck Rod N7.
COMMENTS EVALUATOR CUE: State "This JPM is complete" STOP TIME: _ _ _ _ _ __
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
The plant is in a normal startup evolution.
The reactor trip breakers are closed
All initial conditions are met to withdraw the Shutdown banks.
The Rod Control System has been started to the point of withdrawing the shutdown banks.
Full out position for Shutdown Bank 'A' rods this cycle is 228 steps.
10M-50.4.D2 has been completed through step IV.B.1.k.
INITIATING CUE: Your Supervisor directs you to withdraw Shutdown Bank 'A' in accordance with 1OM-50.4.D2, "Reactor Startup From Mode 3 To Mode 2", Step IV.C.l.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Perform Manual Makeup to the Charging Pump Suction TRAINING MATERIAL NUMBER: lCR-581
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lCR-581 REVISION NUMBER: 7 TECHNICAL
REFERENCES:
1OM-7.4.P, "Blender Manual Makeup Operation", Revision 11 Unit 1 Plant Curve Book (1 CB-29), Rev. 7 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: lCR-581 New Revision: 7 Description of Change(s):
1. Updated for Curve Book (1 CB-29) revision.
2. Added note to reset the integrators after each Simulator Reset
3. Clarified JPM step 14 regarding totalizer and integrator readings.
Reason for Change (s):
1. Curve Book (1 CB-029) was revised.
2. Note to remind Simulator operator for subsequent JPM performances.
3. Clarified at the request of the NRC evaluator.
BVPS-TR-0026 Page 1 of 10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: lCR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 KIA
REFERENCE:
004 A4.01 3.8/3.9 TASK ID: 0071-025-01-013 004 A4.04 3.213.6 004 A4.07 3.913.7 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D SROONLY ~ ALTERNATEPATHJPM D ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
~ Perform D Plant Site D Annual Requa! Exam D BVT D Simulate ~ Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EV ALDA TION RESULTS Performer Name: Performer SSN:
Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
Evaluator Signature:
BVPS-TR-0026 Page 2of10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Begins manual makeup at correct settings and terminates makeup upon discovery of no boric acid flow.
RECOMMENDED Simulator STARTING LOCATION:
INITIAL CONDITIONS:
Core burn up is 1000 MWD/MTU
RCS boron concentration is 1207 ppm from the most recent Chemist's sample
The in service Boric Acid Tank concentration is 7380 ppm
VCT level is currently 24%
INITIATING CUE: Your supervisor directs you to add 300 gallons of blended makeup to the VCT at the corrected boron concentration and a flow of 100 gpm in accordance with lOM-7.4.P, "Blender Manual Makeup Operation".
All Initial Conditions have been verified met.
REFERENCES:
lOM-7.4.P, "Blender Manual Makeup Operation", Revision 11 Unit 1 Plant Curve Book (ICB-29), Rev. 7 TOOLS: Calculator HANDOUT: lOM-7.4.P, "Blender Manual Makeup Operation", Revision 11 Unit 1 Plant Curve Book (1 CB-29), Rev. 7
BVPS-TR-0026 Page 3of10 Revision 0 OPERATIO NS JOB PERFORMANCE MEASURE JPMNUMBER: lCR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT ::::::> SIU SIMULATOR SETUP: Select a Mode 1 IC. Ensure VCT level at 24% by setting ACVCVCTW = 6975.
Select remote functions and insert CHS067 to close 1CH-P-2A discharge valve to boric acid filter by entering 0 in remote value and selecting insert. Ensure blender setpoint is set to 1254 ppm value (4.25) on FCV-1CH-113A. Snap IC to save for future use.
EVALUATOR NOTE: Ensure in-service BAST placard is updated to 7380 ppm and RCS Cb placard is updated to 1207 ppm, PRIOR to bringing candidate into simulator.
ENSURE LAPTOP IS RESET FOR AUDIBLE BEEPs (Each Simulator Reset)
RESET both Integrators to ZERO after each Simulator Reset Provide candidate a copy of lOM-7.4.P, Blender Manual Makeup Operation. Place simulator in run when candidate is ready to begin JPM.
START TIME: - - - - - - - -
1. Reviews procedure. 1.1 Candidate reviews 1OM-7.4.P.
COMMENTS:
BVPS-TR-0026 Page 4of10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: lCR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU
2. At the discretion of the RO 2.1 This step is NIA based on initial conditions of 24%
and SM/US, Take manual VCT level.
control of the VCT Level and Pressure using [LCV -1 CH- EVALUATOR CUE: If asked, role play as Unit 115A], VCT to Degas Divert Supervisor, and state diverting of the VCT is not and/or [SOV-lCH-258], VCT required.
Vent Isol.
COMMENTS:
3. If letdown flow to a de gasifier 3.1 This step is NIA.
will exceed 75 gpm, perform either of the following: COMMENTS:
4. Obtain the existing RCS 4.1 Candidate should obtain RCS Boron concentration boron concentration obtained from the Initial Conditions or posted placard.
from the Chemist's sample.
COMMENTS:
5. If the plant is operating at 5.1 Locates Curve Book and determines correction factor power, Obtain the B-10 from lCB-29 equals 0.981.
Correction Factor from Curve Book Figure 29, Otherwise COMMENTS:
Contact Reactor Engineering to obtain a B-10 Correction Factor.
BVPS-TR-0026 Page 5of10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: lCR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU
6. Calculate Corrected Boron 6.1 Calculates a corrected boron concentration of 1184 Concentration AND record in ppm.
the Narrative Log.
(1207 x 0.981=1184)
Corrected Boron Concentration = Present EVALUATOR CUE: If asked, inform the Candidate Boron Concen. X B-10 that another operator will make the Narrative Log Correction Factor entry.
COMMENTS:
7. Obtain the inservice Boric 7.1 Candidate should obtain the inservice Boric Acid Acid Tank boron Tank boron concentration from the Initial Conditions concentration obtained from or the posted placard. (7380 ppm)
Chemist's sample COMMENTS:
8. Place lMU to STOP for 8.1 Places lMU control switch to STOP for> 1 second.
greater than 1 second to allow the blender to unarm. 8.2 Verifies makeup control GREEN light - LIT and RED light - NOT LIT.
COMMENTS:
BVPS-TR-0026 Page 6of10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU
9. Adjust [FCV-1CH-113A], 9.1 Calculates boric acid flow:
Boric Acid to Blender FCV, controller to the desired I 184ppm X IOOgpm = 16 .0 m setting as follows: 7380 gp Determine Boric Acid Flow EVALUATOR CUE: If desired, inform candidate from the following that another operator will update the Narrative Log.
calculation:
Boric Acid Flow = Desired COMMENTS:
blender outlet concentration X Desired blender total flow/
Actual boric acid supply concentration 10.C Set [FCV-1CH-113A] as IO.IC Sets FCV-ICH-l 13A for the desired flowrate. (400 follows: units)
Pot setting= 16.0 gpm/4gpm x 100 = 400 units Pot Setting = Boric Acid Flow/4 gpm X 100 EVALUATOR NOTE: A pot setting of 395-405 units is acceptable.
COMMENTS:
BVPS-TR-0026 Page 7of10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: lCR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ S/U 11.C Set [YIC-lCH-113], Boric 11.lC Adjusts YIC-lCH-113 to 48 (GREEN LED).
Acid Integrator, to the total volume in gallons of boric BA Vol= 16 X 300/100 = 48 acid to be added from the following equation: (BB-A) 11.2 Depresses YI C-1 CH-113 reset pushbutton.
11.3 Verifies YIC-lCH-113 is reading ZERO (RED LED).
B.A. Volume= B.A. Flow X Total Makeup Flow/Total COMMENTS:
Makeup Volume
12. Adjust [FCV-1CH-114A] 12.1 Sets FCV-1CH-114A for the desired blender total Primary Water to Blender flow setpoint of 100 gpm.
FCV, controller to the desired blender total flow. 100/16 X 100 = 625 units (+/-25)
COMMENTS:
Pot Setting = (Total Flow Rate/16 gpm) X 100 13.C Set [YIC-1CH-168A], 13.lC Adjusts YIC-1CH-168A to 300 (GREEN LED).
Blender Output Integrator, for desired quantity. 13.2 Depresses YIC-1 CH-168A reset pushbutton.
a. Reset [YIC-1CH-168A], 13.3 Verifies YIC-1CH-168A reading ZERO (RED LED).
Blender Output Integrator.
COMMENTS:
BVPS-TR-0026 Page 8of10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: ICR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT ~ S/U
14. Note the flow totalizer 14.1 Sums the totalizer and integrator values, then records indication and add to it the the summed values for both.
number of gallons set into the batch integrator for [YIC- YIC-lCH-113 Totalizer+ 48 gal.=
1CH-113 ], Boric Acid YIC-1CH-168A Totalizer+ 300 gal.= _ _ _ __
Integrator AND [YIC-1CH-168A], Blender Output COMMENTS:
Integrator.
15. If in Mode 4, 5 or 6, align PG 15 .1 This step is NIA. Plant is in Mode 1.
water to the blender by unlocking and opening either COMMENTS:
of the following valves:
(Blender Room)
16. Immediately prior to initiating 16.1 Verifies all Reactor coolant pumps are operating -
makeup, perform the RED lights - LIT and WHITE lights - NOT LIT.
following:
Verify a reactor coolant 16.2 Makes a notation in the Narrative Log.
pump is operating in an unisolated loop. EVALUATOR CUE: Another operator will update
Record the commencement the narrative log.
of the makeup and the RCS flow verification in the Narrative log.(LRS COMMENTS:
3.1.10.1)
BVPS-TR-0026 Page 9of10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: lCR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 17.C Place [FCV-1CH-113B], 17.lC Places FCV-1CH-113B control switch to OPEN.
Blender Outlet to Chg Pumps FCV, control switch to OPEN. 17.2 Verifies RED light-LIT and GREEN light-NOT (BB-A) LIT.
COMMENTS:
18.C Place 43/MU to MAN. (BB- 18.lC Places 43/MU control switch to MANUAL.
A)
COMMENTS:
FAULT STATEMENT: The boric acid flowpath is isolated, no boric acid flow will occur in the next step.
19.C To initiate makeup, Place lMU 19.lC Places lMU control switch to START.
to START. (BB-A) 19 .2 Verifies makeup control RED light - LIT and GREEN light - NOT LIT.
19 .3 Boric Acid Transfer Pump FAST speed RED light -
LIT.
COMMENTS:
BVPS-TR-0026 Page 10of10 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-581 JPM TITLE: Perform Manual Makeup to the Charging Pump Suction JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => S/U 20.C Verify boric acid and PG Water 20.1 Determines from FR-lCH-113 that no boric acid flow to Blender flow on [FR-lCH- exists. (FCV-1CH-l 13A red light-LIT, Boric Acid 113], Boric Acid Flow. flow - ZERO, and Total makeup flow indicates upscale).
20.2C Places lMU control switch to STOP to immediately terminate dilution. (Dilution must be stopped prior to 100 gallons of water being added to the RCS).
COMMENTS:
EVALUATOR CUE: State "This JPM is complete" STOP TIME: _ _ _ _ _ __
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
Core bumup is 1000 MWD/MTU
RCS boron concentration is 1207 ppm from the most recent Chemist's sample
The in service Boric Acid Tank concentration is 7380 ppm
VCT level is currently 24%
INITIATING CUE: Your supervisor directs you to add 300 gallons of blended makeup to the VCT at the corrected boron concentration and a flow of 100 gpm in accordance with lOM-7.4.P, "Blender Manual Makeup Operation".
All Initial Conditions have been verified met.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Depressurize RCS During SGTR TRAINING MATERIAL NUMBER: lCR-638
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training (Retraining)
COMPUTER CODE: lCR-638 REVISION NUMBER: 4 TECHNICAL
REFERENCES:
1OM-53A.1.E-3, Issue 3 Rev. 0 10M-53A.1.6-A, Issue IC Rev. 0 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: 1CR-638 New Revision: 4 Description of Change(s):
1. Updated JPM for new format
2. Updated for procedure revision
3. Added Note to reset the computers to the reactor trip sprays after each Simulator Reset.
Reason for Change (s):
1. JPM format has changed
2. E-3 procedure has been revised to Issue 3 Rev 0.
3. Note to remind Simulator Operator for subsequent JPM peformances.
BVPS-TR-0026 Page 1of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-638 JPM TITLE: Depressurize RCS During SGTR JPM REVISION: 4 KlA
REFERENCE:
010 A4.03 4.0/3.8 TASK ID: 0531-004-05-013 038 EAl.04 4.3/4.1 038 EAl.05 4.1/4.3 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D SRO ONLY ~ ALTERNATEPATHJPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
~ Perform D Plant Site D Annual Requal Exam D BVT D Simulate ~ Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SAP:
Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
IEvaluator Signature:
BVPS-TR-0026 Page 2of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: RCS pressure reduced in accordance with the RCS Depressurization step of 1OM-53A.1.E-3. Candidate Stops pressure reduction when conditions are met in accordance with direction given in this step.
RECOMMENDED Simulator STARTING LOCATION:
INITIAL CONDITIONS: A SGTR has occurred on the lC steam generator, resulting in a reactor trip and safety injection. Step 14of10M-53A.l.E-3, Steam Generator Tube Rupture, is being performed at this time.
INITIATING CUE: Your supervisor directs you to depressurize the RCS by continuing with E-3, Steam Generator Tube Rupture, step 14.
REFERENCES:
1OM-53A.1.E-3, Issue 3, Rev. 0 10M-53A.1.6-A, Issue lC, Rev. 0 TOOLS: None HANDOUT: 10M-53A.1.E-3, place kept up to Step 14 1OM-53A.1.6-A
B VPS-TR-0026 Page 3of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: ICR-638 JPM TITLE: Depressurize RCS During SGTR JPM REVISION: 4 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT)=>
EVALUATOR NOTE: This is a FAULTED JPM.
The failure of the PORV to close will require the candidate to close the appropriate PORV Block valve to stop the RCS depressurization.
EVALUATOR SET-UP:
Initialize Simulator to I 00% pwr IC. Insert I 000 gpm SGTR on the IC SIG. Progress thru E-0 to E-3, stop and freeze at step I4 ofE-3, Write JPM snap at this point. Insert following PORV RESEAT failures PRS04A, PCV-IRC-455C PRS04B, PCV-IRC-455D PRS04C, PCV-IRC-456 RESET the COMPUTER to the REACTOR TRIP SPRAYS after each Simulator Reset.
START TIME: - - - - - - -
1. Locate and review I OM- 1. I Locates and reviews I OM-53A.1.E-3, Steam 53A. I .E-3, Steam Generator Generator Tube Rupture.
Tube Rupture.
EVALUATOR NOTE: If the procedure is to be provided, NIA this JPM step.
COMMENTS:
2. RCPs IA and IC - BOTH 2.1 Verifies IA and IC RCPs are both running, RED RUNNING. lights lit, WHITE lights not lit.
COMMENTS:
BVPS-TR-0026 Page 4of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-638 JPM TITLE: Depressurize RCS During SGTR JPM REVISION: 4 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 3.C Fully open available PRZR 3.1 Locates both Pressurizer Spray Valves, PCV-lRC-spray valves. 455A and PCV-1RC-455B.
3.2C Opens Pressurizer Spray Valve, PCV-1RC-455A by putting 100% demand on the controller, in MANUAL.
3.3C Opens Pressurizer Spray Valve, PCV-1RC-455B by putting 100% demand on the controller, in MANUAL.
COMMENTS:
4.C Open one PRZR PORV. 4.1 Locates PRZR PORV's, PCV-1RC-455C, PCV-1RC-455D, OR PCV-lRC-456.
4.2C Places control switch for one PRZR PORV in the open position.
4.3 Verifies one PORV is open by observing the RED light is lit and GREEN light is not lit.
COMMENTS:
5. Check depressurization method 5.1 Verifies RCS/Pressurizer Pressure is reducing on PI-
- EFFECTIVELY REDUCING lRC-402, 403, or IPC.
RCS PRESSURE.
COMMENTS:
B VPS-TR-0026 Page 5of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-638 JPM TITLE: Depressurize RCS During SGTR JPM REVISION: 4 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::> SIU
6. Continue depressurization until 6.1 Locates instrumentation to determine PRZR Level, ANY of the following RCS Subcooling, RCS Pressure and Ruptured SIG conditions satisfied. Pressure and monitors for the following conditions.
PRZR level > 76%
OR
RCS subcooling based on Core Exit TCs LESS THAN SUBCOOLING ON ATTACHMENT 6-A OR BOTH:
RCS pressure LESS THAN RUPTURED SG PRESSURE AND
PRZR Level GREATER THAN 17%
OR BOTH:
RCS pressure WITHIN 300 PSI OF RUPTURED SG PRESSURE AND
PRZR Level GREATER THAN 4 7%
EVALUATOR NOTE: They should continue to depressurize until any of the above conditions are satisfied.
COMMENTS:
BVPS-TR-0026 Page 6of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-638 JPM TITLE: Depressurize RCS During SGTR JPM REVISION: 4 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT =>
FAULT STATEMENT PORV fails to Close, the PORV must be isolated by manually closing the associated PORV Block valve.
7.C Close PORV 7.1 Attempts to close PORV previously opened.
7.2 C Recognizes that PORV will NOT close and Closes the appropriate PORV Block valve.
GREEN light - LIT and RED light - NOT LIT COMMENTS:
8.C Close spray valves. 8.1 C Closes both Pressurizer spray valves.
Demand signal - At ZERO COMMENTS:
EVALUATOR NOTE: Terminate JPM when Pressurizer spray valves are closed, and candidate has checked RCS pressure rising. If the stuck open PORV is not noticed immediately, it is acceptable to close the spray valves before closing the PORV block valve. Do not terminate the JPM until they have addressed the PORV unless they state that the JPM is complete.
EVALUATOR CUE: State "This JPM is complete" STOP TIME: - - - - - - - -
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS: A SGTR has occurred on the lC steam generator, resulting in a reactor trip and safety injection. Step 14of10M-53A.l.E-3, Steam Generator Tube Rupture, is being performed at this time.
INITIATING CUE: Your supervisor directs you to depressurize the RCS by continuing with E-3, Steam Generator Tube Rupture, step 14.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Respond to a Loss of the RHR System TRAINING MATERIAL NUMBER: ICR-694 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: ICR-694 REVISION NUMBER: 0 TECHNICAL
REFERENCES:
IOM-53C.l.10.I, Loss of the Residual Heat Removal Capability, Rev I5 I OM-I 0.4.B, Residual Heat Removal System Operation, Rev I I 1OM-I0.4.AAB, Residual Heat Removal System Disch Flow Low, Rev 4 1OM-10.4.AAC, Residual Heat Removal PP Auto Stop, Rev 2 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: I5 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERA TIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: 1CR-694 New Revision: 0 Description of Change(s):
1. Update to new JPM format.
2. Updated to latest procedure revision.
3. Modified JPM initial conditions to match alternate JPM lCR-594.
4. JPM is significantly modified from the original version, begins with a normal evolution.
5. JPM is now Alternate Path, revision 0.
6. Renumbered to new JPM lCR-694, since JPM is Alternate path. Formerly was lCR-094 Reason for Change (s):
1. JPM format has changed.
2. Procedure has been revised since JPM last used.
3. Maintain consistency between similar versions of the JPMs.
4. JPM steps were changed to align with revised procedure flowpath of the AOP.
5. JPM is now Alternate Path, begins as a normal evolution, then progresses to AOP for recovery ..
6. Added new number to JPM, since it is Alternate Path, aligns with numbering scheme.
BVPS-TR-0026 Page I of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-694 JPM TITLE: Respond to a Loss of the RHR System JPM REVISION: 0 KJA
REFERENCE:
APE 025 AAl.09 3.2/3.1 TASK ID: 0535-018-04-013 JPM APPLICATION: Cg} REQUALIFICATION Cg} INITIAL EXAM 0 TRAINING 0 SROONLY Cg} ALTERNATEPATHJPM 0 ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
~ Perform D Plant Site D Annual Requa! Exam D BVT D Simulate ~ Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EV ALVA TION RESULTS Performer Name: Performer SAP:
Time D Yes Allotted 15 Minutes Actual minutes Critical: Cg] No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
Evaluator Signature:
BVPS-TR-0026 Page 2 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: The "A" RHR pump is started, the RCS Cooldown rate is less than 100 °F /hr. and RHR flow is restored to between 3000 and 4000 gpm.
RECOMMENDED Simulator STARTING LOCATION:
INITIAL CONDITIONS:
The plant is in Mode 4, with RCS pressure at -310 psig and RCS temperature (Tc) at -230°F.
lRH-P-lB is in service.
lRH-P-lA is in standby.
RHR flow and RCS Temperature are stable.
INITIATING CUE: Your Supervisor directs you to reduce RHR Outlet (Loop Return) temperature by -10°F by adjusting the RHR system per 1OM-10.4.B Step IV.A.
REFERENCES:
lOM-10.4.B, Residual Heat Removal System Operation, Rev 11 lOM-10.4.AAC, Residual Heat Removal PP Auto Stop, Rev 2 1OM-10.4.AAB, Residual Heat Removal System Disch Flow Low, Rev4 10M-53C.l.10.1, Loss of the Residual Heat Removal Capability, Rev 15 TOOLS: None HANDOUT: Place Kept copy of lOM-10.4.B, Residual Heat Removal System Operation, Rev 11 DO NOT PROVIDE THESE PROCEDURES UNTIL REFERENCED lOM-10.4.AAC, Residual Heat Removal PP Auto Stop, Rev 2 lOM-10.4.AAB, Residual Heat Removal System Disch Flow Low, Rev4 10M-53C.l.10.1, Loss of the Residual Heat Removal Capability, Rev 15.
BVPS-TR-0026 Page 3of8 Revision 0 OPERATIO NS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-694 JPM TITLE: Respond to a Loss of the RHR System JPM REVISION: 0 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT =>
SIMULATOR SETUP:
Use IC-24 Mode 4, RCS pressure ~310 psig, RCS temperature
~230°F.
RH-P-IB is in service RH-P-IA in STBY Trigger RH-P-IB to Trip due to MEPT after MOV-IRH-758 is adjusted. X04A061P Stop any running RCP's.
Remove Permanent Caution Tag from MOV-ICH-142.
Ensure that RH-P-lA pump flow is LESS than 3200 GPM when the pump is started.
Put up the OPPS Placard.
Open lCH-67 N2 to VCTwhen going to RUN command CHS006-100.
Use the following POT Settings after EACH Simulator RESET:
MOV-lCH-142 138 Units MOV-lRH-605 150 Units MOV-lRH-758 24 Units EVALUATOR NOTE:
It is the intent that the candidate use procedures in the Simulator, replace the copy after JPM.
BVPS-TR-0026 Page 4 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-694 JPM TITLE: Respond to a Loss of the RHR System JPM REVISION: 0 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=:>
START TIME: - - - - - - - -
1. Reviews procedure, 1OM- 1.1 Reviews lOM-10.4.B Steps IV.A.I and 2.
10.4.B Steps IV.A.1and2 to establish RCS temperature 1.2 Verifies that MOV-lRH-605 is controlling flow control. between 3000 and 4000 gpm.
1.3 Adjusts the cooldown rate to lower RCS temperature by throttling open MOV-lRH-758 using the valve controller.
COMMENTS:
ALTERNATE PATH:
Once MOV-lRH-758 is throttled, the lB RHRpump will trip on Motor Electrical Protection.
EVALUATOR NOTE:
Candidate may directly enter the Loss of RHR Abnormal procedure. If the Alarm Response Procedures are referenced, provide a copy.
2. Acknowledges Annunciators 2.1 Acknowledges the alarms.
Al-127, Residual Heat Removal PP Auto Stop and 2.2 Reviews Al-127 and Al-126 alarm response A 1-126, Residual Heat procedures Removal System Disch Flow Low alarms. 2.3 Transitions to Abnormal Procedure AOP 1.10.1, Loss of Residual Heat Removal Capability.
COMMENTS:
BVPS-TR-0026 Page 5 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-694 JPM TITLE: Respond to a Loss of the RHR System JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT ~ S!V EVALUATOR NOTE: Candidate may determine the cause of the pump trip by reviewing the computer trends.
3. Candidate reviews procedure, 3.1 Reviews AOP 1.10.1.
AOP 1.10.1 3.2 Investigates the cause of the loss of lRH-P-lB.
EVALUATOR CUE:
If asked, inform the candidate that an operator at emergency switchgear has reported a motor ground overcurrent relay is tripped for lRH-P-lB.
COMMENTS:
4. Check If RHR Pumps Should 4.1 Sounds the Standby Alarm.
Be Stopped 4.2 Using Page party system, announces "LOSS OF
a. Sound standby alarm AND RESIDUAL HEAT REMOVAL CAPABILITY" announce "LOSS OF RESIDUAL HEAT COMMENTS:
REMOVAL CAP ABILITY"
BVPS-TR-0026 Page 6of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-694 JPM TITLE: Respond to a Loss of the RHR System JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT ::::::> SIU
5. RHR Pumps - ANY 5.1. Determines that no RHR pumps are running.
RUNNING.
EVALUATOR NOTE:
Given in initial conditions - IRH-P-IA is in standby and IRH-P-IB has just tripped due to Motor Electrical Protection conditions.
5.2. Determines that the reason for the pump trip is electrical in nature.
EVALUATOR CUE:
Inform the candidate that IRH-P-IB was tripped by a motor electrical protection relay.
5.3 Performs RNO actions to start IRH-P-IA.
COMMENTS:
BVPS-TR-0026 Page 7of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-694 JPM TITLE: Respond to a Loss of the RHR System JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSA =:> SIU 6C. IF RHR pump trip due to loss 6.1 Throttles MOV-lRH-758 to -60% open by adjusting of power or motor protection, dial pot to 60 units.
THEN Start standby RHR pump: 6.2 Throttles MOV-lRH-605 to -15% open by depressing "manual" PB then depressing "Down" PB
1) Verify MOV-lRH-758, until indicating at-15%.
throttled open - 60%.
6.3 Verifies MOV-lCH-142 closed, GREEN light-LIT
2) Verify MOV-lRH-605, and RED light NOT LIT.
throttled open - 15%
Verify MOV-lCH-142 Closed 6.4C Starts lRH-P-lA by placing CS to START position
3) Start standby RHR pump. and verifies RED light -LIT and WHITE light - NOT IF standby pump fails to LIT, flow and AMPS increasing.
start, THEN GO TO Step 5.
6.5 Verifies that the lRH-P-lA ammeter is stable.
4) Verify the following:
Pump amps- STABLE 6.6 Verifies that pump flow is greater than 3200 gpm on FI-lRH-605.
Pump flow - > 3200 GPM
5) Position MOV-lCH-142 as EVALUATOR CUE: Your Supervisor directs you to directed by SM/US.
position MOV-lCH-142 to 10% Open.
6) Return to procedure and step in effect.
6.7C Positions MOV-lCH-142 dial pot to -10% Open as directed by the Supervisor.
IF RHR pump trip due to unstable flow or loss of 6.8 Transitions to procedure and step in effect, 1OM-inventory, THEN continue 10.4.B.
with Step 1.c.
COMMENTS:
BVPS-TR-0026 Page 8 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-694 JPM TITLE: Respond to a Loss of the RHR System JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT =:> SIU EVALUATOR CUE: Your Supervisor directs you establish RHR system flow and RCS Cooldown Rate to within the limits listed in lOM-10.4.B.
7C. Adjusts RHR system flows to 7.lC Throttles MOV-lRH-758 CLOSED by adjusting the maintain system operating dial pot lower, to reduce RCS Cooldown Rate to less limits. than 100 °F/ hr.
7.2 Verifies RHR flow or adjusts MOV-lRH-605 controller in "manual" or "auto" to establish RHR system flow to between 3000 gpm and 4000 gpm.
7 .3 Verifies RCS Cooldown rate lowers to less than 100 °F/ hr. on plant computer or control board indications.
COMMENTS:
EVALUATOR NOTE: Candidate may decide to raise temperature to establish the ~ 10 °F temperature reduction that was directed in the initiating cue.
Once the RCS Cooldown rate is lowered to less than 100 °F/hr and RHR flow is between 3000 and 4000 gpm the JPM may be terminated.
EVALUATOR CUE: State "This JPM is complete" STOP TIME: _ _ _ _ _ __
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
The plant is in Mode 4, with RCS pressure at ~310 psig and RCS temperature (Tc) at ~230°F.
lRH-P-lB is in service.
lRH-P-lA is in standby.
RHR flow and RCS Temperature are stable.
INITIATING CUE: Your Supervisor directs you to reduce RHR Outlet (Loop Return) temperature by ~10°F by adjusting the RHR system per lOM-10.4.B Step IV.A.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Transfer from Bypass to Main Feed Regulating Valve TRAINING MATERIAL NUMBER: ICR-520
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: ICR-520 REVISION NUMBER: 7 TECHNICAL
REFERENCES:
IOM-52.4.B, "Load Following", Attachment 18 Rev. 53 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 20 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: lCR-520 New Revision: 7 Description of Change( s):
1. Updated for procedure revision and lOM-52.4.B, Load Following.
2. Added Evaluator Cue for step 11.3 that another Operator will monitor for valve leakage.
3. Added additional Evaluator Note prior to starting JPM to set up IPC trend for SG A NR Range levels L0400A, L0401A, and L0402A on the lowest scan rate per Att. 18 step 2.
Reason for Change (s):
1. lOM-52.4.A was revised to refer to lOM-53.4.B, Load Following. The Attachment actions to transfer from BFRVs to MFRVs are the same in the new procedure.
2. Added cue based on NRC feedback.
3. Added based on NRC feedback.
BVPS-TR-0026 Page 1 of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 7 KIA
REFERENCE:
035 A3.01 4.013.9 TASK ID: 0521-001-01-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM 0 TRAINING 0 SRO ONLY ~ ALTERNATE PATH JPM 0 ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
[81 Perform D Plant Site D Annual Requal Exam D BVT D Simulate [81 Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SSN:
Time D Yes Allotted 20 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
Evaluator Signature:
BVPS-TR-0026 Page 2 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Transfer control of [FCV-IFW-479] in AUTO to [FCV-IFW-478] in AUTO.
[FCV-IFW-478] is placed BACK in MANUAL AFTER the automatic controller failure has been identified and IA S/G NR level is stabilized between 60% and 70%.
RECOMMENDED Simulator STARTING LOCATION:
INITIAL CONDITIONS: The plant is in Mode I during a plant startup. I OM-52.4.B, "Load Following", is in progress. Step IV.I.I6 directs placing the S/G Main Feed Regulating Valves in service.
INITIATING CUE: Your supervisor directs you to perform Attachment I8 of IOM-52.4.B, for [FCV-IFW-478], IA Main Feed Regulating Valve. The valve is to be placed in automatic to control Steam Generator water level. Use "MANUAL" control of [FCV-IFW-479], IA S/G FW Bypass FCV during step 8 of Attachment I8.
REFERENCES:
IOM-52.4.B, "Load Following", Attachment I8 Rev. 53 TOOLS: None HANDOUT: IOM-52.4.B, "Load Following", Attachment I8 Rev. 53, (Provide Attachment I 8, pages I 63 & I 64 ONLY).
BVPS-TR-0026 Page 3 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU SIMULATOR SETUP:
Start with IC-13 with MFRBVs in auto Ensure Xenon is at Equilibrium Insert Malfunction FWM09A with a 20% severity, and a 10 second delay with a 60 period. ([FCV-1FW-478] malfunctions when placed in AUTO).
Select Event Trigger (1)
Enter X09I096E== 1 TRGSET 1 'X09I096E' IMF FWM09A (1 10) 20 IMF PLP MALOS (0 0) 60 EVALUATOR NOTE: The above PLP Malfunction MUST be entered EACH time the Simulator is RESET.
Set up IPC trend for SG A NR Range levels L0400A, L0401A, and L0402A on the lowest scan rate per Att. 18 step 2.
EVALUATOR NOTE: Provide candidate with a copy of 1OM-52.4.B, Attachment 18. When candidate is ready to begin JPM, PLACE the simulator in RUN.
START TIME: - - - - - - -
1. Review 1OM-52.4.B 1.1 Reviews lOM-52.4.B, Attachment 18.
Attachment 18.
COMMENTS:
BVPS-TR-0026 Page 4of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: I CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU
2. Verify [FCV-IFW-478] IA 2.1 Verifies FCV- I FW-4 78 Auto/Manual station MAN Main Feed Regulating Valve light LIT and AUTO light NOT LIT and 0% demand.
(MFRV) in MANUAL and Closed. (BB-C) 2.2 Verifies Loop I FD WTR FCV GREEN light (A-I)-
LIT and RED light (A-2) - NOT LIT on Status Light Panel 623.
COMMENTS:
3. Verify closed [MOV-IFW- 3.1 Verifies MOV-1FW-154A GREEN light-LIT and 154A], IA SG Main FW Isol RED light-NOT LIT.
Vlv (BB-C).
and 3.2 Dispatches an operator to IA MFRV to observe local Station an operator at the valve stroke.
Main Feed Regulating Valve to observe local valve stroke. EVALUATOR CUE: Role-play part of local operator to report valve operation locally.
COMMENTS:
BVPS-TR-0026 Page 5of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => S/U
4. Stroke [FCV-lFW-478], lA 4.1 Strokes FCV-lFW-478 full OPEN by depressing _.
Main Feed Reg Valve to the output pushbutton.
full open position, THEN to full closed AND check 4.2 Verifies RED light - LIT and GREEN light - NOT position indication on BB-C LIT on Status Light Panel 623.
AND locally.
4.3 Strokes FCV-lFW-478 full CLOSED by depressing T output pushbutton.
4.4 Verifies GREEN light - LIT and RED light - NOT LIT on Status Light Panel 623.
EVALUATOR CUE: As the field operator report FCV-lFW-478 traveled smoothly full open with no hesitation and now indicates full closed.
COMMENTS:
5. Trend L0400A (L0401A) 5.1 Trends L0400A (L0401A) (L0402A)- SG A (L0402A), SG A NARROW NARROW RANGE 1 (2) (3) Level FW-474 (475)
RANGE 1 (2) (3) Level FW- (476) on the In-Plant Computer using lowest scan 474 (475) (476) on the In- rate.
Plant Computer using lowest scan rate. 5.2 Monitors recorders and indicators for lA SG level, feed flow, AND steam flow.
COMMENTS:
BVPS-TR-0026 Page 6 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EVALUATOR NOTE: If this JPM is paired with another JPM, then Cue that the RO will monitor the parameters listed in the following step.
6. Maintain stable temperature 6.1 Verifies stable Tavg and reactor power by monitoring and reactor power. NI power and Loop DT and Tavg or directs the RO to monitor these parameters.
COMMENTS:
7.C Open [MOV-1FW-154A], IA 7.lC Places MOV-1FW-154A control switch to OPEN SG Main FW Isol Vlv. position.
7.2 Verifies RED light-LIT and GREEN light-NOT LIT.
COMMENTS:
8. If feed flow to the Steam 8.1 Continuously monitors steam flow and feed flow Generator rapidly rises or recorders and/or indicators for rapidly changing lowers when performing the feedwater flow.
following steps, THEN Manually Close the main feed COMMENTS:
valve AND Establish proper feed flow AND level with bypass feed control.
BVPS-TR-0026 Page 7 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 9.C Verify controller in 9.1 Verifies FCV-1FW-478 Auto/Manual station MAN MANUAL AND slowly open light LIT and AUTO light NOT LIT.
[FCV-IFW-478], IA Main Feed Reg Valve. 9.2C Slowly opens FCV- I FW-4 78 using £. pushbutton.
COMMENTS:
EVALUATOR NOTE: Initiating Cue stated that
[FCV-IFW-479] is to be controlled in MANUAL. The candidate may need to be reminded if AUTO control is used.
IO.C As the IA Main Feed Reg 10.IC Places FCV-IFW-479 Bypass Valve controller in Valve is being OPENED, MANUAL.
Close [FCV-IFW-479], IA SG FW Bypass FCV, in 10.2C Slowly CLOSES FCV-IFW-479 Bypass Valve using MANUAL or AUTO to T pushbutton.
maintain IA S/G NR level between 60% and 70%. 10.3C Continues to open FCV-IFW-478.
Continues to Open [FCV -
lFW-478], IA Main Feed Reg COMMENTS:
Valve UNTIL the 1A SG FW Bypass FCV is closed.
BVPS-TR-0026 Page 8 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: ICR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU I 1. When [FCV-IFW-479], IA I I. I Verifies FCV-IFW-479 is full CLOSED (0% demand SG FW Bypass Valve is fully & FCV-479 GREEN Light- LIT and RED Light-closed, Perform the NOT LIT.
following:
Verify [FCV-IFW-479], IA I 1.2 Verifies FCV- I FW-4 79 Auto/Manual station MAN SG FW Bypass FCV light LIT and AUTO light NOT LIT.
controller in MAN.
Observe Feedwater flow, I 1.3 Verifies no leakage past valve by observing no steam flow and SG level for change in feedwater flow, steam flow, and S/G water evidence of leakage past the level.
IA SG FW Bypass FCV.
EVALUATOR CUE: Another Operator will monitor for valve leakage.
COMMENTS:
FAULT STATEMENT:
The faulted portion of the JPM begins with the next step. When the operator places the MFRV controller in AUTO, it will begin to oscillate. This will require the operator to take MANUAL control and stabilize SG water level manually.
12.C Place controller for [FCV- I2.IC Places FCV-IFW-478 controller to AUTO.
lFW-478], IA Main Feed Reg Valve in AUTO AND I2.2 Monitors level, feed flow, and steam flow.
monitor SG level AND feed flow and steam flow. I2.3 Recognizes oscillating MFRV and erratic feed flow.
COMMENTS:
BVPS-TR-0026 Page 9 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT :::::> SIU 13.C If level control is NOT stable, 13.lC Places FCV-lFW-478 controller in MANUAL.
Restore [FCV-lFW-478], lA Main Feed Reg Valve 13.2C Slowly adjusts FCV-lFW-478 using T
controller to MANUAL AND pushbuttons to stabilize SG level and feed flow.
Maintain SIG NR level between 60% and 70%. 13.3C Re-establishes control of lA SIG NR level between 60% and 70%.
EVALUATOR CUE:
Once it is demonstrated that the candidate can control lA SIG NR water level between 60% and 70%, inform the candidate that the JPM is COMPLETE.
COMMENTS:
STOP TIME: _ _ _ _ _ __
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS: The plant is in Mode 1 during a plant startup. 1OM-52.4.B, "Load Fallowing", is in progress. Step IV .I.16 directs placing the S/G Main Feed Regulating Valves in service.
INITIATING CUE: Your supervisor directs you to perform Attachment 18 of lOM-52.4.B, for [FCV-lFW-478], lA Main Feed Regulating Valve. The valve is to be placed in automatic to control Steam Generator water level. Use "MANUAL" control of [FCV-lFW-479], lA S/G FW Bypass FCV during step 8 of Attachment 18.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Manually Actuate CIB TRAINING MATERIAL NUMBER: ICR-578
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: ICR-578 REVISION NUMBER: 2 TECHNICAL
REFERENCES:
10M-53A.l.1-K, "Verification Of Automatic Actions", Rev. 7.
1OM-53A.1.1-E, "Containment Isolation Phase B Checklist", Rev. 6 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 10 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: 1CR-578 New Revision: 2 Description of Change(s):
1. Updated to latest revision of the procedure.
2. Updated to latest JPM format.
3. Removed Evaluator Cue from beginning of JPM, and added the following information to the Initiating Cue. "You are responsible for simulator alarms on the primary side of the plant. The BOP will respond to secondary alarms ONLY."
Reason for Change (s):
1. Verification of Automatic Actions attachment has been revised
2. JPM format has been updated.
3. Moved at the request of the NRC evaluator.
BVPS-TR-0026 Page 1of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-578 JPM TITLE: Manually Actuate CIB JPM REVISION: 2 KIA
REFERENCE:
026 A3.01 4.3/4.5 TASK ID: 0533-016-05-013 026 A4.01 4.5/4.3 0131-003-06-013 JPM APPLICATION: L8J REQUALIFICATION L8J INITIAL EXAM 0 TRAINING D SROONLY ['.8J ALTERNATE PATH JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
k8J Perform D Plant Site D Annual Requal Exam D BVT D Simulate k8J Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EV ALU A TION RESULTS Performer Name: Performer SAP:
Time D Yes Allotted 10 Minutes Actual minutes Critical: L8J No Time: Time:
JPM RE SULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
IEvaluator Signature:
B VPS-TR-0026 Page 2of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Manually initiate CIB, start IQS-P-IA, open MOV-IQS-IOIA, and stop the RCP's.
RECOMMENDED Simulator STARTING LOCATION:
INITIAL CONDITIONS:
A large break LOCA has occurred coincident with the Loss of SSST "IB".
The No. 2 Emergency Diesel Generator failed immediately following startup.
The actions of E-0 are being performed.
INITIATING CUE: The Unit Supervisor directs you to perform Attachment 1-K, "Verification Of Automatic Actions", Step 10 to check CIB and CNMT Spray status.
You are responsible for simulator alarms on the primary side of the plant. The BOP will respond to secondary alarms ONLY.
REFERENCES:
10M-53A.1.1-K, "Verification Of Automatic Actions", Rev 7.
10M-53A.1.1-E, "Containment Isolation Phase B Checklist", Rev. 6 TOOLS: None HANDOUT: 10M-53A.1.l-K, "Verification Of Automatic Actions, Rev 7. Place kept up to step 10.
10M-53A.1.l-E, "Containment Isolation Phase B Checklist, Rev. 6 (DO NOT INITIALLY PROVIDE TO CANDIDATE)
BVPS-TR-0026 Page 3of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: lCR-578 JPM TITLE: Manually Actuate CIB JPM REVISION: 2 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT =>
SIMULATOR SETUP: Initialize to any Mode 1 IC.
1. Insert MALF EPS03B (Loss of SSST lB)
2. Insert MALF INH42 (lQS-P-lA auto start failure)
3. Insert MALF INH50 (Auto CIB failure)
4. Insert MALF INH54 (#2 EDG failure)
5. Event Trigger #1 Enter X02I052C
6. Insert MALF VL V-QSS03 0 Enter Command DMF VLV-QSS03 and accept new event. (MOV-1QS-101A Fails Closed and opens once control switch is taken to Open)
Allow Sim to run and then:
Insert MALF RCS02D (DBA Hot Leg Loop 1)
Allow Sim to run until majority of alarms clear and snap into IC. (at least three minutes)
EVALUATOR CUE:
Provide a copy of marked up EOP Attachment 1-K.
START TIME: - - - - - - -
1. Reviews place kept copy of 1.1 Reviews 10M-53A.l.1-K, "Verification Of Automatic 1OM-53A. l.1-K, "Verification Actions".
Of Automatic Actions" provided.
COMMENTS:
BVPS-TR-0026 Page 4of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-578 JPM TITLE: Manually Actuate CIB JPM REVISION: 2 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU
2. Checks CIB And CNMT Status 2.1 Determines that containment pressure has NOT
Containment pressure - HAS remained less than 11 psig by checking any of the REMAINED LESS THAN following:
11 PSIG.
Al-72, "CONTAINMENT ISOLATION PHASE B" annunciated (should be LIT but is NOT).
PR-LM-lOOA, Containment Pressure Recorder indicates greater than 11 psig.
PI-lLM-lOOA, lOOB, lOOC, lOOD, Containment Pressure Indicators indicating > 11 psig.
Status Light PNL 62, HHCP Press CH Trip/Defeat CH I - IV Lights - LIT.
COMMENTS:
EVALUATOR NOTE: It is acceptable that the completion of this step may be out of order and they may choose to perform 10M-53A.l.1-E, "Containment Isolation Phase B Checklist". RCPs may be tripped based on Hi-Hi Vibration Alarms.
3. Check BLUE CIB marks - LIT. 3 .1 Checks components properly aligned and determines CIB components not positioned as required, and CIB NOT actuated.
COMMENTS:
B VPS-TR-0026 Page 5of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: ICR-578 JPM TITLE: Manually Actuate CIB JPM REVISION: 2 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT ~ SIU FAULT STATEMENT CIB fails to AUTO actuate and IQS-P-IA fails to AUTO START, and MOV-IQS-IOIA fails to auto open upon manual actuation of CIB.
CIB must be manually actuated, IQS-P-IA must be manually started, and MOV-IQS-IOIA must be opened.
4.C IF NOT, THEN manually 4.IC Simultaneously DEPRESSES both Spray Actuation initiate CIB (both pushbuttons and CIB Actuation Train "A" pushbuttons.
for both trains).
4.2 Simultaneously DEPRESSES both Spray Actuation and CIB Actuation Train "B" CIB pushbuttons.
EVALUATOR NOTE:
Either train may be actuated first followed by the opposite train. Train B of Containment Isolation is not critical since there is no power on that train.
COMMENTS:
BVPS-TR-0026 Page6of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-578 JPM TITLE: Manually Actuate CIB JPM REVISION: 2 STEP STANDARD
( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU
5. Check BLUE CIB marks - LIT. 5.1 Checks all indicating lights with BLUE CIB marks LIT.
5.2 Determines lQS-P-lA & lB, Quench Spray Pumps not running.
EVALUATOR NOTE:
Ifrequested, provide a copy of Attach. 1-E. lQS-P-lB will NOT start due to no power to DF Bus.
COMMENTS:
6.C IF CIB NOT actuated, THEN 6.lC Places lQS-P-lA control switch to START.
manually align equipment. If necessary, refer to Attachment 6.2 Verifies RED light - LIT and WHITE light - NOT 1-E, "Containment Isolation LIT.
Phase B Checklist".
6.3 Determines MOV-lQS-lOlA, lA Quench Spray Pump Disch Vlv did NOT Auto OPEN.
6.4C Places MOV-lQS-lOlA to OPEN position.
6.5 Verified RED Light-LIT and GREEN Light-NOT LIT.
COMMENTS:
BVPS-TR-0026 Page 7of7 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: lCR-578 JPM TITLE: Manually Actuate CIB JPM REVISION: 2 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT :::> SIU 7.C Stop all RCP's. 7.lC Places control switches for lRC-P-lA and lB to STOP. (lRC-P-lC already shutdown) 7.2 Verifies lRC-P-lA, lB and IC RED lights-NOT LIT and WHITE lights - LIT.
7.3 Verifies lRC-FI-414, (415), (416) and lRC-FI-424, (425), (426) flows dropping.
7.4 Verifies lRC-P-lA and lB amps dropping (BB-A kickup).
COMMENTS:
8. Request BV-2 operator verify 8.1 Contacts Unit 2 to verify CREVS equipment CREVS equipment actuation. operations.
EVALUATOR CUE:
Role play Unit 2 operator and inform candidate that all CREVS equipment is functioning properly then state -
"This COMPLETES the JPM."
COMMENTS:
EVALUATOR CUE: State "This JPM is complete" STOP TIME: - - - - - - -
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
A large break LOCA has occurred coincident with the Loss of SSST "lB".
The No. 2 Emergency Diesel Generator failed immediately following startup.
The actions of E-0 are being performed.
INITIATING CUE: The Unit Supervisor directs you to perform Attachment 1-K, "Verification Of Automatic Actions", Step 10 to check CIB and CNMT Spray status.
You are responsible for simulator alarms on the primary side of the plant. The BOP will respond to secondary alarms ONLY.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Transfer Bus IAE from Emergency to Normal Feed TRAINING MATERIAL NUMBER: 1CR-097 PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: ICR-097 REVISION NUMBER: 7 TECHNICAL
REFERENCES:
IOM-36.4.Q, Transferring Emergency Busses IAE and IDF From Emergency Feed To Normal Feed, Rev. 14 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 20 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: 1CR-097 New Revision: 7 Description of Change(s):
1. Modified initial conditions to remove normal 4KV bus alignment
2. Modified step 2 to allow JPM to be performed when the normal bus is powered from either the USST or SSST.
3. Modified Simulator Setup to reduce #1 EDG loading to< 1200 KW to allow for a EDG shutdown without requiring a 10 minute load reduction.
4. Combined JPM steps 12 and 13 to reduce EDG load to 200 KW, and deleted evaluator cue in step 12 pertaining to the 10 minute load reduction ifloading is> 1200KW.
5. Renumbered JPM steps after step 12.
Reason for Change (s):
1. Allows for JPM to be paired with shutdown or at power IC sets.
2. Made step an "OR" step depending upon initial conditions.
3. Modified at the request of the NRC evaluator.
4. Combined steps to ensure JPM follows the procedure.
5. Renumbered for proper JPM sequence.
BVPS-TR-0026 Page 1of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-097 JPM TITLE: Transfer Bus IAE from Emergency to Normal Feed JPM REVISION: 6 KIA
REFERENCE:
064 A4.06 3.913.9 TASK ID: 0362-007-01-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM 0 TRAINING D SRO ONLY D ALTERNATE PATH JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
~ Perform D Plant Site D Annual Requal Exam D BVT D Simulate ~ Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SAP:
Time D Yes Allotted 20 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/ SAP: Name/ SAP:
Name/ SAP: Name/ SAP:
EVALUATOR Evaluator (Print): Date:
Evaluator Signature:
1
BVPS-TR-0026 Page 2of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Bus IAE is energized from Bus IA. Load has been removed from the
1 EDG, and the # 1 EDG output breaker is open.
RECOMMENDED Simulator STARTING LOCATION:
INITIAL CONDITIONS:
Breaker IAI 0 has spuriously tripped open.
#1 EDG is running and carrying loads on the IAE bus.
4KV normal to emergency tie breakers, IAIO and 1E7, are open.
The relay crew has replaced a defective relay on breaker IAI 0.
#1 EDG has only been operating for 45 minutes.
INITIATING CUE: Your supervisor directs you to return 4160 EMER Bus IAE to Normal Feed in accordance with IOM-36.4.Q, "Transferring Emergency Busses IAE and IDF From Emergency Feed To Normal Feed" part IV.A.
REFERENCES:
1OM-36.4.Q, "Transferring Emergency Busses IAE and IDF From Emergency Feed To Normal Feed", Rev. 14.
TOOLS: None HANDOUT: IOM-36.4.Q, "Transferring Emergency Busses IAE and IDF From Emergency Feed To Normal Feed, Rev. 14
BVPS-TR-0026 Page 3 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-097 JPM TITLE: Transfer Bus lAE from Emergency to Normal Feed JPM REVISION: 7 STANDARD (Indicate "S" FOR SAT or "U" FOR UNSAT)=>
SIMULATOR SETUP:
Insert malfunction (IMF EPS04E) to trip lAlO, and wait for DIG sequencer to complete loading. Reduce
1 EDG loading to< 1200 KW.
Then delete malfunction, and allow plant to stabilize.
Lower EDG voltage for an ~2 volts difference from 4Kv Bus IA voltage.
Set Trigger 1 action to adjust "Speed Droop" to 55 when requested, command LOA-EPS288 (1 0) 1, ensure plant is stable then SNAP IC.
EVALUATOR CUE:
Provide candidate a copy of lOM-36.4.Q.
When candidate is ready to begin the JPM, Place the Simulator in RUN.
START TIME: _ _ _ _ _ _ __
1. Reviews procedure. 1.1 Reviews 1OM-36.4.Q, "Transferring Emergency Busses lAE and lDF from Emergency Feed to Normal Feed".
COMMENTS:
BVPS-TR-0026 Page 4of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: I CR-097 JPM TITLE: Transfer Bus IAE from Emergency to Normal Feed JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU EVALUATOR NOTE:
JPM is written to be performed when powered from the Unit or Offsite, so candidate will perform either of the following steps.
2. If Bus IA is aligned to System 2.1 This step is NIA if powered from USST IC.
Station Service Transformer IA, Perform Data Sheet I OR (otherwise, NIA).
2.2 If powered from SSST IA, then completes Data Sheet I readings.
EVALUATOR CUE:
If Data Sheet I is performed, inform the candidate that another operator will perform the independent verifications.
COMMENTS:
3.C Place the Emerg Gen I 3.IC Places EMERG GEN I SYNCHRONIZING SEL SW Synchronizing Sel SW to the to the I E7 position.
ACB 1E7 position and verifies ANN, A9-8, "ACB 3.2 Verifies Annunciator A9-8 is LIT.
IE7 OR IE9 IN SYNCHRONIZING MODE", COMMENTS:
is ON.
4. Verify control switch 4KV 4.I Momentarily places I E7 breaker control switch to the Bus IAE to IA, ACB IE7 is AFTER-OPEN position. (Green Target).
in the AFTER-OPEN position. (Green Target) COMMENTS:
BVPS-TR-0026 Page 5 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-097 JPM TITLE: Transfer Bus lAE from Emergency to Normal Feed JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 5.C Close 4KV Bus IA to lAE 5.lC Momentarily places ACB lAlO control switch in the ACB lAlO. CLOSE position.
5.2 Verifies RED light - LIT I WHITE light - NOT LIT.
EVALUATOR CUE:
Provide the second verification if requested.
COMMENTS:
6. Adjust the governor speed 6.1 Requests operator at EDG #1 to adjust SPEED droop knob to 55 while DROOP to 55 with frequency being maintained at maintaining frequency at 60Hz.
approximately 60 hz. (EDG
1 Building) EVALUATOR CUE:
When requested instruct booth instructor to actuate TRG 1 (LOA-EPS288 1), then role-play outside operator and report that local EDG #1 Gov. speed droop is set at 55.
6.2 Intermittently places the EMERG GEN 1 GOVERNOR control switch in the RAISE direction to maintain frequency at ~60 Hz.
COMMENTS:
BVPS-TR-0026 Page 6 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: I CR-097 JPM TITLE: Transfer Bus IAE from Emergency to Normal Feed JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP ) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU
7. C Using the Emerg Gen I 7. IC Intermittently places the EMERG GEN I Governor control switch, GOVERNOR control switch in the RAISE direction adjust the generator speed UNTIL the synchroscope needle is rotating very UNTIL the Synchroscope slowly in the FAST direction.
needle is rotating very slowly in the FAST direction. COMMENTS:
8.C Using the Emerg Gen I Volt 8. IC Intermittently adjusts the EMERG GEN I VOLT Adjust, match generator ADJUST control switch as necessary (RAISE on CS voltage (running) with the will raise VOLTAGE) until generator voltage is voltage in Bus I A (Incoming). matched with Bus IA voltage without exceeding I30 volts on the generator voltmeter.
EVALUATOR NOTE:
EDG Voltage is indicated on the 8.2 Monitors Bus IA voltage on the SYNCH VOLTS Sync Volts Running Norm INCOMING NORM voltmeter and EDG voltage on voltmeter, Bus IA voltage is on the SYNCH VOLTS RUNNING NORM voltmeters the Sync Volts Incoming Norm on the BB-C kickup.
voltmeter.
COMMENTS:
9. C When both synchronizing 9.IC Places ACB 1E7 control switch in the CLOSE lights are completely dark position when the synchroscope needle is at the I 2 AND the synchroscope needle o'clock position.
is at I2 o'clock position, THEN close 4KV Bus IAE to 9.2 Verifies RED light- LIT I WHITE light- NOT LIT.
IAACB IE7.
EVALUATOR CUE:
Provide the Concurrent Verification if requested.
COMMENTS:
BVPS-TR-0026 Page 7of8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lCR-097 JPM TITLE: Transfer Bus lAE from Emergency to Normal Feed JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU
10. Place the Emerg Gen 1 10.l Places EMERG GEN 1 SYNCHRONIZING SEL SW Sychronizing Sel SW to the in the OFF position.
OFF position and verifies ANN A9-8, "ACB 1E7 or 1E9 10.2 Verifies annunciator A9-8, "ACB 1E7 or 1E9 IN IN SYNCHRONIZING SYNCHRONIZING MODE" is reset.
MODE" is OFF.
COMMENTS:
11. Perform the following to clean 11.1 This step is NIA. The EDG has only been running for out the exhaust system prior ~45 minutes.
to shutting down the diesel generator, as necessary. EVALUATOR CUE:
If needed, remind the candidate that the EDG has only been operating for ~45 minutes.
COMMENTS:
12.C Remove 1EE-EG-1, 12.lC Intermittently places EMERG GEN 1 GOVERNOR Emergency Diesel Generator control switch in the LOWER position to lower load No. 1, from service as to <200KW.
follows:
12.2 Monitors/Maintains the following parameters during
a. Step 12a. is NIA since #1 the load decrease:
EDG loading is< 1200 KW. a. EMERG GEN 1 VOLTS(< 130 volts)
b. EMERG GEN 1 POWER FACTOR (0.8 - 1.0
b. Reduce load on the No. 1 lagging)
Diesel Generator to less c. EMERG GEN 1 WATTS (Lower to < 500 than 200 KW (as read on KW) the Emerg Gen 1 Watts meter VB-C) by Placing the COMMENTS:
Emerg Gen 1 Governor control switch intermittently to the LOWER position.
BVPS-TR-0026 Page 8 of 8 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-097 JPM TITLE: Transfer Bus lAE from Emergency to Normal Feed JPM REVISION: 7 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 13.C When the load on No. 1 13 .1 C Momentarily places the ACB 1E9 control switch in Diesel Generator has been TRIP when EDG 1is<200 KW.
reduced to less than 200 KW (as read on the Emerg Gen 1 13.2 Verifies WHITE light-LIT and RED light-NOT Watts meter VB-C), Open LIT.
Emerg Gen 1 Circuit Breaker ACB 1E9 (spring return to COMMENTS:
center).
14. Verify the Emerg Gen 1 14.1 Verifies the EMERG GEN 1 Motor Operated GND Motor Operated Gnd Sw DS 1, SW DSl is OPEN. WHITE light-LIT and RED is Open. light-NOT LIT.
COMMENTS:
EVALUATOR CUE: State "This JPM is complete" STOP TIME: - - - - - - -
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
Breaker lAlO has spuriously tripped open.
#1 EDG is running and carrying loads on the lAE bus.
4KV normal to emergency tie breakers, lAlO and 1E7, are open.
The relay crew has replaced a defective relay on breaker lAlO.
#1 EDG has only been operating for 45 minutes.
INITIATING CUE: Your supervisor directs you to return 4160 EMER Bus lAE to Normal Feed in accordance with 1OM-36.4.Q, "Transferring Emergency Busses lAE and lDF From Emergency Feed To Normal Feed" part IV.A.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERlAL TITLE: Verify CREVS Actuation TRAINING MATERIAL NUMBER: ICR-662
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: ICR-662 REVISION NUMBER: 0 TECHNICAL
REFERENCES:
10M-53A.1.E-1, Loss of Reactor Or Secondary Coolant, Iss. 3 Rev. 0 1/20M-44A.4A.A, Post Control Room Habitability System Actuation/ Recovery, Rev 17 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 15 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: lCR-662 New Revision: 0 Description of Change(s):
1. New issue.
Reason for Change (s):
1. New JPM for initial exam.
BVPS-TR-0026 Page 1 of 9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-662 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 KIA
REFERENCE:
060 AAI.02 2.9/3.1 TASK ID: 0441-003-01-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D SRO ONLY ~ ALTERNATEPATHJPM 0 ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
~ Perform D Plant Site D Annual Requal Exam D BVT D Simulate ~ Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SAP:
Time D Yes Allotted 15 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
Evaluator Signature:
I
BVPS-TR-0026 Page 2of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: MANUALLY closes 1VS-D-40-lB which failed to AUTO close.
MANUALLY starts 1VS-F-41A due to Unit 2 Fans 2HVC*FN241A and 2HVC*FN241B failing to start.
RECOMMENDED Simulator STARTING LOCATION:
INITIAL CONDITIONS:
A Large Break LOCA has occurred.
A transition to E-1, "Loss of Reactor or Secondary Coolant" has just been made.
CIB has actuated.
INITIATING CUE: The Unit Supervisor directs you to perform Step 1 RNO actions of E-1, "Loss of Reactor or Secondary Coolant".
REFERENCES:
10M-53A.l.E-1, "Loss of Reactor or Secondary Coolant", Iss. 3 Rev.
0 1/20M-44A.4A.A, Post Control Room Habitability System Actuation/
Recovery, Rev 17 TOOLS: None HANDOUT: 10M-53A.l.E-1, "Loss of Reactor or Secondary Coolant", Iss. 3 Rev.
0, place kept at step I.
DO NOT PROVIDE THIS PROCEDURE UNTIL REFERENCED.
1/20M-44A.4A.A, Post Control Room Habitability System Actuation/
Recovery, Rev 17
BVPS-TR-0026 Page 3 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-662 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT ~
SIMULATOR SETUP:
Begin with any power IC.
Insert a LB LOCA Malfunction (MALF RCS03A(B,C))
on either loop.
Perform actions ofE-0, up to step 1 of E-1.
Fail 1VS-D-40-lB from AUTO closing (can manually close) as follows:
Select VL V-HVA02 100
Select Event Trigger, Select Event#, Enter Event X19I44C, Enter command DMF VLV-HVA02 Freeze and take a snap.
EVALUATOR NOTE:
When the candidate is ready to begin the JPM, place the simulator in RUN.
EVALUATOR NOTE:
Provide candidate a place kept copy of E-1. Place simulator in RUN when candidate is ready to begin.
START TIME: _ _ _ _ _ __
1. Review procedure. 1.1 Reviews procedure (E-1 Step 1 RNO) provided.
COMMENTS:
2. Actuate both trains using the 2.1 Actuates BOTH trains of CREVS using the CONTROL ROOM EMERG CONTROL ROOM EMERG AIR SUP AIR SUP ACTUATION ACTUATION pushbuttons located on the Building pushbuttons. Service Control Panel COMMENTS:
BVPS-TR-0026 Page 4 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-662 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT :::::> SIU EVALUATOR NOTE: The following steps can be done in any order.
3.C Verify CREVS actuation: 3.1 Verifies 1VS-D-40-1 A, "Control Room Air Intake Control Room Air Intake and Damper" CLOSED.
Exhaust Dampers -
CLOSED. 3.2 Verifies GREEN Light-LIT and RED Light-NOT LIT.
3.3C Verifies 1VS-D-40-1 B, "Control Room Air Intake Damper" CLOSED. Recognizes 1VS-D-40-lB did NOT AUTO close 3.4C Manually places 1VS-D-40-1 B control switch to close.
3.5 Verifies GREEN Light-LIT and RED Light-NOT LIT.
3.6 Verifies 1VS-D-40-1 C, "Control Room Air Exhaust Damper" CLOSED.
3.7 Verifies GREEN Light- LIT and RED Light - NOT LIT.
3.8 Verifies lVS-D-40-lD, "Control Room Air Exhaust Damper" CLOSED.
3.9 Verifies GREEN Light - LIT and RED Light - NOT LIT.
COMMENTS:
BVPS-TR-0026 Page5of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-662 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU
4. Request Unit 2 Control 4.1 Requests Unit 2 Control Room staff verify CREVS Room staff to verify CREVS actuation.
actuation and place intake and exhaust damper control EVALUATOR CUE: When requested, role play switches to CLOSE. and acknowledge request for Unit 2 Control Staff verification of CREVS actuation.
COMMENTS:
EVALUATOR NOTE: The following steps can be done in any order.
5. Place Control Room intake 5.1 Places lVS-D-40-lA control switch in CLOSE.
and exhaust damper control switches in CLOSE: 5.2 Places lVS-D-40-lB control switch in CLOSE, or verifies in close if previously performed.
[1 VS-D-40-lA]
5 .3 Places 1VS-D-40-1 C control switch in CLOSE.
[1 VS-D-40-lB]
5.4 Places lVS-D-40-lD control switch in CLOSE.
[ 1VS-D-40-1 C]
COMMENTS:
[1 VS-D-40-lD]
EVALUATOR CUE: Role play as Unit 2 operator and report that NEITHER Unit 2 Control Room Pressurization Fan will start.
BVPS-TR-0026 Page 6 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-662 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT =>
FAULT STATEMENT:
Neither Unit 2 Control Room Pressurization Fan 2HVC*FN241A or FN241B will start. Candidate will to refer to 1/20M-44A.4A.A and start a Unit 1 Fan.
6. Refer to 1/20M-44.4A.A, 6.1 Locates and references 1/20M-44A.4A.A, "Post "Post Control Room Control Room Emergency Habitability System Emergency Habitability Activation/Recovery, Part A".
System Activation/Recovery, Part A". EVALUATOR NOTE: If this JPM is Paired with another JPM, this procedure may be provided once it is identified. Otherwise, once located, provide candidate a copy of 1/20M-44A.4A.A, "Post Control Room Emergency Habitability System Activation/Recovery, Part A".
COMMENTS:
7. If CREVS was initiated as a 7. I NIA this step since CREVS was initiated by a Large result of a toxic gas release, Break LOCA as opposed to a Toxic Gas Release.
refer to 1/20M-53C.4A.44A.A, "Toxic Gas COMMENTS:
Release".
BVPS-TR-0026 Page7of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-662 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EVALUATOR NOTE: This 8.1 Recognizes from the previous Unit 2 report that procedure is a dual unit procedure, therefore step 3 may be given to the 2HVC*FN241A has failed to start.
Unit 2 operator to perform, or it may be completed step by step by the 8.2 Requests Unit 2 to perform Step 3 of 1/20M-Unit I Operator. This step is 44A.4.A.
scripted for either response.
EVALUATOR CUE: Unit 2 reports that step 3 is
8. Check 2HVC*FN241A, complete and that BOTH 2HVC-FN241A and "Control Room Erner Vent 2HVC-FN241B have failed to start. Per step 3.e, Fan", has auto started AND Unit 2 Annunciator Al 0-3E is ON.
2HVC*MOD204A, "Control Room Erner Outside Air OR (directs Steps 8.3 through 8.6)
Intake Damper has opened.
8.3 Requests Unit 2 place 2HVC*FN241A CS in OFF.
If [2HVC*FN241A], Control EVALUATOR CUE: 2HVC-FN241A CS is in Room Erner Vent Fan, has OFF.
failed to start, Perform the following:
a. Place [2HVC*FN241A], 8.4 Requests Unit 2 start 2HVC*FN241B.
Control Room Erner Vent EVALUATOR CUE: 2HVC-FN241B will NOT Fan, control switch in OFF.
start.
b. lf[2HVC*FN241B],
Control Room Erner Vent 8.5 Requests Unit 2 verify open 2HVC*MOD204B.
Fan, has NOT started EVALUATOR CUE: 2HVC*MOD204B is automatically, Start OPEN.
[2HVC*FN241B], Control Room Erner Vent Fan. 8.6 Requests Unit 2 check the status of A10-3E,
c. Verify Open, "CONTROL ROOM EMER SUPPLY AIR FLOW
[2HVC*MOD204B], Control LOW".
Room Emerg Outside Air I EVALUATOR CUE: Al0-3E is ON.
I Intake Damper.
d. Check OFF annunciator COMMENTS:
Al 0-3E, "CONTROL ROOM EMER SUPPLY AIR FLOW LOW".
e. If annunciator Al 0-3E, EVALUATOR NOTE: Candidate should proceed "CONTROL ROOM EMER to step IV.A.6 based upon report of Unit 2 SUPPLY AIR FLOW LOW" Annunciator Al0-3E. Refer to JPM Step 11 for the is ON, Proceed to Step next action.
IV.A.6.
BVPS-TR-0026 Page 8 of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-662 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EVALUATOR NOTE: The following may be omitted if they were previously performed.
9. If Unit 1 Control Room 9.1 Verifies lVS-D-40-lA control switch in CLOSE.
intake and exhaust damper are closed place the control 9.2 Verifies 1VS-D-40-lB control switch in CLOSE.
switches in CLOSE:
9.3 Verifies 1VS-D-40-1 C control switch in CLOSE.
[1 VS-D-40-lA]
9.4 Verifies 1VS-D-40-lD control switch in CLOSE.
[1 VS-D-40-lB]
COMMENTS:
[lVS-D-40-lC]
[1 VS-D-40-lD]
10. If2HVC-FN241A or Bis in 10.1 This step is N/A.
operation, check the total combined differential EVALUATOR NOTE/CUE: Unit 2 Control pressure is< 5.6 in. WG on Room pressurization fans are NOT in Operation.
the indicators:
2HVC-PDIS21A COMMENTS:
2HVC-PDIS22A
2HVC-PDIS23A
2HVC-PDIS21BA
2HVC-PDIS22B
2HVC-PDIS23BA Per Step 5 and 6of1/20M-44A.4A.A I
BVPS-TR-0026 Page 9of9 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1CR-662 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EVALUATOR NOTE: There is a typographical error in the procedure, there are two steps numbered 6, the following is for the second one.
11. If neither 2HVC-FN241A or 11.1 Dispatches an Operator to OPEN 1VS-257 and 1VS-B is available, dispatch an D-98D.
operator to OPEN 1VS-257 Control Room Emergency EVALUATOR CUE: Report as local operator that Vent Outside Air Intake 1VS-257 and 1VS-D-98D are OPEN.
Isolation and 1VS-D-98D Control Room Emerg Air Filter Outlet. COMMENTS:
12.C Start 1VS-F-41A Control 12.lC Places the Control Switch for 1VS-F-41A to START.
Room Emergency Supply Fan. 12.2 Verifies the fan RED Light-LIT and GREEN Light
-NOT LIT.
12.3 Contacts local Operator to verify OPEN 1VS-D-98A.
EVALUATOR CUE: Report as local operator that 1VS-D-98A is OPEN.
COMMENTS:
EVALUATOR CUE: Once one fan is started State "This JPM is complete" STOP TIME: _ _ _ _ _ __
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
A Large Break LOCA has occurred.
A transition to E-1, "Loss of Reactor or Secondary Coolant" has just been made.
CIB has actuated.
INITIATING CUE: The Unit Supervisor directs you to perform Step 1 RNO actions of E-1, "Loss of Reactor or Secondary Coolant".
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Vent the Charging Pump Suction Header TRAINING MATERIAL NUMBER: lPL-057
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Non-Licensed Operator Training COMPUTER CODE: IPL-057 REVISION NUMBER: 8 TECHNICAL
REFERENCES:
IOM-7.4.AV, "Charging Pump Suction Header Venting", Rev. 4 VOND lOM-7.
INSTRUCTIONAL SETTING: In-Plant APPROXIMATE DURATION: 15 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: IPL-057 New Revision: 8 Description of Change(s):
I. Updated cues to match what operator would see in the plant.
2. Updated expected time to 15 minutes Reason for Change (s):
I. Cues modified to match the observable valve positions.
2. Expected completion time extended.
BVPS-TR-0026 Page I of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-057 JPM TITLE: Vent the Charging Pump Suction Header JPM REVISION: 8 KlA
REFERENCE:
2.1.30 4.4/4.0 TASK ID: 0071-021-01-043 JPM APPLICATION: 0 REQUALIFICATION 0 INITIAL EXAM D TRAINING D SROONLY D ALTERNATEPATHJPM D ADMINISTRATIVEJPM EV ALDA TION METHOD: LOCATION: TYPE: ADMINISTERED BY:
D Perform ~ Plant Site D Annual Requa! Exam D BVT
~ Simulate D Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SSN:
Time D Yes Allotted 15 Minutes Actual minutes Critical: 0 No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
Evaluator Signature:
BVPS-TR-0026 Page 2of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: A solid stream of water is observed through the vent flow indicator and the vent system is isolated.
RECOMMENDED In-Plant STARTING LOCATION:
INITIAL CONDITIONS: The unit is at 100% power. The 'A' charging pump is in operation with the 'B' charging pump in standby, and will be started within one hour.
NDE has determined that a gas void greater than limits exists in the 6 inch Charging Pump suction header.
INITIATING CUE: Your supervisor directs you to vent the Charging Pump 6 inch suction header per lOM-7.4.AV. Steps IV.A.I and 2 are complete.
REFERENCES:
1OM-7.4.AV, "Charging Pump Suction Header Venting", Rev. 4 TOOLS: None HANDOUT: 1OM-7.4.AV, "Charging Pump Suction Header Venting", Rev. 4, place kept up to but not including step IV.A.3. Should also NIA the 8" header portion to identify the performance steps.
Have a Copy ofVOND 7.1 available as a reference
BVPS-TR-0026 Page 3of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-057 JPM TITLE: Vent the Charging Pump Suction Header JPM REVISION: 8 STANDARD Indicate "S" FOR SAT or "U" FOR UNSAT =>
EVALUATOR NOTE:
Provide candidate with a place kept copy of 1OM-7.4.AV. If asked provide VOND 7-1.
START TIME: - - - - - - -
1. Review procedure. 1.1 Candidate reviews 1OM-7.4.AV.
COMMENTS:
2.C Open [lCH-487], "Charging 2.1 C OPENS [l CH-487] by rotating valve T-Handle in the Pump Vent Common counterclockwise position.
Isolation, located in Aux Bldg 735'. EVALUATOR CUE: 1CH-487 T Handle is full counterclockwise.
COMMENTS:
3.C Open [lCH-486], Outlet 3.IC OPENS [lCH-486] by rotating valve T-Handle in the Isolation for [FI-lCH-170], counterclockwise position.
located in Aux Bldg. 735'.
EVALUATOR CUE: lCH-486 T Handle is full counterclockwise.
COMMENTS:
BVPS-TR-0026 Page 4of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-057 JPM TITLE: Vent the Charging Pump Suction Header JPM REVISION: 8 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT)=:} S/U 4.C Open [lCH-484], Inlet 4.lC OPENS [lCH-484] by rotating valve T-Handle in the Isolation for [FI-1 CH-170], counterclockwise position.
located in Aux Bldg. 735'.
EVALUATOR CUE: lCH-484 T Handle is full counterclockwise.
COMMENTS:
5.C Vent the 6 inch charging pump 5.lC OPENS [lCH-483] by rotating valve T-Handle in the suction header from the safety counterclockwise position.
injection system by performing the following: EVALUATOR CUE: lCH-483 T Handle is full counterclockwise.
a. Open [lCH-483], Charging Pump Vent Isolation Valve, 5.2C Observes the vent flow indicator, [lCH-FI-170].
located in Aux Bldg. 735'.
EVALUATOR CUE: You initially observe an air/water mixture and now there is a solid stream of
b. When a solid stream of water flowing through the indicator.
flow is observed through
[FI-1 CH-170], Charging Pump Suction Line Vent 5.3C CLOSES [ICH-483] by rotating valve T-Handle in Sight Flow Indicator, the clockwise position.
located in Aux Bldg. 735',
Close and independently EVALUATOR CUE: lCH-483 T Handle is full verify closed on daily clockwise.
journal, [1 CH-483],
Charging Pump Vent 5.4 Requests independent verification that [ICH-483] is Isolation Valve. closed.
EVALUATOR CUE: When asked, Inform the candidate that another operator has performed an independent verification of [1 CH-483].
COMMENTS:
BVPS-TR-0026 Page 5of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-057 JPM TITLE: Vent the Charging Pump Suction Header JPM REVISION: 8 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSA :::::> SIU
6. Notify NDE to perform an 6.1 Notifies NDE to perform a UT on the 6 inch Charging Ultrasound Test (UT) to Pump suction header.
confirm no gas voids exist in the 6 inch Charging Pump EVALUATOR CUE: NDE has determined NO gas suction header, in accordance voids exist in the 6 inch Charging Pump suction with 3BVT01-11.04, "Void header and the void limit was NOT exceeded.
Monitoring".
EVALUATOR NOTE: If the candidate continues onto the next step (Venting the 8 inch header), inform the candidate, that step of the procedure is NIA. They are to continue with the next step.
COMMENTS:
7.C Close [lCH-484], Inlet 7.IC CLOSES [lCH-484] by rotating valve T-Handle in Isolation for [FI-1 CH-170]. the clockwise position.
EVALUATOR CUE: ICH-484 T Handle is full clockwise.
COMMENTS:
BVPS-TR-0026 Page 6of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-057 JPM TITLE: Vent the Charging Pump Suction Header JPM REVISION: 8 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT ~ S!U 8.C Close [lCH-486], Outlet 8.IC CLOSES [lCH-486] by rotating valve T-Handle in Isolation for [FI-1 CH-170]. the clockwise position.
EVALUATOR CUE: lCH-486 T Handle is full clockwise.
COMMENTS:
9.C Close [lCH-487], "Charging 9.lC CLOSES [lCH-487] by rotating valve T-Handle in Pump Vent Common the clockwise position.
Isolation.
EVALUATOR CUE: lCH-487 T Handle is full clockwise.
COMMENTS:
10. Independently verify closed on 10 .1 Indicates that Independent Verification is required.
Daily Journal, the following valves: EVALUATOR CUE: An independent Verifier will be sent from the Control Room. Venting of the
a. [lCH-484], Inlet Isolation for charging pump individual suctions lines is not
[FI-1 CH-170]. required.
b. [lCH-486], Outlet Isolation for [FI-lCH-170]. COMMENTS:
c. [1 CH-487],
"Charging Pump Vent Common Isolation..
EVALUATOR CUE: State "This JPM is complete" STOP TIME: - - - - - - -
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS: The unit is at 100% power. The 'A' charging pump is in operation with the 'B' charging pump in standby, and will be started within one hour.
NDE has determined that a gas void greater than limits exists in the 6 inch Charging Pump suction header.
INITIATING CUE: Your supervisor directs you to vent the Charging Pump 6 inch suction header per 1OM-7.4.AV. Steps IV.A.1 and 2 are complete.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Startup the Dedicated Auxiliary Feedwater Pump [FW-P-4]
TRAINING MATERIAL NUMBER: lPL-007
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training COMPUTER CODE: lPL-007 REVISION NUMBER: 8 TECHNICAL
REFERENCES:
10M-53A.1.2-K, "Dedicated AFW Pump [lFW-P-4] Startup" Rev. 4 INSTRUCTIONAL SETTING: In-Plant APPROXIMATE DURATION: 20 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: 1PL-007 New Revision: 8 Description of Change(s):
1. Updated for current procedure revision.
Reason for Change (s):
1. Procedure was revised with minor changes.
BVPS-TR-0026 Page 1of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1PL-007 JPM TITLE: Startup the Dedicated Auxiliary Feedwater Pump [FW-P-4]
JPM REVISION: 8 K/A
REFERENCE:
054 AK3.04 4.4/4.6 TASK ID: 0534-005-05-041 E05 EKI.2 3.9/4.5 JPM APPLICATION: ~ REQUALIFICA TION ~ INITIAL EXAM 0 TRAINING D SROONLY D ALTERNATE PATH JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
D Perform ~ Plant Site D Annual Requal Exam D BVT
~ Simulate D Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SSN:
Time D Yes Allotted 20 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
I Evaluator Signature:
BVPS-TR-0026 Page 2of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Startup the Dedicated Auxiliary Feedwater Pump [lFW-P-4] and open the Discharge Isolation Valve [MOV-lFW-160].
RECOMMENDED In-Plant STARTING LOCATION:
INITIAL CONDITIONS:
The crew is performing FR-H.1, "Response to Loss of Secondary Heat Sink"
The Auxiliary Feedwater Pumps [lFW-P-2, 3A & 3B] are inoperable due to a fire
[ 1WT-TK-1 O] has been depleted and is unavailable for use
The DAFWP [lFW-P-4] is in NSA, and aligned to 1WT-TK-11
The DAFWP Discharge Isolation Valve [MOV-lFW-160] is closed
ERP substation 4160V Bus H is energized by offsite power
The ERP Diesel is not running
Steps 1 through 3 of Attachment 2-K are complete INITIATING CUE: Your supervisor directs you to Startup the Dedicated Auxiliary Feedwater Pump [lFW-P-4] per Steps 4 through 8 of EOP Attachment 2-K, and report when complete.
REFERENCES:
10M-53A.1.2-K, "Dedicated AFW Pump [lFW-P-4] Startup" Rev. 4 TOOLS: None HANDOUT: 10M-53A.1.2-K, "Dedicated AFW Pump [lFW-P-4] Startup" Rev. 4 with steps 1-3 completed.
Have a copy ofVOND 24-3 available as a reference
BVPS-TR-0026 Page 3of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-007 JPM TITLE: Startup the Dedicated Auxiliary Feedwater Pump [FW-P-4]
JPM REVISION: 8 STEP STANDARD
( "C" Denotes CRITICAL STEP ) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU EVALUATOR NOTE: All steps required should be performed from the Feed Reg. Valve Room.
EVALUATOR CUE: Provide candidate a copy of 10M-53A.l.2-K with steps 1-3 completed. Provide VOND 24-3 is asked.
START TIME: - - - - - - -
1. Reviews procedure. 1.1 Reviews EOP Att. 2-K.
COMMENTS:
2.C At the DAFW Panel (PNL- 2.1 C Places LOCAL-TEST switch to LOCAL.
DAFWPl) place the LOCAL-TEST Switch to LOCAL and EVALUATOR CUE: LOCAL-TEST switch in the ON-OFF Panel Switch to LOCAL.
ON to energize the panel.
2.2C Places ON-OFF switch to ON.
I EVALUATOR CUE: ON-OFF switch is ON.
COMMENTS:
BVPS-TR-0026 Page 4of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1PL-007 JPM TITLE: Startup the Dedicated Auxiliary Feedwater Pump [FW-P-4]
JPM REVISION: 8 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT ~ SIU
3. Check closed [MOV-FW- 3.1 Checks MOV-FW-160 is CLOSED. GREEN light-160], DAFW Discharge LIT and RED light - NOT LIT.
Isolation Valve.
EVALUATOR CUE: GREEN light- LIT and RED light - NOT LIT.
EVALUATOR NOTE: Candidate may opt to check MOV-lFW-160 local position. Initial Conditions are that the valve is closed. Cue as needed.
COMMENTS:
4. Establish communications 4.1 Establishes communication with Control Room.
with the control room.
EVALUATOR CUE: Communications have been established with the Control Room.
COMMENTS:
BVPS-TR-0026 Page 5of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1PL-007 JPM TITLE: Startup the Dedicated Auxiliary Feedwater Pump [FW-P-4]
JPM REVISION: 8 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU 5.C Start [lFW-P-4], Dedicated 5.lC Places DAFWP Control switch to the START AFW Pump. (Feed Reg Valve position.
Room, PNL-DAFWPl).
EVALUATOR CUE: DAFWP Control Switch is in START.
If asked, suction flow is approximately 150 GPM.
5.2 Checks RED light - LIT and WHITE light- NOT LIT.
EVALUATOR CUE: RED light-LIT and WHITE light - NOT LIT.
COMMENTS:
6.C Open [MOV-FW-160]. 6.lC Places MOV-FW-160 Control Switch to the OPEN Dedicated AFW Pump position.
Discharge Isolation Valve.
EVALUATOR CUE: MOV-FW-160 Control Switch is in the OPEN position.
6.2 Verifies RED light - LIT and GREEN light - NOT LIT.
EVALUATOR CUE: RED light-LIT and GREEN light - NOT LIT.
COMMENTS:
BVPS-TR-0026 Page 6of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1PL-007 JPM TITLE: Startup the Dedicated Auxiliary Feedwater Pump [FW-P-4]
JPM REVISION: 8 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU
7. Report to the control room 7 .1 Reports to control room startup of Dedicated step 4 through 8 of Auxiliary Feedwater Pump is complete.
Attachment 2-K are complete.
COMMENTS:
EVALUATOR CUE: State "This JPM is complete" STOP TIME:~~~~~~~
CANDIDATE DIRECTION SHEET
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
The crew is performing FR-H.1, "Response to Loss of Secondary Heat Sink"
The Auxiliary Feedwater Pumps [lFW-P-2, 3A & 3B] are inoperable due to a fire
[ 1WT-TK-1 O] has been depleted and is unavailable for use
The DAFWP [lFW-P-4] is in NSA, and aligned to 1WT-TK-11
The DAFWP Discharge Isolation Valve [MOV-lFW-160] is closed
ERF substation 4160V Bus H is energized by offsite power
The ERF Diesel is not running
Steps 1 through 3 of Attachment 2-K are complete INITIATING CUE: Your supervisor directs you to Startup the Dedicated Auxiliary Feedwater Pump [lFW-P-4] per Steps 4 through 8 ofEOP Attachment 2-K, and report when complete.
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE TRAINING MATERIAL TITLE: Locally Start the No. 1(2) Emergency Diesel Generator TRAINING MATERIAL NUMBER: IPL-006
~~~~~~~~~~~~~~~~~~~~~~~
PROGRAM TITLE: Licensed Operator Training (Retraining)
COMPUTER CODE: IPL-006 REVISION NUMBER: 13 TECHNICAL
REFERENCES:
IOM-53.A.l.2-E, Local Actions To Restore AC Power, Revision 5 INSTRUCTIONAL SETTING: In-Plant APPROXIMATE DURATION: 20 Minutes PREPARED BY: M. Klingensmith Date PEER REVIEW BY:
Date APPROVED FOR USE:
Training Supervisor or Designee Date
BVPS-TR-0026 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM CHANGE
SUMMARY
Affected JPM: lPL-006 New Revision: 13 Description of Change(s):
1. Updated for current procedure revision.
2. Added step 2 and cue to address new EDG overspeed Caution
3. Modified Evaluator Cue when EDG is started to state speed is 850 RPM.
4. Added JPM step 6 for reviewing the caution regarding EDG operation without cooling water.
5. Added Evaluator Note/Cue in step 11 for the River Water supply valves for cueing purposes if the valves are verified open.
Reason for Change (s):
1. Procedure was revised with minor changes.
2. New step 2 EDG overspeed Caution and figure included in the attachment.
3. 850 RPM was stated to ensure the EDG speed is adjusted in the next critical step.
4. Added based on NRC feedback.
5. Added based on NRC feedback.
BVPS-TR-0026 Page I of 6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1PL-006 JPM TITLE: Locally Start the No. 1(2) Diesel Generator JPM REVISION: 13 KIA
REFERENCE:
055 EAl.02 4.3 I 4.4 TASK ID: 0532-001-05-013 055 EA2.03 3.9 I 4.7 0532-009-05-043 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM 0 TRAINING D SROONLY D ALTERNATE PATH JPM 0 ADMINISTRATIVEJPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:
D Perform ~ Plant Site D Annual Requal Exam D BVT
~ Simulate D Simulator D Initial Exam D NRC D Classroom D Training D Other:
D Other:
EVALUATION RESULTS Performer Name: Performer SSN:
Time D Yes Allotted 20 Minutes Actual minutes Critical: ~ No Time: Time:
JPM RESULTS:
D SAT D UNSAT (Comments required for UNSAT evaluation)
Comments:
OBSERVERS Name/SSN: Name/SSN:
Name/SSN: Name/SSN:
EVALUATOR Evaluator (Print): Date:
Evaluator Signature:
BVPS-TR-0026 Page 2of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Locally start the No. 1 (2) Diesel Generator and energize the 4KV
'AE (DF)' emergency bus.
RECOMMENDED In-Plant STARTING LOCATION:
INITIAL CONDITIONS:
A station blackout has occurred.
1OM-53A. l .ECA-O.O, "Loss of All AC Power" has been performed to the step where local actions must be taken to restore power.
The lA(lB) RPRW pump is in AUTO.
INITIATING CUE: Your Supervisor directs you to use EOP Attachment 2-E to start the No. 1(2) Diesel Generator and ensure that the 4KV 'AE(DF)' bus is energized.
You are given the key 48 for the No. 1(2) Diesel Generator.
(Simulated)
REFERENCES:
lOM-53.A.l.2-E, Local Actions To Restore AC Power, Revision 5 TOOLS: None HANDOUT: EOP Attachment 2-E, Revision 5.
The use of keys will be simulated.
BVPS-TR-0026 Page 3of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 1PL-006 JPM TITLE: Locally Start the No. 1(2) Diesel Generator JPM REVISION: 13 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=>
EVALUATOR CUE: Provide Candidate a copy of EOP Attachment 2-E. If asked, the required RPRW pump control switch is in AUTO. The use of keys will be simulated.
START TIME: - - - - - - - -
1. Establish communications 1.1 Calls the Control Room on PAX or Page Party.
between Diesel Generator Room 1(2) and Control Room. EVALUATOR CUE: Role play as RO and acknowledge the call.
COMMENTS:
2. References Caution and Figure 2.1 Reads Caution related to EDG Overspeed trip and 1 to determine if the EDG proper limit switch position.
tripped on Overs peed ..
EVALUATOR CUE: If candidate evaluates the Overspeed trip, cue that the limit switch is in the position shown on Figure 1 (2 o'clock)
COMMENTS:
3. Clear all start failure alarms on 3 .1 Depresses the alarm Reset pushbutton, or Alarm Test &
[PNL-EE-EG-lA (2A)]. Reset & Silence, to clear all alarms.
I EVALUATOR CUE: No alarms are present.
COMMENTS:
BVPS-TR-0026 Page 4of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: IPL-006 JPM TITLE: Locally Start the No. 1(2) Diesel Generator JPM REVISION: 13 STEP STANDARD
( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 4.C With Key 48, Place Selector 4.1 Simulates inserting Key 48 into selector switch.
Switch to LOCAL START on
[PNL-EE-EG-lA (2A)]. 4.2C Selects the LOCAL START Position.
I EVALUATORCUE: KeyisinLOCALSTART. I COMMENTS:
5. Prime diesel fuel system by 5.1 Depresses the FUEL PRIME pushbutton.
pressing FUEL PRIME pushbutton on [PNL-EE-EG- EVALUATOR CUE: If asked, fuel oil pressure on 1A(2A)]. PI-EE-205(206) is 35 psig and PI-EE-207(208) is 0 psig.
COMMENTS:
6. Reviews Caution: A Diesel 6.1 Acknowledges Caution regarding cooling water flow Generator Should Not Operate after the EDG starts.
For Greater Than Five Minutes, Loaded Or Unloaded, EVALUATOR NOTE: River Water automatically Without Cooling Water. aligns after the EDG starts and sequences on the Motor Control Center (MCC) supplying the River Water supply valves.
1 EDG-MOV-1RW-113A and 113B will OPEN.
2 EDG- MOV-1RW-113C and 113D will OPEN.
COMMENT:
BVPS-TR-0026 Page 5of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: IPL-006 JPM TITLE: Locally Start the No. 1(2) Diesel Generator JPM REVISION: 13 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT => SIU 7.C Depress ENGINE START 7.IC Depresses the ENGINE START pushbutton and holds pushbutton on [PNL-EE-EG- until the diesel starts and is self-sustaining.
1A(2A)] and maintain pushbutton depressed until the I EVALUATORCUE: EDG is running at 850 rpm.
I Diesel starts and is self-sustaining, then release COMMENTS:
pushbutton.
8.C Adjust EDG speed using 8.IC Adjusts mechanical governor speed setting knob to raise Governor "Speed Setting" speed and obtain an engine speed of 900 rpm.
knob to an operating speed of 900 RPM. EVALUATOR CUE: EDG speed rises and is stable at 900 rpm.
COMMENTS:
9. Verify DG output voltage on 9.1 Locates EDG output voltmeter on PNL-DIGEN-1(2)
[PNL-DIGEN-1 (2)]. and reads voltage by rotating Diesel GEN N0.1(2)
Voltmeter GYM Selector Switch to any phase EXCEPT OFF.
EVALUATOR CUE: EDG output voltage is 4160 volts.
COMMENTS:
BVPS-TR-0026 Page 6of6 Revision 0 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: lPL-006 JPM TITLE: Locally Start the No. 1(2) Diesel Generator JPM REVISION: 13 STEP STANDARD
( "C" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "U" FOR UNSAT ~ SIU
10. Check if the emergency bus is 10.1 Calls the Control Room to verify that the emergency bus energized. is energized OR energizes generator ammeter to monitor generator current.
EVALUATOR CUE: The emergency bus is energized and/or the ammeter indicates 250 amps.
COMMENTS:
. 11. Notify Control Room that EOP 11.1 Candidate informs the Control Room that EOP Attachment 2-E is complete. Attachment 2-E is complete.
11.2 Candidate may check that River Water is aligned the operating EDG.
EVALUATOR CUE: Acknowledge report as the Control Room.
EVALUATOR NOTE/CUE: Candidate may check that the River Water valves have opened.
1 EDG- MOV-1RW-113A and 113B OPEN.
2 EDG - MOV-IRW-113C and l 13D OPEN.
COMMENTS:
EVALUATOR CUE: State "This JPM is complete."
STOP TIME: _ _ _ _ _ __
CANDIDATE DIRECTION SHEET Use This Sheet When Protected Train "A"
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
A station blackout has occurred.
1OM-53A.1.ECA-O.O, "Loss of All AC Power" has been performed to the step where local actions must be taken to restore power.
The IB RPRW pump is in AUTO.
INITIATING CUE: Your Supervisor directs you to use EOP Attachment 2-E to start the No. 2 Diesel Generator and ensure that the 4KV 'DF' bus is energized.
You are given the key 48 for the No. 2 Diesel Generator. (Simulated)
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
CANDIDATE DIRECTION SHEET Use This Sheet When Protected Train "B"
THIS SHEET TO BE GIVEN TO CANDIDATE
D Read:
INITIAL CONDITIONS:
A station blackout has occurred.
1OM-53A.1.ECA-O.O, "Loss of All AC Power" has been performed to the step where local actions must be taken to restore power.
The IA RPRW pump is in AUTO.
INITIATING CUE: Your Supervisor directs you to use EOP Attachment 2-E to start the No. 1 Diesel Generator and ensure that the 4KV 'AE' bus is energized.
You are given the key 48 for the No. 1 Diesel Generator. (Simulated)
D At this time, ask the evaluator any questions you have on this JPM.
D When satisfied that you understand the assigned task, announce "I am now beginning the JPM".
Simulate performance or perform as directed the required task.
D Point to any indicator or component you verify or check and announce your observations.
After determining the Task has been met announce "I have completed the JPM".
D Then hand this sheet to the evaluator.
A,ppen d"1x D s cenario
. 0 utrme 1L 16N1 Facility: BVPS Unit 1 Scenario No. 1 Op Test No.: BV1LOT16 NRC Examiners: Candidates: SRO ATC BOP Initial IC-62 (17): 67% power, MOL, Equ. XE Conditions, CB "D" @ 177 steps, Conditions: RCS boron - 985 ppm, 1FW-P-3A OOS Turnover: Maintain 67% power.
Critical Tasks: 1. CT-2 (E-0.D) Crew manually actuates at least 1 train of SIS
2. CT-51 (FR-S.l.B) Crew starts AFW pumps
3. CT-52 (FR-S.l.C) Crew inserts negative reactivity Event Malf. No. Event Type Event Description No.
(I,A) ATC, SRO 1 PRS06A Pressurizer level transmitter, LT-lRC-459 drifts low.
(TS) SRO (I,A) BOP, SRO 2 XMT-MSS021A PT-lMS-446 fails low.
(TS) SRO 3 CHS03 (C,A) A TC, SRO Isolable 25 gpm RCS leak on letdown line. (AOP 1.6. 7)
(R) ATC Main feedwater pump trip, requires turbine runback and 4 FWMOlA (C,A) BOP, SRO manual rod insertion.
GENO I, Spurious Gen Trip with auto & manual Rx trip failures.
5 (M) ALL CRF12A, 12B (ATWS) 6 IOR X06i068C (C) ATC, SRO MOV-lCH-350 failed closed.
7 INH20,21,36 (C) BOP, SRO All AFW pumps fail to auto start.
8 RCS02A (M)ALL 950 gpm LOCA 9 VLV-MSS03,04 (C) BOP, SRO Reheat steam failure to auto isolate.
10 SIS 1OA, SIS 1OB (C) ATC, SRO Automatic SI actuation failure.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0--+ FR-S.1 --+ E-0--+ E-1 --+Terminate after evaluating SI termination criteria.
NUREG-1021, Revision 10 FENOC Facsimile Rev AG
Appendix D Scenario Outline 1L 16N1 After taking the shift at 67% power with AFW pump, 1FW-P-3A OOS, Pressurizer level transmitter, LT-1 RC-459 will drift low. The crew will diagnose the indications and IA W AOP 1.4.1, Process Control Failure, remove the failed channel from service and ensure the plant is stable, the SRO will transition to the instrument failure procedure for further channel actions and will address Tech Specs for the failed channel.
The non-selected Turbine First Stage pressure transmitter, PT-lMS-446 will fail low. IAW the instrument failure procedure, the crew will take action to transfer the condenser steam dump control to "Steam Pressure" mode. The SRO will address Tech Specs for the failed channel.
An isolable 25 gpm leak will then occur on the letdown line, the crew will enter AOP 1.6.7, Excessive Primary Plant Leakage, to evaluate leak rate and leak location. The crew will determine the leak rate is
> 10 gpm and is isolable.
The "A" Main feed pump will then trip, the crew will enter AOP 1.24.1, Loss of Main Feedwater, and determine that a power reduction to <52% is required. The crew will reduce power IA W AOP 1.24.1.
After the power reduction is underway, the Main Unit Generator will spuriously trip. The reactor will fail to automatically trip as expected due to the MUG trip. The crew will identify the automatic Rx trip failure. The SRO will direct the crew to manually trip the Rx and perform IOA's ofE-0. The ATC will attempt to manually trip the Rx which will also fail. The SRO will direct the crew to perform IOA's for FR-S.1, Response to Nuclear Power Generation-ATWS. The control rods will fail to automatically insert, the A TC will place the Rod Control system in manual and begin inserting rods. When control bank "D" inserts to <100 steps, an "Urgent Failure" will occur in the Rod control system, stopping all rod motion. When the crew attempts to align the Emergency Boration flowpath, the Emergency Boration Valve, MOV-lCH-350, will fail to open. The crew will align an alternate boration flow path by aligning the Charging pump suction to the R WST. At the lead evaluator's discretion, when an emergency boration flowpath is aligned, the reactor will be locally tripped via a field operator if dispatched.
Additionally, the remaining main feed pump will trip following the generator trip and all available AFW pumps will fail to automatically start, the BOP will start the Turbine Driven AFW pump and the "B" Motor driven AFW pump. The BOP will recognize that Reheat steam failed to automatically isolate on the Turbine Trip and manually close, MOV-lMS-lOOA and lOOB.
When the Rx is locally tripped and verified, the crew will transition back to E-0, Reactor Trip Response, coincident with the local Rx trip, a 950 gpm LOCA will occur on the "A" Loop cold leg, While performing the IOA's of E-0, the crew will recognize that RCS pressure and level are reducing and that conditions require a Safety Injection which failed to automatically actuate. The crew will actuate SI and continue in E-0. The crew will progress thru E-0 and transition to E-1 after diagnosing that containment pressure and sump level are not consistent with pre-event values.
The scenario will be terminated after the crew has evaluated SI termination criteria in E-1.
Expected procedure flow path is E-0---+ FR-S.1 ---+ E-0---+ E-1.
NUREG-1021, Revision 10 FENOC Facsimile Rev AG
BEAVER VALLE'r . JWER STATION INITIAL CONDITIONS: IC-62(17): 67% power, MOL, Equ. XE Conditions, CB "D"@ 177 steps, RCS boron - 985 ppm.
Use HTML, 1L16Nl.HTM, Initialize into specified IC and insert preloads per the HTML.
ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP 1FW-P-3A CS in PTL 1FW-P-3A CS tagged Normal Splash w/ High Power Screen, on VB-B EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 1FW-P-3A OOS, pump bearing replacement Yesterday I 1800 3.7.5, Condition B SHIFT TURNOVER INFORMATION
1. 67% power for the past week due to System request, MOL equilibrium conditions, shift goal is to maintain current power.
SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED
1. MOL Reactivity Placard E-0
2. Protected Train "B" Placard E-1
3. Safety Status PNL lights LIT for "A" AFW FR-S.l
3. lFW-P-2 aligned to A hdr placard lOM-7.4.AF lOM-46.4.G 6 IF, Attach 1 24 IF, Attach 5 Attachment 1-K AOP 1.4.1 AOP 1.6.7 AOP 1.7.1 AOP 1.24.1 BVPS-1L16 NRC 1, Rev AG 3 of24
BEAVER VALLE'r. uWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE l EXPECTED STUDENT RESPONSE l Assign shift positions SRO:, _ _ _ _ _ _ _ __
ATC:- - - - - - - - -
BOP: _ _ _ _ _ _ _ __
Conduct a shift turnover with oncoming Simulator frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.
When the shift turnover is completed, Simulator running. Crew assumes control of the unit.
place the simulator to RUN and commence the scenario.
BVPS-1L16 NRC 1, Rev AG 4 of24
BEAVER VALLE) . OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT 1:
Pressurizer level transmitter LI-1RC-459A indicates downscale. ATC reports unexpected PRZR level deviation alarm.
LT-lRC-459 drifts low. ALARM: ATC identifies LT-lRC-459 is failing low.
A4-4, PRZR Control Low Level Deviation, IAW AOP 1.41, Part C, ATC removes LT-lRC-459 IMF PRS06A (0 0) 0 60 from service by placing PRZR level control channel selector to POS 3 (461/460).
If necessary A TC places FCV -1 CH-122 in manual and restores PRZR level.
NOTE: SRO enters AOP 1.4.1, Process Control Failure.
A control band and Rx trip criteria are SRO provides a control band and Rx trip criteria of not applicable if the PRZR level 5% low/90% high for manual PRZR level control.
controls remained in AUTO.
BOP refers to ARP.
NOTE: SRO enters Part B of AOP 1.7.1, Loss of If necessary ATC performs IOA's of AOP 1.7.1, Part If Letdown automatically isolated, the Charging or Letdown. B for loss of letdown.
SRO will enter AOP 1. 7.1 vs 1.4.1.
Verifies TV-1CH-200A,B, Call closed.
Closes FCV-lCH-122.
Adjusts HCV-lCH-186 to just above low seal injection flow alarm setpoint.
Crew verifies letdown flowpath in proper alignment and determines that cause of letdown isolation was due to low failure of LT-lRC-459.
SRO enters the Reactor Coolant System SRO transitions to Reactor Coolant System Instrument Instrument failure procedure, lOM-6.4.IF, failure procedure, lOM-6.4.IF, attachment 1.
attachment 1.
BVPS - 1L16 NRC 1, Rev AG 5 of24
H-,
BEAVER VALLE) . JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE EVENT 1: (continued) ATC places PRZR level control channel selector to POS 3. (previously performed IA W AOP 1.4.1.
A TC verifies PRZR level recorder selector is positioned to record the controlling level channel.
ATC verifies there is adequate makeup to the VCT.
ATC verifies PRZR heaters (Control & Backup) groups have returned to normal operation or manually energizes heaters as necessary.
SRO directs crew to restore letdown.
Letdown restoration IAW lOM-7.4.AF. ATC establishes letdown as follows:
Verifies normal charging is established.
Opens TV-lCH-204.
Places PCV-lCH-145 in MAN & 75% open.
Opens LCV-1CH-460A and 460B.
Adjusts FCV-lCH-122; 30-50 gpm.
Places 1st orifice in service by opening, as desired, TV-1CH-200A(B)(C).
Lowers LD pressure to< 300 psig.
Increases charging flow to >60 gpm.
Places 2"d orifice in service by opening, as desired, TV-1CH-200A(B)(C).
Adjusts letdown pressure to 300 psig using PCV-lCH-145 and places PCV in AUTO.
Adjusts seal injection and charging flow as necessary & returns FCV-lCH-122 to AUTO.
BVPS-1L16 NRC 1, Rev AG 6 of24
BEAVER VALLE) . -JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ]
EVENT 1: (continued) SRO references Tech Specs. SRO references Technical Specifications:
3.3.l (RTS Instrumentation) Condition A, immediately enter the Condition referenced in Table 3.3.1-1 function 9 (PRZR level high) Condition K; trip channel in 72 hrs. or reduce power to < P-7 in 78 hrs.
SRO determines following TS are for tracking only 3.3.3 (PAM instrumentation) Table 3.3.3-1 function 11 is met if LT460 and LT461 are operable.
3.3.4 (Remote Shutdown System) Table B.3.3.4-1 function 4.a requirement is met ifLT460 is operable.
SRO contacts operations management and notifies I&C of level transmitter failure.
Proceed with next event at LE discretion.
BVPS - 1L16 NRC 1, Rev AG 7 of24
BEAVER VALLEY . JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE .]
EVENT2:
1st Stage Pressure Transmitter, PT-lMS-446 failed low (Non controlling Ch) BOP identifies PT-lMS-446 has failed low.
PT-IMS- 446 fails low. ALARM:
IMF XMT-MSS021A (0 0) 0 10 A3-20, AMSAC Trouble SRO enters lOM-24.4.IF, Attach 5 SRO enters 1OM-24.4.IF, "Instrument Failure Procedure" Attachment 5. BOP verifies Steam Dump Control Mode Selector Switch is in TAVG mode.
BOP places Steam Dumps in Stm Pressure Mode;
Places AM-1MS-464B, stm press controller, in MAN with 'zero' percent output signal.
Verify or adjust the setpoint for AM-1MS-464B to the equivalent value for 1005 psig.
Places the Train A and Train B Steam Qump
~ ....,.. 4 4 -*control Bypass Interlock Selector Switches to OFFIRESET/INTLK.
Place the Steam Dump Control Mode Selector Switch in SIM PRESS.
Place AM-1MS-464B, In AUTO.
Checks TI-lRC-408, Stm Dump Demand, is indicating 0% (BB-B)
Places the Train A and Train B Steam Dump Control Bypass Interlock Selector SW's to ON.
Check all steam dump valves remain closed.
NOTE: SRO references Tech Specs.
It is not the intent of the scenario to allow the crew to re-arm AMSAC, after the crew has 3.3.1 Condition P for P-13, Verify interlock in placed the Condenser steam dumps in Steam Pressure Mode, next event can be entered at required state for existing conditions within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .
the Lead Evaluator discretion.
BVPS- 1L16 NRC 1, Rev AG 8 of24
BEAVER VALLE'r, JWER STATION
[ INSTRUCTIONALGUIDELfNES-[PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT 3: A4-71 and 72, Rad Monitor High and High-High BOP reviews ARPs.
alarms on Incore Instrument Area Rad monitor, BOP verifies valid Rad monitor indication using ARP.
25 gpm letdown line leak inside RIS-RM-204.
CNMT. (isolable) Based on RM alarms with VCT level dropping, SRO VCT level slowly decreasing. may directly enter AOP 1.6.7.
IMF CHS03 (0 0) 25 CNMT sump level rising.
A TC determines PRZR level is capable of being SRO enters 1.6.7, Excessive Primary Plant maintained > 5%.
Leakage ATC checks if leakage is RCS/CV CS leakage by:
CNMT particulate Rad monitor, RIS-1 RM-215A
Checking CNMT, PAB and safeguards alarms. conditions are consistent with pre-event.
Crew determines conditions are NOT consistent with pre-event based upon rising radiation levels on RIS-1RM-204 and RIS-1RM-215A.
SRO transitions from AOP 1.6.7, step 2 to step 6 Crew verifielR.CS temperature is stable.
A TC verifies FCV -1 CH-122 is maintaining constant PRZR level in AUTO or places FCV-lCH-122 in MAN and controls charging flow to maintain a constant PRZR level.
Crew checks VCT level trend and determines that VCT level is DROPPING at >0.7%/min. and determines that leak.rate is > 10 gpm.
SRO informs SM that leak rate is> 10 gpm but may be isolable from the RCS.
BVPS-1L16 NRC 1, Rev AG 9 of24
BEAVER VALLEt . OWER STATION
[ INSTRUCTIONAi.. GUIDELINES-- J PG\NTSTATUS I PROCEDURAL GUIDANCE] EXPECTED STUDENT RESPONSE- - I EVENT 3: (continued) ATC quantifies leakage & checks for CVCS leakage:
Isolates charging/letdown by closing valves:
TV-1 CH-200A & B Letdown orifice isol.
LCV-1CH-460A & B Regen Ht Ex inlet.
FCV-lCH-122, charging flow control vlv.
ATC adjusts RCP seal injection flow to obtain NET RCS input of 10 gpm.
Crew determines PRZR level is rising.
Crew determines that with PRZR level rising, the leak has been isolated.
ATC adjusts RCP seal injection to 6-9 gpm/pump.
ATC determines VCT level can be maintained >5%
with normal makeup.
,., 1
'-~* ATC controls FCV-lCH-122 and HCV-lCH-186 as --
necessary to maintain at approximately programmed PRZR level.
Crew determines it is NOT desirable to restore charging and letdown to service.
SRO directs the crew to place EXCESS letdown in service.
NOTE:
It is not the intent of this scenario for the crew to demonstrate placing Excess Letdown in service. At the Lead Evaluators discretion, Event 4 can be inserted.
BVPS - 1L16 NRC 1, Rev AG 10 of24
BEAVER VALLE'. . JWER STATION
[ -INSTRUCTTONALGWDELlNES - f PLANTSTATUSTPROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT4: lFW-P-lA trips. BOP recognizes feed pump trip and informs crew.
Trip of "A" Main Feed Pump ATC performs IOA's of AOP 1.24.1 and verifies Rx Rapid Power reduction, Control rods A7-37, SG Feed Pump Auto Stop power is < 70%
fail to insert in AUTO. A7-39, SG Feed Pump Disch Flow Hi Start 2nd BOP performs IOA's of AOP 1.24. l and verifies Pump 1FW -P-1 B remains running.
IMF FWMOlB (0 0) A7-40, Steam Generator Feed Pump Disch IMF CRF02A (0 0) TRUE Equalize Press Low ATC refers to ARPs as time permits.
NOTE: SRO enters AOP 1.24.1, Loss of Main IA W AOP 1.24.1, crew verifies Rx power is >52%.
Crew may enter AOP 1.51.1, Feedwater. SRO directs load decrease to < 52% at 5%/minute.
Unplanned Power Reduction.
BOP initiates turbine load reduction; NOTE:
Depress 1st STG IN pushbutton Crew may elect to begin the load
Set EHC SETTER to < 50% power equivalent reduction at 2%/min then increase rate
Set LOAD RATE thumbwheel to 5%/minute to 5%/min.
Depresses GO
,,,. -*<llt(llt A TC reduces Rx power by manually inserting control rods or initiating either a normal or emergency boration.
BOP:
Verifies both condensate pumps and one heater drain pump are running
Verifies A7-6, "Steam Generator Feed Pump Suet Press Low" - NOT IN ALARM
Verifies proper operation of FCV 1FW-150A,B SG Main FW Pump Recirc Vlvs BVPS - 1L16 NRC 1, Rev AG 11 of24
BEAVER VALLE'r . JWER STATION
,- -INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT 4: (continued) BOP stabilizes SG levels by verifying steam flow is less than available feed flow.
BOP verifies SG levels are at or trending to program.
ROLE PLAY: BOP:
5 minutes after being dispatched to
Verifies MFP < 450 amps on each motor investigate lFW-P-lA trip, report
Verifies A7-40, "Steam Generator Feed Pump lFW-P-lA has a severe oil leak, oil Disch Equalize Press Low" - NOT IN ALARM reservoir is extremely low. Crew dispatches an operator to investigate lFW-P-lA trip.
NOTE:
Event 5, SPURIOUS GENERATOR TRIP is to be inserted at Lead Evaluators discretion, however, to ensure Auto Reactor trip signal will be generated, Event 5 will automatically insert when Rx power lowers to <52% (>P9).
EVENTS:
MUG trips with AUTO and MANUAL Rx trip Crew reports MUG trip with automatic Rx trip failure.
Spurious Generator Trip failures. - .,..
TRGSET 4 'FNISPR(3) <52' 1st out, A5-49, Generator Protection Gen trip SRO directs ATC to manually trip the reactor.
IMF GENOl (4 0) followed by trip of lFW-P-lB.
(preloaded) Numerous generator related alarms. SRO directs the crew to perform IOA's for E-0.
EVENTS 6, 7, 8, 9 & 10: SRO enters E-0, Reactor Trip or Safety Injection ATC attempts a manual reactor trip, reports Rx trip (all malfunctions are preloaded) failure/ ATWS condition.
Emerg Boration valve, MOV-lCH-350 SRO enters FR-S.l, Response to Nuclear Power failed closed, Urgent Rod failure. Generation - ATWS. SRO directs operators to perform IOA's ofFR-S.l, Trip of lFW-P-lB, Loss of all AFW and enters FR-S.l from RNO ofE-0, step 1.
due to AUTO start failure of AFW pumps.
"A" Loop, 950 gpm LOCA (Occurs when Rx is locally tripped.)
Auto isolation failure of Reheat steam.
Auto SI actuation failure.
BVPS - 1Ll6 NRC 1, Rev AG 12of24
BEAVER VALLE'r , 0WER STATION J INSTRUCTIONAL GUIDELINES J PLANT STATUS I PROCEDURAL GUIDANCE J EXPECTED STUDENT RESPONSE J EVENTS 6 - 10: (continued)
Critical Task CT-52 (FR-S.1.C):
Crew inserts negative reactivity into When Bank D Rods insert to <100 steps, an Crew performs IOA's ofFR-S.1.
the core by (1) inserting RCCAs Urgent Failure will occur causing the rods to before completing the immediate "lockup" and will quit inserting, requiring the BOP verifies an automatic turbine trip occurred or action steps of FR-S.1 and (2) crew to initiate Emergency Boration via MOV- manually trips Turbine.
initiating Emergency Boration flow 1CH-350, which will also fail closed, requiring before transitioning from FR-S.1. the crew to establish an Alternate Emergency A TC recognizes control rods are not inserting in Boration flowpath via aligning the charging AUTO and places rods in Manual and begins inserting SAFETY SIGNIFICANCE-- Failure to pump suction to the RWST. rods.
insert negative reactivity, under the postulated plant conditions, results in an unnecessary situation in which the reactor remains critical or returns to a critical condition. Performance of the critical task would make the reactor subcritical and provide sufficient shutdown margin to prevent (or at least minimize the power excursion associated with) any subsequent return to criticality.
Failure to insert negative reactivity constitutes "mis-operation or incorrect crew performance which leads to incorrect reactivity control (e.g., failure to initiate emergency boration or manually insert RCCAs ). "
BVPS-1L16 NRC 1, Rev AG 13 of24
BEAVER VALLE'r . uWER STATION I INSTRUCTIONAL GUIDELINES I PU\NTSTATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ]
EVENTS 6-10: (continued)
Critical Task CT-51 (FR-S.1.B) BOP verifies AFW status, Notes there are NO AFW Crew starts AFW pumps before WR pumps runnmg.
SG level is less than 10%.
BOP manually starts 1FW-P-3B motor-driven AFW SAFETY SIGNIFICANCE -- Failure to pump.
start at least the minimum required number of AFW pumps under the BOP manually opens TV-1MS-105A and 105B to start postulated plant conditions can lead to Turbine-driven AFW pump, lFW-P-2 and verifies violation of the RCS emergency stress pump running by A7-7 NOT lit.
limit.
BOP verifies all AFW throttle valves are open.
IMF INH20, IMF INH21 IMFINH36 BOP verifies AFW flow.
(preloaded)
Crew initiates Emergency Boration Flow by:
NOTE:
Verifying at least 1 charging pump is running.
Local operator actions to trip the
Checking Safety Injection is NOT actuated.
reactor will not be effective until after
Aligning Boration path by; the crew has established emergency
Opening MOV-lCH-350, ATC reports MOV-boration flow. lCH-350 has failed closed and won't open.
SRO directs ATC to open MOV-1CH-115B(D)
NOTE: and close MOV-1CH-115C(E).
After the crew has identified MOV-lCH-350 failure and performed ATC aligns charging flow path by adjusting contingency action with emergency FCV-lCH-122 to establish> 75 gpm charging flow.
boration flow verified, the command ATC verifies RCS pressure is< 2335 psig.
can be entered to locally trip the Rx if the crew previously dispatched an operator to locally trip the Rx.
BVPS - 1L16 NRC 1, Rev AG 14of24
BEAVER VALLEt . OWER STATION
[--INSTRUCTIONAL GUIDELINES j-PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6 - 10: (continued)
Crew alerts plant personnel by; ROLE PLAY:
Sounding the standby alarm When requested to open the reactor trip
Announcing a Unit 1 Rx trip w/o SCRAM breakers & trip the rod drive MG set
Dispatching an operator to locally trip the Rx.
output ACBs, insert: TRG! 10 Following commands are preloaded, activate Trigger 10 after the crew has established an alternate Emergency Crew continues in FR-S.1 after dispatching an BOP verifies turbine is tripped.
Boration flowpath via MOV-ICH- operator. BOP verifies MOV-IMS-IOOA, B did not l 15B(D) and verified flow. automatically close and MANUALLY CLOSES 1st Rx trip breaker will open 10 valves, (BB-C).
seconds after actuating Trigger 10. BOP depresses the RESET Pushbutton on the Reheater Controller.
IMF CRF14A (1010)
IMF CRF14B (1015) ATC checks if SI is actuated and reports SI is not IMF CRFOlA (10 30) 1 actuated at this time. _. _
IMF CRFOlB (10 45) 1 (NOTE: Event 8, 950 gjjiftotA, automatically inserts when the Rx is locally tripped, SI actuation ROLE PLAY: may be required at this point, depending upon the When all breakers are open, report crews timing and progression thru FR-S.1.)
actions to the control room.
NOTE:
Event 8, 950 gpm, Loop "A" LOCA will insert when the Rx is locally tripped.
NOTE:
This is a continuous action step, when A TC checks if Rx is subcritical:
the Rx is locally tripped, the crew will
Power range channels < 5%.
return to this step and then transition
IR channels - negative startup rate.
back to E-0, Step 1.
BVPS-1L16 NRC 1, Rev AG 15of24
BEAVER VALLE'\ . JWER STATION
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6-10; (continued) When the Rx is locally tripped. ATC verifies Reactor trip:
SRO returns to E-0, step 1.
Rx trip and bypass breakers open.
Power range indication is < 5%.
Neutron flux is dropping.
BOP verifies Turbine trip:
Throttle OR Governor valves ALL closed.
Main Generator output breakers - open.
Exciter Circuit breaker - open.
AE and DF Busses are energized from offsite. BOP verifies power to AC Emergency Busses:
Using VB-C voltmeters or IPC, verifies AE and DF busses have voltage indicated.
BOP identifies that both emergency busses are energized from offsite power.
-~-
SI will be required due to low RCS pressure. Check SI Status.
Critical Task CT-2 (E-0.D) ATC checks if SI is required:
.'i'.">~
Crew manually actuates at least one
A TC verifies CNMT press < 5psig.
train of SIS-actuated safeguards
A TC verifies PRZR press is not > 1850 psig.
before transition to any ORP.
ATC/BOP verifies Steamline press> 500 psig.
SAFETY SIGNIFICANCE -- Failure to Crew determines SI is required; ATC manually manually actuate SI under the actuates SI by depressing both trains' pushbuttons.
postulated conditions constitutes "misoperation or incorrect crew ATC/BOP, sounds standby alarm, announces reactor performance that leads to degraded trip and safety injection.
ECCS capacity."
BVPS - 1Ll6 NRC 1, Rev AG 16 of24
BEAVER VALLE'r . JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6-10; (continued) Check if SI flow should be reduced:
Crew verifies CNMT radiation, Pressure and Sump level are not consistent PRE-EVENT.
SRO determines SI flow should not be secured.
ATC verifies SI system status:
Charging pumps running - 2 running.
LHSI pumps running - 2 running.
BIT Flow indicated - YES.
BOP verifies AFW status:
If AFW pump automatic start failure
Motor-driven AFW Pumps - ONE RUNNING.
was not previously identified, the crew
Turbine-driven pump:
would identify and start lFW-P-2 and TV-1MS-105A, B open.
1FW-P-3B at this step. A7-7 is NOT LIT, turbine driven pump runnmg.
AFW Throttle Valves all FULL OPEN.
Total AFW Flow is> 370 GPM.
NOTE: List of Attachment 1-K Discrepancies: SRO directs BOP to perform Attachment 1-K.
Evaluation of BOP performing
SIS failed to automatically actuate.
Attachment 1-K begins on page 22.
AFW pumps failed to automatically start.
Reheat steam failed to automatically isolate.
NOTE: If Reheat steam automatic RCS temperature < 54 7°F and dropping due to ATC checks RCS temp. stable at or trending to 547°F:
isolation failure was not previously Safety Injection flow.
A TC verifies no steam release is occurring.
identified, the crew will identify and
A TC verifies Reheat steam is isolated.
isolate Reheat steam at this step by
ATC reduces total feedflow to minimize CID.
closing MOV-lMS-lOOA and B.
BVPS-1L16 NRC 1, Rev AG 17 of24
BEAVER VALLE't . vWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6 - 10; (continued) ATC verifies PRZR isolated:
PORVs - CLOSED (all)
Spray Valves- CLOSED (both)
Safety relief valves - CLOSED (all)
Power to at least one block valve -
AVAILABLE (all available)
Block valves -AT LEAST ONE OPEN (all)
NOTE: A TC checks if RCPs should be stopped:
Depending upon crew timing and
DIP between RCS pressure and highest SG procedure progression, the RCP trip pressure-< 200 PSID (350 PSID ADVERSE criteria may have previously been met, CNMT).
and the RCP's previously tripped.
Criteria for stopping is not met - all RCPs left runnmg.
ATC/BOP checks if any SGs are faulted:
Pressures in all SGs - ANY DROPPING IN AN UNCONTROLLED MANNER OR
ANY SG COMPLETELY DEPRESSURIZED Crew determines NO SG's are faulted.
Crew checks if SG tubes are intact:
Check all SG levels-NONE RISING IN AN UNCONTROLLED MANNER
Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES Crew determines all SG tubes are intact.
BVPS - 1L16 NRC 1, Rev AG 18of24
BEAVER VALLEY. vWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6 - 10; (continued) Hi-Hi Radiation alarm is in due to containment Crew checks if RCS is intact by checking CNMT radiation levels. conditions consistent with pre-event values:
CNMT radiation Incore room, RM-204 and containment,
CNMT pressure RM-215A and 215B in Hi-Hi alarm.
CNMT sump level Containment Pressure is rising.
Containment Sump level is rising. Crew determines the RCS is not intact based on CNMT conditions and verifies HHSI valves, MOV-1SI-867A,B,C,D all open & transitions to E-1.
SRO transitions to E-1, Loss of Reactor or Secondary Coolant.
Crew checks if CREVS should be actuated by checking EITHER of the following:
Control Room Radiation Monitor RM-1RM-218A,B- NOT IN HIGH ALARM.
CIB - HAS NOT OCCURRED.
Crew determines CREVS actuation NOT required.
A TC checks if RCPs should be stopped:
DIP between RCS pressure and highest SG NOTE: pressure-< 200 PSID (350 PSID ADVERSE Depending upon crew timing and CNMT).
procedure progression, the RCP trip
Criteria for stopping is not met - all RCPs left criteria may have previously been met, runnmg.
and the RCP's previously tripped.
ATC checks Recirc Spray Pumps - NONE RUNNING BVPS - 1L16 NRC 1, Rev AG 19 of24
BEAVER VALLE) . 0WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ]
EVENTS 6 - 10; (continued) A TC/BOP checks if any SGs are faulted:
Pressures in all SGs - ANY DROPPING IN AN UNCONTROLLED MANNER OR
ANY SG COMPLETELY DEPRESSURIZED Crew determines NO SG's are faulted.
BOP checks intact SG levels:
Narrow range levels> 31 % (50% Adverse)
BOP controls feed flow to maintain narrow range level between 31 % (50% adverse) and 65%.
BOP checks station instr air hdr press > 100 PSIG.
Crew checks if SG tubes are intact:
Check all SG levels - NONE RISING IN AN UNCONTROLLED MANNER.
Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES.
Crew determines no SG levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all SG tubes are intact.
ATC checks PORV's and block valves:
Power to block valves. (all available)
PORVs-ALLCLOSED.
Block valves-AT LEAST ONE OPEN. (all)
BVPS - 1L16 NRC 1, Rev AG 20 of24
BEAVER VALLE) JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE j EVENTS 6 - 10; (continued) Crew checks if SI flow should be reduced.
NOTE: SI reduction criteria are not met. ATC verifies RCS subcooling is NOT> 46°F (54°F Depending upon procedure progression, Adverse) based on CETC's.
RCS subcooling may be less than ATC verifies RCS subcooling is > Attachment 6-A Attachment 6-A requirements at this requirements.
time. BOP verifies a secondary heat sink exists.(AFW flow
> 370 gpm OR NR level> 31 % (50% Adverse).
NOTE: A TC verifies RCS pressure is not Stable or Rising.
After the crew evaluates SI termination criteria and determines transition to ES- Crew determines that current plant conditions for RCS 1.1 is appropriate or not, at the LE pressure/level, does NOT support SI reduction.
discretion, the Scenario can be terminated.
Classify Event:
SITE AREA EMERGENCY based on EAL SS3 due to a failure of the reactor protection system.
BVPS - 1L16 NRC 1, Rev AG 21 of 24
BEAVER VALLE) . JWER STATION
(-INSTRUCTIONAL GUIDELINES j PLANT STATUS I PROCEDURAL GUIDANCE j EXPECTED STUDENT RESPONSE ]
Attachment 1-K 'Verification of BOP performs the verifications/actions of Attachment Automatic Actions' 1-K 'Verification of Automatic Actions' as follows:
Both EDG's are running. Diesel generators-BOTH RUNNING with no Trouble Alarms, R W pumps running supplying cooling water flow.
Verifies power to both Emergency 4KV AC busses.
Check at least 1 Leak Collection Exhaust fan running, 1VS-F-4A(4B).
Station instrument air header pressure> 100 PSIG.
Reheat steam failed to automatically Ensure Reheat Steam Isolation. Ensure Reheat Steam Isolation:
isolate on the trip, if crew failed to
Verify MOV-lMS-IOOA,B-CLOSED.
identify and close valves in FR-S.1 or
Reset reheater controller.
E-0, BOP will close them at this step.
Close MOV-lMS-204, gland stm spillover vlv.
Verify CCR Pumps - ONE RUNNING with recirc pressure > 100 psig.
Align Neutron Flux Monitoring For Shutdown:
When operable IR channels <lE-10 amp, check SR channels energized.
Transfer NR-lNI-45 recorder to operable source and intermediate range displays.
BVPS - 1L16 NRC 1, Rev AG 22 of24
BEAVER VALLE'T . JWER STATION CINSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I- EXPECTED STUDENT RESPONSE - I Attachment 1-K 'Verification of Verify River Water System In Service:
Automatic Actions' (continued)
RPRW Pumps - TWO RUNNING.
Check CCR Heat EX R W press is > 20 psig.
OR (IF CIB has occurred)
Verify RPRW flow to recirc spray hxs.
Check If Main Steamline isolation required:
CNMT pressure - > 7 PSIG
-OR-
Steamline pressure - < 500 PSIG
-OR-
Steamline pressure high rate of change - ANY ANNUNCIATOR LIT (A7-41, A7-49, A7-57)
Determines steamline isolation is NOT required.
Check CIB And CNMT Spray Status:
Containment press - REMAINED< 11 PSIG.
Verify ESF Equipment Status:
Critical Task CT-2 (E-0.D) Both Trains of SIS failed to automatically
Verify SI status by checking all RED SIS Crew manually actuates at least one actuate, manual actuation successful. marks-LIT.
train of SIS-actuated safeguards
Verify CIA by checking all ORANGE CIA before transition to any ORP. marks-LIT.
Verify FWI by checking all GREEN FWI marks-LIT.
BVPS- 1L16 NRC 1, Rev AG 23 of24
BEAVER VALLE'r . 0WER STATION
[ INSTRUCTIONAL GUIDELINES ] PLANT STATUS I PROCEDURAL GUIDANCE j EXPECTED STUDENT RESPONSE -- [
Attachment 1-K 'Verification of When SR' s are energized, verify Audible indication:
Automatic Actions' (continued)
Verify operating SR Ch selected on Audio Count Rate Channel Selector Switch.
Audible indication functioning properly.
Adjust Multiplier Sw & Volume as necessary.
Start CNMT Hydrogen Analyzers:
Using lOM-46.4.G, gets keys, opens isolation valves (VB-A) and dispatches an operator to continue putting Hydrogen analyzers in service.
Attachment 1-K-COMPLETE Discrepancies: Upon completion, reports any discrepancies to SRO.
SIS failed to automatically actuate
AFW pumps failed to automatically start.
Reheat steam failed to automatically isolate.
BVPS - 1L16 NRC 1, Rev AG 24 of24
A.ppen d"1x D s cenario
outme r 1L16N2 Facility: BVPS Unit 1 Scenario No. 2 Op Test No.: BV1LOT16 NRC Examiners: Candidates: SRO ATC BOP Initial IC-64 (18): 100% power, MOL, Equ. XE Conditions, CB "D"@228 steps, Conditions: RCS boron - 870 ppm. 1FW-P-3A OOS Turnover: Maintain 100% power.
Critical Tasks: 1. CT-18 (E-3.A) Crew isolates ruptured SG
2. CT-19 (E-3.B) Crew establishes/maintains temperature Event Malf. No. Event Type Event Description No.
"C" SG, selected Main steam flow transmitter, lMS-FT-494 1 XMT-MSS039A (I,A) BOP, SRO fails low, requires manual control of feedwater and placing alternate channel in service.
(l,A) A TC, SRO PRZR pressure control transmitter, PT-lRC- 444 fails high, 2 PRS08D (TS) SRO requires closing PORV and manual PRZR pressure control.
(C,A) ATC, SRO 3 RCS03A 22 gpm SG Tube leak on "A" SG. (AOP 1.6.4)
(TS) SRO (R) ATC 4 SG tube leak requires plant S/D IA W AOP 1.51.1.
(N) BOP, SRO 5 RCS03A (M) ALL 650 gpm SGTR occurs on "A" SG during S/D.
6 INH40 (C) ATC, SRO "B" HHSI pump auto start failure on SI.
7 VL V-SGBO 1,02,03 (C) BOP, SRO SG BD isolation failure, requires manual valve closure.
Condenser steam dump valves fail open following cooldown, 8 MSS08C (C) BOP, SRO requires Main steam line isolation.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0---+ E-3 NUREG-1021, Revision 10 FENOC Facsimile Rev AG
Appendix D Scenario Outline 1L16N2 After taking the shift at 100% power with AFW pump, 1FW-P-3A OOS, the "C" SG selected Steam flow transmitter will fail low requiring the BOP to take manual feedwater control IA W AOP 1.4.1, Process Control Failure. After the plant has been stabilized, the SRO will transition to the instrument failure procedure and direct placing the alternate steam flow channel in service, Feedwater control will then be returned to automatic.
The controlling PRZR pressure channel, PT-1 RC-444 will drift high causing RCS pressure to lower due to the pressurizer spray valves and a PORV opening. The crew will initially respond IA W AOP 1.4.1, identify the failure and close the spray valves and PORV, the SRO will then transition to lOM-6.4.IF, attachment 2 to address the failed channel. The A TC controls PRZR pressure by manually operating the PRZR heaters and spray valves, or manual control of the PRZR pressure master controller. The SRO will address applicable TS entered due to the instrument failure.
Subsequently, a 22 gpm SG tube leak will develop on the "A" SG. AOP 1.6.4 will be entered and the leak will be quantified. Due to the leak rate, AOP 1.6.4 will provide direction to enter Mode 3 IAW AOP 1.51.1. The SRO will address Technical Specifications which also will require Mode 3 entry.
The crew will initiate an emergency shutdown IA W AOP 1.51.1, when Rx power is reduced to <94%, the tube leak will become a 650 gpm tube rupture. The crew will identify degrading plant parameters and the SRO will direct a pre-emptive reactor trip and enter E-0.
An automatic Safety Injection will occur upon the Rx trip, the "B" HHSI pump will fail to automatically start on the SI signal, the ATC will identify the failure and manually start the pump. Additionally, the steam generator blowdown system will fail to automatically isolate requiring the BOP to identify and isolate the SG Blowdown system.
The crew will proceed thru E-0, perform diagnostics and determine that indications of a SGTR exist, the SRO will transition to E-3 to take actions to address the tube rupture.
After the crew identifies the "A" SG as the ruptured SG and isolates it, a target temperature will be determined and a cooldown commenced. Two condenser steam dump valves will fail open during the cooldown, when the cooldown to target temperature is reached, the BOP will identify the failed open steam dumps and report it to the crew. The SRO will direct the BOP to manually close the Main steam line isolation valves, requiring the BOP to stabilize RCS temperature using the "B" and "C" SG atmospheric steam dump valves at which time the scenario will be terminated.
Expected procedure flow path is E-0 ~ E-3 NUREG-1021, Revision 10 FENOC Facsimile Rev AG
BEAVER VALLEY .--0WER STATION INITIAL CONDITIONS: IC-64(18): 100% power, MOL, Equ. XE Conditions, CB "D" @ 228 steps, RCS boron - 870 ppm.
Use HTML, 1Ll6N2.HTM, Initialize into specified IC and insert preloads per the HTML.
ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP 1FW-P-3A CS in PTL 1FW-P-3A CS tagged Normal Splash w/ Full Power Screen, on VB-B EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 1FW-P-3A OOS, pump bearing replacement Yesterday I 1800 3.7.5, Condition B SHIFT TURNOVER INFORMATION
1. 100% power for the past month, MOL equilibrium conditions, shift goal is to maintain current power.
SCENARIO SUPPORT MATERIAL REQUIRED ""-
PROCEDURESNEEDED
1. MOL Reactivity Placard E-0
2. Protected Train "B" Placard E-3
3. Safety Status PNL lights LIT for "A" AFW lOM-46.4.G
3. lFW-P-2 aligned to A hdr placard 6 IF, Attach 2 24 IF, Attach 3 Attachment 1-K AOP 1.4.1 AOP 1.6.4 AOP 1.51.1 BVPS-1L16 NRC 2, Rev AG 3 of21
BEAVER VALLEY ,-OWER STATION
[ INSTRUCTIONAL GUIDELINES [ PLANT-STATUS I P-ROCEi5URAL GUIDANCE [ EXPECTED STUDENT RESPONSE [
Assign shift positions SRO: _ _ _ _ _ _ _ __
ATC:- - - - - - - - -
BOP: _ _ _ _ _ _ _ __
Conduct a shift turnover with oncoming Simulator frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.
When the shift turnover is completed, Simulator running. Crew assumes control of the unit.
place the simulator to RUN and commence the scenario.
BVPS-1L16 NRC 2, Rev AG 4 of21
BEAVER VALLEY ,-OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ]
EVENT 1:
FT-IMS-494, Steam Flow Trans fails low. BOP reports unexpected SG alarms.
CH 3, "C" SG selected feedwater flow FCV-lFW-498, IC SG MFRV modulates shut BOP identifies "C" SG level is lowering in Automatic.
transmitter, FT-IMS-494 fails low. lowering SG level. IAW AOP 1.41, BOP takes Manual control ofFCV-ALARMS: 1FW-498 and establishes control of SG level.
IMF XMT-MSS039A (0 0) 0 45 A7-58, Loop C Feedwater flow> Steam Flow A 7-61, 1C SG Level Deviation SRO enters AOP 1.4.1, Process Control Failure, and directs BOP to place FCV-lFW-498 controller to Manual and establish control of SG level.
SRO provides a control band of 65 +/-5% and Rx trip criteria of 25% low/85% high for manual feedwater level control.
SRO transitions to Feedwater System Instrument failure procedure, lOM-24.4.IF, attachment 3.
SRO enters Instrument Failure procedure, 1OM- Crew identifies steam flow channel, FT- I MS-494, has 24.4.IF, Attachment 3. failed low.
SRO directs BOP to take manual control of FCV-lFW-498 and restore SG level to normal.
SRO directs BOP to transfer C SG control to CH. 4.
BOP places FC-lFW-498 (SF) in the FM 495 pos.
BOP places FC-lFW-498 (FF) in the FM 496 pos.
When SG level is stabilized within normal range, SRO directs BOP to place FCV-lFW-498 in AUTO.
SRO contacts I&C to take actions per Attachment 3 of Proceed with next event at LE IF procedure and to investigate failed steam flow discretion. transmitter.
BVPS-1L16 NRC 2, Rev AG 5 of21
BEAVER VALLE'r . 0WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE ] EXPECTED-STU5§J(RESPONSE I EVENT2:
PR-lRC-444 fails high PT-1 RC-444 fails high.
IMF PRS08D (0 0) 2500 15 A4-10, Pressurizer Control High Pressure Dev, A TC recognizes pressurizer pressure related alarms followed by numerous Pressurizer pressure and announces to the crew.
related alarms.
PCV-1RC-445A & 445B PRZR spray valves modulate open. Crew identifies PT-lRC-444 failure.
PORV, PCV-1RC-455C opens.
All PRZR heaters turn off.
RCS pressure decreases.
NOTE: IA W AOP 1.4.1; Part B IOA's, ATC responds to A TC is required to manually control PT-1 RC-444 failure by:
RCS pressure for remainder of
Closing PCV-1RC-455C.
scenano.
Placing Master Pressure control in Manual and adjusting demand to < 40%.
Checking pressure trending to 2235 psig.
SRO provides a control band of2235 +/-15psig and Rx trip criteria of 2100 psig low/2340 psig high for manual press control.
After A TC stabilizes PRZR pressure, SRO transitions to lOM-6.4.IF, Attachment 2 SRO enters Instrument Failure procedure, Crew identifies PRZR Pressure control transmitter, lOM-6.4.IF, Attachment 2. PT-1 RC-444 has failed high.
BVPS-1L16 NRC 2, Rev AG 6 of21
BEAVER VALLE"! . OWER STATION I INST-RUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPON-SE I EVENT 2: (continued) SRO directs ATC to manually control PRZR press.
ATC places CS for PCV-1RC-455C to close.
NOTE: A TC places Master Pressure Control in manual and PORV 455C remains operable as manually operates PRZR Spray valves, PCV -1 RC-manual operation is still available. 455A, Band all PRZR heaters as necessary to control RCS pressure.
NOTE: SRO evaluates Technical Specifications:
If DNB Tech Spec entry not identified by the crew at this time, ask as a 3.4.l (RCS DNB Parameters, RCS press< 2218 psia) follow-up question. Condition A: restore RCS pressure within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
3.3.4 (Remote Shutdown System) Table B 3.3.4-1 Function 2.a: LCO met if PT-lRC-455 is operable.
Proceed with next event at LE discretion EVENT3: SG "A" 22 gpm Tube Leak A TC notes Radiation Monitor Alarms.
22 gpm "A" SG Tube Leak. A4-88, Stm Gen N-16 Monitor Alert/High Trbl IMF RCS03A (0 0) 30 A4-71; Radiation Monitoring High BOP reviews ARPS, A4-72; Radiation Monitoring High-High N-16 ARP directs entry into AOP 1.6.4.
ROLE PLAY: SG Blowdown Sample, RIS-SS-100 High 2 minutes after being dispatched to the Air Ejector, RIS-SV-100 is High-High Crew dispatches an operator to the N-16 monitor to N-16 monitor: report "A" SG tube BD-101 Alert & Hi alarms on SPING determine leakrate and affected SG.
leakage indicates full scale.
SRO estimates initial primary-to-secondary leakrate SRO enters AOP 1.6.4, Steam Generator Tube using radiation monitor alarm setpoints IA W AOP Leakage. 1.6.4.
Based on existing RM alarms, estimates > 75 gpd.
BVPS - 1L16 NRC 2, Rev AG 7 of21
BEAVER VALLE) . 0WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT 3: (continued) A TC controls charging flow as necessary to maintain programmed PRZR level using FCV-lCH-122 and HCV-lCH-186.
Crew determines PRZR level can be maintained with normal charging flow.
Crew identifies the affected SG via N-16 field report.
ATC verifies VCT lvl maintained by normal makeup.
Crew verifies RCS temperature is stable.
A TC verifies FCV -1 CH-122 is maintaining constant PRZR level in AUTO or places FCV-lCH-122 in MAN and controls charging flow to maintain a constant PRZR level.
Crew checks VCT level trend, determines that VCT level is DROPPING at <1.8%/min. and >0.7%/min.
Crew determines leak.rate is > 10 gpm & < 25 gpm.
SRO informs SM of leak rate.
Crew checks Unit Shutdown Requirement to Mode 3.
SRO refers to Attachment 1, "SG Tube Leak Monitoring."
IA W with AOP 1.6.4, SRO determines plant shutdown is required; Be <= 50% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and MODE 3 entry within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
SRO evaluates Tech Specs for leakage.
TS 3.4.13 Condition B, Primary to secondary leakage not within limit, be in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
BVPS-1L16 NRC 2, Rev AG 8 of21
BEAVER VALLE'r, OWER STATION c=Ti'JSTRUCTIONAL GUIDELINES J PLANT STATUS I PROCEDURAL GUIDANCE J EXPECTED STUDENT RESPONSE --J EVENT 3: (continued) Crew verifies Safety Injection is NOT required due to PRZR level at or trending to program level with FCV-1CH-122 in AUTO.
Crew checks Condenser Air Ejector Rad Monitor, reports RM-lSV-100 is in HIGH-HIGH alarm.
BOP verifies Condenser Air Ejector discharge has aligned to CNMT, TV-lSV-lOOA- OPEN and TV-lSV-lOOB is CLOSED.
SRO directs the crew to establish Mode 3 conditions using AOP 1.51.1 and continues in AOP 1.6.4.
EVENT4:
Unplanned Power Reduction IA W AOP SRO enters AOP 1.51.1, Unplanned Power SRO directs A TC and BOP to reduce power to take 1.51.1. Reduction. the plant offline IA W AOP 1.51.1.
Crew commences Power Reduction.
BOP initiates turbine load reduction:
Depress 1st STG IN pushbutton.
Set EHC SETTER to desired load.
Set LOAD RATE thumbwheel to 2%.
Depresses GO.
Maintains power factor within limits during SID.
BVPS - 1L16 NRC 2, Rev AG 9 of21
BEAVER VALLEY , OWER STATION
[~INSTRUCTIONAL GUliSEllNES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE =1 EVENT 4: (continued) Crew commences Power Reduction.
ATC initiates Normal boration IA W Attachment 1:
(2% per minute power reduction).
Places lMU CS to STOP for>l sec.
Places mode selector switch, 43/MU to BORATE.
Sets FCV-1CH-113A to flow rate desired.
Sets YIC-1 CH-113, BA integrator, to total volume in gals of BA to be added per reactivity plan.
Resets YIC-lCH-113.
Verifies YIC-lCH-168 is set to "zero", then depresses reset.
Places lMU CS to START, then verifies inservice BA pump starts, FCV-1CH-l 13B opens and boric acid flow is indicated on FR-lCH-113.
Adjusts FCV-1CH-113A setpoint as desired to control boration flowrate.
Crew sounds the standby alarm and announces a Unit 1 rapid power reduction.
ATC places all PRZR heaters to ON.
ATC verifies rod control in AUTO and maintaining Tavg within+/- 5F of Tref.
NOTE: Event 5 will automatically BOP prepares to perform Attachment 3 to transfer initiate when reactor power is reduced busses to the offsite sources.
to <94% (approx. 6% power reduction).
BVPS-1L16 NRC 2, Rev AG 10of21
BEAVER VALLE't , OWER STATION j INSTRUCTIONAL GUIDELINES j PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE -]
EVENTS:
650 gpm SGTR on "A" SG PRZR level and pressure decreases. ATC reports degrading primary plant conditions.
TRGSET 4 'FNISPR(3)<=94' A4-12, PRZR Control Low press deviation.
IMF RCS03A (4 0) 650 120' followed by; SRO directs ATC to manually trip the reactor and (preloaded) A4-11, PRZR Control press low. initiate Safety Injection.
A4-4, PRZR Control low level deviation. SRO directs the crew to perform IOA's for E-0.
EVENTS 6, 7, & 8: "B" HHSI pump auto start failure on SI. A TC verifies Reactor trip:
(all preloaded to occur on the reactor SG Blowdown isolation failure.
Rx trip and bypass breakers open.
trip) Condenser stm dump fails open following CID.
Power range indication is < 5%.
Neutron flux is dropping.
SRO enters E-0, Reactor Trip or Safety Injection BOP verifies Turbine trip:
Throttle OR Governor valves ALL closed.
Main Generator output brks - open.
Exciter Circuit breaker - open.
AE and DF Busses are energized from offsite. BOP verifies Power to AC Emergency Busses:
Using VB-C voltmeters or IPC, verifies AE and DF busses have voltage indicated.
BOP identifies that both emergency busses are energized from offsite power.
SI automatically actuated. Check SI status:
A TC reports SI automatically actuated and manually actuates SI by depressing both trains' pushbuttons.
A TC/BOP, sounds standby alarm, announces reactor trip and safety injection.
BVPS-1L16 NRC 2, Rev AG 11 of21
BEAVER VALLE'r. vWER STATION I INSTRUCTIONALGUllSELINES -, PLANT STATUS I PROCEDURAL GUIDANCQ EXPECTED STUDENT RESPONSE .. -,
EVENTS 6, 7, & 8: (continued) Check if SI flow should be reduced.
Verifies that the "A" SG level is rising in an uncontrolled manner.
SRO determines SI flow should not be secured.
ATC verifies SI system status:
IMF INH40 (preloaded) lCH-P-lB auto start failure.
Charging pumps running - identifies only 1 HHSI pump is running and manually starts lCH-P-lB.
LHSI pumps running - 2 running.
BIT Flow indicated - YES.
1FW-P-3A OOS on turnover. BOP verifies AFW status:
Motor-driven AFW Pumps - ONE RUNNING.
Turbine-driven pump; TV-1MS-105A, B open.
A7-7 is NOT LIT, turbine driven pump runnmg.
AFW Throttle Vlvs all FULL OPEN.
Total AFW Flow - > 370 GPM.
NOTE: List of Attachment 1-K Discrepancies: SRO directs BOP to perform Attachment 1-K.
Evaluation of BOP performing * "B" HHSI pump failed to auto start.
Attachment 1-K begins on page 19.
SG Blowdown failed to isolate.
ATC checks RCS temp. stable at or trending to 547°F:
RCS temperature (Tavg) < 547°F and dropping
A TC verifies no steam release is occurring.
due to Safety Injection flow.
A TC verifies Reheat steam is isolated.
A TC reduces total feedflow to minimize CID.
BVPS-1L16 NRC 2, Rev AG 12 of21
BEAVER VALLE) , JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE - - - ]
EVENTS 6, 7, & 8: (continued) ATC verifies PRZR isolated:
PORVs - CLOSED. (all)
Spray Valves-CLOSED. (both)
Safety relief valves - CLOSED. (all)
Power to at least one block valve -
AVAILABLE. (all available)
Block valves-AT LEAST ONE OPEN. (all)
ATC checks if RCPs should be stopped:
DIP between RCS pressure and highest SG pressure is not< 200 PSID.
Criteria for stopping is not met - all RCPs left runmng.
ATC/BOP checks if any SGs are faulted:
Pressures in all SGs - ANY DROPPING IN AN UNCONTROLLED MANNER.
OR
ANY SG COMPLETELY DEPRESSURIZED.
Crew determines NO SG's are faulted.
Crew checks if SG tubes are intact:
Check all SG levels - NONE RISING IN AN UNCONTROLLED MANNER.
Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES.
Crew determines "A" SG level is rising in an uncontrolled manner and verifies HHSI valves, MOV-1SI-867A,B,C,D all open & transitions to E-3.
BVPS-1L16 NRC 2, Rev AG 13 of21
BEAVER VALLEY , 0WER STATION CJNSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, & 8: (continued) SRO transitions to E-3, Steam Generator Tube SRO directs STA to commence control room Rupture. ventilation actions. Refer to Attachment 4-F.
ATC checks if RCPs should be stopped:
DIP between RCS pressure and highest SG pressure - <200 PSID.
Crew determines criteria for stopping RCPs is not met.
"A" SG ruptured Crew notes that "A" SG was previously identified as the ruptured SG based upon unexpected NR level rise.
NOTE:
BOP verifies "A" SG NR level >31 %.
AFW flow may have been preemptively
SRO directs BOP to isolate feed flow to isolated after level rose to > 31 %. ruptured SG.
BVPS-1Ll6 NRC 2, Rev AG 14 of21
BEAVER VALLEY, 0WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENTRESPONSE - I EVENTS 6, 7, & 8: (continued) ATC/BOP isolates flow from the ruptured SG.
NOTE:
Critical Task: CT-18 (E-3.A) The items underlined in the right column are the BOP verifies "A" SG atmospheric steam dump, PCV-Crew isolates feed flow into and components that are required to be 1MS-10 lA, in MANUAL and closed.
steam flow from the ruptured SG verified/manipulated to confirm isolation of a and directs operator to close isolation ruptured SG. BOP verifies residual heat removal valve- CLOSED.
valve(s) operated from outside of the control room before a transition to Isolate ruptured SG to turbine driven AFW pump.
ECA-3.1 occurs.
Crew identifies that the steam supply from the "A" SG, lMS-15 is open.
SAFETY SIGNIFICANCE -- Failure to
BOP reports B motor-driven AFW pp running.
isolate the ruptured SG causes a loss of
BOP closes MOV-lMS-105, AFW Turbine differential pressure between the Steam Isol Vlv.
ruptured SG and the intact SGs. Upon a loss of differential pressure, the crew Crew dispatches an operator to locally isolate steam must transition to a contingency supply valve from "A" SG, lMS-15 and to:
procedure that constitutes an incorrect
Verify open steam supply valve from "B" SG, performance that necessitates the crew lMS-16.
taking compensating action which
Unlock and open steam supply valve from "C" complicates the event mitigation SG, lMS-17.
strategy.
If required, reopens MOV-lMS-105 starting lFW-P-2.
ROLE PLAY:
5 minutes after being dispatched to Verify closed, ruptured SG blowdown isolation valve.
locally isolate lMS-15 and open lMS-
BOP identifies TV-lBD-lOOA is NOT 17, insert CLOSED, and valve failed to manually close.
IRF FWM34 (0 0) 0
SRO directs BOP to CLOSE TV-1BD-101Al.
IRF FWM36 (0 0) 100
BOP CLOSES TV-1BD-101Al.
then report 1MS-15 is CLOSED Close ruptured SG Pre-non-return drain isol valve.
lMS-16 is OPEN
BOP closes TV-lMS-11 lA.
& lMS-17 was OPENED.
BVPS - 1L16 NRC 2, Rev AG 15of21
BEAVER VALLE'r . OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 6, 7, & 8: (continued) BOP closes ruptured SG main steam trip, bypass, and non-return valves; Critical Task: CT-18 (E-3.A)
TV-1MS-101A trip (continued)
NRV-lMS-lOlA non return BOP checks ruptured SG pressure is> 380 PSIG.
BOP initiates RCS cooldown:
Determine required core exit temperature as a function of ruptured SG pressure.
WHEN PRZR pressure < 1950 PSIG, THEN blocks low steamline pressure SI.
Checks MSIVs -AT LEAST ONE OPEN
("B" & "C" SG MSIV s are open).
Verifies Condenser is available.
Places Steam dump controller in MANUAL.
Selects STM PRESS Mode, stm dump control.
Defeats TAVG interlock when necessary.
Gradually raises steam dump demand to obtain a maximum cooldown rate.
Verifies Core Exit TCs (CETC's) are reducing.
When CETC's (average of five hottest), Less than REQUIRED Core exit temp, BOP stops RCS cooldown and maintains CETC's <REQUIRED TEMPERATURE.
BVPS-1L16 NRC 2, Rev AG 16of21
BEAVER VALLE't . JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I- EXPECTEDSTUDENTRESPONSE - - -I EVENT 8: BOP recognizes RCS cooldown has not stopped and that two condenser steam dump valves have not Condenser steam dump valves fail open closed.
following cooldown.
IMF MSSOSB (7 0) 100 SRO directs BOP to isolate Main Stearn lines and IMF MSSOSC (7 0) 50 (preloaded) stabilize RCS temp using Atmospheric strn dumps.
Critical Task: CT-19 (E-3.B) BOP closes TV-1MS-101B and TV-1MS-101C.
Crew establishes/maintains an RCS temperature so that transition from BOP manually controls PCV-lMS-lOlB and E-3 does not occur because the RCS PCV -1MS-101 C to stabilize RCS temperature.
temperature is in either of the following conditions:
Too high to maintain minimum required subcooling for subsequent RCS depressurization.
OR Below the RCS temperature that causes a red or orange path challenge to Sub-criticality or Integrity CSF.
SAFETY SIGNIFICANCE -- Failure to establish and maintain the correct RCS temperature during a SGTR leads to a transition from E-3 to a contingency procedure, which constitutes an incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy.
BVPS - 1L16 NRC 2, Rev AG 17 of 21
BEAVER VALLE'r . JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE - I EVENTS 6, 7, & 8 (continued) BOP checks intact SG levels:
Narrow range level> 31 %.
Controls feed flow to maintain narrow range level between 25% and 65%.
ATC checks PRZR PORVs and block valves:
Power to block valves. (all available)
PORVs - CLOSED. (all)
Block valves-AT LEAST ONE OPEN. (all)
A TC resets SI, CIA and CIB.
NOTE BOP checks if RCS cooldown should be stopped:
If cooldown not previously completed,
When CETCs (average of five hottest) -
Crew will identify failed open Stm <REQUIRED TEMPERATURE dump at this point and take previously scripted contingency actions to isolate BOP stops RCS cooldown and maintains CETCs the main steam lines. <REQUIRED TEMPERATURE.
Terminate scenario when the crew has isolated the main steam lines in response to failed open condenser steam dumps and stabilized RCS temperature using the Atmospheric steam dumps.
Classify Event:
ALERT per F Al, due to a LOSS of RCS Barrier because of a RUPTURED SG resulting in an SI Actuation.
BVPS-1L16 NRC 2, Rev AG 18 of21
BEAVER VALLE'r . JWER STATION I --INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of BOP performs the verifications/actions of Attachment Automatic Actions' 1-K 'Verification of Automatic Actions' as follows:
Both EDG's are running. Diesel generators - BOTH RUNNING with no Trouble Alarms, RW pumps running supplying cooling water flow.
Verifies power to both Emergency 4KV AC busses.
Check at least 1 Leak Collection Exhaust fan running, 1VS-F-4A(4B).
Station instrument air header pressure> 100 PSIG.
Ensure Reheat Steam Isolation:
Verify MOV-lMS-lOOA,B-CLOSED.
Reset reheater controller.
Close MOV-lMS-204, gland stm spillover vlv.
Verify CCR Pumps - ONE RUNNING with recirc pressure > 100 psig.
Align Neutron Flux Monitoring For Shutdown:
When operable IR channels <lE-10 amp, check SR channels energized.
Transfer NR-lNI-45 recorder to operable source and intermediate range displays.
BVPS-1L16 NRC 2, Rev AG 19 of21
BEAVER VALLE'v. OWER STATION j INSTRUCTIONAL GUIDELINES j PLANT STATUS I PROCEDURAL GUIDANCE j EXPECTED STUDENT RESPONSE ---]
Attachment 1-K 'Verification of Verify River Water System In Service:
Automatic Actions' (continued)
RPRW Pumps-TWO RUNNING.
Check CCR Heat EX RW press is> 20 psig.
OR (IF CIB has occurred)
Verify RPRW flow to recirc spray hxs.
Check If Main Steamline isolation required:
CNMT pressure - > 7 PSI G
-OR-
Steamline pressure - < 500 PSIG
-OR-
Steamline pressure high rate of change - ANY ANNUNCIATOR LIT (A7-41, A7-49, A7-57)
Determines steamline isolation is NOT required.
~*'*'¢'*~~.,,
Check CIB And CNMT Spray Status:
Containment press - REMAINED< 11 PSIG.
Verify ESF Equipment Status:
"B" HHSI pump failed to automatically start
Verify SI status by checking all RED SIS upon the SIS actuation signal, manual start was marks-LIT.
successful.
Verify CIA by checking all ORANGE CIA SG Blowdown failed to isolate on CIA, marks-LIT.
redundant valves closed.
Verify FWI by checking all GREEN FWI marks-LIT.
BVPS - 1L16 NRC 2, Rev AG 20 of21
BEAVER VALLE't , OWER STATION I- INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of When SR's are energized, verify Audible indication:
Automatic Actions' (continued)
Verify operating SR Ch selected on Audio Count Rate Channel Selector Switch.
Audible indication functioning properly.
Adjust Multiplier Sw & Volume as necessary.
Start CNMT Hydrogen Analyzers:
Using lOM-46.4.G, gets keys, opens isolation valves (VB-A) and dispatches an operator to continue putting Hydrogen analyzers in service.
Attachment 1-K-COMPLETE Discrepancies: Upon completion, reports any discrepancies to SRO.
"B" HHSI pump failed to auto start.
SG Blowdown failed to isolate.
~..~ .....
BVPS-1L16 NRC 2, Rev AG 21of21
A,ppen d"1x D s cenano
. 0 utrme 1L 16N3 I Facility: BVPS Unit 1 Scenario No. 3 Op Test No.: BV1LOT16 NRC Examiners: Candidates: SRO ATC BOP Initial IC-66(5): ~5% power, BOL, CB "D"@ 109 steps, RCS boron - 1750 ppm.
Conditions:
Turnover: Raise Rx power and place turbine online.
Critical Tasks: 1. CT-1 (E-0.A) Crew manually trips the reactor.
2. CT-24 (E-0.C) Energize 1 AC emer bus
3. CT-9 (E-0.L) Establish flow from RPRW pump Event Malf. No. Event Type Event Description No.
(R) ATC 1 Power increase to> P-10.
(N) SRO "B" Bypass feed regulating valve fails asis in Auto. Requires 2 FWM08B (C,A) BOP, SRO manual control CHS22 Failure of FCV-1 CH-122 controller, requires manual control 3 (C,A) ATC, SRO X06D088M of PRZR lvl.
4 (N) BOP, SRO Startup standby Turbine plant River water pump (C,A) BOP, SRO 5 NIS08B N-42 Instrument power fuse blown. (>P6 and< PIO)
(TS) SRO 6 XMT-CNM004A (TS) SRO CH 2, CNMT Pressure transmitter fails High, PT-lLM-lOOB 7 SIS I OB (M) All Inadvertent Train "A" SI with Rx trip failure.
8 (C,A) ATC, SRO Manual Rx trip EPS04E, 04F Loss of lAE and lDF 4kv Busses on Rx trip w/ EDG auto 9 (C) BOP, SRO INH53, 54 start failures.
Reactor plant River water pump auto start failures on 10 INH32, 33 (C) BOP, SRO Sequencer, requires manually starting WR-P-lA and lB.
Letdown isolation on SI unable to be recovered due to failure 11 CHS21A (C) ATC, SRO of LCV -1 CH-460A, requires Excess letdown.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E ES-1.1 NUREG-1021, Revision 10 FENOC Facsimile Rev AG
Appendix D Scenario Outline 1L 16N3 The crew will assume the shift at approximately 5% (4.8%) power with instructions to raise power to place the turbine online IA W the reactivity plan and I OM-52.4.B. The ATC will initiate a dilution and withdraw control rods.
After the power has raised to >5.5%, "B" SG Bypass Feed regulating valve will fail as is in Auto, failure will become evident as Rx power continues to be raised, the BOP will be required to identify the malfunction and take action to control FCV-I FW-489 in manual IA W AOP I .4. I Process Control Failure.
Additionally, at >5.5% Rx power, FCV-ICH-I22 will fail closed in Auto, the ATC will be required to identify the failure and manually control FCV-ICH-I22 IAW AOP I .4.I, to maintain PRZR level.
A field operator will then report that the "A" Turbine Plant River Water pump, has a significant seal leak and needs to be shutdown. IA W I OM-30.4.N, Standby Turbine Plant River Water Pump Startup, the BOP will startup I WR-P-6B and shutdown I WR-P-6A.
An instrument power fuse will then blow for Power Range Nuclear instrument, N-42. The crew will identify the N-42 blown fuse failure and the SRO will enter AOP I .2. IC, Power Range Channel Malfunction, and direct the BOP to remove the failed channel from service. The SRO will address Tech Specs for the failed instrument.
After the crew has removed N42 from service, CH 2 containment pressure transmitter, PT-ILM-IOOB fails high. The SRO will enter IOM-1.4.IF and review the Technical Specifications. The SRO will then contact I&C to trip the applicable bistables.
After the SRO has determined the appropriate Technical Specifications for the CNMT pressure channel, a spurious Train "A" Safety Injection signal will occur with an automatic Rx trip failure. The crew will recognize the automatic Rx trip failure and the SRO will direct the ATC to manually trip the Rx and perform the IOA's of E-0.
Upon the Rx trip, both Emergency 4Kv buses will deenergize with auto start failures of both Emergency Diesel Generators. The BOP will start an EDG IA W E-0 IOA's (RNO actions).
Upon EDG start, each respective River water pump will fail to auto start via sequencer, the crew will identify the auto start failure and start each RW pump.
The crew will continue progressing thru E-0 and perform diagnostic steps and determine that no accident has occurred and plant conditions support Termination of Safety Injection and transition to ES-I. I. LCV-1CH-460A fails closed upon the SI signal and will not be able to be reopened requiring the crew to place Excess letdown in service.
The scenario will be terminated when the crew establishes Excess letdown flow.
Expected procedure flow path is E-0 ~ ES-1. I NUREG-1021, Revision 10 FENOC Facsimile Rev AG
BEAVER VALLE'r, 0WER STATION INITIAL CONDITIONS: IC-66(5): 4.8% power, BOL, Start up in progress, CB "D" @ 109 steps, RCS boron - 1750 ppm.
Use HTML, 1L16N3.HTM, Initialize into specified IC and insert preloads per the HTML.
ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP Normal Splash w/ MID Power Screen, on VB-A EQUIPMENT STATUS DATEffIME OOS TECHNICAL SPECIFICATION(S)
SHIFT TURNOVER INFORMATION
1. 4.8% power, BOL, plant startup in progress, shift goal is to raise power IA W the reactivity plan and make preparations for turbine roll.
2. SM requests the crew use "Alternate Dilute" method for required dilutions.
3. Procedure package to include, Reactivity plan, 1OM-52.4.B (placekept), 1OM-7.4.N .
.<*- -- ~---
SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED
1. BOL Reactivity Placard E-0
2. 1OM-52.4B, place kept up to step 11. ES-1.1
3. Reactivity plan lOM-7.4.H
4. lOM-7.4.N lOM-30.4.N
5. Protected Train "B" Placard lOM-46.4.G
6. Aux steam from Unit 2 placard posted 1 IF, Attach 1 Attachment 1-K AOP 1.2.IC AOP 1.4.1 AOP 1.36.2 BVPS-1L16 NRC 3, Rev AG 3 of24
BEAVER VALLEY , OWER STATION L-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Assign shift positions SRO:- - - - - - - - -
ATC: _ _ _ _ _ _ _ __
BOP: _ _ _ _ _ _ _ __
Conduct a shift turnover with oncoming Simulator frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.
When the shift turnover is completed, Simulator running. Crew assumes control of the unit.
place the simulator to RUN and commence the scenario.
BVPS-1L16 NRC 3, Rev AG 4 of24
BEAVER VALLE'r. OWER STATION
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS l, 2 & 3: ATC commences raising reactor power to between 10 and 14%.
Normal Plant Startup, Rx Power increase to 10-14% to support Turbine Startup.
ATC initiates control rod withdrawal and dilution NOTE: IAW lOM-7.4.N and the reactivity plan.
Reactivity plan requires 300 gallons dilution and 9 rod steps to raise power
Places lMU control switch to STOP for greater to 10%. Crew may elect to add total than 1 second.
dilution volume in multiple steps.
Place 43/MU Control switch in ALT DIL.
Set AM-lCH-114, Blender Total Flow Set Point NOTE: to desired flow rate.
Events 2 & 3 are triggered to actuate on
Set YIC-1CH-168A, Blender Output Integrator, to rising power at 5.5% on N43. Both desired dilution quantity.
events will enter at 5.5% but event 3
Reset YIC-1CH-168A.
will be more obvious sooner then event
Place lMU Control Switch to START.
2. It is expected that operator response
Verify FCV-1CH-114B opens.
to event 3 will be complete prior to
Verify FCV-1CH-113B opens.
event 2 symptoms being observable.
Verify PG water to Blender flow rate indicated on FR-lCH-113.
When YIC-1CH-168A reaches setpoint, verify dilution automatically stops.
When Rx Power increases to > 10%. Status lights on Panel 176 actuate at 10%. ATC verifies P-10 bistables lit on Panel 176.
BVPS-1L16 NRC 3, Rev AG 5 of24
BEAVER VALLE'r . OWER STATION
[ - - INSTRffCTTONALGUTDELINES--T-PT.fa:NT STATUS I PROCEDURAL GUIDANCE [ EXPECTED STUDENT RESPONSE [
Status Light PNL 176, DlO, - 'INT RNG RX ATC blocks the IR High Flux Trip AND IR High Flux TRIP BLOCKED' - LIT. Rod Stop by placing the IR BLOCK TRAIN and TRAIN B control switches to the BLOCK position and verifies status pnl 176, D 10 is LIT.
Status Light PNL 176, B 12, - 'PW RA LO SET ATC blocks the Power Range Low Overpower Trip by R TRIP BLKD' - LIT. placing the PR BLOCK TRAIN A and TRAIN B control switches to the BLOCK position and verifies status pnl 176, B12 is LIT.
A TC selects highest power ranges on NR-45.
EVENT3:
(Automatically occurs at 2: 5.5% pwr) FCV-lCH-122 closes, Valve demand increases ATC notes alarm and notifies crew.
FCV-lCH-122 fails closed in Auto A3-58, Charging Pump Discharge Flow Hi-Lo ATC notes problem with PRZR level control, IAW A3-115 Regen Hx LID temp Hi (dependent on AOP 1.4.l, Process Control Failure, takes manual IMF CHS22 (4 0) 0 20 operator response) control ofFCV-lCH-122 and informs SRO.
PRZR level decreases. BOP reviews ARP.
NOTE: SRO may enter lOM-7.4.IF, attachment 2. SRO directs ATC to restore PRZR level to program ATC is required to manually control value using FCV-1 CH-122 in manual.
PRZR level for remainder of scenario.
Due to manual control of PRZR level, SRO establishes a level control band of program level +/-5% and Rx trip criteria of 5% low and 90% high.
SRO notifies I&C to investigate.
BVPS-1L16 NRC 3, Rev AG 6of24
BEAVER VALLEY , JWER STATION
[ - -INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE -]
EVENT2: "B" SG level decreases due to increased BOP recognizes "B" SG level decreasing.
Malfunction for event 2 is triggered to steaming rate at higher power and constant valve IAW Process Control Failure procedure, AOP 1.4.1, insert at 5.5% power and will become position. BOP places controller for FCV-lFW-489 in manual evident when power rises. and restores SG level to program.
A7-54 will alarm for SG level dev. ifthe crew ROLE PLAY: doesn't notice FCV -1 FW-489 malfunction. SRO provides a control band of 65 +/-5% and Rx trip If dispatched to FCV -1 FW-498, wait 2 criteria of 25% low/85% high for manual feedwater minutes then report nothing obvious level control.
wrong at the valve.
SRO directs BOP to start the standby TPRW pump EVENT4: SRO enters lOM-30.4.N to startup the standby and secure the inservice TRPW pump.
At LE discretion, call in and give TPRW pump and shutdown the inservice TPRW following ROLE PLAY. pump. BOP places motor bearings on trend on IPC.
ROLE PLAY: BOP starts 1WR-P-6B, verifies starting current drops Report in as outside operator and state off to normal running current.
"The inservice Turbine plant River water pump, 1WR-P-6A, has a BOP verifies discharge valve, MOV-lRW-1 lOB significant seal leak and needs to be automatically opens.
removed from service. All local prestart checks have been completed and the BOP places and holds 1WR-P-6A CS to STOP, standby pump, 1WR-P-6B, is ready for verifies Annunciator A6-118 is OFF and releases CS.
service."
BOP verifies discharge valve, MOV-lRW-1 lOA closes.
Proceed with next event at LE discretion BVPS - 1L16 NRC 3, Rev AG 7 of24
BEAVER VALLEY , vWER STATION
[-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT 5:
N-42 Instrument Power blown fuse N-42 failure. Alarms; ATC reports multiple unexpected NIS alarms.
IMF NISOSB (0 0) 0 A4-57: NIS PR Low SP Neutron Flux Hi A4-65: NIS PR High SP Flux Hi ATC and BOP verifies plant remains stable.
A4-66: NIS PR High SP overpower Rod stop A4-68: NIS PR Comparator Deviation ATC reports N-42 indication is not consistent with A4-69: NIS PR Neutron Flux Rate Hi other power range channels.
Crew identifies Blown Instrument fuse indications for N-42.
SRO enters Power Range Channel Malfunction procedure, AOP 1.2. lC to address failed NI ATC reports only one PR channel (N-42) has failed.
channel.
BOP turns "Rod Stop Bypass Switch" for N42 on NIS Rack N50 to BYPASS.
ATC verifies status light for Overpower Rod Stop Bypass for N42 is lit. (status pnl 176, B-14) ,,*
BOP turns "Comparator Channel Defeat Switch" on NIS rack N37/N46 to N42 position.
Within 1 hr, verifies P-8, P-9, & P-10 interlocks in required state for current power level.
Within 72 hrs, trips nuclear bistables by removing control power fuses from Drawer A for N42 or directing I&C to remove the failed ch from service.
Crew recognizes failure is an OTIi T channel and directs I&C to trip the applicable bi-stables from Attachment 1 within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .
BVPS - 1Ll6 NRC 3, Rev AG 8 of24
BEAVER VALLEY , vWER STATION l INSTRUCTIONAL GUIDELINES l PLANT STATUS I PROCEDURAL GUIDANCE l EXPECTED STUDENT RESPONSE ]
ATC ensures VB recorders are selected to operable detectors.
SRO evaluates Tech Specs for N-42 failure. SRO addresses TS for N-42 failure:
3.3.1, Function 2.a, PR Neutron flux - HIGH, Condition D, trip ch w/in 72 hrs and QPTR every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
3.3.1, Function 2.b, PR Neutron flux - LOW, Condition E, trip ch w/in 72 hrs.- (N/A if> P-10).
3.3.1, Function 3, PR Hi flux rate, Condition E, trip ch w/in 72 hrs.
3.3.1, Function 6, OT~T, Condition E, trip ch w/in 72 hrs.
3 .3 .1, Functions 17 .c, d, Rx trip interlocks, Condition P, verify in required state w/in 1 hr.
3 .3 .1, Function 17 .e, Rx trip interlocks, Condition 0, verify in required state w/in 1 hr.
'""' 3.3.3, foi'PAM instrumentation - for Info Only.
Proceed with next event at LE discretion EVENT6: Containment Pressure Ch 2 transmitter A TC announces multiple unexpected containment PT-lLM-lOOB fails high. pressure related alarms.
Containment Pressure Ch 2 transmitter ATC reports PT-lLM-lOOB failed high.
(PT-lLM-lOOB) fails high Al-58, Containment Press High (1/3)
Al-60, Containment Press Intermediate High- BOP reviews ARPs and reports entry into IF IMF XMT-CNM004A (0 0) 55 40 High (1/3) procedure is required.
Al-66, Containment Press High-High (1/4)
BVPS-1L16 NRC 3, Rev AG 9 of24
BEAVER VALLE'T . OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE - - - I EVENT 6: (continued) SRO enters lOM-1.4.IF, Attach. 1, Instrument Failure procedure for failed Ch 2 CNMT Tech Specs 3.3.2, Condition A requires actions from NOTE: Pressure. Table 3.3.2-1, If SRO did not identify applicable TS Functions 1.c, & 4.c, Condition D - Place channel in prior to next event being entered, ask as SRO evaluates Tech Specs for failed CNMT TRIP within 72 hrs or Shutdown.
a follow up question. pressure channel. Functions 2.a.3, 2.b.2, & 3.b.3, Condition E - Place channel in BYPASS within 72 hrs or Shutdown.
Proceed with next event at LE SRO notifies I&C to investigate and trip/bypass discretion. bistables within 72 hrs.
,,..,....,'iff!iSlllf* ~,....,.._11(.,,r.,,.,
BVPS-1L16 NRC 3, Rev AG 10 of24
BEAVER VALLE'r . JWER STATION I- - -INSTRUCTIONALGUT5EUNES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 7 and 8:
Inadvertent Train "A" SI with Train "A" SIS components actuate, including Crew recognizes a loss of feedwater/Safety Injection automatic Reactor Trip failure. Feedwater isolation and CIA. signal has occurred and the Reactor has failed to IMF SIS08 Main feedwater pump trips due to FWI. automatically trip.
IMF CRF12A (preloaded)
Manual Rx trip successful. SRO directs the ATC to manually trip the Rx.
Critical Task CT-1 (E-0.A):
Crew manually trips the reactor SRO directs the crew to perform IOA's for E-0.
from the Control Room before performing the mitigation strategy of FR-S.1.
SAFETY SIGNIFICANCE -- Failure to manually trip the reactor causes a challenge to the subcriticality CSF . c t beyond that irreparably introduced by the postulated conditions.
NOTE:
'~
... , )
For this fast acting event, the crew may trip the Rx due to loss of feed. If this occurs quickly, the crew may not recognize the automatic Rx trip failure.
SRO enters E-0 ATC verifies Reactor trip:
Rx trip and bypass breakers open.
Power range indication is < 5%.
Neutron flux is dropping.
BOP verifies Turbine was not online and is tripped:
Throttle OR Governor valves ALL closed.
Main Generator output brks - open.
Exciter Circuit breaker - open.
BVPS-1L16 NRC 3, Rev AG 11 of 24
BEAVER VALLEY
JWER STATION
[ - TNSTRUCTIONALGUIDELINES--fPLANT STATUS I PROCEDURAL GUIDANCE I- EXPECTED STUDENT RESPON-SE - - . I EVENTS 9 and 10: AE and DF Busses are both de-energized. BOP verifies Power to AC Emergency Busses:
Offsite power not available.
Using VB-C voltmeters, verifies neither AE Loss of lAE and lDF 4Kv Emergency nor DF 4Kv busses have voltage indicated.
Busses on Rx trip with auto start Both 4Kv emergency busses de-energize when failures of EDG'S and Reactor plant the Reactor is manually tripped. BOP identifies that both emergency busses are de-River Water pumps. EDG's fail to automatically start. (Both will energized with no EDGs running.
IMF SIS08 manually start from BB controls.)
IMF CRF12A (preloaded) When emergency bus is powered from EDG, Reactor plant River water pumps will fail to start ROLE PLAY: from the sequencer.
If directed to investigate EDG status, wait 4 minutes then report as appropriate:
If not manually started, report no obvious problems identified at diesel(s).
~
If manually started, diesel(s) running sat with normal cooling flow (if RPRW pump was started.)
BVPS-1L16 NRC 3, Rev AG 12 of24
BEAVER VALLEY , vWER STATION I INSTRUCTIONAL GUIDELINES JPLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 9 and 10: (continued) BOP verifies Power to AC Emergency Busses:
(continued)
Critical Task: CT-24 (E-0.C)
Using VB-C voltmeters, verifies neither AE Crew energizes at least one AC nor DF has voltage indicated.
emergency bus before transition out of E-0, unless the transition is to BOP identifies that both emergency busses are de-ECA-0.0, in which case the critical energized with no EDGs running.
task must be performed before placing safeguards equipment hand BOP performs RNO actions ofE-0, step 3.
switches in pull-to-lock position.
Verifies no Orange or Purple bordered alarms for Electrical Protection are lit.
SAFETY SIGNIFICANCE -- Failure to
Depresses both DG STOP pushbuttons.
energize an ac emergency bus
Places CS to EXERCISE.
constitutes "misoperation or incorrect
Depresses START pushbutton.
crew performance which leads to
Verifies 900 RPM on tachometer.
degraded ... emergency power capacity."
Depresses Field Flash pushbutton.
Failure to perform the critical task also
Closes EDG output breaker.
results in needless degradation of a
Verifies associated RPRW pump is running.
barrier to fission product release, Identifies RPRW pump is not running.
specifically of the RCS barrier at the point of the RCP seals.
NOTE:
IA W Transient Response Guidelines, the BOP is expected to start only 1 EDG IA W E-0 RNO, and then start the second EDG following completion of the IOA's using either AOP 1.36.2 or Attachment 1-K.
BVPS-1L16 NRC 3, Rev AG 13 of24
BEAVER VALLEY , uWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 9 and 10: (continued) When BOP starts a given EDG, BOP verifies associated RPRW pump is not running.
Critical Task CT-9 (E-0.L):
Crew establishes flow from at least BOP reports failure ofRPRW pump to one SWS pump to required ESF automatically sequence onto the EDG and equipment before the EDG trips due manually starts the RPRW pump.
to loss of cooling.
SAFETY SIGNIFICANCE -- Failure to manually start at least the minimum required number of SW pumps in an operating safeguards train represents a failure by the crew to "demonstrate the following abilities:
Effectively direct or manipulate engineered safety feature (ESF) controls that would prevent a significant reduction of safety margin beyond that irreparably introduced by the scenario
Recognize a failure or an incorrect automatic actuation of an ESF system or component" Check SI Status:
NOTE: ATC reports Train "A" SIS was previously actuated.
IA W Transient Response Guidelines, the BOP is expected to start only 1 ATC manually actuates SI by depressing both trains' EDG IA W E-0 RNO, and then start the pushbuttons.
second EDG following completion of the IOA's using either AOP 1.36.2 or E-0 IOA's completed. SRO directs BOP to start 2"d EDG IA W AOP 1.36.2 Attachment 1-K. or waits and starts IA W Attachment 1-K.
BVPS - 1L16 NRC 3, Rev AG 14 of24
BEAVER VALLE'r .-OWER STATION
[--INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 9 and 10: (continued) ATC/BOP, sounds standby alarm, announces reactor trip and safety injection.
Crew checks if SI flow should be reduced by verifying following parameters are all consistent with PRE-EVENT.
CNMT radiation, Pressure and Sump level.
SG pressures.
SG levels - none rising uncontrollably.
RCS subcooling - > 46°F.
Secondary heat sink-Total AFW flow> 370 gpm OR at least 1 NR level > 31 %.
RCS pressure is STABLE or RISING.
PRZR level is > 17%,
SI actuation was AUTO MATIC.
Crew determines SI flow should be secured.
Crew secures HHSI flow by:
Depressing both trains SI RESET PBs.
Closing BIT inlet valves, MOV-1SI-867A, B.
Closing BIT outlet valves, MOV-ISI-867C, D.
Verifying HHSI flow is secured.
Adjusting RCP seal injection flow as needed.
ATC verifies SI system status:
Charging pumps running - 2 running.
LHSI pumps running - 2 running.
BIT Flow indicated-NO, previously isolated.
BVPS -1L16 NRC 3, Rev AG 15of24
BEAVERVALLE'r, OWER STATION
[-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 9 and 10: (continued) BOP verifies AFW status:
Motor-driven AFW Pumps - Both RUNNING.
Turbine-driven pump; TV-1MS-105A, B open.
A7-7 is NOT LIT, turbine driven pump runmng.
AFW Throttle Vlvs all FULL OPEN.
Total AFW Flow is> 370 GPM.
NOTE: List of Attachment 1-K Discrepancies: SRO directs BOP to perform Attachment 1-K.
Evaluation of BOP performing
Train "B" SIS failed to auto actuate.
Attachment 1-K begins on page 22.
Both EDG' s failed to auto start.
Both RPRW pumps failed to auto start.
NOTE: RCS temperature < 54 7F and dropping due to ATC checks RCS temp. stable at or trending to 547F; If the crew has preemptively throttled low decay heat and AFW flow.
ATC verifies no steam release is occurring.
AFW flow, RCS temperature will be ~-' ,,_.,, __
A TC verifies Reheat steam is isolated.
stable at or trending to 547F.
ATC reduces total feedflow to minimize CID.
ATC verifies PRZR isolated:
PORVs - CLOSED (all)
Spray Valves- CLOSED (Controlling press)
Safety relief valves - CLOSED (all)
Power to at least one block valve -
AVAILABLE (all available)
Block valves - AT LEAST ONE OPEN (all)
BVPS-1Ll6 NRC 3, Rev AG 16 of24
BEAVER VALLE'< , 0WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ]
EVENTS 9 and 10: (continued) ATC checks if RCPs should be stopped:
DIP between RCS pressure and highest SG pressure is< 200 PSID (350 PSID ADVERSE CNMT).
Criteria for stopping is not met - all RCPs left runmng.
ATC/BOP checks if any SGs are faulted:
Pressures in all SGs-ANY DROPPING IN AN UNCONTROLLED MANNER.
OR
ANY SG COMPLETELY DEPRESSURIZED.
Crew determines NO SG's are faulted.
Crew checks if SG tubes are intact:
Check all SG levels - NONE RISING IN AN UNCONTROLLED MANNER.
Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES.
Crew determines all SG tubes are intact.
Crew checks if RCS is intact by checking CNMT conditions consistent with pre-event values:
CNMT radiation.
CNMT pressure.
CNMT sump level.
Crew determines the RCS is intact based on CNMT conditions consistent with PRE-EVENT VALUES.
BVPS - 1Ll6 NRC 3, Rev AG 17of24
BEAVER VALLEY ,-OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ]
Crew checks if SI flow should be reduced.
ATC verifies RCS subcooling is >46F based on CETC's.
BOP confirms secondary heat sink available by >370 gpm of feed flow available OR NR level in at least 1 SG>31%.
ATC confirms RCS pressure is stable or rising.
ATC confirms PRZR level is > 17%.
Crew determines that current plant conditions support SI reduction.
SRO transitions to ES-1.1, SI Termination NOTE: ATC/BOP resets SI - both trains.
SIS signal previ01.t~~SET.
ATC/BOP resets CIA and CIB - both trains.
NOTE: Charging pump is running on ATC stops 1 charging pump.
sequencer, requires PTL to SID.
SRO directs A TC to isolate the BIT:
ATC verifies MOV-1SI-867A,B,C, D closed.
HHSI flow previously isolated in E-0.
A TC verifies HHSI flow is secured.
BVPS-1L16 NRC 3, Rev AG 18of24
BEAVER VALLEY .-OWER STATION CINSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE- - - I SRO directs ATC to establish normal charging flowpath by:
Verifying normal charging is isolated.
Closing FCV-lCH-122.
Opening MOV-lCH-310.
Opening MOV-lCH-289.
Controlling FCV-1 CH-122 as necessary to maintain PRZR level.
BOP verifies 4160V and 480V stub busses energized:
Verifies ACB-1E5 and ACB-1F5 closed.
BA transfer pumps or CNMT vacuum pump indicating lights are lit.
BOP verifies CNMT Instrument air is available:
Station Instrument Air > 100 psig.
-"-ct~"""""*
TV,. UAJlOO open.
CNMT Instrument Air header > 85 psig.
ATC checks if LHSI pumps should be stopped:
LHSI pumps are running with RWST suction.
ATC stops LHSI pumps AND places CS's in AUTO.
ATC resets SI Auto Recirc Changeover by depressing both trains RESET PBs.
ATC verifies SI flow is NOT required:
Verifies RCS subcooling is >46F.
Verifies PRZR level is > 17%.
Crew confirms that SI is NOT required.
BVPS-1L16 NRC 3, Rev AG 19 of24
BEAVER VALLE't ,,OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ]
Maintain RCS temp. via condenser steam dumps:
BOP confirms ALL MSIV's are open.
Condenser steam dumps previously in steam pressure mode.
Defeats Tavg interlock as necessary.
Adjust controller setpoint as necessary to maintain RCS temperature.
ATC verifies RCS Hot Leg temperatures - STABLE.
Crew verifies no Quench or Recirc Spray pps running.
Crew checks if Letdown can be Established, A TC verifies;
PRZR level > 31 %.
CCR Hx RW hdr press > 20 psig.
. .,..
At least 1 CCR pump is running.
Crew determines conditions support establishing LID.
EVENT 11: SRO directs the crew to monitor LID rad monitor.
LCV-1 CH-460A failed closed. ATC establishes letdown as follows:
IMF CHS21A (6 0) 1
Verifies normal charging is established.
(preloaded)
Places PCV-lCH-145 in MAN & 75% open.
Opens TV-lCH-204.
Attempts to opens LCV-1 CH-460A.
ATC reports LCV-1CH-460A will NOT open.
SRO enters lOM-7.4.H, "Excess Letdown Heat Exchanger Operation."
BVPS - 1L16 NRC 3, Rev AG 20 of24
BEAVER VALLE'r . 0WER STATION
,- - -INSTRUCTIONALGUIDELINES-=1PLANT STATUSfPROCE.t5ffRAL GUIDANCE] ___-rX?EcrE5sf05ENf RESPONSE- - - - I Crew places Excess Letdown Hx in service:
BOP dispatches operator to energize loop drain ROLE PLAY: valve.
2 minutes after being dispatched to
A TC opens energized loop drain valve.
energize a loop drain valve, enter
ATC places HCV-lCH-389 CS to "PDT command and report back. TANK" position.
ATC opens MOV-lCH-201.
ATC slowly adjusts MOV-lCH-137 to warm up the Excess LID Hx, limiting temperature at
< 140F (TI-lCH-139) and pressure at <135 psig (PI-lCH-138.)
Terminate scenario when the crew has aligned Excess letdown and initiated a wannup of the Excess letdown system.
Classify Event:
The highest EPP call would be an ALERT based on EAL SA3 due to a Failure of the reactor protection system.
However, due to initially being a fast moving scenario, the Rx trip failure may not be recognized until the post-trip review.
Therefore, if the manual Rx trip was based upon a loss of main feed water, the expected EPP call would be UNUSUAL EVENT based on EAL SUl - due to a loss of offsite power to both 4KV Emergency busses for > 15 minutes.
BVPS-1L16 NRC 3, Rev AG 21 of24
BEAVER VALLEY
OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE - - -]
Attachment 1-K 'Verification of BOP performs the verifications/actions of Attachment Automatic Actions' 1-K 'Verification of Automatic Actions' as follows:
NOTE: Both EDG's failed to auto start on loss of power. Diesel generators- Both NOT running.
Neither EDG auto started on loss of Verifies no Orange (Purple) Alarms.
power, 1 EDG would have been started Depresses both STOP PB's.
IA W E-0 step. Selects EXERCISE and depresses START PB.
2nd EDG would have been started IA W Depresses FIELD FLASH PB and closes output brkr.
AOP 1.36.2 or this attachment. Identifies R W pump failed to start on sequencer and manually starts RW pump to supply cooling water.
Verifies power to both Emergency 4KV AC busses.
Check at least 1 Leak Collection Exhaust fan running, 1VS-F-4A(4B).
- Station instrument air header pressure> 100 PSIG.
Ensure Reheat Steam Isolation:
Verify MOV-lMS-lOOA,B-CLOSED.
Reset reheater controller.
Close MOV-lMS-204, gland stm spillover vlv.
Verify CCR Pumps - ONE RUNNING with recirc pressure > 100 psig.
Align Neutron Flux Monitoring For Shutdown:
When operable IR channels <lE-10 amp, check SR channels energized.
Transfer NR-lNI-45 recorder to operable source and intermediate range displays.
BVPS - 1L16 NRC 3, Rev AG 22 of24
BEAVER VALLEY , 0WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTEDSTU-DENTRESPONS_E__ - - - -I Attachment 1-K 'Verification of Both RPR W pumps failed to auto start on Verify River Water System In Service:
Automatic Actions' (continued) sequencer.
RPRW Pumps - TWO RUNNING.
Check CCR Heat EX R W press is > 20 psig.
OR (IF CIB has occurred)
Verify RPRW flow to recirc spray hxs.
Check If Main Steamline isolation required:
CNMT pressure - > 7 PSIG.
-OR-
Steamline pressure - < 500 PSIG.
-OR-
Steamline pressure high rate of change - ANY ANNUNCIATOR LIT (A7-41, A7-49, A7-57).
Determines steamline isolation is NOT required.
Check CIB And CNMT Spray Status;
Containment press - REMAINED < 11 PSIG.
Verify ESF Equipment Status:
"B" Train of SIS failed to automatically actuate,
Verify SI status by checking all RED SIS manual actuation successful. marks-LIT.
Verify CIA by checking all ORANGE CIA marks-LIT.
Verify FWI by checking all GREEN FWI marks-LIT.
BVPS - 1L16 NRC 3, Rev AG 23 of24
BEAVER VALLEY rOWER STATION
,- INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE j EXPECTED STUDENT RESPONSE j Attachment 1-K 'Verification of When SR' s are energized, verify Audible indication:
Automatic Actions' (continued)
Verify operating SR Ch selected on Audio Count Rate Channel Selector Switch.
Audible indication functioning properly.
Adjust Multiplier Sw & Volume as necessary.
Start CNMT Hydrogen Analyzers:
Using 1OM-46.4.G, gets keys, opens isolation valves (VB-A) and dispatches an operator to continue putting Hydrogen analyzers in service.
Attachment 1-K-COMPLETE Discrepancies: Upon completion, reports any discrepancies to SRO.
Train "B" SIS failed to auto actuate.
Both EDG's failed to auto start.
Both RPRW pumps failed to auto start.
,.~~
'""'~
BVPS - 1L16 NRC 3, Rev AG 24 of24
A,ppen d"1x D s cenario
outrme 1L16N5 Facility: BVPS Unit 1 Scenario No. 5 Op Test No.: BV1LOT16 NRC Examiners: Candidates: SRO ATC BOP Initial IC- 68 (10): 100% power, BOL, Equ. XE Conditions, CB "D" @ 228 steps, Conditions: RCS boron - 1210 ppm, 1FW-P-3A OOS Turnover: Maintain 100% power.
Critical Tasks: 1. CT-10 (E-0.M) Crew closes failed PORV valves.
2. CT-11 (E-0.0) Crew closes CNMT isolation valves.
3. CT-43 (FR-H.1.A) Crew establishes feedwater flow before feed and bleed required.
Event Malf. No. Event Type Event Description No.
VCT Level Transmitter, LT-lCH-115 fails low causing auto 1 CHS20B (l,A) ATC, SRO makeup to occur.
"A" Feedwater flow transmitter fails high, requires manual 2 FWM14B (C,A) BOP, SRO control of Feedwater control valve and placing alternate channel in service and return to auto control.
(C,A) ATC, SRO 3 NIS03D N44 failed high, control rods automatically insert. (AOP 1.1.3)
(TS) SRO (N) BOP, SRO 4 N44 removal from service. (AOP 1.2.1 C)
(TS) SRO (C,A) BOP, SRO 5 CRF04 Dropped Rod, requires turbine load reduction (AOP 1.1.8)
(TS) SRO 6 CRF04BP (C,A) ATC, SRO 2°d Dropped Rod, requires manual Rx trip.
7 (M)ALL Reactor Trip PT-lRC-445 fails high on Rx trip, PORVs open, requires 8 PRS08E C) ATC, SRO closing valves.
INH49 Train "B" CIA Actuation failure with MOV-lCH-378 (Tm A) 9 (C) BOP, SRO VLV-SEA09 auto close failure.
Loss of ALL Feedwater - FR-H.1 with main feed pump 10 (M) ALL recovery.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 ~ FR-H.l ~ E-0 NUREG-1021, Revision 10 FENOC Facsimile Rev AG
Appendix D Scenario Outline 1L16N5 After taking the shift at 100% power with AFW pump 1FW-P-3A OOS, VCT level transmitter, LT-lCH-115 will fail low causing an automatic Makeup to occur. The ATC will diagnose the indications and IAW AOP 1.4.1, Process Control Failure, tum the blender off to stop the makeup and ensure the plant is stable, the SRO will transition to the instrument failure procedure for further channel actions.
The channel 3, "A" SG feed flow transmitter, FT-lFW-477, will then drift high, the crew will recognize the SG level perturbation and IAW AOP 1.4.1, the BOP will place the controller for lFW-FCV-478 in manual and restore SG level, the SRO will transition to the instrument failure procedure for additional channel removal actions and place the alternate channel in service, the BOP will then return lFW-FCV-478 to automatic control.
Power Range Nuclear instrument, N-44 will then fail high causing the control rods to automatically insert.
The crew will perform the Immediate Operator Actions for AOP 1.1.3, Unexpected Control Rod Movement. The ATC will identify the N-44 failure and place the rods in manual. The SRO will then transition to AOP 1.2.1 C, Power Range Channel Malfunction, and direct the BOP to remove the failed channel from service. The SRO will address Tech Specs for the failed instrument.
As a result of the N-44 failure causing control rod insertion, a control rod will then drop; the crew will enter AOP 1.1.8 for an Inoperable Rod. Due to the magnitude of the RCS temperature drop, the crew will be required to lower power to restore RCS temperature. The SRO will address Tech Specs for the dropped rod.
After the crew has completed a power reduction and stabilized the plant, a 2nd control rod will drop. The ATC will recognize that 2 control rods are now dropped. Due to 2 dropped rods, IAW AOP 1.1.8 IOA's, the SRO will direct the ATC to manually trip the Rx and enter E-0.
When the Rx is manually tripped, PT-lRC-445 will fail high causing 2 PORV's to open resulting in a Safety Injection signal, the ATC will recognize the open PORV's with lowering RCS and manually close the valves.
The safety injection that occurred as a result of the PORV's opening, will fail to actuate the train "B" CIA signal, and MOV-lCH-378 (a train "A" CIA valve) will fail to automatically close. The crew will be required to isolate the containment penetration via either manually actuating Train "B" CIA or manually closing MOV-lCH-378.
On the trip, the turbine driven AFW pump, lFW-P-2 will start but not produce any flow, the remaining available motor driven AFW pump, 1FW-P-3B will start but will trip when the SI Manual actuation PB's are depressed. When "Verifying AFW Status" in E-0, the crew will identify that all auxiliary feedwater pumps have failed, the SRO will transition to FR-H. l.
IA W FR-H. l direction the crew will restore feedwater flow by starting a main feedwater pump. After feed flow is verified, the SRO will return to E-0 at which point the scenario will be terminated.
Expected procedure flow path is E-0 ~ FR-H. l ~ E-0 NUREG-1021, Revision 10 FENOC Facsimile Rev AG
BEAVER VALLE'r . 0WER STATION INITIAL CONDITIONS: IC-68 (10): 100% power, BOL, Equ. XE Conditions, CB "D" @228 steps, RCS boron - 1210 ppm.
Use HTML, 1Ll6N5.HTM, Initialize into specified IC and insert preloads per the HTML.
ADDITIONAL LINEUP CHANGES STICKERS MONITOR SETUP 1FW-P-3A CS in PTL 1FW-P-3A CS tagged Normal Splash w/ Full Power Screen, on VB-B EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 1FW-P-3A OOS, pump bearing replacement Yesterday I 1800 3.7.5, Condition B SHIFT TURNOVER INFORMATION
1. 100% power for the past month, BOL equilibrium conditions, shift goal is to maintain current power.
SCENARIO SUPPORT MATERIAL REQUIRED PROCEDURES NEEDED
1. BOL Reactivity Placard E-0
2. Protected Train "B" Placard FR-H.1
3. Safety Status PNL lights LIT for "A" AFW lOM-46.4.G
3. lFW-P-2 aligned to A hdr placard 7 IF, Attach 1 24 IF, Attach 2 Attachment 1-K AOP 1.1.3 AOP 1.1.8 AOP 1.2.lC AOP 1.4.1 BVPS - 1L16 NRC 5, Rev AG 3 of20
BEAVER VALLE'\ . OWER STATION
[--INSTRUCTIONAL GUIDELINES j PLANT STATUS I PROCEDURAL GUIDANCE j EXPECTED STUDENT RESPONSE I Assign shift positions SRO: _ _ _ _ _ _ _ __
ATC:- - - - - - - - -
BOP:- - - - - - - - -
Conduct a shift turnover with oncoming Simulator frozen until after shift turnover unless operators. it needs to be run momentarily for an alignment change.
When the shift turnover is completed, Simulator running. Crew assumes control of the unit.
place the simulator to RUN and commence the scenario.
BVPS-1Ll6 NRC 5, Rev AG 4 of20
BEAVER VALLE'r . 0WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE -]
EVENT 1:
Crew acknowledges alarm, verifies plant stability and LT-lCH-115 fails low. LI-lCH-115 VCT level indication decreases recognizes auto makeup is occurring due to LT-lCH-IMF CHS20B (0 0) 0 0 ASIS (computer trend for LT-1 CH-112 increases) 115 failing low.
A3-53: VCT level low.
Auto makeup initiates. IAW AOP 1.4.1, ATC stops the Auto makeup by placing the Boric Acid Blender CS to STOP.
SRO enters AOP 1.4.1 then transitions to the CVCS Instrument failure procedure, 1OM-7.4 .IF, Attachment 1 to address VCT level channel failure.
Crew confirms LT-1 CH-115 has failed low by comparing LI-lCH-115 and computer point for LT-lCH-112 (IPC point L2704A).
SRO verifies A TC previously stopped the makeup by placing the Boric Acid Blender CS to STOP after verifying adequate VCT level as indicated by IPC.
For remainder of scenario, ATC manually initiates V CT makeup when necessary.
Proceed with next event at LE discretion.
BVPS - 1L16 NRC 5, Rev AG 5 of20
BEAVER VALLE, . OWER STATION
[-INSTRUEffONALOODELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENT2:
Feed flow channel FT-lFW-477 drifts Controlling feed flow channel for "A" steam BOP acknowledges and reports alarms, diagnoses feed high. generator level control drifts high, main feed flow channel failure, IA W AOP 1.4.1, establishes regulating valve closes in response. Actual feed manual control of "A" MFRV to stabilize "A" SG IMF FWM14B (0 0) 5E6 120 ASIS flow and level lower. level.
NOTE: Both ARPs direct manual A7-42, Loop A feed flow> steam flow (due to ATC reviews ARPs.
MFRV control (FCV-lFW-478) and IF feed flow failure).
procedure implementation. A7-45, SG IA Level Deviation from Setpoint.
SRO enters AOP 1.4.1. IA W AOP 1.41, SRO establishes a control band of 65 plus or minus 5% and Rx trip criteria of 25% low and 85% high for manual SG level control.
SRO transitions to lOM-24.4.IF Attachment 2. BOP identifies FT-lFW-477 has failed high and is the controlling channel.
SRO directs BOP to take Manual control of FCV -
1FW-478 and restore SG level to normal.
SRO directs BOP to transfer A SG to CH. 4.
BOP places redundant feedflow channel, FC-lFW-478 (FF) in the FM 476 pos.
BOP places redundant steamflow channel, FC-lFW-478 (SF) in the FM 475 pos.
When SG level is stabilized, SRO directs BOP to place FCV-lFW-478 in AUTO.
Insert next event at LE discretion.
BVPS-1L16 NRC 5, Rev AG 6 of20
BEAVER VALLE'\ . JWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE j EXPECTED STUDENT RESPONSE- - -,
EVENTS 3,4 & 5: ATC reports unexpected alarms and rod motion.
Rods automatically step inward in response to N44 fails high I removal from service N44 failure. ATC verifies Control Rods are in AUTO.
Control bank D dropped rod Control bank D Rod F06 drops, causing Tavg Requires turbine load reduction drop. ATC verifies no load rejection in progress and places IMF NIS03D (0 0) 200 0 ASIS rod control to MANUAL to stop the rod insertion.
Crew enters AOP 1.1.3, Unexpected Control Rod Movement. ATC verifies reactor overpower has not occurred.
BOP verifies PT-lMS-446 and 447 are consistent with current power level and Tref.
ATC reports N-44 indication is not consistent with other power range channels.
Crew recognizes Control bank D rod F06 has dropped.
NOTE: SRO transitions to Rod Inoperability procedure, SRO directs the ATC to perform IOA's for a dropped The SRO may transition to AOP 1.2.1 C AOP 1.1.8 to address the dropped rod. rod IAW AOP 1.1.8; to address the N-44 failure before
A TC verifies only one dropped rod.
transitioning to AOP 1.1.8.
ATC verifies Rod Control previously placed in MANUAL due to N-44 failure. (AOP 1.1.3)
ATC verifies Rx is critical and Tavg is> 541F.
Crew verifies TAVG is NOT w/in 4F ofTref.
SRO directs BOP to adjust turbine load for Tavg.
BOP depresses 1st STG IN.
Sets turbine load AND reduction rate as directed by SRO.
Initiates load reduction by depressing GO.
Reduces power incrementally until Tavg is within 4F ofTref.
Crew verifies Tavg is STABLE.
BVPS-1L16 NRC 5, Rev AG 7 of20
BEAVER VALLE'r . JWER STATION
[- INSTRUCTIONAL GUIDELINES [ PLANT STATUS I PROCEDURAL GUIDANCE [ EXPECTED STUDENT RESPONSE [
SRO evaluates Tech Specs for the dropped rod. SRO addresses TS for dropped rod:
3.1.4, Rod Group Alignment Limits, Condition B, w/in 1 hr, either restore Rod to within alignment limits OR verify SDM.
3.4.1 (RCS DNB Parameters, RCS press< 2218 psia)
Condition A: restore RCS pressure within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .
EVENT4: SRO transitions to Power Range Channel ATC reports only one PR channel (N44) has failed, Malfunction procedure, AOP 1.2.1 C to address and verifies rods previously placed in manual.
failed NI channel.
BOP turns "Rod Stop Bypass Switch" for N44 on NIS Rack N50 to BYPASS.
A TC verifies status light for Overpower Rod Stop Bypass for N44 is lit. (status pnl 176, D-14)
BOP turns "Comparator Channel Defeat Switch" on NIS rack N3 7/N46 to N44 position.
Within 1 hr, verifies P-8, P-9, & P-10 interlocks in required state for 100% power.
ATC verifies reactor power is> 50%.
NOTE: Crew may initiate performance BOP determines all PR channel upper and lower of 10ST-2.4A, however next event will detector inputs to QPTR are operable.
occur before completion of OST.
BOP determines all detector inputs to AFD monitor alarm are operable or requests I&C assistance in determining AFD alarm operability.
Within 72 hrs, trips nuclear bistables by removing control power fuses from Drawer A for N-44 or directing I&C to remove the failed ch from service.
BVPS-1L16 NRC 5, Rev AG 8 of20
BEAVER VALLE't . OWER STATION I INSTRUCTIONALGUIDELINES HH] PLANT STAfOSTPROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I A TC ensures VB recorders are selected to operable detectors.
SRO evaluates Tech Specs for N-44 failure. SRO addresses TS for N-44 failure:
3.3.1, Function 2.a, PR high flux, Condition D, trip ch w/in 72 hrs and QPTR every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
3.3.1, Function 2.b, PR Neutron flux - LOW, Condition E, trip ch w/in 72 hrs.- for Info Only.
3.3.1, Function 3, PR Hi flux rate, Condition E, trip ch w/in 72 hrs.
3 .3 .1, Functions 17 .c, d, Rx trip interlocks, Condition P, verify in required state w/in 1 hr.
Proceed with next event at LE 3 .3 .1, Function 17 .e, Rx trip interlocks, Condition 0, discretion verify in required state w/in 1 hr.
3.3.3, for PAM instrumentation - for Info Only.
EVENT6: Bank D, rod BOS drops, Crew recognizes a 2nd dropped rod.
2nd dropped rod RCS temperature and pressure drops. ATC performs IOA's for Rod Drop and per the RNO IMF CRF04BP (0 0)1 A4-12, Low Pressurizer pressure alarm, action, with 2 or more rods dropped, manually trips followed by; the reactor.
A4-46, Tavg Deviation alarm.
EVENTS 7, 8, 9, & 10:
lRC-PT-445 fails high causing 2 PORV's to Multiple malfunctions occur on reactor open.
trip. Train "B" CIA fails to actuate along with MOV-l CH-378 (Tm A) auto close failure.
All commands preloaded Loss of all Feedwater SRO enters E-0. ATC and BOP commence IOA's ofE-0.
BVPS-1L16 NRC 5, Rev AG 9 of20
BEAVER VALLEi . OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE -]
EVENTS 7, 8, 9, & lO:(continued) A TC verifies Reactor trip:
Rx trip and bypass breakers open.
Power range indication is < 5%.
Neutron flux is dropping.
BOP verifies Turbine trip:
Throttle OR Governor valves ALL closed.
Main Generator output brks - open.
Exciter Circuit breaker - open.
AE and DF Busses are energized from offsite. BOP verifies Power to AC Emergency Busses:
Using VB-C voltmeters or IPC, verifies AE and DF busses have voltage indicated.
BOP identifies that both emergency busses are energized from offsite power.
EVENTS: PORV's PCV-1RC-455D and 456 fail open After ATC completes IOA's for E-0, recognizes lRC-PT-445 fails high when electrical upon transmitter failure. transmitter failure and 2 PORV's are open, verifies busses transfer to Offsite. pressure is< 2325 psig and manually places CS's for IMF PRSOSE (4 2) 2500 (preloaded) both valves to CLOSE.
SI automatically actuated due to Low PRZR Check SI status:
pressure. A TC reports SI automatically actuated and manually actuates SI by depressing both trains' pushbuttons.
ATC/BOP, sounds standby alarm, announces reactor trip and safety injection.
BVPS-1L16 NRC 5, Rev AG 10of20
BEAVER VALLE, . OWER STATION I INSTRUCTIONAi... GUIDELINES Ill.ANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Check if SI flow should be reduced.
Crew verifies that an adequate secondary heat sink does not exist.
SRO determines SI flow should not be secured.
ATC verifies SI system status:
Charging pumps running - 2 running.
LHSI pumps running - 2 running.
BIT Flow indicated - YES.
BOP verifies AFW status:
Motor-driven AFW Pumps - NONE RUNNING.
Turbine-driven pump; TV-1MS-105A, B OPEN.
A 7-7 is NOT LIT, turbine driven pump runnmg
AFW Throttle Vlvs all FULL OPEN.
Total AFW Flow is< 370 GPM.
BOP reports no Aux feed water flow exists.
BVPS-1L16 NRC 5, Rev AG 11 of 20
BEAVER VALLE'l . JWER STATION
[-INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE ]
EVENTS 7, 8, 9, & IO:( continued) SRO recognizes that AFW flow cannot be A TC checks if secondary heat sink is required by:
established and enters FR-H.1, Response to Loss
Verifying RCS press is> any non-faulted SG.
of Secondary Heat Sink.
RCS hot leg temperatures >350°F.
Crew determines a secondary heat sink is required.
Crew checks SG WR levels and determines if RCS bleed and feed should be initiated.
BOP verifies WR lvl in at least 2 SG' s is > 14%.
BOP reports ALL WR levels are > 14%.
Crew determines bleed and feed is not required at this time and continues to monitor WR level.
BOP checks Primary Plant Demineralized Water storage tank level is> 27.5 feet.
BVPS - 1L16 NRC 5, Rev AG 12 of20
BEAVER VALLE'i . OWER STATION L INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 7, 8, 9, & lO:(continued) Crew tries to establish AFW flow to at least 1 SG.
ROLE PLAY:
When directed to investigate AFW ATC/BOP verifies SG Blowdown and blowdown pump status: sample lines are isolated.
If dispatched to Emergency Switchgear, Crew confirms:
wait 2 minutes then report 1FW-P-3B; * "A" motor-driven pump previously OOS.
ACB 1F16 ground OC relay 50- * "B" motor-driven pump initially started but VF 116G is flagged. tripped and will not restart.
Turbine-driven pump running but no flow.
If dispatched to AFW room, wait 3 minutes then report as appropriate. BOP reports that ALL AFW throttle valves are open.
FW-P-3B, not running, nothing obvious wrong at the pump. Crew continues to try to restore AFW flow while SRO FW-P-2, appears to be running, recirc continues in FR-H.1.
valve is open.
Local Suction Press. is 10 psig, normal. BOP confirms AFW flow is not> 370 gpm.
ROLE PLAY: SRO dispatches operator with attachment 2-K to If dispatched with attachment 2-K, as establish alternate AFW flow using the Dedicated operator do not report in unless called, AFWpump.
then report that you are having trouble getting the local panel to energize.
Crew reports that feed flow is NOT verified.
SRO directs A TC to stop ALL RCP' s.
NOTE: Restoration of feed using a main feed pump. Crew takes actions to restore a main feedwater pump.
It is expected that the crew will not wait
Verifies a condensate pump is in service.
for lFW-P-4 field actions before
Resets SI/FWI and opens feedwater CNMT continuing with procedure and restore a isolation valves, HYV-lFW-lOOA, B, C.
main feed pump.
Starts and holds CS for main feedpump.
BVPS-1L16 NRC 5, Rev AG 13 of20
BEAVER VALLE) . OWER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I EVENTS 7, 8, 9, & IO:(continued) Feedwater flow established With a main feed pump running as a source, BOP SG levels begin rising. throttles the Bypass feed regulating valves to establish Critical Task: CT-43 (FR-H.1.A) flow to intact SGs.
Crew establishes f eedwater flow into at least one SG before RCS feed and Crew checks at least 1 SG NR level> 31 % (50%)
bleed is required. IfNR not >31 %, crew verifies either CETC's are SRO returns to E-0, Step 9 IAW FR-H-1, step 8. dropping OR SG WR levels are rising.
Basis for Selection:
SAFETY SIGNIFICANCE -- Failure to establish feedwater flow to any SG results in the crew's having to rely upon the lower-priority action of establishing RCS bleed and feed to minimize core uncovery. This constitutes incorrect performance that "leads to degradation of any barrier to fission product release."
NOTE:
At the LE discretion, the scenario can be terminated after the crew has established feedwater flow if the crew has previously identified and performed corrective actions for CT-10 (Close PORV valves) and CT-11 (Close CNMT Isol valves). Otherwise, allow the crew to return to E-0 and perform E-0 up through the diagnostic steps and terminate after SI termination criteria is evaluated.
NOTE: List of Attachment 1-K Discrepancies: SRO directs BOP to perform Attachment 1-K.
Evaluation of BOP performing Train "B" CIA failed to automatically actuate, Attachment 1-K begins on page 18. and Train "A" CNMT Isolation valve, MOV-1CH-378 failed to automatically close.
Critical Task CT-11 (E-0.0):
Crew closes CNMT isolation valves ....
BVPS - 1L16 NRC 5, Rev AG 14of20
BEAVER VALLE\ . OWER STATION
[-1Ns-tROu10NAL Gu1DELINEs - r F>L.ANf-stJ\Tus, PRoc~EbuRAL GUIDANCE r- ---
EXPECTED stuoEWR.EsPoNsE 1 EVENTS 7, 8, 9, & lO:(continued) RCS temperature may be decreasing due to ATC checks RCS temp. stable at or trending to 547F:
feedwater flow to SG's.
A TC verifies no steam release is occurring.
A TC verifies Reheat steam is isolated.
ATC reduces total feedflow to minimize CID.
Critical Task: CT-10 (E-0.M) A TC verifies PRZR isolated:
Crew closes the failed open PRZR
PORVs-CLOSED, ATC reports PORVs, PO RVS prior to completion of the PCV-1RC-455D and 456, were both open due "PRZR PORV check" step of E-0. to failure of IRC-PT-445.
A TC reports both valves successfully closed SAFETY SIGNIFICANCE -- Failure to manually.
close the PORV or block MOV under the postulated plant conditions A TC continues verifying PRZR isolated:
constitutes "misoperation or incorrect
Spray Valves - CLOSED (controlling press).
crew performance which leads to
Safety relief valves - CLOSED.
degradation of any barrier to fission
PRT conditions - CONSISTENT WITH product release." In this case, the RCS EXPECTED VALUES.
fission-product barrier can be restored
Power to at least one block valve -
to full integrity simply by closing the AVAILABLE. (all).
PORV or block MOV. Therefore,
Block valves - AT LEAST ONE OPEN. (all) failure to close the PORV/MOV also represents a "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety."
A TC checks if RCPs should be stopped:
NOTE:
DIP between RCS pressure and highest SG RCP's were previously SID in FR-H.1 pressure - LESS THAN 200 PSID [350 PSID]
due to loss of heat sink.
A TC reports all RCPs previously stopped.
BVPS-1L16 NRC 5, Rev AG 15of20
BEAVER VALLE) . JWER STATION J INSTRUCTIONAL GUIDELINES J PLANT STATUS I PROCEDURAL GUIDANCE J EXPECTED STUDENT RESPONSE J EVENTS 7, 8, 9, & lO:(continued) ATC/BOP checks if any SGs are faulted:
Pressures in all SGs - ANY DROPPING IN AN UNCONTROLLED MANNER.
OR
ANY SG COMPLETELY DEPRESSURIZED.
Crew determines NO SG's are faulted.
Crew checks if SG tubes are intact:
Check all SG levels - NONE RISING IN AN UNCONTROLLED MANNER.
Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES.
Crew determines no SG levels are rising in an uncontrolled manner and Secondary Radiation is consistent with pre-event values, therefore all SG tubes are intact.
Crew checks if RCS is intact by checking CNMT conditions consistent with pre-event values:
CNMT radiation.
CNMT pressure.
CNMT sump level.
Crew determines the RCS is intact based on CNMT conditions consistent with PRE-EVENT VALUES.
BVPS - 1L16 NRC 5, Rev AG 16 of20
BEAVER VALLE'r . JWER STATION 1 * *1NSTR.DcfloNAL Gu1DELINEs 1 PLANT sTATus / PROCEDURAL GUIDANCE 1 EXPECTED sTuDENT REsPoNsE 1 EVENTS 7, 8, 9, & lO:(continued) Crew checks if SI flow should be reduced.
A TC verifies RCS subcooling is >46F based on CETC's.
BOP confirms secondary heat sink available by >370 gpm of feed flow available OR NR level in at least 1 SG>31%.
A TC confirms RCS pressure is stable or rising.
ATC confirms PRZR level is > 17%.
Crew determines that current plant conditions support SI reduction.
Terminate scenario when the crew determines transition to ES-1.1 is appropriate or not.
Classify Event:
SITE AREA EMERGENCY based on EAL FSl due to entry into FR-H.1 which indicates a "Potential loss of the RCS barrier" and a "Potential loss of the Fuel Clad barrier" due to a loss of heat sink when a Heat Sink is required.
BVPS - 1L16 NRC 5, Rev AG 17 of20
BEAVER VALLE'r . 0WER STATION I INSTRUCTIONAL GUIDELINES I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of BOP performs the verifications/actions of Attachment Automatic Actions' 1-K 'Verification of Automatic Actions' as follows:
Both EDG's are running. Diesel generators-BOTH RUNNING with no Trouble Alarms, RW pumps running supplying cooling water flow.
Verifies power to both Emergency 4KV AC busses.
Check at least 1 Leak Collection Exhaust fan running, 1VS-F-4A(4B).
Station instrument air header pressure > 100 PSIG.
Ensure Reheat Steam Isolation. Ensure Reheat Steam Isolation:
Verify MOV-lMS-lOOA,B-CLOSED.
Reset reheater controller.
Close MOV-lMS-204, gland stm spillover vlv.
Verify CCR Pumps - ONE RUNNING with recirc pressure > 100 psig.
Align Neutron Flux Monitoring For Shutdown:
When operable IR channels <lE-10 amp, check SR channels energized.
Transfer NR-lNI-45 recorder to operable source and intermediate range displays.
BVPS-1L16 NRC 5, Rev AG 18of20
BEAVER VALLE'r , 0WER STATION C]NSTRlJc'r-10NAL GUIDELINES- I PLANT STATUS I PROCEDURAL GUIDANCE I EXPECTED STUDENT RESPONSE-* ---]
Attachment 1-K 'Verification of Verify River Water System In Service:
Automatic Actions' (continued)
RPRW Pumps-TWO RUNNING.
Check CCR Heat EX R W press is > 20 psig.
OR (IF CIB has occurred)
Verify RPRW flow to recirc spray hxs.
Check If Main Steamline isolation required:
CNMT pressure - > 7 PSIG
-OR-
Steamline pressure - < 500 PSIG
-OR-
Steamline pressure high rate of change - ANY ANNUNCIATOR LIT (A7-41, A7-49, A7-57)
Determines steamline isolation is NOT required.
Check CIB And CNMT Spray Status:
Containment press - REMAINED < 11 PSIG BVPS-1L16 NRC 5, Rev AG 19 of20
BEAVER VALLE) . OWER STATION
[ INSTRUCTIONAL GUIDELINES j PLANT STATUS I PROCEDURAL GUIDANCE j EXPECTED STUDENT RESPONSE I Attachment 1-K 'Verification of Automatic Actions' (continued) Verify ESF Equipment Status;
Verify SI status by checking all RED SIS Critical Task CT-11 (E-0.0): marks-LIT Crew closes CNMT isolation valves Train "B" CIA failed to actuate with Train "A"
Verify CIA by checking all ORANGE CIA such that at least one valve is closed CIA valve, MOV-lCH-378 failing to marks - LIT on each critical phase A penetration automatically close.
Verify FWI by checking all GREEN FWI before the end of the scenario. marks-LIT SAFETY SIGNIFICANCE-- Closing When SR's are energized, verify Audible indication:
at least one containment isolation valve
Verify operating SR Ch selected on Audio.
on each critical Phase A penetration, Count Rate Channel Selector Switch.
under these conditions and when it is
Audible indication functioning properly.
possible to do so, constitutes a task that
Adjust Multiplier Sw & Volume as necessary.
"is essential to safety," because "its improper performance or omission by an operator will result in direct adverse consequences or significant degradation in the mitigative capability of the plant."
Start CNMT Hydrogen Analyzers:
Using lOM-46.4.G, gets keys, opens isolation valves (VB-A) and dispatches an operator to continue putting Hydrogen analyzers in service.
Attachment 1-K-COMPLETE Discrepancies: Upon completion, reports any discrepancies to SRO.
Train "B" CIA failed to automatically actuate, and Train "A" CNMT Isolation valve, MOV-1CH-378 failed to automatically close.
BVPS-1L16 NRC 5, Rev AG 20 of20

ML16342C521

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