Text

Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML102520199
Person / Time
Site:	Beaver Valley
Issue date:	06/30/2010
From:	; FirstEnergy Nuclear Operating Co
To:	D'Antonio J; Operations Branch I
	Hansell S
Shared Package
ML102560049	List: ML102520199;
References
	TAC U01821
	Download: ML102520199 (266)
	v • d • e

RTL#A5.640U 1/2-ADM-130 l.F04 Page 3 of 11 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-036 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) (RO ONLY)

KJA

REFERENCE:

2.1.25 3.9 TASK ID: 0011-006-06-013 JPM APPLICATION: [g] REQUALIFICATION [g] INITIAL EXAM D TRAINING D FAULTEDJPM [g] ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EV ALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 25 Minutes Actual minutes Critical: [g] No Time: Time:

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

i i

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of II Revision I OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Calculated Shutdown Margin is between 1.77% and 2.4%.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: Determine Shutdown Margin in accordance with 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15).

INITIAL CONDITIONS: The Unit is in Mode 1, 100% power. All rods at 230 steps.

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 838 ppm. Current bumup is 12,000 MWDIMTU INITIATING CUE: The Unit Supervisor directs you to perform a shutdown margin (SDM) calculation for the present plant conditions by performing steps VILA through VILB.5 of20ST-49.l, Shutdown Margin Calculation (Plant Critical). Report your results in the space provided. (Space provided on candidate direction sheet),

REFERENCES:

20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15), Rev. 16, Unit 2 Curve Book Cycle 15.

TOOLS: Calculator HANDOUT: 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15), Rev. 16 Filled out up to step VILA.

Unit 2 Curve Book Cycle 15.

RTL#A5.640U 1/2-ADM-130 I.F04 Page 5 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Determine Shutdown Margin in accordance with 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15).

INITIAL CONDITIONS: The Unit is in Mode 1, 100% power. All rods at 230 steps.

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 838 ppm. Current burnup is 12,000 MWD/MTU INITIATING CUE: The Unit Supervisor directs you to perform a shutdown margin (SDM) calculation for the present plant conditions by performing steps VILA through VII.B.5 of20ST-49.l, Shutdown Margin Calculation (Plant Critical). Report your results in the space provided. (Space provided on candidate direction sheet).

RESULTS:

Calculated SDM is- - - - - - - -

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-036 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) (RO ONLY)

STEP STANDARD

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

EVALUATOR NOTE:

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

START TIME: _ _ _ _ _ __

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

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

(Otherwise N/A). COMMENTS:

(Step VII.AI)

2. If the plant is in Mode 2, 2.1 N/A's Step VII.A2, (Plant not in Mode 2).

VerifY that Tavg is less than 8°F above Program Tavg as follows: (Otherwise N/A) COMMENTS:

(Step VILA2)

3. Request Chemistry to 3.1 Determines current boron concentration is 838 ppm determine current RCS Boron from initial conditions.

concentration in ppm.

(Step VII.A.3)

COMMENTS:

RTL#A5.640U 1/2-ADM-130I.F04 Page 7 of II Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-036 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) (RO ONLY)

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "V" FOR VNSAT)=> S/U

4. Record the number of steps 4.1 Records Control Bank D as 230 steps withdrawn on withdrawn for Control Bank D Data Sheet 1 (Block AA) from initial conditions.

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

(Step VILAA)

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

power from [2NME-NR45],

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

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

(Step VILA.5) 6.C Record the number of 6.1C Records number of immovable or untrippable rods as immovable or untrippable "ONE" on Data sheet 1 (Block A.6) (given in Initial control rods on Data Sheet 1. Conditions).

(Step VII.A.6)

COMMENTS:

7. If the number of immovable or 7.1 Determines Step VII.A.7 is N/A and marks step N/A untrippable control Rods is greater than 1, Use Attachment 1 to determine the required COMMENTS:

boron concentration with greater than one struck rod and Record below. (Otherwise N/A)

(Step VILA. 7)

'*RTL#A5.640U 1/2-ADM-1301.F04 Page 8 of 11 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-036 JPM TITLE: Perfonn Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) (RO ONLY)

I STEP i STANDARD I ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=> SIU I 8.C Detennine control bank 8.1C Detennines ARO Total Bank Worth (from the Data reactivity worth per the Sheet 1 table) to be 7.425 %L\k/k and records on Data following: Sheet 1 (Block Rl.a).

Using the ARO Total Bank Worth table on Data Sheet 1, COMMENTS:

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

I

(Step VILRI.a) 9.C Using Curve Book Figures 9.lC Using Curve Book Figure CB-24B, detennines CB-24A, 24B or CB-24C, integral rod worth to be ZERO and records on Data Detennine integral rod worth Sheet 1 (Blocks Rl.b.l) and RI.b).

for the current bank position AND Enter this value on Data Sheet 1. COMMENTS:

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

%L\k/k AND Record on Data Sheet 1.

(Step VII.RI.b)

10. Subtract the integral rod 10.1 Detennines TBW-IRW is 7.425 %L\k/k and records worth from the Total Bank on Data Sheet I (Block B.l.c).

Worth AND Enter the result on Data Sheet 1.

COMMENTS:

(Step VILB.I.c)

I !

RTL#A5.640U 1I2-ADM-130 I.F04 Page 9 of 11 Revision 1 OPERAnONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-036 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) (RO ONLY)

STEP STANDARD

( "c" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)=.:) S/U 11 Multiply this result by 0.9 to 11.1 Determines 90% ofTBW to be 6.6825 %~kJk and apply a 10% uncertainty AND records on Data Sheet 1 (Block B.1.d).

Enter the result on Data Sheet 1.

(Step VILB.1.d)

COMMENTS:

12.C If ONE rod is inoperable 12.lC Determines stuck rod worth to be 2.330 %~kJk and (untrippable), Record "Worst records on Data Sheet 1 (Block B.2).

Case Stuck Rod with Inoperable Rod" worth on Data Sheet 1. Value is COMMENTS:

determined from Column "B" on Attachment 2 for the appropriate Cycle Burnup.

(Step VII.B.2.b)

13. Subtract Stuck Rod(s) Worth 13.1 Determines 90% Total Bank Worth minus Stuck from the 90% Total Bank Rod(s) Worth to be 4.3525 %~kJk and records on Worth value AND Enter the Data Sheet 1 (Block B.3).

result on Data Sheet 1.

(Step VILB.3) COMMENTS:

14. Determine Power Defect as 14.1 Record RCS Boron Concentration of 838 ppm on follows: Data Sheet 1 (Block B.4.a).

Record RCS Boron Concentration results from COMMENTS:

Chemistry on Data Sheet 1.

i (Step VII.BA.a)

RTL#A5.640U 112-ADM-1301.F04 Page 10 of 11 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-036 JPM TITLE: Perfonn Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) (RO ONLY)

STEP STANDARD

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

15. Using Curve Book Figure 29, 15.1 Detennines B-1 0 Correction Factor to be 0.895 and Detennine the B-1 0 records on Data Sheet 1 (Block BA.b).

Correction Factor for the present Bumup (If between two Bumup values, Use the COMMENTS:

B-I0 Correction Factor for the greater MWDIMTU Bumup entry) AND Record on Data Sheet 1.

(Step VII.BA.b)

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

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

Record on Data Sheet 1.

. (Step VII.BA.c)

17. Using Curve Book Figure 21 , 17.1 Detennines ABSOLUTE VALUE of the Power Detennine the ABSOLUTE Defect to be 2340 pcm and records on Data Sheet 1 VAL UE of the Power Defect (Block BA.d).

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

this value on Data Sheet 1.

(Step VILBA.d)

RTL#A5.640U II2-ADM-I30 I.F04 Page 11 of 11 Revision 1 OPERAnONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-036 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) (RO ONLY)

STEP STANDARD

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

lS.C Divide value from curve (in lS.l C Converts ABSOLUTE VALUE of the Power Defect pcm) by 1000 to convert to of 2340 pcm to 2.34 %flklk and records on Data

%flklk AND Record on Data Sheet 1 (Block B.4.e).

Sheet 1.

(Step VILBo4.e)

COMMENTS:

19. Add 0.150 % flklk for 19.1 Determines Power Defect plus operating temperature operating temperature band band margin to be 2049 % flklk and records on Data margin to the Power Defect Sheet 1 (Block B.4.t).

recorded in Step VII.Bo4.e AND Record on Data Sheet

1. COMMENTS:

(Step VII.Bo4.t) 20.C Determine SHUTDOWN 20.1 C Determines SDM to be I.S625 % flklk and records on MARGIN by subtracting Data Sheet 1 (Block B.4.t) AND space provided on Power Defect (Step candidate direction sheet.

VII.Bo4.t) from the value determined in Step VII.B.3 AND Record on Data Sheet COMMENTS:

1.

(Step VILB.5)

EVALUATOR CUE:

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

BVPS - SBS Unit 2 20ST-49.1 Revision 16 Operating Surveillance Test Page 12 of 17 Shutdown Margin Calculation (Plant Critical)

(Updated For Cycle 15)

~lfJL "N(.wfR

,./' -11 U KEV~~ATASHEET1 AHUTDOWN MARGIN CALCULATION A. 4. CBD Steps Withdrawn (OR CSC If CBD @ 0 stepI) STEPS

5. Reactor Power

6. Number of Inoperable Rods

ROD(S): C* ]

B. 1. a. ARO Total Bank Worth (See Table above) (TBW) ~~.I:;I""'iIIIIiIi-~iiiiII1

b. Integral Rod Worth (Curve Book Figure 24A. 24B OR 24C) (IRW)

1) ~ (pcm from B.1.b) X~

1000pcm

c. TBW (B.1.a) -IRW (B.1.b.1) =7.4f2S%AkA<

d. 90% Current Total Bank Worth 0.9x7.425 (B.1.c) ~'B2S%AkA<

2.

3.

Stuck Rod(s) Worth (90% Total Bank Worth) - (Stuck Rod(s) Worth) llp~M~ ci

('."81S (B.1.d)

)-( 2.330 (B.2)

=4.35Z5%AkA<

4. a. RCS Boron Concentration . 839 ppm

b. B-10 Correction Fador (CB Figure 29) ,,0.815

750 ppm

d. ABSOLUTE VALUE of Power Defect (CB Figure 21) =2310 pcm

e. 2310 1%Aklk (pcm from B.4.d) x -

1000 ~.~, %AkA< C :~

f. Power Defect + Operating temperature band margin 2.?4 (B.4.e)+0.150%AkIk . 2.11 %AkIk l =I.8&'2 S q \

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

(1.35Z5 )-f 1.~1 ) %AkIk (B.3) (BAt)

(1 )

Initial (2)

Initial DATA SHEET 1

RTL#A5.640U I/2-Aulh .

Page 3 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-030 JPM TITLE: Calculate The RCS Initial Void Volume And Final Void JPM REVISION: 0 Volume (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel)

(ROONLY)

KIA

REFERENCE:

2.1.7 4.4 TASK ID: 0061-016-01-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM o TRAINING o FAULTED JPM ~ ADMINISTRATIVEJPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

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

o Training o Other:

EVALUATION RESULTS I

Performer Name: Performer SSN:

Time DYes Allotted Actual 8 Minutes minutes Critical: [8J No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

I Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Calculated RCS Initial Void Volume is 5781 FT3 + 4 AND Final Void Volume is 5477 F T 3 +/- 4 RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: Calculate The RCS Initial Void Volume And Final Void Volume (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel)

INITIAL CONDITIONS:

A Reactor trip from 100% power has occurred.

SI has NOT been actuated

Power was lost to all RCPs.

Both Trains of RVLIS are inoperable.

Normal Charging and Letdown are in operation.

A plant cooldown was in progress.

RCS Hot Leg temperature is stable.

Voids are indicated in the Reactor Coolant System by an abnormal change in Pressurizer level due to a change in Reactor Coolant System pressure.

INITIATING CUE: The Unit Supervisor has directed the performance of20M-6.4.T, Response To Voids In The Reactor Vessel. The necessary data to calculate the RCS Initial Void Volume And Final Void Volume has been collected and recorded within 20M-6.4.T, Response To Voids In The Reactor Vessel.

Using the data recorded in 20M-6.4.T, Response To Voids In The Reactor Vessel:

The Unit Supervisor directs you to Calculate The RCS Initial Void Volume And Final Void Volume lAW 20M-6.4.T, Response To Voids In The Reactor Vessel steps IV.B.5 and 6. Report your results in the space provided. (Space provided on candidate direction sheet).

REFERENCES:

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

TOOLS: Calculator HANDOUT: 20M-6.4.T, Response To Voids In The Reactor Vessel Rev. 3 filled out up to step N.B.5.

OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Calculate The RCS Initial Void Volume And Final Void Volume (IA W 20M~6.4.T, Response To Voids In The Reactor Vessel)

INITIAL CONDITIONS:

A Reactor trip from 100% power has occurred.

SI has NOT been actuated

Power was lost to all RCPs.

Both Trains of RVLIS are inoperable.

Normal Charging and Letdown are in operation.

A plant cooldown was in progress.

RCS Hot Leg temperature is stable.

Voids are indicated in the Reactor Coolant System by an abnormal change in Pressurizer level due to a change in Reactor Coolant System pressure.

INITIATING CUE: The Unit Supervisor has directed the performance of20M~6.4.T, Response To Voids In The Reactor Vessel. The necessary data to calculate the RCS Initial Void Volume And Final Void Volume has been collected and recorded within 20M-6.4.T, Response To Voids In The Reactor Vessel.

Using the data recorded in 20M~6.4.T, Response To Voids In The Reactor Vessel:

The Unit Supervisor directs you to Calculate The RCS Initial Void Volume And Final Void Volume lAW 20M-6.4.T, Response To Voids In The Reactor Vessel steps IV.B.S and 6. Report your results in the space provided. (Space provided on candidate direction sheet).

RESULTS:

RCS Initial Void Volume RCS Final Void Volume _ _ _ _ _ _ _ _ __

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

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

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-030 JPM TITLE: Calculate The RCS Initial Void Volume And Final Void JPM REVISION: 0 Volume (IA W 20M-6.4.T, Response To Voids In The Reactor Vessel)

(ROONLY) i STEP STANDARD

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

EVALUATOR NOTE:

Infonnation used to fill-out procedure:

Pi 1800 psig Pr= 1900 psig Li 50%

Lr= 25%

EVALUATOR NOTE:

Some judgment may be required to detennine satisfactory perfonnance on this JPM.

START TIME: _ _ _ _ _ __

1.C Calculate the size of the RCS 1.1 C Calculates the size of the RCS initial void volume initial void volume (G j ) as (Gi) follows:

G i =<<Li% - Lr%) x 12.17)/(1 - (Pipsig/Prpsig))

Gj =<< Li % - Lr%) x 12.17) 1(l

- (Pi psig 1 Pr psi g>>)

_ _ _--"x 12.17)/(1-(~ _ __

1 ))

Gi = - - - - cu-ft.

Gi =(L25~ x 12.17) 1(1- <-.947368421~)

G i =<-304.25.-> 1 (.052631579)

Gi = 5781 cu-ft.

COMMENTS:

RTL#A5.640U 1/2*ADM-I..1Vt .* _

Page 7 of7 Revision 1 OPERAnONS JOB PERFORMANCE MEASURE JPM NUMBER' 2AD-030 JPM TITLE: Calculate The RCS Initial Void Volume And Final Void JPM REVISION' 0 Volume (lAW 20M-6.4.T, Response To Voids In The Reactor Vessel)

. (ROONLY)

STEP STANDARD

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

2.C Calculate the size of the RCS 2.1 C Calculates the size of the RCS final void volume (Gf) final void volume (Gf) from from the initial RCS void volume.

the initial RCS void volume (Step B.S) as follows:

Gf =Gi x ( Pi psig / Pf psig )

Gf x( / Gf=L5781.Jx L1800_ /_1900~

)

Gf=- - - cu-ft. Gf =L5781.J x L947368421.J Gf=L5477.J COMMENTS:

EVALUATOR CUE:

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

Beaver Valley Power Station Unit 2 20M-6.4.T Response to Voids in the Reactor Vessel Revision 3 Prepared by Date Pages Issued Effective Date W. K. Glffrow 10/04199 1 through 7 Reviewed by Date Validated by Date C. O'Neill 10/04/99 N/A OSC Meeting No. Date Approved by Date Non-Intent 10/04/99

. Beaver Valley Power Station Unit 2 20M-SAT Reactor Coolant System Revision 3 Operating Procedures Page 2 of 7 Response to Voids in the Reactor Vessel I. PURPOSE This procedure provides the instructions necessary to detect and size voids in the Reactor Coolant System. Discrimination between voids in the Reactor Vessel and the Steam Generators is not possible.

This procedure may be entered into from an EOP.

II.. . PRECAUTIONS & LIMITATIONS A. If Safety Injection is in operation, THEN this procedure is not to be used.

III. INITIAL CONDITIONS A. Normal Charging and Letdown are in operation.

B. RCS Hot Leg temperature is stable.

C. Voids are indicated in the Reactor Coolant System by an abnormal change in Pressurizer level due to a change in Reactor Coolant System pressure.

IV. INSTRUCTIONS A. Prepare for determining the RCS Void Volume by performing the following:

1. Using normal Pressurizer controls establish constant Pressurizer level and pressure. .

Note: System pressure and level are placed on a Trend Recorder for better accuracy in recording values. The range of RCS parameters is not expected to exceed 150 psi (+/- 75 psi) or 10% (+/- 5%) of level span for the Reactor Coolant System transient.

2. Place the following parameters on a Trend Recorder, ([2IHC-UR760 or 761]. Trend Recorder, VB-B):

Pressurizer OR RCS Wide Range pressure

Pressurizer level

3. Record the following initial RCS parameters:

,S ODpSi9

~1ODAY

a. RCS pressure (PI) =

& 1DtJA,/ Initial! Date

b. PRZR level (1.,) = SO ?' % .

Beaver Valley Power Station Unit 2 20M-6AT Reactor Coolant System Revision 3 Operating Procedures Page 30f7 Response to Voids in the Reactor Vessel B. Determine the RCS Gaseous Void as follows:

CAUTION: IF PRESSURIZER LEVEL DECREASES TO LESS THAN 20%. THE RCS PRESSURE INCREASE SHOULD BE STOPPED AND CHARGING FLOW

.INCREASED TO.RESTORE PRESSURIZER LEVEL.

Note:

The Reactor Coolant System void volume is equal to the change in Pressurizer volume for a change in RCS pressure. The ratio of initial void volume to final void volume is equal to the ratio of initial to final RCS pressures. The final void volume may be determined by substituting the void volume change into the equation for the void and pressure ratios.

Initial Void GI =<<(~L) x (12.17 fefOA,)) I (1- (PI I Pt))

Final Void Gt =GI x (PI' Pt)

1. Maintain charging and letdown flow constant during RCS pressure change.

2. Increase RCS pressure ~50 psig by energizing all Pressurizer heaters.

a. If Pressurizer level falls to < 20%. THEN deenergize Pressurizer Heaters AND restore Pressurizer level by increasing charging flow.

3. When RCS pressure has been raised at least 50 psig. THEN stabilize RCS pressure.

4. Record the following final RCS parameters:

a. RCS pressure (P,) = IqOf.) psig

~/~t1-Y Initial I Date

b. PRZR level (L,) = 2..5

5. Calculate the size of the RCS initial void volume (G I) as follows:

GI =<< L, % - L, %) x 12.17) I (1 - (PI psig I Pt psig>>

GI=({I-_ __ _ _ _....I) x 12.17) I (1 - (\-_ _ _ ,_ _ _--1))

Step A.3.b Step B.4.b Step A.3.a Step BAa

Beaver Valley Power Station Unit 2 20M-6.4.T Reactor Coolant System Revision 3 Operating Procedures Page 4 of 7 Response to Voids in the Reactor Vessel GI =

--- cu-ft.

(1) 1_ _

Initiall Date (2) 1_ _

Inltiall Date

6. Calculate the size of the RCS final void volume (G,) from the initial RCS void volume (Step B.5) as follows:

G, =GI x ( PI psig , P, psig )

G, =(_ _ _ _ _...1) x (1...-_ _ _ , _ _ _---I)

Step B.5 Step A.3.a Step B.4.a G, = . cu-ft.

(1) 1__- -

Initlall Date (2) 1-::--_

Initial I Date

7. Increase RCS pressure an additional 50 psig by energizing Pressurizer Heaters.

B. When pressure has been increased 50 psig, proceed as follows:

a. If Pressurizer level decreases due to the pressure increase, THEN a void is indicated and should be vented in accordance with Step C.

b. If Pressurizer level does not change on the pressure increase, THEN this procedure is complete.

C. Vent Non-Condensable Gasses from the Reactor Coolant System as follows:

1. Ensure Pressurizer Relief Tank is available AND capable of being vented to the Gaseous Waste System.

2. Ensure RCS Subcooling is > 500 F by increasing RCS pressure OR dumping Steam from a non-faulted Steam Generator.

3. Adjust charging and letdown as necessary to establish Pressurizer level at 50 to 90%.

.4. Verify Reactor Coolant System is borated to the Cold Shutdown Boron Concentration.

Beaver Valley Power Station Unit 2 20M-S.4.T Reactor Coolant System Revision 3 Operating Procedures Page 50f7 Response to Voids in the Reactor Vessel CAUTION: *. VENTING THE REACTOR COOLANT SYSTEM MAY RESULT IN A SAFETY INJECTION SIGNAL DUE TO DECREASING PRESSURE. THE SI SIGNAL SHOULD BE BLOCKED WHEN PRESSURIZER PRESSURE DROPS TO LESS THAN 2000 PSIG.

THE SAFETY IN~IECTION SIGNAL WILL BE AUTOMATICALLY UNBLOCKED IF PRESSURIZER PRESSURE INCREASES TO GREATER THAN 2000 PSIG REQUIRING THE SIGNAL TO BE BLOCKED AGAIN IF PRESSURE IS TO BE REDUCED TO LESS THAN 2000 PSIG.

5. Limit Pressurizer pressure and level drop on venting by manually raising charging flow to maximum.

Note: Reactor Vessel Vent Valve burping may occur during valve cycling due to differential pressure across the valve. If this is the case. the valve should be closed when pressure equalizes.

S. Align to vent the Reactor Vessel Head by performing one of the following, (BB-A):

a. Open [2RCS*SOV200A} AND [2RCS*SOV201A]. Rx Vessel Vent to PRT Train A Isol Vlvs.

b. Open [2RCS*SOV200B] AND [2RCS*SOV201 B]. Rx Vessel Vent to PRT Train B Isol Vlvs.

Note:

Venting of the Reactor Coolant System should be terminated when any of the following limits are reached:

Reactor Coolant Subcooling is < 50°F.

Pressurizer level < 20%.

Pressurizer Relief Tank level increases at a rate consistent with RCS makeup indicating the void has been vented.

7. Initiate Vessel vent by opening [2RCS*HCV250A or B], Rx Vessel Vent to PRT Train A or B Vlv (100%). (BB-A)

8. When one of the vent termination criteria is met, THEN close the valve opened in the previous step: (N/A valve not operated)

a. [2RCS*HCV250A], Rx Vessel Vent to PRT Train A (1) 1_ _

Inltlall Date (2) I~_

Initial I Date

Beaver Valley Power Station Unit 2 20M-S.4.T Reactor Coolant System Revision 3 Operating Procedures Page 6 of 7 Response to Voids in the Reactor Vessel

b. [2RCS*HCV250B], Rx Vessel Vent to PRT Train B (1) 1 Inltlal/::"O-a-te (2) 1_ __

lnltiall Date

9. Ensure all Rx Vessel Vent to PRT Isolation Valves are closed, (BB-A):

a. [2RCS*SOV200A], Rx Vessel Vent to PRT Train A Isol Vlv.

b. [2RCS*SOV201A], Rx Vessel Vent to PRT Train A Isol Vlv.

c. [2RCS*SOV200B], Rx Vessel Vent to PRT Train B Isol Vlv.

d. [2RCS*SOV201B], Rx Vessel Vent to PRT Train B Isol Vlv.

10. Place the following controls to normal:

a. Pressurizer level control

b. Pressurizer pressure control D. Repeat Steps A3 through Step B.8 to determine the effectiveness of the Vessel venting.

PenonnedBy ____________________________

Verified By _ _ _ _ _ _ _ _ _ _ _ _ _ __

Reviewed By Date _ _ __

NSS/ANSS E. Route the completed copy of this procedure to Document Control via the Operations clerk's daily transmittal.

V. REFERENCES A TECHNICAL SPECIFICATIONS NONE B. UPDATED FINAL SAFETY ANALYSIS REPORT NONE

Beaver Valley Power Station Unit 2 20M-6.4.T Reactor Coolant System Revision 3 Operating Procedures Page 7 of7 Response to Voids in the Reactor Vessel C. COMMITMENTS

1. LER 1-99-002, CATS A990155A. CR 981459, CR 990132, BCO 2-98-004 Rev 2" The Chemical and Volume Control System will be operated with a letdown flow rate of greater than 75 gpm and less than or equal to 120 gpm only on a temporary basis to address a transient condition and only when the RCS specific activity is verified to be less than or equal to 0.35 lJCi/gram dose equivalent 1-131. (Revision 2)

D. ADMINISTRATIVE NONE E. VENDOR INFORMATION NONE F. DRAWINGS

1. 10080-RM-406-2, VOND Reactor Coolant System G. OPERATING MANUAL

1. 20M-6.1 Reactor Coolant System Description t

2. 20M-6.3 2RCS Valve List H. PLANT MODIFICATION NONE I. OTHER

1. OMDR 2-91-0738 (Rev. 0)

2. BCO 2-98-004 (Original issue) established a normal letdown flow limit of 66 gpm.

Cautions were placed in the procedure prior to Steps B.1 and C.3 to make the user aware of this limitation. (Revision 1)

3. OMCN 2-98-324 incorporated Revision 1 to BCO 2-98-004 which changed normal letdown flow limit to 75 gpm. (Revision 2)

4. OMCR 2-96-0477 adds a dual signoff to Step 8 to ensure return to NSA, and corrects a typographical error. BCO 2-98-004 (Rev. 2) changed the maximum permissible RCS specific activity to 0.35 lJCi/gram dose equivalent 1-131 in the Cautions containing letdown flow and RCS specific activity limits. (Revision 2)

5. Removed Cautions containing letdown flow and RCS specific activity limits from steps that control charging and letdown flow (Steps B.1 and C.3), and the associated reference to BCO 2-98-004, to support implementation of TS Amendment 101. (Issue 4/Rev. 3)

RTL#A5.640U 112-ADM-130 I.F04 Page30f6 Revision I JPM NUMBER: 2AD-031 JPM TITLE: Prepare a Clearance Tagout [2QSS-P21B] Quench Spray JPM REVISION: 0 Pump 21B KIA

REFERENCE:

2.2.13 4.1 TASK ID: 0481-007-03-043 JPMAPPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM 0 TRAINING o FAULTEDJPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

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

0 Training D Other:

EV ALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 25 Minutes Actual minutes Critical: ~ No Time: Time:

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1I2-ADM-1301.F04 Page 4 of6 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Identify the tags and sequence of placement for a tagout of2QSS-P21B Quench Spray Pump 21B.

RECOMMENDED Classroom STARTING LOCATION:

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

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

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

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

Quench Spray Pump 21B for pump seal replacement lAW the attached clearance coversheet. Document your results on the worksheet provided.

REFERENCES:

NOBP-OP-I001, Manual Clearance Generation, Rev. 3 NOP-OP-IOOI, Clearance/Tagging Program, Rev. 12 TOOLS: None HANDOUT: NOBP-OP-1001, Manual Clearance Generation, Rev. 3 NOP-OP-lOOI, Clearance/Tagging Program, Rev. 12 OP Manual Fig. No. 13-2, 10080-RM-413-2, Rev. 19 OM Chapter 20M-13.3.C, Power Supply and Control Switch Checklist Rev. 9.

Clearance coversheet 2RI5-13-QSS-TRNG 2R15-13-QSS-TRNG 0811612010 2QSS-P2IB]

Quench Spray Pump 21 B Seal Replacement Yes Mode 4 Use caution when breaching seal package; casing may not be completely drained.

2R15 SEAL REPLACEMENT 2001005844

RTL#A5.640U 112-ADM-130 I.F04 Page 5 of6 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

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

INITIAL CONDITIONS: The plant is in Refueling Mode, no fuel is in the reactor. [2QSS-P21 B]

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

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

Quench Spray Pump 21B for pump seal replacement lAW the attached clearance coversheet. Document your results on the worksheet provided.

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

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

Simulate perfonnance 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.

II

RTL#A5.640U 1I2-ADM-J30I.F04 Page 6 of6 Revision J OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-031 JPM TITLE: Prepare a Clearance Tagout [2QSS-P2IB] Quench Spray JPM REVISION: 0 Pump 21B STANDARD Indicate "s" FOR SAT or "U"FOR UNSAT)=> I S/U ;

START TIME: _ _ _ _ _ __

EVALUATOR NOTE:

This task is normally performed using the SOMS clearance computer and signed electronically. For this JPM, the SOMS computer is NOT available. IF necessary inform candidates that it is not required to follow the instructions for Manual Clearance Generation (lAW NOP-OP-lOOI section 4.28).

EVALUATOR NOTE:

Provide JPM handout and student copy of table.

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

COMMENTS:

EVALUATOR eUE:

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

STOP TIME: _ _ _ _ _ __

ANSWER KEY (DO NOT GIVE TO STUDENTS)

Evaluator NOTE: Student may identify additional points. The points listed below are the minimum required for this lPM. All additional Doints must be evaluated to ensure the clearance is correct.

COmponent ID I

-~~ ~------~~

Component Description Position ---

Sequence 2QSS*P21B-CS Control Switch for Quench Spray Pump Pull-To-Lock 1 DF 2!J3?QSS*P?lB (DF) (PTL) -----

4KVS-2DF-2F2 Supply to Quench Spray Pump 21B Racked Out 2 OR Bus Barrier 2QSS*P21B I 2QSS*MOV101B-CS Quench Pump 21B Discharge Isolation Shut 3 Valve ~~-----~~ ~ ~~~ I--~ ~ ~ ~ -----~ ~

2055-9 uench Pump 21B Recirc Isol Shut 3 2QSS*MOV100B-CS Quench Pump 21B Suction Isolation Shut 4 Valve 480 VAC MCC*2 Supply to Quench Pump 21B Suction Open E12 Cub 1A Isolation Valve ---------

480 VAC MCC*2 Supply to Quench Pump 21B Discharge Open 5 E12 Cub 2A Isolation Valve ----- -----

2QSS-206 Quench Spray Pmp 21B Discharge Drain Open 6 Isol Valve 2055-310 Vent valve for Quench Spra'i Pmp 21B Open 7 I

~

o U

I Z

w Q

)

Iii

/earance Covel'5heet BVPS Tagout: 2BVP-CYC-015-1 Clearance: 2R15-13-QSS-TRNG 08116/2010 1.2:38*

Component to be Worked:

"lSS-P21B Quench Spray Pump 21B Description IReason Seal Replacement Placement Notes

MECH.MAINT.ClEARANCE Cautions Use caution when breaching seal package; casing may not be completely drained.

Completion Instructions /F.edback Verify pump operability.

Clearance Attributes:

Attribute , . Attribute Description Value

~Quipment Required For Mode ChanQe :yes

~estored/Removed Prior to Mode Mode 4 ESF Clearance Required No

'chedule 2R15 Clearance Type Danger 1e to Post (In Minutes) lime to Remove (In Minutes) mpacts Reactivity No TIme for DralnlngNentlng (In Minutes) mme for FllllngNentlng (In Minutes)

Grew Size for DralnlnQ Crew Size for Filling Posting Pre-Job Brief Card completed

~emovaIPre-Job Brief card completed

~egulatorv Applicability Determination # --~ ..

Work Documents LIst: 2R15 - SEAL REPLACEMENT 2001005844 Clearance Verification:

Status Description Name Verification Da' Prepared Prepared By Reviewed Reviewed, By Second Reviewed second Reviewed By

~pproved *I\pprove(l By ssued for Work [ssued for Work By Restoration Review Restoration Review By Removal Authorized Removal Authorized By

~Iearance Closed ~earance dosed By NOP-OP-lOO1. I

RTL#A5.640U 112-ADM-130l.F04 Page 3 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: 2AD-OIO I: . .

JPM REVISION: 1 JPM TITLE: Detennme GW Storage Tank DIscharge Bleed Flow rate KIA

REFERENCE:

2.3.11 3.8/4.3 TASK ID: 0191-006-01-011 0191-010-01-013 JPM APPLICATION: [8J REQUALIFICATION [8J INITIAL EXAM D TRAINING D FAULTED JPM [8J ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perfonn D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Ini tial Exam D NRC D Classroom D OJTITPE D Other:

D Training D Other:

EVALUATION RESULTS Perfonner Name: Perfonner SSN:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 1.F04 Page 4 of?

Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: GW Storage Tank Discharge Bleed Flow rate is calculated to be GREATER than 2 SCFM and the candidate determines that the discharge MUST BE TERMINATED.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to calculate the GW Storage Tank Discharge Bleed Flow rate AND based on your calculation make a recommendation for continuing the discharge.

INITIAL CONDITIONS:

The plant is in Mode 5, making preparations to enter Mode 6.

Unit 2 Gaseous waste Decay Tanks 2GWS-TK-25A, 25B, 25C, 25D, 25E, 25F, and 25G are being discharged to the Unit 1 Atmospheric Vent, lAW 1/2-0M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent.

The initial pressure in ALL of the tanks was 64 psig.

The discharge has been ongoing for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

The current pressure of ALL tanks is 59.8 psig.

The Shift chemist has completed proper tritium sampling.

INITIATING CUE: Determine the GW Storage Tank Discharge Bleed Flow rate lAW 112 OM-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent.

Step IV.M.20 AND make a recommendation for continuing the discharge in the box below. (Provided in the candidate direction sheet)

REFERENCES; 1I2-0M-19.4A.B, Unit 2 OW Storage Tk Disch To Unit 1 Atmos Vent.

Rev. 15 1I2-HPP-3.06.006.FOI RWDA-G.

TOOLS: Calculator HANDOUT: 1I2-0M-19.4A.B, Unit 2 OW Storage Tk Disch To Unit 1 Atmos Vent.

Rev. 15 filled out up to step IV.M.20.

1I2-HPP-3.06.006.FOI RWDA-O filled out with a MAXIMUM undiluted discharge rate of2 SCFM.

RTL#A5.640U 1/2-ADM-1301.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to calculate the GW Storage Tank Discharge Bleed Flow rate AND based on your calculation make a recommendation for continuing the discharge.

INITIAL CONDITIONS:

The plant is in Mode 5, making preparations to enter Mode 6.

Unit 2 Gaseous waste Decay Tanks 2GWS-TK-25A, 25B, 25C, 25D, 25E, 25F, and 25G are being discharged to the Unit I Atmospheric Vent, lAW 1/2-0M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit I Atmos Vent.

The initial pressure in ALL of the tanks was 64 psig.

The discharge has been ongoing for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

The current pressure of ALL tanks is 59.8 psig.

The Shift chemist has completed proper tritium sampling.

INITIATING CUE:

Determine the GW Storage Tank Discharge Bleed Flow rate lAW 1/2 OM-19.4A.B, Unit 2 GW Storage Tk Disch To Unit I Atmos Vent.

Step IV.M.20 AND make a recommendation for continuing the discharge in the box below.

GW Storage Tank Discharge Bleed Flow rate_ _ _ _ _ _ _ _ __

Recommendation:

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F04 Page 60f7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-OIO JPM REVISION: 1 JPM TITLE: Detennine GW Storage Tank Discharge Bleed Flow rate STEP STANDARD

( "e" Denotes CRITICAL STEP)

START TIME:

1. Reviews procedure step 1.1 Reviews 1I2-0M-19.4A.B, Unit 2 GW Storage Tk Disch To Unit 1 Atmos Vent. Step IV.M.20 COMMENTS:

2.C Two hours after the 2.1 C Inserts the numbers from the initial conditions and discharge has been initiated, detennines bleed flow:

perfonn the following steps:

Confinn the bleed flow rate using the following Bleed flow rate (SCFM) =

equation:

(132)(64-59.8)(7)

Bleed flow rate (SCFM) (14.7)( 120)

(132FT3)(P j -P r)(# ofTanks being discharged)

(14.7 psi)(Tr-Tj ) min. Bleed flow rate (SCFM) = 2.2 SCFM COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-O 10 JPM REVISION: 1 JPM TITLE: Detennine GW Storage Tank Discharge Bleed Flow rate STEP STANDARD

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

Pi Initial Gaseous Waste Storage Tank pressure in PSIG from [2GWS-PR125] OR PCS computer trend on GP 352.

Pf Current Gaseous Waste Storage Tank pressure in PSIG from [2GWS-PR125] OR PCS computer trend on GP 352.

Ti Time the discharge started Tf Current time (Tf-Ti) shall have units of minutes 3.1C. If the bleed flow rate exceeds 3.1C. Detennines that the discharge MUST be Terminated 2 SCFM, THEN Stop the discharge by perfonning Steps IV.M.21 and IV.M.22 AND Notify Radiation Protection of the problem.

(Otherwise NI A)

COMMENTS:

EVALUATOR CUE:

When the applicant makes the decision to tenninate the discharge, the evaluation for this JPM is complete STOP TIME: _ _ _ _ _ __

'orm 1/2-HPP-3.06.006.FOl (Paqe 1 of 5) RTL A9. 520B BEAVER VALLEY POWER STATION-2 RWDA-G- TR99999

, GASEOUS Radioactive Waste Discharge Authorization This permit authorizes the discharge ofl 4032. cu. ft. . (64.0 psig) of gaseous radioactivity at a maximum undiluted 'discharge rate*<Df-2 cfm from gaseous wal?te decayJ;:.ank: 2GWS-TK25A,2SB,25C, 2SD,25E, 25F ,25G .

Eo the env~ronment v~a the process vent.

Monitor alarm setpoints shall be adjusted to the default values ,shown below on this permit. This permit valid until Tomorrow 12: 07 Monitor Alarms Adjusted (cpm) HI-HI

~~---------

HI prere~is'ites of

~. I . } RM-G~10BB 2.36E+05 1.lBE+05 aDCM 2-0DC-3.03 HI !Jw HI-HI ~\rJ Table .3-13 met INIT~>' 1 11' 'RM-GW-I09(S} 3.60E+05 1.20E+05 INIT :rS

'Prepared By Reviewed By Chemistry Notified R~:t~ -r:a~ -------------------------

~~-----------

RP~~9~:'t~ LJ~ ~

Chemist Signature Tv,(}fl.-1 Date Sample ID APpro~e~ ~oved By'

~~~i9 TEST SamDle Date/Time' To4ay 12: 07 t;fL ~ \ClOA-j 1Vn,,"Y.

) U1 Shift Mngr Sig Date Date

. /

Discharge Record Discharge Start '" Discharge Stop psig/ ps~g/

mo 1 dy I yr hr 1 ron psia init mo I dy I yr hr I ron ps~a init

\OI~I _ l.~~~ 104.0 I":J _1_1 _ _ 1_ _ _ __

_1_1 _ 1 __ 1__ 1_ __ 1_______

f'fOOl~l1armSKeS~r-HI IN I'!'

HI-HI IN!1' (c m RM-G~108B --m-!m-1-nr 3.60E+OS 1.20E+OS RM-GW-I09(S) 3.60E+05 1.20E+OS

1' Total ,Discharge minutes Reviewed By Reviewed By Post Review U1 Shift Mngr Sig Date U2 Shift Mngr Sig Date signature Date EXERCISE USE ONLY

/

~rm 1!2-HPP-3.06.006.F01 (page 2 of 5) RTL A9. 52011 BEAVER VALLEY POWER STATION-2 RWDA-G- TR99999 Gaseous Release Dose and Dose Rate Summary

- SITE DOSE RATE VALUES***

-Mrem/Yr-----

Total Body Skin ----------------~-----Organ Dose Rates (mrem!yr)-- ---- --

Dose Rate Dose Rate Bone Liver Total Body Thyroid Kidney Lung GI-LLI PROJECTED RELEASE DOSE RATE m 2.107E-08 4.789E-08 O.OOOE+OO 1.554E-I0 1.554E-I0 1.554E-I0 1.554E-I0 1.554E-I0 1.554E-I0 Site Continuous Dose Rate. 4.58013-07 7.520E-06 O.OOOE+OO 1.980E+00 1.980E+00 1.980E+00 1.98013+00 1.980E+00 1.980E+00 SITE PROJECTED DOSE RATE - 4.791E-07 7.568E-06 O.OOOE+OO 1.980E+00 1.980E+00 1.980E+00 1.980E+00 1.980E+00 1.98013+00

'*UNIT DOSE VALUES***

mrad--------- -------------~-----------Organ Dose {mrem)-------------------------

Gamma Air Beta Air Bone Liver Total Body Thyroid Kidney Lung GI-LLI rOTAL PROJECTED*RELEASE DOSE - 1.187E-10 6.892E-11 O.OOOE+OO 2.774:8-11 2.774E-11 2.774B-11 2.774E-11 2.7748-11 2.774E-11 Unit 1 CUrrent Month Dose - 2.890E-07 1. 360E-09 O.OOOE+OO 1.690E-Ol 1.690E-Ol 1.690E-Ol 1. 690E-Ol 1.69013-01 1.690E-01 UNIT 1 PROJECTED MONTH DOSE - 2.891E-07 1. 394E-09 O.OOOE+OO 1.690E-01 1.690E-01 1.690E-Ol 1.69013-01 1.690E-01 1. 690E-01 Unit 2 Current Month Dose s 2.890E-07 1.360E-09 O.OOOE+OO 5.040E-04 5.040E-04 5.040E-04 5.040E-04 5.040E-04 5.040E-04

UNIT 2 PROJECTED MONTH DOSE - 2.891E-07 1. 39413-09 O.OOOE+OO 5.040E-04 5.040E-04 5.040E-04 5.040E-04 5.040E-04 5.040E-04 Unit 1 CUrrent Quarter Dose = 2.890E-07 1.360E-09 O.OOOE+OO 3.440E-Ol 3.440E-01 3.44013-01 3.440E-01 3.44013-01 3.440E-01

>fIT 1 PROJECTED QUARTER DOSE - 2.891E-07 1.39413-09 O.OOOE+OO 3.440E-01 3.440E-01 3.44013-01 3.440E-Ol 3.44QE-01 3.440E-01 Unit 2 Current Quarter Dose a 2.89013-07 1.360E-09 0.00013+00 1.008E-03 1.008E-03 1.00BE-03 1.00BE-03 1.00BE-03 1. 008E-03

'lIT :2 PROJECTED QUARTER DOSE - 2.891E-07 1.3948-09 O.OOOE+OO 1.008E-03 1.00813-03 1. 00BE-03 1. 00BE-03 1.0088-03 1.008E-03 Unit 1 Current Year Dose = 2.890E-07 1.3608-09 O.OOOE+OO 3.440E-01 3.440E-01 3.440E-01 3.440E-01 3.440E-01 3.440E-Ol UNIT 1 PROJECTED YEAR DOSE - 2.891E-07 1.394E-09 0.0008+00 3.440E-Ol 3.4408-01 3.440E-01 3.4408-01 3.440E-01 3.440E-Ol Unit :2 Current Year Dose = 2.890E-07 1.360E-09 O.OOOE+OO 1.00BE-03 1.008E-03 1.008E-03 1. 008E-03 1.008E-03 1. 008E-03 UNIT 2 PROJECTED YEAR DOSE - 2.891E-07 1. 3948-09 O.OOOE+OO 1.008E-03 1. 008E-03 1. 008E-03 1. 008E-03 1.008E-03 1. 008E- 03 1b _dm of the RQ's is < 1; this is not considered a Reportable Quantity.

EXERCISE USE ONLY

~rm 1/2-HPP-3.06.006.F01 (Page 3 of 5) RTL A9.520B BEAVER VALLEY POWER STATION-2 RWDA-G-TR99999 Noble Gas Dose Rates and Doses Total Body Skin Gamma Beta Concentration Dose Rate Dose Rate Air Dose Air Dose EPA-RQ Nuclide uCi/cc mrem/yr mrem/yr mrad mrad Fraction KR.-85 1.440E-OS 2.107E-08 . 4.789B-08 4.010E-12 :L329S-12 1. 593E-06 TOTALS 1.440E-OS 2.107E-08 4.789B-08 4.010E-12 2.329E-12 1. S93E-06 EXTENDED TOTALS 2.107E-08 4.789E-08 1.187B-10 6.992E-11 1. 593E-06 Calculated at Site Boundary EXERCISE.USB ONLY

)rm 1/2-HPP-3.06.006.FOI (Page 4 of 5) RTL A9.520B BEAVER VALLEY POWER STATION-2 RWDA-G- TR99999 Dose Rates From Radioiodines and Particulates Concentration Bone Liver Tot.Body 'l'hyroid Kidney Lung GI-LLI EPA-RQ Nuclide uCi/cc mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr mrem/yr Fraction M-l 2.100E-07 O.OOOE+OO 1.554E-10 1.554E-10 1.554E-10 1.554E-10 1.554E-10 1.5548-10 2.323E-07 TOTALS 2.100E-07 O.OOOE+OO 1.554E-10 1.554E-10 1.554E-10 1.554E-10 1.554E-10 1.554E-10 2.323E-07 Dose Rates are Calculated for the Inhalation.Pathway - Child The Controlling Location is 0.35 miles NW.

EXERCISE USE ONLY

~rm 1/2-HPP-3.06.006.F01 (Page 5 of 5) RTL A9.520B BEAVER VALLEY POWER STATION-2 RWDA-G-'TR99999 Doses From Radioiodines and Particulates Concentration Bone Liver Tot.Body Thyroid Kidney Lung GI-LLI BPA-RQ Nuclide uCi/cc mrem mrem mrem mrem mrem mrem mrem Fraction H-3 2.1o.OE-07 0.qOOIHOO,:}~.373B-13. 9 *.373E-13 .9.373E-13. 9.. 373E-13 9.373E-13 9.373E-13 2.323E-07 TOTALS 2.10DB-D7 0..0.0.0.8+0.0. 9.3738-13 9.373E-13 9.373E-13 9.373E-13 9.373E-13 9.373E-13 2.323B-D7 EXTENDED TOTALS 0.0008+00 2.774E-11 2.7748-11 2.7748-11 2.774E-11 2.774E-11 2.7748-11 2.3238-07 Dose are Calculated for the Inhalation, Ground and Vegetation Pathway Child The Controlling Location is 0..99 miles NW.

EXERCISE USE ONLY

RTL#A5.640U 1I2-ADM-130 l.F04 Page 3 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) SRO ONLY KIA

REFERENCE:

2.1.25 4.2 TASK ID: 0011-006-06-013 JPM APPLICATION: ~ REQUALIFICA TION ~ INITIAL EXAM D TRAINING D FAULTEDJPM ~ ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 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:

RTL#A5.640U 1!2-ADM-1301.F04 Page 4 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determine that Shutdown Margin is greater than COLR required value of 1.77% and less than 2.4%. Determines Power defect is 2340 +/- 20 pcm.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: Determine Shutdown Margin in accordance with 20ST-49.l, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15).

INITIAL CONDITIONS: The Unit is in Mode 1, 100% power. All rods at 230 steps.

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 838 ppm. Current burnup is 12,000 MWD/MTU INITIATING CUE: The Shift Manager directs you to perform a shutdown margin (SDM) calculation for the present plant conditions by performing steps VILA through VILC.l of 20ST-49.1, Shutdown Margin Calculation (Plant Critical). Report your results in the space provided. Be sure to include a determination of whether or not the Technical Specification required SDM is being met. (Space provided on candidate direction sheet).

REFERENCES:

20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15), Rev. 16, Unit 2 Curve Book Cycle 15, License Requirement Manual, Technical Specifications.

TOOLS: Calculator HANDOUT: 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15), Rev. 16 Filled out up to step VII.A.

Unit 2 Curve Book Cycle 15, License Requirement Manual, Technical Specifications.

RTL#A5.640U 112-ADM-130I.F04 Page 5 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Determine Shutdown Margin in accordance with 20ST-49.1, Shutdown Margin Calculation (Plant Critical) (Updated for Cycle 15).

INITIAL CONDITIONS: The Unit is in Mode 1, 100% power. All rods at 230 steps.

Annunciator [A4-3C], TAVG DEVIATION FROM TREF is "NOT LIT". ONE control rod has been determined to be inoperable, untrippable, and immovable during performance of 20ST-1.1, Control Rod Assembly Partial Movement Test. Chemistry has just reported current RCS boron concentration at 838 ppm. Current bumup is 12,000 MWD/MTU INITIATING CUE: The Shift Manager directs you to perform a shutdown margin (SDM) calculation for the present plant conditions by performing steps VILA through VII.C.1 of 20ST-49.1, Shutdown Margin Calculation (Plant Critical). Report your results in the space provided. Be sure to include a determination of whether or not the Technical Specification required SDM is bein met.

RESULTS:

Calculated SDM is_ _ _ _ _ _ __

Calculated SDM _ _ _ _ _ _ _ _within the limits specified in the Technical Specifications?

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM -130 I.F04 Page 6 of 12 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perfonn Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) SRO ONLY STEP STANDARD

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

EVALUATOR NOTE:

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

START TIME: _ _ _ _ _ __

1. If the plant is in Mode 1, 1.1 Initials Step VILA 1, (Plant in Mode 1, Tavg <3 OF VeritY that Tavg is less than above Tref (Annunciator A4-3C OFF) from Initial 3°F above Tref (Annunciator Conditions.

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

(Otherwise N/A). COMMENTS:

(Step VILA 1) i 2. If the plant is in Mode 2, 2.1 N/A's Step VILA.2, (Plant not in Mode 2).

VeritY that Tavg is less than 8°F above Program Tavg as follows: (Otherwise NIA) COMMENTS:

(Step VILA2)

3. Request Chemistry to 3.1 Determines current boron concentration is 838 ppm detennine current RCS Boron from initial conditions.

concentration in ppm.

(Step VII.A.3) COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 7 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) SRO ONLY STEP STANDARD

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

4. Record the number of steps 4.1 Records Control Bank D as 230 steps withdrawn on withdrawn for Control Bank D Data Sheet 1 (Block A.4) from initial conditions.

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

(Step VILA.4)

5. Record the current reactor 5.1 Records reactor power as 100% on Data Sheet 1 power level in percent of full (Block A5).

power from [2NME-NR45],

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

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

(Step VII.A5) 6.C Record the number of 6.1 C Records number of immovable or untrippable rods as immovable or untrippable "ONE" on Data sheet 1 (Block A.6) (given in Initial control rods on Data Sheet 1. Conditions).

(Step VII.A6)

COMMENTS:

7. If the number of immovable or 7.1 Determines Step VILA7 is NIA and marks step NIA untrippable control Rods is greater than 1, Use Attachment 1 to determine the required COMMENTS:

boron concentration with greater than one struck rod and Record below. (Otherwise N/A)

(Step VILA 7)

RTL#A5.640U 112-ADM-130 I.F04 Page 8 of 12 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) SRO ONLY STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate liS" FOR SAT or "U" FOR UNSAT)=> S/U I S.C Determine control bank 8.1C Determines ARO Total Bank Worth (from the Data reactivity worth per the Sheet 1 table) to be 7.425 %L\k/k and records on Data following: Sheet 1 (Block B.l.a).

Using the ARO Total Bank Worth table on Data Sheet 1, COMMENTS:

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

i (Step VILB.l.a) 9.C Using Curve Book Figures 9.lC Using Curve Book Figure CB-24B, determines CB-24A, 24B or CB-24C, integral rod worth to be ZERO and records on Data Determine integral rod worth Sheet 1 (Blocks B.1.b.1) and B.l.b).

for the current bank position AND Enter this value on Data Sheet 1. COMMENTS:

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

%L\k/k AND Record on Data Sheet 1.

(Step VII.B.l.b)

10. Subtract the integral rod 10.1 Determines TBW-IRW is 7.425 %L\k/k and records worth from the Total Bank on Data Sheet 1 (Block B.l.c).

Worth AND Enter the result on Data Sheet 1.

COMMENTS:

(Step VILB.l.c)

RTL#A5.640U 1/2-ADM-1301.F04 Page 9 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perfonn Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) SRO ONLY STEP STANDARD

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

14. Multiply this result by 0.9 to 11.1 Detennines 90% ofTBW to be 6.6825 %8k/k and apply a 10% uncertainty records on Data Sheet 1 (Block B .I.d).

AND Enter the result on Data Sheet 1.

COMMENTS:

(Step VII.B.I.d) l2.C If ONE rod is inoperable I2.1C Detennines stuck rod worth to be 2.330 %8k/k and (untrippable), Record "Worst records on Data Sheet 1 (Block B.2).

Case Stuck Rod with Inoperable Rod" worth on Data Sheet 1. Value is COMMENTS:

detennined from Column "B" on Attachment 2 for the appropriate Cycle Burnup.

(Step VII.B.2.b)

13. Subtract Stuck Rod(s) Worth 13.1 Determines 90% Total Bank Worth minus Stuck from the 90% Total Bank Rod(s) Worth to be 4.3525 %8k/k and records on Worth value AND Enter the Data Sheet 1 (Block B.3).

result on Data Sheet 1.

(Step VII.B.3) COMMENTS:

14. Determine Power Defect as 14.1 Record RCS Boron Concentration of 838 ppm on follows: Data Sheet 1 (Block B.4.a).

Record RCS Boron Concentration results from COMMENTS:

Chemistry on Data Sheet 1.

(Step VII.BA.a)

I

RTL#A5.640V 112-ADM-130 I.F04 Page 10 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) SRO ONLY STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR S~T or "V" FOR VNSAT)=> SIU

15. Using Curve Book Figure 29, 115.1 Determines B-IO Correction Factor to be 0.895 and Determine the B-1 0 records on Data Sheet 1 (Block BAb).

Correction Factor for the present Bumup (If between two Bumup values, Use the COMMENTS:

B-10 Correction Factor for the greater MWD/MTU Bumup entry) AND Record on Data Sheet 1.

(Step VILBA.b)

! 16. Determine Corrected Boron 16.1 Determines Corrected Boron Concentration to be 750 Concentration by multiplying ppm and records on Data Sheet 1 (Block BA.c).

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

Record on Data Sheet 1.

(Step VILBA.c)

17. Using Curve Book Figure 21, 17.1 Determines ABSOLUTE VALUE of the Power Determine the ABSOLUTE Defect to be 2340 pcm and records on Data Sheet 1 VALUE of the Power Defect (Block BAd).

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

this value on Data Sheet 1.

(Step VILBA.d)

I

RTL#A5.640U I/2-ADM-I301.F04 Page 11 of 12 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perfonn Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) SRO ONLY STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT)=> S/U 18.C Divide value from curve (in 18.1C Converts ABSOLUTE VALUE of the Power Defect pcm) by 1000 to convert to of2340 pcm to 2.34 %~k/k and records on Data

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

Sheet 1.

(Step VII.BA.e)

COMMENTS:

19. Add 0.150 % ~k/k for 19.1 Detennines Power Defect plus operating temperature operating temperature band band margin to be 2049 % ~k/k and records on Data margin to the Power Defect Sheet 1 (Block BA.f).

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

1. COMMENTS:

(Step VII.BA.f) 20.C Detennine SHUTDOWN 20.1 C Detennines SDM to be 1.8625 % ~k/k and records on MARGIN by subtracting Data Sheet 1 (Block BA.f) AND space provided on Power Defect (Step candidate direction sheet.

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

1.

(Step VII.B.5)

RTL#A5.640U 1/2-ADM-130 1.F04 Page 12 of 12 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-035 JPM TITLE: Perform Shutdown Margin Calculation (At Power and JPM REVISION: 0 ONE Inoperable Rod) SRO ONLY STANDARD tes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT =>

21.C Consult the Acceptance 21.1 Consults the Acceptance Criteria, LRM 5.1.2, and Criteria for acceptable Technical Specification 3.1.1.

performance.

2I.2C Determines SDM is within limits and records on (Step VILC.I) space provided on candidate direction sheet.

COMMENTS:

EVALUATOR CUE:

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

BVPS - SBS Unit 2 20ST-49.1 Revision 16 Operating Surveillance Test Page 12 of 17 Shutdown Margin Calculation (Plant Critical)

(Updated For Cycle 15)

~lfJ£ l\N<.wfr

,. /1- 11 U r\

KE"~JC~ATASHEET1

~HUTDOWN MARGIN CALCULATION A. 4. CBD Steps Withdrawn (OR CBC If CBD @ 0 steps)

5. Reactor Power

6. Number of Inoperable Rods B. 1. a. ARO Total Bank Worth (See Table above) ~BW)~~~~,,~__~~

b. Integral Rod Worth (Curve Book Figure 24A, 24B OR 24C) (IRW)

1) ~ (pcm from B.1.b) X ~

1000pan

c. TBW (B.1.a) -IRW (B.1.b.1)

d. 90% Current Total Bank Worth 0.9x7*125 (B.1.c)

2. Stuck Rod(s) Worth

3. (90% Total Bank Worth) - (Stuck Rod(s) Worth)

(,_"S25 (B.1.d) l-( 2.. 330 (B.2)

=4.3SZ50IoAkIk

4. a. RCS Boron Concentration = 838 ppm

b. B*10 Correction Factor (CB Figure 29) =0.8'5

= 7S0 ppm 2310

d. ABSOLUTE VALUE of Power Defect (CB Figure 21) = pan

e. 2310 1%Aklk (pan from S.4.d) x - -

1000 t3.3~ c:\

f. Power Defect + Operating temperature band margin 2,,? '" (B.4.e) + 0.150% AkIk = 2.11 %AkIk

5. SHUTDOWN MARGIN (Acceptance Criteria* Within Limits Specified In COLR)

(~.35Z5 ).( 1*~1 )

(B.3) (B.4.f)

(1) _ __

Initial (2) _ __

Initial DATA SHEET 1

RTL#A5.640U 112-ADM-130 1.F04 Page 3 of7 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-024 JPM REVISION: 1 JPM TITLE: Determine Availability For Call-in (3 ROs) SRO ONLY KIA

REFERENCE:

2.1.3 3.9 TASK ID: 0481-002-03-043 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D FAULTED JPM I:8J ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Ini tial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Narne/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-J30 1.F04 Page 4 of7 Revision J OPERA TIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Determines that working hour limits ofNOP-LP-4011, FENOC Work Hour Control, will be exceeded for ROs Bill and Joe AND NOT exceeded for Sam.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to perform the task "Determine availability for call-in".

INITIAL CONDITIONS: Both Units have been in Mode 1 for the past 100 days. Today is 8114110. The daylight RO for 8115/10 has called in sick. It is desired to replace the daylight RO by assigning an RO to till this vacancy.

Three ROs are available to assume this vacancy, beginning at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on 8115110. The available RO replacements have the listed work hour history.

INITIATING CUE: As the Unit Supervisor, determine which one(s), if any ofthe available RO replacements are able to work the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months daylight shift on 8/1511 0 without violating the 10CFR 26 Work Hour Limits specitied in NOP LP-4011, FENOC Work Hour Control. Explain why or why not.

Document your results on the sheet provided.

REFERENCES:

NOP-LP-4011, FENOC Work Hour Control, Rev. 3 TOOLS: Calculator.

HANDOUT: Working hour history; NOP-LP-4011, FENOC Work Hour Control, Rev. 3

RTL#A5.640U 112-ADM-130 1.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perform the task "Determine availability for call-in".

INITIAL CONDITIONS: Both Units have been in Mode 1 for the past 100 days. Today is 8/14110. The daylight RO for 8/15/10 has called in sick. It is desired to replace the daylight RO by assigning an RO to fill this vacancy.

Three ROs are available to assume this vacancy, beginning at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on 811511 O. The available RO replacements have the listed work hour history.

INITIATING CUE: As the Unit Supervisor, determine ~hich one(s), if any of the available RO replacements are able to work the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months daylight shift on 811511 0 without violating the 10CFR 26 Work Hour Limits specified in NOP LP-40 11, FENOC Work Hour Control. Explain why or why not.

Document your results on the sheet provided.

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 JPMf!.

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-1301.F04 Page 6 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-024 JPM REVISION: 1 JPM TITLE: Detennine Availability For Call-in (3 ROs) SRO ONLY STEP STANDARD

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

EVALUATOR CUE:

PROVIDE WORK HISTORY SHEET (LAST PAGE OF JPM)

START TIME: _ _ _ _ _ __

1. Evaluate work hour history. 1.1 Compares work hour history against NOP-LPAO 11, FENOC Work Hour Control requirements of section

4.2. COMMENTS

2.C Detennines working hour 2.1 C Detennines that RO Bill may NOT be called in.

limit will be exceeded for RO 2.2C Detennines that RO Bill will exceed 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in 48 Bill, and documents on the hours after working 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months on 8115. (Turnover times sheet provided. are not considered in this detennination) 2.3C Documents the result in the space provided.

EVALUATOR NOTE:

Bill also does not have the required 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months break before assuming the shift. This is an Alternate acceptable answer.

COMMENTS:

RTL#AS.640U 1/2-ADM-\301.F04 Page 7 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-024 JPM REVISION: 1 JPM TITLE: Determine Availability For Call-in (3 ROs) SRO ONLY STEP STANDARD

( "c" Denotes CRITICAL STEP) Indicate "S" FOR SAT or "V" FOR VNSAT):::;>

3.C Determines working hour 3.1 C Determines that RO Joe may NOT be called in.

limit will be exceeded for RO 3.2C Determines that the RO Joe will exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 Joe, and documents on the days.

sheet provided. 3.3C Documents the result in the space provided.

COMMENTS:

4.C Determines working hour 4.1 C Determines that RO Sam may be called in.

limit will NOT be exceeded 4.2C Determines that RO Sam meets all of the call-in for RO Sam, and documents requirements on the sheet provided. 4.3C Documents the result in the space provided.

COMMENTS:

EVALUATOR CUE:

The evaluation on this JPM is complete when the applicant determines whether the ROs may be called m.

STOP TIME: _ _ _ _ _ __

WORK HISTORY T/O = Turnover time Joe, Sam, and Bill are all 8- hour Operations Shift workers.

Date Joe Sam Bill 7/18/10 through Vacation Vacation Vacation 8/7110 8/8/10 OFF 0700-1500 1500-2300 T/O 20 min T/O 20 min I 8/9/10 0700-1900 0700-1900 1500-2300 T/O 20 min T/O 20 min T/O 20 min I 8/10110 0700-1900 1100-2300 OFF I T/O 20 min T/O 20 min 8111/10 0700-1900 1500-2300 OFF T/O 20 min T/O 20 min 8112/10 0700-1900 1500-2300 0700-1500 T/O 20 min T/O 20 min T/O 20 min I 8113/10 0700-1900 0700-1500 1100-2100 T/O 20 min T/O 20 min T/O 20 min I 8/14/10 0700-1700 0700-1900 0700-2300 T/O 20 min T/O 20 min T/O 20 min I 8115110 OFF OFF OFF RESULTS:

WORK HISTORY ANSWER KEY DO NOT GIVE TO STUDENTS T/0 = Turnover tinle Joe, Sam, and Bill are all 8- hour Operations Shift workers.

Date Joe Sam Bill i 7118110 I I through Vacation Vacation Vacation 8/7110 I I

8/8/10 OFF 0700-1500 1500-2300 I T/O 20 min T/O 20 min 8/9/10 0700-1900 0700-1900 I 1500-2300

\

T/O 20 min T/O 20 min I T/O 20 min 8110/10 0700-1900 1100-2300 OFF i T/O 20 min T/O 20 min 8111110 0700-1900 1500-2300 OFF T/O 20 min T/O 20 min 811211 0 0700-1900 1500-2300 0700-1500 I

i T/O 20 min T/O 20 min T/O 20 min I 8113/10 I 0700-1900 0700-1500 1100-2100 i

T/O 20 min T/O 20 min T/O 20 min I 8114110 0700-1700 0700-1900 0700-2300 I

i TIO 20 min TIO 20 min TIO 20 min I 8115110 OFF OFF OFF RESULTS:

1. RO Bill may NOT be called in. He will exceed 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after working 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months on 8/15.

(Alternate acceptable answer - Bill does not have the required 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months break)

2. RO Joe may NOT be called in. He will exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 days.

3. RO Sam may be called in. He meets all of the call-in requirements

RTL#A5.640U 1/2-ADM-1301.F04 Page 3 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-033 JPM TITLE: Determine Compensatory Actions for Low CO 2 Tank Level JPM REVISION: 0 SRO ONLY KIA

REFERENCE:

2.2.37 4.6 TASK ID: 1300-029-03-023 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINn'JG D FAULTEDJPM ~ ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EV ALUATION RESULTS Performer Name: Performer SSN:

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

JPM RESULTS:

D SAT D lTNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-J30 J.F04 Page 4 of7 Revision J OPERAnONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Required actions of 112-ADM-1900, Fire Protection Program Attachment B items 4a and 4b are identified.

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: You are to Determine appropriate Compensatory Actions for Low C02 Tank Level.

INITIAL CONDITIONS: Both Units have been in Mode 1 for the past 100 days. The 24 Ton C02 storage tank 2FPD-TK24 is empty and on clearance for maintenance. The tour operator reports the following C02 Storage Tank levels:

10 Ton CO2 Storage Tank 2FPD-TK22 is 86%

10 Ton CO2 Storage Tank 2FPD-TK23 is 80%.

7.5 Ton C02 Storage Tank 2FPD-TK21 is 70%

INITIATING CUE: Determine the required 1/2-ADM-1900, Fire Protection Program compensatory actions, if any, for these C02 Storage Tank levels. List any required actions on the attached answer sheet.

REFERENCES:

1I2-ADM-1900, Fire Protection Program Rev. 22 TOOLS: None HANDOUT: 1I2-ADM-1900, Fire Protection Program Rev. 22

RTL#AS.640U I12-ADM-130 l.F04 Page 5 of7 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to Determine appropriate Compensatory Actions for Low CO2 Tank Level.

ThTITIAL CONDITIONS: Both Units have been in Mode 1 for the past 100 days. The 24 Ton CO2 storage tank 2FPD-TK24 is empty and on clearance for maintenance. The tour operator reports the following CO2 Storage Tank levels:

10 Ton C02 Storage Tank 2FPD-TK22 is 86%

10 Ton CO2 Storage Tank 2FPD-TK23 is 80%.

7.5 Ton CO2 Storage Tank 2FPD-TK21 is 70%

INITIATING CUE: Determine the required 112-ADM-1900, Fire Protection Program compensatory actions, if any, for these CO2 Storage Tank levels. List any required actions on the attached answer sheet.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 1.F04 Page 6 of7 Revision 1 OPERATrONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-033 JPM TITLE: Determine Compensatory Actions for Low CO2 Tank Level JPM REVISION: 0 SROONLY STEP NDARD

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

EVALUATOR CUE:

Provide student with attached answer sheet to document the determination.

START TIME: _ _ _ _ _ __

I.C Determines 1I2-ADM-l900, 1.] C Utilizes Attachment B item 4a and determines the Fire Protection Program item following actions are required:

4a required actions Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Establish a continuous fire watch in the following areas:

Cable Spreading Area Cntrl. Bldg. Elev. 725

Process Rack Area Cntrl. Bldg. Elev. 707

Cable Tunnel (Between Cntrl. & Aux. Bldgs.) Elev.

712

West Cable Vault Elev. 735

Cable Vault & Rod Cntrl. Area Elev. 755

Cable Spreading Area Service Bldg. Elev. 745 l.2e Restore to operable status within 14 days

COMMENTS:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 7 of7 Revision 1 OPERAnONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-033 JPM TITLE: Determine Compensatory Actions for Low CO2 Tank Level JPM REVISION: 0 SROONLY

STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "UI! FOR UNSAT)~

2.C Determines 1/2-ADM-1900, 2.1 C Utilizes Attachment B item 4b and determines the Fire Protection Program item following actions are required:

4b required actions Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Establish an hourly fire watch patrol and establish controls to prohibit transient combustibles and ignition sources in the following areas:

Relay Room Elev. 755

Emergency Diesel Generator Bldg. Rooms

East Cable Vault Elev. 735 2.2C Identifies the need to verifY the operability of Early Warning Fire Detection in the following affected areas:

Relay Room Elev. 755

Emergency Diesel Generator Bldg. Rooms

East Cable Vault Elev. 735 2.3C Restore to operable status within 14 days COMMENTS:

EVALUATOR CUE:

That Completes this lPM.

STOP TIME: _ _ _ _ _ __

ANSWER SHEET PROVIDED TO STUDENT 1/2-ADM-1900, Fire Protection Program required Actions, if any, if there are none, simply state NONE:

RtL#A5.640U 1/2-ADM-1301.F04 Page 3 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-0 14 JPM REVISION: 1 JPM TITLE: Approve Emergency Exposure KIA

REFERENCE:

2.3.4 3.7 TASK ID: 1350-006-03-023 JPM APPLICATION: cgJ REQUALIFICATION cgJ INITIAL EXAM o TRAINING o FAULTED JPM cgJ ADMINISTRA TIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

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

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 15 Minutes Actual minutes Critical: cgJ No Time: Time:

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 I.F04 Page 4 of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Detennine appropriate Emergency authorization limit in accordance with EPP/IP 5.3 (Limit exposure to: 75 rem TEDE; 225 rem lens of eye, 750 rem organ CDE)

RECOMMENDED Classroom STARTING LOCATION:

DIRECTIONS: Detennine the Emergency Exposure Authorization Limit.

INITIAL CONDITIONS:

A Site Area Emergency has been declared at Unit 2.

An individual is trapped and bleeding in a Locked High Radiation Area.

An immediate response is necessary to save their life.

It has been clearly detennined that actions establishing adequate or equivalent protection, with less dose are not readily available.

Bill Jones, a qualified radiation worker has volunteered to perfonn the rescue activity and has been briefed on risks of projected radiation exposure.

Bill Jones has a year to date exposure of 880 mR (TEDE).

The area dose rate is 8,110 mRlhr and there is no airborne radioactivity present.

The rescue activity could take up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

INITIATING CUE: As the Emergency Director, you are to evaluate the listed conditions and determine the Emergency Exposure Authorization Limit.

Document your detennination in the box below. The Emergency Exposure Authorization Fonn will NOT be filled out at this time.

REFERENCES:

112*EPP/IP 5.3 Emergency Exposure Criteria and Control, Rev. 10 TOOLS: None HANDOUT: 1I2-EPP/IP 5.3 Emergency Exposure Criteria and Control, Rev. 10

RtL#A5.640U I12-ADM-130 I.F04 Page 5 of6 Revision I OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: Detennine the Emergency Exposure Authorization Limit.

INITIAL CONDITIONS:

A Site Area Emergency has been declared at Unit 2.

An individual is trapped and bleeding in a Locked High Radiation Area.

An immediate response is necessary to save their life.

It has been clearly detennined that actions establishing adequate or equivalent protection, with less dose are not readily available.

Bill Jones, a qualified radiation worker has volunteered to perform the rescue activity and has been briefed on risks of projected radiation exposure.

Bill Jones has a year to date exposure of 880 mR (TED E).

The area dose rate is 8,110 mRlhr and there is no airborne radioactivity present.

The rescue activity could take up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

INITIATING CUE: As the Emergency Director, you are to evaluate the listed conditions and detennine the Emergency Exposure Authorization Limit.

Document your detennination in the box below. The Emergency Exposure Authorization Form will NOT be filled out at this time.

DETERMINATION:

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 perfonn as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 I.F04 Page6of6 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2AD-0 14 I JPM REVISION: 1 i JPM TITLE: Approve Emergency Exposure "S" FOR START TIME: ----------------

I.C Per Attachment A, determine 1.1 C Using Attachment A, determines the Emergency the appropriate Emergency Exposure Authorization Limit:

Exposure Authorization Limit.

Block 1:

(Step 8.1.1)

Declared Emergency YES Site Area 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 briefed on risks of projected radiation exposure Block 4C:

Sr. Vice President authorization for NO (3,332 mR) exposure >75 rem Block 5C:

Limit exposure to: 75 rem TEDE; 225 rem lens of eye, 750 rem organ CDE COMMENTS:

EVALUATOR CUE:

That completes this JPM STOP TIME:

k"tL#A5.640U 1I2-ADM-130I.F04 Page30fS Revision I JPM NUMBER: 2AD-034 JPM TITLE: Classify an Emergency Event (Scenario Specific)

JPM REVISION: 0 KJ A

REFERENCE:

2.4.41 4.6 TASK ID: 1350-004-03-023 JPM APPLICATION: r8J REQUALIFICATION r8J INITIAL EXAM D TRAINING D FAULTED JPM r8J ADMINISTRATIVE JPM EVALUA TION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EV ALUATION RESULTS Performer Name: Performer S SN:

Time D Yes Allotted 10 Minutes Actual minutes Critical: r8J No Time: Time:

JPM RESULTS:

D SAT D lJNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-1301.F04 Page 4 of8 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: The correct EPP classification is made for the associated scenario AND all "critical" steps of the initial notification form are correctly completed.

RECOMMENDED Simulator STARTING LOCATION:

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

INITIAL CONDITIONS: The simulator scenario just completed.(2LOT7 NRC Exam)

INITIATING CUE: As the Unit Supervisor, you are to classify the events in the scenario

\....' just completed in accordance with EPP/I-1a, Recognition and Classification of Emergency Conditions AND complete the initial notification form.

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

The code word is "TANGO"

Unit 1 is at 100% steady state power

Wind direction at 150' is 65°

Wind speed at 35' is 7 mph

REFERENCES:

EPP/I-l b, Recognition and Classification of Emergency Conditions, Rev. 14, 1I2-EPP-IP-1.1.F01, Nuclear Power Plant Initial Notification Form Rev. 4 TOOLS: None HANDOUT: EPP/I-l b, Recognition and Classification of Emergency Conditions, Rev. 14, 1I2-EPP-IP-l.l.FO 1, Nuclear Power Plant Initial Notification Form Rev. 4

1I2-EPP-IP-1.1.FOl ItNSWER I\ty RTL# AS.71SDP SC.ENA RIO #- l Rev. 4 Page 1 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM

1. Call Status ) ( THIS IS A DRILL o THIS IS AN ACTUAL EVENT

2. This is:

At: Beaver Valley Power Station My Tele~hone Number IS:

724~643-8000 The Code Word is:""J I"

N'--O

\7 Notification Time is:

"C.' 3. Emergency Classification: 0 Unusual Event o General Emergency

~ Alert o This event has been terminated o Site Area Emergency Unites): 1 6) Both Declaration Time: T, fV\ e.. Date: ---'D-=-.;;.I9--=......a.v..;:oe-=:-_ __

Power Level at time of Notification UNIT 1 IbO % UNIT 2 (J %

This represents alan:

\'

C )5 Initial Declaration II D Escalation ] In Classification Status D No Change L

.1

4. The Emergency Action Level (EAL) number is: UB 1.1.1 Brief non~technical description of the event:

D No Radiological Release in Progress due to the event

'"C" 5. There is: ~ Arl Airborne Radiological Release in Progress due to the event A Liquid Radiological Release in Progress due to the event e."

,\

6. Wind Direction is FROM: degrees at 150' Wind Speed is:

1 mph at 35'

7.

Conclusion:

~ THIS IS A DRILL D THIS IS ANACTUAL EVENT APPROVED: DATE:

PEER CHECK

1/2-EPP-IP-1.1.FOI RTL# A5.715DP Rev. 4 Page 2 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM BEAVER VALLEY POWER STATION PROTECTIVE ACTION RECOMMENDATION (PAR) o INITIAL _ _ _ TIME o UPGRADED _ _ _ TIME

~ NONE (Done) _ _ _ !NIT.

D N/A D 2 Miles Evacuate 360 0 D 5 Miles 0 10 Miles I------AND D N/A Evacuate Downwind Wedge D 5 Miles (circle appropriate sectors)

D 10 Miles (circle appropriate sectors)

A B C D E F G H J K L M N P Q R D N/A D Remainder of lO-Mile Emergency Planning Zone (EPZ)

Shelter D lO-Mile EPZ D 0-2 Miles, 360 Degrees and 5 Mile Downwind Wedge (circle appropriate sectors)

A B C D E F G H J K L M N P Q R D Administer Potassium Iodide in accordance with State Plan D Plant Conditions Release In Progress Dose Projection REASON Other (Explain)

Other Info:

Current Wind Direction is FROM _ _ _ degrees at 150' Wind Speed is _ _ _ mph at 35' APPROVED:

DATE PEER CHECK:

1I2-EPP-IP-1.l.FOl ft NSWE K 1\ t Y3 RTL# A5.715DP Rev. 4 SC.ENA RID # Page 1 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM

1. Call Status )r! THIS IS A DRILL THIS IS AN ACTUAL EVENT

2. This is:

At: Beaver Valley Power Station My Tele~hone Number IS:

724-643-8000 The Code Word is: -rAN I " \7

'--0 Notification Time is:

..- .1 C 3. Emergency Classification: 0 Unusual Event o General Emergency o Alert o This event has been terminated

~ Site Area Emergency Unit(s): o Both Declaration Time: II fV\ e-- Date: _f)""""'--.:.A-...::.....LV...::le~_ __

Power Level at time of Notification UNIT 1 IbO % UNIT2 rJ %

This represents alan: "

C II

~ Initial Declaration o Escalation ] In Classification Status o No Change

4. The Emergency Action Level (EAL) number is: JitB 1.3 Briefnon-technical description of the event: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

\1\ II o No Radiological Release in Progress due to the event C 5. There is: ~ An Airborne Radiological Release in Progress due to the event o A Liquid Radiological Release in Progress due to the event e."

\' 6. Wind Direction is FROM: to 5 degrees at 150' Wind Speed is:

1 mph at 35'

7.

Conclusion:

~ THIS IS A DRILL o THIS IS ANACTUAL EVENT APPROVED: DATE:

PEERCIIECK

1I2-EPP-IP-1.1.FOl RTL# A5.715DP Rev. 4 Page 2 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM BEAVER VALLEY POWER STATION PROTECTIVE ACTION RECOMMENDATION (PAR) 0 INITIAL TIME 0 UPGRADED TIME

~ NONE (Done) !NIT.

0 N/A 0 2 Miles Evacuate 3600 0 5 Miles 0 10 Miles AND 0 N/A Evacuate Downwind Wedge 0 5 Miles (circle appropriate sectors) 0 10 Miles (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o N/A Shelter o Remainder of 10-Mile Emergency Planning Zone (EPZ) o lO-Mile EPZ o 0-2 Miles, 360 Degrees and 5 Mile Downwind Wedge (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o Administer Potassium Iodide in accordance with State Plan o Plant Conditions D Release In Progress 0 Dose Projection REASON o Other (Explain)

Other Info:

Current Wind Direction is FROM . . _ _ degrees at 150' Wind Speed is _ _ _ mph at 35' APPROVED:

DATE PEER CHECK:

1I2-EPP-IP-l.l.FOl ffNSWEt< r\ty RTL# A5.715DP Rev. 4 SC.ENA RIO #-

NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM 4 Page 1 of2

1. Call Status ) ( THIS IS A DRILL o THIS IS AN ACTUAL EVENT

2. This is:

Beaver Valley Power Station

At:

My Tele~hone 724-643-8000 The Code Word is: -rJ N"-0 Notification Time is:

Number IS: I" \7 -----

e

\, "

3. Emergency Classification: 0 Unusual Event o General Emergency o Alert o This event has been terminated

~ Site Area Emergency Unit(s): o Both Declaration Time: T, fV\ e-- Date: ---'DO:""';;'~...::.....Lh...;:oe..:....._ __

Power Level at time of Notification UNIT I 100 % UNIT 2 rJ This represents alan: " C II ~ fIt Initial Declaration o Escalation In Classification Status o No Change

4. The Emergency Action Level (EAL) number is: I. 3.2.

Briefnon-technical description of the event: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

o No Radiological Release in Progress due to the event

'"C"5. There is: ~ An Airborne Radiological Release in Progress due to the event o A Liquid Radiological Release in Progress due to the event e.

,l "

6. Wind Direction is FROM: ~_~ees at 150' Wind Speed is: 1 mph at 35'

7.

Conclusion:

~ THIS IS A DRILL 0 THIS IS AN ACTUAL EVENT APPROVED: DATE:

PEER CHECK

1I2-EPP-IP-1.1.FOl RTL# A5.715DP Rev. 4 Page 2 of2 NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM BEAVER VALLEY POWER STATION PROTECTIVE ACTION RECOMMENDATION (PAR) o INITIAL _ _ _ TIME o UPGRADED _ _ _ TIME

~ NONE (Done) _ _ _ INIT.

0 N/A 0 2 Miles Evacuate 3600 0 5 Miles 0 10 Miles l-----AND 0 N/A Evacuate Downwind Wedge 0 5 Miles (circle appropriate sectors) 0 10 Miles (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o N/A Shelter o Remainder of 10-Mile Emergency Planning Zone (EPZ) o 10-Mile EPZ o 0-2 Miles, 360 Degrees and 5 Mile Downwind Wedge (circle appropriate sectors)

A B C D E F G H J K L M N P Q R o Administer Potassium Iodide in accordance with State Plan o Plant Conditions o Release In Progress 0 Dose Projection REASON o Other (Explain)

Other Info:

Current Wind Direction is FROM _ _ _ degrees at 150' Wind Speed is _ _ _ mph at 35' APPROVED:

DATE PEER CHECK:

RTL#A5.640U 112-ADM-130LF04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 K/ A

REFERENCE:

004A4.07 3.9/3.7 TASK ID: 0071-011-01-013 004A4.12 3.8/3.3 JPM APPLICATION [ZJ REQUALIFlCATION [ZJ INITIAL EXAM 0 TRAINING o FAULTED JPM o ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

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

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 10 Minutes Actual minutes Critical: [ZJ No Time: Time:

0 SAT JPM RESULTS:

0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

I Evaluator Signature:

RTL#A5.640U 1I2-ADM-1301.F04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Approximately 226 gallons of primary makeup water added to the RCS at a rate of75 gpm.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to perform a Reactor Coolant System dilution.

INITIAL CONDITIONS:

The plant is 100% power, with all systems in NSA.

The Control Rods are fully withdrawn.

Tavg is 1°F below Tref

Current RCS boron concentration is 1030 ppm.

IA W the current reactivity placard, 226 gallons of dilution water will be needed to raise Tavg 1°F.

INITIA TING CUE: Your supervisor directs you to dilute the RCS 226 gal in accordance with 20M-7.4.AR, "Blender Operation in Mode 1", at a rate of75 gpm to raise Tavg 1°F. All procedure required initial conditions are satisfied. It is NOT desired to take manual control ofVCT Level and Pressure. It is desired to use the "DILUTE" Mode.

REFERENCES:

20M-7.4.AR, "Blender Operation in Mode 1", Revision 7 Reactivity Plan (Placard) to coincide with 226 gals/OF.

TOOLS: None 20M-7.4.AR, "Blender Operation in Mode 1", Revision 7 HANDOUT:

RTL#A5.640U 112-ADM-1301.F04 Page 5 of 10 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

o Read:

TASK:

You are to perform a Reactor Coolant System dilution.

INITIAL CONDITIONS:

The plant is 100% power, with all systems in NSA.

The Control Rods are fully withdrawn.

Tavg is 1°F below Tref.

Current RCS boron concentration is 1030 ppm.

IA W the current reactivity placard, 226 gallons of dilution water will be needed to raise Tavg 1°F.

INITIATING CUE:

Your supervisor directs you to dilute the RCS 226 gal in accordance with 20M-7.4.AR, "Blender Operation in Mode I", at a rate of75 gpm to raise Tavg 1°F. All procedure required initial conditions are satisfied. It is NOT desired to take manual control of VCT Level and Pressure. It is desired to use the "DILUTE" Mode.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 1,F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NlJMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 SIMULATOR SETUP:

Initialize to a MOL 100% power Ie. Reduce Tavg ~OI F below Tref.

Adjust [2CHS*FCVlI4A] pot setting to 568 units EVALUATOR CUE:

Provide candidate with a copy of20M-7.4,AR, "Blender Operation in Mode 1". When candidate is ready to begin JPM, PLACE the simulator in RUN.

START TIME: - - - - - - - - - - - - - - - -

1. Review procedure, 1.1 Reviews procedure provided.

COMMENTS:

ROand 2.1. NI A - Initiating cue states that it is NOT desired to take SM/US, take control ofVCT manual control of VCT level and pressure.

Level and Pressure, EVALUATOR CUE:

IF necessary, remind the candidate to refer to initiating cue, COMMENTS:

RTL#A5.640U 112-ADM-130 1.F04 Page 7 of 10 Revision I OPERATIONS JOB PERFORMANCE :MEASURE JPM NUMBER: 2CR-089 I JPM TITLE RCS 0'1 '

JPM REVISION: 7 i : 1 utlOn STANDARD "en Denotes CRITICAL STEP (Indicate "S" FOR SAT or "U" FOR UNSAT)~ JSitU 3.C Place Boric Acid Blender 3.1 C Places Boric Acid Blender Makeup Control Switch to Control Switch to Stop STOP.

3.2 Verifies green light - LIT and red light NOT LIT.

COMMENTS:

4.C Set [2CHS*FCVI14A] to 4.1 C Adjusts [2CHS*FCVI14A] pot setting to 468 units desired flow rate. based on the following formula:

75gpm = 4.68 16gpm EVALUATOR NOTE:

Pot should be set at 468 units +/-2 units. I COMMENTS:

5.C Set Total Makeup From Blender 5.IC Adjusts [2CHS-FQIS 168] to 226 (Green LED)

Flow Totalizer.

5.2C Depresses [2CHS-FQISI68] RESET PB.

5.3 Verifies [2CHS-FQISI68] is reading ZERO (Red LED).

COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 SAT or "U" FOR 6, Ensure [2CHS-FQISl13], Boric 6.1. Verifies that [2CHS-FQIS 113], Boric Acid Flow To Acid Flow To Blender is set to Blender is set to ZERO (Red and green LED),

zero, COMMENTS:

7, C Place makeup Mode Selector 7.1C Places the makeup Mode Selector switch in DILUTE, switch in Dilute or Alternate Dilute.

EVALUATOR NOTE:

Initiating cue stated that it is desired to use the "DILUTE" mode, COMMENTS:

8. C Initiate dilution. 8.1 C Places Boric Acid Blender Makeup Control Switch to START.

8.2 Verifies green light - NOT LIT and red light LIT.

COMMENTS:

RTL#A5.640U 112-ADM-130 I.F04 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE JMEASURE JPM NUMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7

9. VerifY proper operation. 9.1 Verifies [2CHS*FCVl14B] green light - NOT LIT and red light LIT.

9.3 Ifin ALTERNATE DILUTE, verifies [2CHS-FCV113B] OPENS.

9.2 Verifies [2CHS-FRl13] is reading ~ 75 gpm.

COMJMENTS:

EVALUATOR NOTE: The candidate may elect to NI A JPM Steps # 10 & 11 because they are only necessary for large amounts ofPG water or frequent dilutions.

10. Operate pressurizer heaters to 10.1 Places control switch for 2RCS*H2A, B, D, or E to equalize boron concentration. ON.

10.2 Verifies green light NOT LIT and red light LIT.

EVALUATOR CUE:

Ifnecessary, role-play the Unit Supervisor and direct candidate to energize one additional backup heater group.

COMMENTS:

RTL#A5.640 U 1I2-ADM-1301.F04 Page 10 oflO Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-089 JPM TITLE: RCS Dilution JPM REVISION: 7 STEP STANDARD

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

11. Verify at least one RCP in 11.1 Checks at least one RCP in operation and notes this operation at least once per hour must be done at least once per hour.

during dilution and document in narrative log. 11.2 Indicates this check must be logged in the Narrative Log.

EVALUATOR CUE:

Another operator will make the appropriate log entry.

COMMENTS:

12. When the dilution or series of 12.1 Verifies Total Makeup From Blender Flow Totalizer dilutions is complete, Perform [2CHS-FQIS 168] reaches 226 gal.

the following to place the makeup control systems in 12.2 Places Boric Acid Blender Makeup Control Switch automatic operations: to STOP.

Place the Boric Acid Makeup 12.3 Verifies green light - LIT and red light NOT LIT.

Blender Control Switch in COMMENTS:

STOP.

i EVALUATOR NOTE:

It is not desired to set-up the blender for AUTOMATIC operation.

EVALUATOR CUE:

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

RTL#A5.640U 112-ADM-130 l.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-560 !

JPM REVISION: 3 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation KJA

REFERENCE:

006A4.05 3.9/3.8 TASK ID: 0531-002-05-013 006A4.07 4.4/4.4 JPM APPLICATION: IZ;J REQUALIFICATION IZ;J INITIAL EXAM D TRAINING IZ;J F AULTED JPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time D Yes Allotted 10 Minutes Actual minutes Critical: IZ;J No Time: Time:

JPMRESULTS:

D SAT D UN SAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

! Evaluator Signature:

i

R1L#A5.640U 1I2-ADM-130 l.F04 Page 4 oflO Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Cold Leg Recirculation established.

RECOMMENDED Simulator ST ARTING LOCATION:

DIRECTIONS: You are to perform the task, Transfer from Hot Leg to Cold Leg Recirculation.

INITIAL CONDITIONS:

The plant has experienced a large break LOCA 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago with all systems having functioned as designed.

The EOP's have been implemented normally to this point and the SI headers are currently split as expected.

The plant is currently in Hot Leg recirculation and has been for 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

A transfer from Hot Leg to Cold Leg Recirculation is required.

Charging High Head Safety Injection Pump [2CHS*P21C] is cleared for pump repairs.

INITIATING CUE: Your supervisor has directed you to transfer recirculation of the RCS from the Hot Legs to the Cold Legs using EOP 1.5, "Transfer from Hot Leg Recirculation to Cold Leg Recirculation".

REFERENCES:

Unit 2 EOP ES-1.5, "Transfer from Hot Leg Recirculation to Cold Leg Recirculation", Issue 1C, Rev 6 TOOLS: Shorting Bars HAf'.!'DOUT: Unit 2 EOP ES-1 5, "Transfer from Hot Leg Recirculation to Cold Leg Recirculation", Issue 1C, Rev 6

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

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

T ASK: You are to perform the task, Transfer from Hot Leg to Cold Leg Recirculation.

INITIAL CONDITIONS:

The plant has experienced a large break LOCA 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago with all systems having functioned as designed.

The EOP's have been implemented normally to this point and the SI headers are currently split as expected.

The plant is currently in Hot Leg recirculation and has been for 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

A transfer from Hot Leg to Cold Leg Recirculation is required.

Charging High Head Safety Injection Pump [2CHS*P21C] is cleared for pump repairs.

INITIATING CUE: Your supervisor has directed you to transfer recirculation of the RC S from the Hot Legs to the Cold Legs using EOP ES-l. 5, "Transfer from Hot Leg Recirculation to Cold Leg Recirculation".

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

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

Simulate performance or perform as directed the required task.

D Point to any indicator or component you verify or check and announce your observations, After determining the Task has been met announce" I have completed the JPM",

D Then hand this sheet to the evaluator,

RTL#A5.640U 112-ADM-130 1.F04 Page 6 of 10 Revision I OPERATIONS JOB PERFORMANCE 1\1EASURE JPM NUMBER: 2CR-560 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation JPM REVISION: 3

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

SIMULATOR SETUP:

Insert a Large Break LOCA and perform E-O, E-1, ES-1.3 and ES-1.4 actions. (Note this takes several hours of setup work) To setup for ES-l. 5 and associated fault which trips [2CHS*P21B] when 2SIS*MOV8888B is opened perform the following:

Select Event Trigger

Enter Event #

Enter in Event Tab XA20058R == 1 Ensure 2CHS*21C is on clearance (Yellow Tagged)

STARTTI1\1E: ______________

1. Review procedure. 1.1 Reviews EOP ES-l.5.

i CO:MMENTS' 2.1 Recirc Spray Pumps - no 2.1 Verifies 2RSS*P21C & D ammeters, flow indicators signs of cavitation. and pressure indications all STABLE.

2.2 Align RSS Pumps for Cold Leg Recirculation: Verify 2.2 Verifies [2RSS*P21C & D] BOTH Red lights - LIT

[2RSS*P21C & D] running. White lights - NOT LIT.

COMMENTS:

EVALUATOR CUE:

A Shorting Bar will be needed in the next step. When requested, Role-play the Shift Manager and supply the shorting bar.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-560 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation JPM REYISION: 3 STEP STANDARD

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

3. C Insert Shorting Bar and close 3.1 Contacts Shift manager and requests a shorting bar.

[2SIS*MOY8889].

3.2C Inserts into [2SIS*MOY8889] jacks.

(ES-I 5 steps 2.b & c) 3.2C Places [2SIS*MOY8889] CS to CLOSE.

3.3 Verifies Green light LIT and Red light NOT LIT.

COMNIENTS:

4.C Close [2SIS*MOY8887A & 4.1C Places [2SIS*MOY8887 A and B] CS to CLOSE.

B].

(ES-I.5 step 2.d) 4.2 Verifies Green lights - LIT and Red lights NOT LIT.

I COMMENTS:

5.C Open [2SIS*MOY8888A & S.IC Places [2SIS*MOY8888A and B] CS to OPEN.

B].

5.2 Verifies Green lights - NOT LIT and Red lights (ES-1. 5 step 2. e) LIT.

EVALUATOR NOTE:

[2CHS*P21B] is triggered to trip when 2SIS*MOY8888B control switch is placed to OPEN.

COMMENTS:

RTL#A5.640U 1I2-ADM-1301.F04 Page 8 of 10 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-560 ! r *

JPM REVISION: 3 JPM TITLE: [ransfer from Hot Leg to Cold Leg ReclrculatIOn STEP STANDARD

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

6. Verify flow indicated on 6.1. Verifies flow indicated on [2SIS*Fl945 & 946].

[2SIS*FI945 & 946].

! COMMENTS:

(ES-1.5 step 2.t)

~---F-A-I-TL-T-S-T-A-T-E-N-I-E-N-T-:-------------------+1 Alternate path begins here: Only ONE CHS Pump

'J

[2CHS*P21A] is available.

7. Verify two Charging Pumps 7.1 Verifies [2CHS *P21 A] White light - NOT LIT and runnmg. Red light LIT.

(ES-1.5 step 3.a and RNO a) 7.2 Verifies [2CHS*P21B] White light LIT and Red light - NOT LIT.

7.3 Determines that neither of the other Charging Pumps can be started and continues with RNO response.

EVALUATOR CUE: If an NLO is dispatched to check charging pump status, role play and acknowledge request. Cue candidate to continue on in the procedure.

COMMENTS:

RTIAA5.640U 1I2-ADM-1301.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-560 ,'JPM TITLE' Transfer from Hot Leg to Cold Leg Recirculation JPM REVISION: 3 ' .

Denotes CRITICAL STEP "S" FOR SAT or "U" 8,C Stop the running Charging 8.1C Places [2CHS*P21A] CS to STOP.

Pump, 8.2 Verifies White light - LIT and Red light - NOT (ES-1.5 step 3.a RNO a.I) LIT.

COMMENTS:

EVALUATOR CUE:

Shorting Bars will be needed in the next two steps, When requested, Role-play the Shift Manager and supply the shorting bars.

i 9,C Insert Shorting Bars and close 9.1 Contacts Shift manager and requests a shorting bar.

[2SIS*MOV869A].

9.2C Inserts into [2SIS*MOV869A] jacks.

(ES-1.5 step 3.c & d) 9.3C Places [2SIS*MOV869A] CS to CLOSE.

9.4 Verifies Green light - LIT and Red light - NOT LIT.

COMMENTS:

RTL#A5.640U 112~ADM-130 1.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-560 JPM TITLE: Transfer from Hot Leg to Cold Leg Recirculation JPM REVISION: 3 STEP STANDARD

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

10. COpen [2SIS-MOV836]. 10.1 Contacts Shift manager and requests a shorting bar.

(ES-1.5 step 3.e & t) lO.2C Inserts into [2SIS-MOV836] jacks.

1O.3C Places [2SIS-MOV836] CS to OPEN.

10.4 Verifies Green light - NOT LIT and Red light - LIT.

COMMENTS:

11. C Start previously running lI.lC Places [2CHS*P21A] CS to START. !

Charging Pump.

11.2 Verifies White light - NOT LIT and Red light -

(ES-I. 5 step 3. g) LIT.

COMMENTS:

12. Verify flow indicated on 12. I V erifi es flow indicated on [2SIS *FI940].

[2SIS*FI940].

COMMENTS:

(ES-1.5 step 3.h) i __

! EVALUATOR CUE:

That completes this JPM.

". . STOP TIME:

I

RTL#A5.640U l/2-ADM-130 1.F04 Page 3 of 10 Revision 1 JPM NUMBER: 2CR-056 I JPM REVISION: 7

JPM TITLE: Place Excess Letdown in Service I

KIA

REFERENCE:

004A.4.06 3.6/3.1 TASK ID: 0071-019-01-013 004A4.08 3.8/3.4 004A2.07 3.4/3.7 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D FAULTED JPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D J\"'RC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

~

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

JPM RESULTS:

D SAT D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 LF04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Excess letdown flow established. Normal charging and letdown secured. Excess letdown heat exchanger outlet temperature :'S140°F.

RECO"MNJENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to place Excess Letdown in Service.

INITIAL CONDITIONS: The plant is operating at 25% power during a plant startup. All systems are operating normally except for a leak on the CCP supply line to the non-regenerative heat exchanger. Isolation ofthis leak will require that normal charging and letdown be secured. Normal letdown is in servIce.

INITIATING CUE: The Unit Supervisor directs you to place excess letdown in service to the VCT and secure normal charging and letdown in accordance with 20M-7.4.G, "Excess Letdown Heat Exchanger Operation". Establish Excess Letdown from the "A" RCS loop. You are to maintain excess letdown heat exchanger outlet temperature :'S140°F and report when task is complete.

REFERENCES:

20M-7.4.G, Revision 6, "Excess Letdown Heat Exchanger Operation" TOOLS: None HANDOUT: 20M-7.4. G, Revision 6, "Excess Letdown Heat Exchanger Operation"

RTL#A5.640U 1/2-ADM-1301.F04 Page 5 of 10 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

T ASK: You are to place Excess Letdown in Service.

INITIAL CONDITIONS: The plant is operating at 25% power during a plant startup. All systems are operating normally except for a leak on the CCP supply line to the non-regenerative heat exchanger. Isolation of this leak will require that normal charging and letdown be secured. Normal letdown is in service.

INITIATING CUE: The Unit Supervisor directs you to place excess letdown in service to the VCT and secure normal charging and letdown in accordance with 20M-7.4.G, "Excess Letdown Heat Exchanger Operation". Establish Excess Letdown from the "A" RCS loop. You are to maintain excess letdown heat exchanger outlet temperature ::;140o:F and report when task is complete.

o 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".

o Simulate performance or perform as directed the required task.

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

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

Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-130 l.F04 Page 6 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION: 7 STEP STANDARD

( "C'. Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UN SAT)=>

SIU SIMULATOR SETUP:

Initialize to any 25% power IC set.

EVALUATOR NOTE: Provide the candidate a copy of 20M-7.4. G. When candidate is ready to begin, place simulator in RUN.

START TIME: ----------------

1. Reviews 20M-7.4.G, "Excess 1.1 Reviews 20M-7.4.G.

Letdown Heat Exchanger Operation." COMMENTS:

2. Verify Open (2CCP* AOVI70), 2.1 Verifies 2CCP* AOV170 OPEN.

Shield Tank & LTDN CLRS 2.2 Verifies Green light NOT LIT and Red light - LIT.

WTR Supply Iso1. Vlv.

COMMENTS:

3. Verify Open (2CCP* AOVI05), 3.1 Verifies 2CCP* AOV105 OPEN.

Excess Letdown Cooler Inlet 3.2 Verifies Green light NOT LIT and Red light - LIT.

Vlv.

COMMENTS:

RTL#AS.640U 1I2-ADM-1301.F04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION: 7 EVALUATOR CUE: Role play the US and inform the candidate that the reactor plant vents and drains system are aligned to receive letdown.

4.C Position (2CHS*HCV389), Ex 4.1C Positions (2CHS*HCV389) to P.D.T. Tank position.

L TDN Hx Disch Diverting Valve to Pri Drn TFR TK 4.2 Verifies Red Valve position light (PRJ DRN TRF position. TK) - LIT and Red Valve position light (VCT)-

NOT LIT COMMENTS:

EVALUATORIINSTRUCTOR CUE:

When asked, role play the US and inform the candidate that MCC-2-17 Cub 5D, Loop A Drain Isolation Valve (2RCS*MOV557A) is ON after having the instructor SELECT REMOTE: Select LOA-LOV304, Click RACKIN to provide power to Loop A Drain Iso1. Valve.

5.C Open (2RCS*MOV557A) "RCS 5.1 C Places control switch for 2RCS*MOV557A to Loop A Drain Valve". OPEN. (BB-A) 5.2 Verifies Red Light - LIT and Green Light - NOT LIT.

COMMENTS:

RTL#A5.640U li2-ADM-130 l.F04 Page 8 of 10 Revision 1 OPERA TIONS JOB PERFORMANCE MEASURE JPM NlJMBER: 2CR-056 I. JPM TITLE: Place Excess Letdown in Service JPM REVISION: 7 . I i ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR Ul'ISAT):::::> i SIU 6.C Open (2CHS*MOV201), 6.1C Places (2CHS*MOV201) to OPEN position. (BB-A).

"Excess Letdown Heat Exchanger Inlet Valve". 6.2 Verifies Red Light - LIT and Green Light - NOT LIT.

COMMENTS:

7. Monitor Seal Injection flow on 7.1 Monitors Seal Injection flow on 2CHS-FI130A, 2CHS-F1130A, 127A, 124A and 127A, 124A and leakoffflow on 2CHS-FRI54A leakoffflow on 2CHS-FRI54A while adjusting excess letdown flow. (VB-A) while adjusting excess letdown flow. COMMENTS:

sc. Establish excess letdown flow 8.1 C Locates hand control station for (2CHS*HCV137) slowly, using Excess Letdown and slowly turns the pot in the clockwise direction to Hx Discharge. Press Reducing open the valve.

Valve (2CHS-HCV137), to allow for warm-up of heat 8.2C Controls Ex Letdown HX temperature at less than or exchanger. equal to140°F on 2CHS-TIl39.

8.3 Controls Letdown HX Pressure <135 psig on

[2CHS-PI138].

EVALUATOR CUE: Ten (10) minutes has elapsed.

COMMENTS:

RTL#A5640U l/2-ADM-130 l.F04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-056 JPM TITLE: Place Excess Letdown in Service JPM REVISION: 7 STEP STANDARD

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

9C Ensures LTDN. HX. 9.1C Locates switch for 2CHS*HCV389 and places switch Discharge. "Diversion in VC Tank position.

Valve" (2CHS*HCV389) is aligned to VCT. 9.2 Verifies Red light (VCT Tank) LIT and RED light (PRl DRN TRF TK) NOT LIT.

COMMENTS:

10. Monitor Seal Inj ection flow 10.1 Verifies seal injection flow meters 2CHS-FIl30A, and adjust if necessary. 127A, 124A indicate 6-9 gpm per pump.

10.2 Coordinates efforts with local operator and adjusts (CHS*179, 178, 180)to maintain 6 - 9 gpm, if necessary.

COMMENTS:

11 C Close Letdown Orifice 11.1 C Places 2CHS *AOV200A and 200B control switches Vlvs 2CHS* AOV200NB. to CLOSED position.

11.2 Verifies Green Lights LIT and Red Lights NOT LIT.

COMMENTS:

I

RTL#A5.640U 1/2-ADM- 130 l.F04 Page 10 of 10 Revision I OPERATIONS JOB PERFORMANCE MEAS"lTRE JPM NUMBER: 2CR-056 I . .

JPM REVISION: 7 I JPM TITLE: Place Excess Letdown 10 ServIce I STEP S~

I STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR UNSAT):::::> :

12C. Place auto/manual station for 12.1C Depresses 2CHS*FCV122 MANUAL ... pushbutton; Charging Pumps Discharge demand increases to 100% to CLOSE valve.

Flow Control Valve (2CHS-FCV122) to MANUAL and COMMENTS:

CLOSE the valve.

13.C Close (2CHS*MOV289), 13.1C Places 2CHS*MOV289 control switch to CLOSE Normal Charging Header position.

Isolation Valve.

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

COMMENTS:

EVALUATOR CUE: Another operator will perform 20ST-6.4 and adjust 2CHS-HCV186 as needed. Shift Manager will discuss chemistry concerns with the Chemistry Department.

14. Report to supervisor. 14.1 Notifies Unit Supervisor that Excess Letdown has been placed into service to VCT, and the outlet temperature is <140°F and pressure is <135 psig.

COMMENTS:

i EVALUATOR CUE:

That completes this JPM.

I STOP TIME:

I

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of 10 Revision I JPM NlJMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 KJA

REFERENCE:

003A2.01 3.5/3.9 TASK ID: 0061-046-04-012 015/017 AA1.22 4.0/4.2 JPM APPLICATION: REQUALIFICATION ~ INITIAL EXAM D TRAINING D FAULTED JPM ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time ~ 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:

Evaluator Signature:

RTL#A5.640U 112-ADM-130 LF04 Page 4 of 10 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD:

2RCS*P21A tripped,

2RCS*PCV455A closed,

2CHS*MOV303A closed greater than three (3) minutes, but less than five (5) minutes, following the time that the reactor coolant pump was tripped.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to respond to reactor coolant pump seal trouble annunciator.

INITL'\'L CONDITIONS: The plant is in Mode 3 at normal operating temperature and pressure, with the reactor trip breakers open and with all RCS loops in operation.

INITIATING CUE: Annunciator A2-4D, "REACTOR COOLANT PUNIP SEAL TROUBLE", will alarm soon. You are to analyze the problem and respond accordingly.

This JPM contains time critical elements.

REFERENCES:

20M-7.4.AAH, "Reactor Coolant Pump Seal Trouble", Rev. 22 Unit 2 AOP 2.6.8, "Abnormal RCP Operation", Rev. 6 Unit 2 EOP E-O, "Reactor Trip or Safety Injection", Issue 1C, Rev. 8 TOOLS: Plant computer.

HANDOUT: 20M-7.4.AAH, "Reactor Coolant Pump Seal Trouble", Rev. 22 Unit 2 AOP 2.6.8, "Abnormal RCP Operation", Rev. 6

RTL#A5.640U 1I2-ADM-130LF04 Page 5 of lO Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to respond to reactor coolant pump seal trouble annunciator.

INITIAL CONDITIONS: The plant is in Mode 3 at normal operating temperature and pressure, with the reactor trip breakers open and with all RCS loops in operation.

INITIATING CUE: Annunciator AZ-4D, "REACTOR COOLANT PIJMP SEAL TROUBLE", will alarm soon. You are to analyze the problem and respond accordingly.

This JPM contains time critical elements.

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

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

Simulate performance or perform as directed the required task D Point to any indicator or component you verify or check and announce your observations.

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-130 l.F04 Page 6 of 10 Revision I OPERATIONS JOB PERFOR.\1ANCE MEASURE JPM NUMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 SIMULATOR SETUP:

Depending on desired core life, initialize IC-3, 11, or

25. Mode 3, all RCP's running, NOPINOT, open RTB and allow the plant to stabilize. Failure to occur 30 seconds after simulator to run.

Set Trigger 1 to actuate 2RCS-P21A #1 seal failure, malfunction. Set Malf RCPO 1A severity = 10, ramp time

= 30 sec, delay time 30 sec.

ENSURE ALL GROUP DEMAND COUNTERS are SET to 000 (Not part of snap)

EVALUA TOR CUE:

When candidate says that they are ready to Begin the JPM, go to run on the simulator and initiate Trigger 1 to actuate the malfunction.

START TIME: _ _ _ _ _ __

1.1 Acknowledge Annunciator A2- 1.1 Acknowledges Annunciator A2-4D, "REACTOR 4D, "REACTOR COOLANT COOLANT PUMP SEAL TROUBLE".

PUMP SEAL TROUBLE".

1.2 Obtain procedure. 1.2 Refers to ARP A2-4D (20M-7.4.AAH), or may directly enter AOP 2.6.8.

EVALUATOR CUE: Provide candidate a copy of whichever procedure is referenced, either ARP A2-4D (20M-7.4.AAH) or AOP 2.6.8 (20M-53C.4.2.6.8).

The ARP can be provided during the JPM Briefing.

NOTE: The candidate may directly enter AOP 2.6.8 which is acceptable in which case step # 2 is Nt A.

COMMENTS:

RTL#A5.640U 112-ADM-130LF04 Page 7 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 STEP STANDARD

( "C" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT):::::> SIU i

2. Evaluate RCP status. 2.1 Evaluates RCP parameters.

2.2 Locates and identifies RCP # 1 seal leakoff on [2CHS-FR154A] is higher than normal.

2.3 Refers to ARP section 4 and transitions to AOP 2.6.8.

COMMENTS:

I 3.1 Proceed to AOP 2.6.8 Step # 1. 3.1 Check criteria for immediate RCP shutdown in Table 1 (Left Hand Page) for any criteria exceeded.

3.2 Check Criteria for Immediate 3.2 Identifies sealleakoff flow >6 GPM immediate RCP RCP Shutdown in Table 1 shutdown criteria is met.

(Left Hand Page)

EVALUATOR NOTE: [2CHS-FRI54A] upper range I is 6 gpm.

COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 8 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NlJMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump Seal Failure JPM REVISION: 6 "S" FOR SAT or "U" FOR EVALUATOR NOTE: It is expected that the candidate will not trip the reactor or transition to EOP E-O, since the reactor is already shutdown. If this is the case, N/A JPM steps 4-8 and continue with JPM step 9.

JPM steps 4-8 are to be used if the candidate does trip the reactor and transitions to EOP E-O in response.

4.1 Trip the reactor. 4.1 Verifies reactor is tripped.

(AOP 2.6.8 step 1.a.I) 4.2 Go to E-O, "Reactor Trip or 4.2 Transitions to E-O, "Reactor Trip or Safety Injection" Safety Injection". for verification ofImmediate Manual Actions.

COMMENTS:

EVALUATOR CUE: Provide candidate a copy of procedure EOP E-O if candidate references procedure.

5. Verify E-O Immediate Manual 5.1 Verifies reactor trip:

Actions.

5.1.1 Annunciator A5-6D lit.

(EOP E-O step 1) 5.1.2 Power Range Indication <5%.

5.1.3 Neutron flux dropping.

COMMENTS:

6. Verify E-O Immediate 6.1 Verifies turbine trip:

Manual Actions.

6.1.1 Throttle or Governor Valves all closed.

(EOP E-O step 2) I 6.1.2 Main Generator Output Breakers open.

6.1.3 Exciter Circuit Breaker open.

COMMENTS:

RTL#A5.640U 1I2-ADM-130 LF04 Page 9 of 10 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUl'vfBER: 2CR-040 i. JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 I STEP I STANDARD 1\

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

7. Verify E-O Immediate Manual 7.1 Verifies power to AC emergency busses:

Actions.

7.1.1 At least one AC Emergency Bus energized.

(EOP E-O step 3)

COMMENTS:

8. Verify E-O Immediate Manual 8.1 Checks SI status:

Actions.

8.1.1 SI actuated.

(EOP E-O step 4) 8.2 Checks if SI is required:

8.2.1 CNMT pressure >5 PSIG.

8.2.2 PRZR pressure <1860 PSIG 8.2.3 SG Steam pressure <500 PSIG.

8.3 Determines SI is NOT REQUIRED and returns to AOP 2.6.8 step 1.a.3, the step in effect.

COMMENTS:

I I i

RTL#A5.640U 1I2-ADM-1301.F04 Page 10 of 10 Revision 1 OPERATIONS JOB PERFORl\1ANCE MEASURE JPM NUMBER: 2CR-040 JPM TITLE: Respond to a Reactor Coolant Pump #1 Seal Failure JPM REVISION: 6 STEP STANDARD

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

9. I C Stop affected RCP 9.1C Places [2RCS*P2IA] control switch in STOP or PTL.

[2RCS*P21Al 9.2 Verifies green light - LIT and red light NOT LIT.

RECORD RCP STOP TIME:

9.3 Close PRZR spray valves for 9.3C Places [2RCS*PCV455A] in MANUAL and affected RCP(s) depresses pushbutton until 0% demand indicated.

COMMENTS:

10. C When 3 minutes has elapsed IO.IC Waits 3 minutes from the time [2RCS*P21A] was from pump shutdown ,Close stopped.

affected RCP( s) seal leakoff isolation valve within the lO.2C Places [2CHS*MOV303A] to CLOSE within the next following 2 minutes: 2 minutes

[2CHS*MOV303A],21A 10.3 Verifies Green Light - LIT and Red Light NOT RCP Seal Water Leakoff LIT.

Vlv. I RECORD MOV CLOSE TIME: _ _ _ __

(AOP 2.6.8 step l,b)

EVALUATOR CUE: Terminate JPM after candidate completes closure of

[2CHS*MOV303A).

COMMENTS:

RTL#A5.640U 1!2-ADM-1301.F04 Page 3 of 11 Revision 1 JPM NUMBER: 2CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 KIA

REFERENCE:

035A3.014.0/3.9 TASK ID: 0241-004-01-013 035A4.01 3.7/3.6 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING

~ FAULTEDJPM ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINIS TERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EV ALUATION RESULTS Performer Name: Performer S SN:

Time 0 Yes Allotted 10 Minutes Actual minutes Critical. ~ No Time: Time:

D SAT JPM RESLTLTS:

D UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-1301.F04 Page 4 of 11 Revision 1 EVALUATOR DIRECTION SHEET TASK STANDARD: Transfer control of21A SG Water Level Control from the Main Feed Regulating Bypass Valve (MFRBV) in AUTO to the Main Feed Regulating Valve (MFRV) in AUTO.

Recognize improper MFRV control in AUTO and either shifts back to Manual MFRV control OR MFRBV control of21A NR S/G Water Level to maintain level between 39% to 49%.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to place 2FWS-FCV478, "21 A SG Main Feed Regulating Valve in service.

INITLt\L CONDITIONS:

The plant is in Mode 1 @ approximately 25% during a plant startup.

20M-52.4.A, "Raising Power from 5% to Full Load Operation" is in effect.

Step F.2 directs SG Main Feed Regulating Valves placed in service in accordance with Attachment 5 (provided).

The Unit Supervisor directs you to perform Part A of Attachment 5 of INITL<\TING CUE:

20M-52.4.A, "Placing [2FWS-FCV478], 2lA SG Main Feedwater Regulating Valve in Service". [2FWS-FCV478] is to be placed in automatic to control Steam Generator level.

REFERENCES:

20M-52.4.A, "Increasing Power From 5% to Full Load Operation" Rev. 69, Attachment 5 TOOLS: None HANDOUT: 20M-52.4.A, "Increasing Power From 5% to Full Load Operation" Rev. 69, Attachment 5

RTL#A5.640U l/2-ADM-1301.F04 Page 5 of 11 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

TASK:

You are to place 2FWS-FCV478, "21A SG Main Feed Regulating Valve in service.

INITIAL CONDITIONS:

The plant is in Mode 1 @ approximately 25% during a plant startup.

20M-52.4.A, "Raising Power from 5% to Full Load Operation" is in effect.

Step F.2 directs SG Main Feed Regulating Valves placed in service in accordance with Attachment 5 (provided).

INITIATING CUE: The Unit Supervisor directs you to perform Part A of Attachment 5 of 20M-52.4.A, "Placing [2FWS-FCV478], 21A SG Main Feedwater Regulating Valve in Service". [2FWS-FCV478] is to be placed in automatic to control Steam Generator level.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 112-ADM-1301.F04 Page 6 of II Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)::::;. I SIU I Simulator Setup: Initialize to any 25% power IC with Bypass Feed Regulating Valves in automatic. Place A,B,C NR levels on analog trend on plant computer.

(L0400A, L0420A, L0440A).

To insert the fault which causes a controller failure on "An MFRV when placed in AUTO insert the following:

Controller Tab -CNH-CFWI OB, Select Event Trigger #, Enter 50% severity, Enter 30 second ramp time.Cl0084A == 1, click accept new event and ensure it is properly entered, Freeze simulator and take a snap.

EVALUATOR CUE:

Provide candidate with a copy of20M-52.4.A, I

Attachment 5 (Part A), "Placing 2FWS-FCV478, 21A SG Main Feedwater Reg Vlv in Service". When candidate is ready to begin JPM, PLACE the simulator in RUN.

START TIME:

I

1. Review procedure, 1.1 Reviews procedure provided.

COMMENTS:

I 2, Verify 21 A SG level is being 2.1 Verifies 21 A SG is being controlled in AUTO using controlled in AUTO or Main Feed Bypass Control Valve and SG NR Water MANUAL using 21A SG Level is STABLE at approximately 44%.

Feedwater Bypass Control Vlv AND is STABLE at COMMENTS:

approximately 44%.

I i

RTL#A5.640U 1I2-ADM-1301.F04 Page 7 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM l\TUMBER: 2CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 STEP I STANDARD I

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

3. Verify [2FWS-FCV478] "21A 3.1 Verifies [2FWS*FCV478] AutolManual station in SG Main Feedwater Regulating MANU AL and 0% demand.

Valve in MANUAL and CLOSED. 3.2 Verifies Green light - LIT and Red light - NOT LIT.

COMMENTS:

i I

4. Verify CLOSED [2FWS- 4.1 Verifies [2FWS-MOVI54A] is CLOSED.

MOV154A] "21A SG Main Feed water Isolation Valve". 4.2 Verifies Green light - LIT and Red light - NOT LIT.

(BB 'C').

4.3 Dispatches an operator to "A" MFRV to observe local valve stroke.

EVALUATOR CUE: Role Play NLO who is dispatched to report local valve operation.

COMMENTS:

RTL#A5,640U 1I2-ADM-1301.F04 Page 8 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 STEP STANDARD

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

5. Stroke [2FWS-FCV478] "21 A 5,1 Stokes [2FWS*FCV478] full OPEN by depressing SG Main Feedwater Reg Vlv." to .. output pushbutton.

full OPEN and then full CLOSED, while verifying local 5.2 Verifies Red light - LIT and Green light NOT LIT.

position indication.

5.3 Strokes [2FWS*FCV478] full CLOSED by depressing ... output pushbutton.

5.4 Verifies Green light LIT and Red light NOT LIT.

EXAMINER CUE: Report as the Field Operator that [2FWS-FCV478] traveled smoothly full open with no hesitation and now indicates full closed.

COMMENTS:

I i I

~i_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-r___________________________________~ __

6.1 Trend L0400A (L0401 A), 6.1 Trend L0400A (L0401A), (L0402A) SG 2lA NR (L0402A) SG21A NRLVL LVL FWS*LT474 (475), (476) on the Plant FWS*LT474 (475), (476) on the Computer (PCS) using lowest scan rate.

Plant Computer (PCS) using lowest scan rate. 6.2 Monitors recorders and indicators for 2] A SG level, feed flow AND steam flow.

6.2 Monitor Steam Generator level, steam flow and feed flow. COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 9 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 I STEP STANDARD

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

7. Maintain stable temperature 7.1 Verifies stable Tavg and reactor power by monitoring AND reactor power. NI power and Loop DT and Tavg.

EVALUA TOR CUE: Tavg and reactor power are stable. Another operator will continue to monitor these parameters.

COMMENTS:

i 8.C Open [2FWS-MOV154A], 8.1C Places [2FWS-MOV154A] control switch to OPEN "21A SG Main Feedwater Isol position.

Vlv.".

8.2 Verifies Red light LIT and Green light - NOT LIT.

COMMENTS:

9. If feed flow to the 21A SG 9.1 Continuously monitors steam flow and feed flow rapidly rises or lowers when recorders and/or indicators for rapidly changing performing the following steps, feedwater flow.

THEN manually CLOSE the 21A SG Main Feedwater Reg COMMENTS:

Vlv AND establish proper feed flow AND level with 21 A SG F eedwater Bypass Valve.

i r

1O.C Verify [2FWS-FCV478] "21A IO.IC Verifies [2FWS*FCV478] is in MANUAL and SG Main Feedwater Reg Vlv." slowly opens using ... output pushbutton.

controller in MANUAL and SLOWLY OPEN. COMMENTS:

I i

RTL#A5.640U l/2-ADM-1301.F04 Page 10 of II Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0 I STEP STANDARD

. ( "e" Denotes CRITICAL STEP) c ..

(Indicate "S" FOR SAT or "U" FOR UNSAT)::::::> I S/U

11. Continue to open [2FWS- 11.1 Continues to open [2FWS*FCV478].

FCV478] "21A SG Main Feed Reg Valve" until [2FWS- 11.2 Verifies [2FWS*FCV479] is closing in AUTO OR is FCV479] "21A SG Feedwater being closed in MANUAL to maintain 21 A SG Water Bypass Control Valve" is Level between 39% and 49%.

CLOSED.

COMMENTS:

I

12. When [2FWS-FCV479], 21A 12.1 Verifies [2FWS*FCV479] full CLOSED.

SG Feedwater Bypass Control Valve is CLOSED, verify 12.2 Verifies [2FWS*FCV479] controller in MANUAL.

[2FWS-FCV 4 79] controller in MANUAL and check for 12.3 Verifies no leakage past valve.

leakage past valve.

COMMENTS:

I I

RTL#A5,640U 112-ADM-130LF04 Page 11 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-520 JPM TITLE: Transfer from Bypass to Main Feed Regulating Valve JPM REVISION: 0

STEP STANDARD I

I ( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "un FOR UNSAT):::::> I SfU I FA ULT STATEMENT: Alternate Path begins here when placing "A" MFRV into AUTO.

13, C Place controller for [2FWS- 13,1 C Places [2FWS *FCV478] controller to AUTO.

FCV478] Main Feed Reg Valve in AUTO and monitor 13.2C Recognizes 21A NR sa level control is NOT stable.

sa level AND feed flow and steam flow. 13.3C Places [2FWS*FCV478] controller back to MANUAL.

13.4C Maintains 21A sa NR water level between 39% and 49% using either [2FWS*FCV478] in MANUAL or

[2FWS*FCV479] in MANUAL or AUTO.

13,5 Reports problem with [2FWS*FCV478] AUTO control to US.

COMMENTS:

EVALVA TOR CUE: Once it is demonstrated that the candidate can control 21 A sa NR water level between 39% and 49%: "This JPM is COMPLETE",

STOP TIME: _ _ _ _ _ __

RTL#A5.640U 112-ADM-130 l.F04 Page 3 of 11 Revision 1 JPM NUMBER: 2CR-524 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 KIA

REFERENCE:

064A4.06 3.9/3.9 TASK ID: 0362-005-06-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM o TRAINING

~ F AULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

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

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 15 Minutes ~:al minutes Critical: ~ No Time: e:

JPM RESULTS:

D SAT D LTNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U I12-ADM-J30 l.F04 Page 4 of 11 Revision I OPERATIONS JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET TASK STANDARD: Diesel Generator 2-1 is synchronized and loaded in accordance with 20ST-36.1, "Emergency Diesel Generator [2EDG*2-1] Monthly Test" AND then tripped in response to Annunciator A8-4C and associated computer alarm indicating DG 2-1 DIFF.

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: You are to synchronize and load Emergency Diesel Generator 2-1.

INITIAL CONDITIONS: The plant is in Mode 1 with 20ST-36.1 being performed. The test has been completed up to step VII, Part B, step 21. All steps up to this point have been completed satisfactorily.

INITIA TING CUE: Your supervisor directs you to perform Section VII, Part B, steps 21 through 35 of20ST-36.1. You are responsible to respond to all alarms on Annunciator panel A8.

REFERENCES:

20ST-36.1, "Emergency Diesel Generator [2EGS*EG2-1] Monthly Test", Rev 62.

20M-36.4.ACS, "Diesel Gen 2-1 Electrical Fault", Issue 1, Rev. 9 TOOLS: None HANDOUT: 20ST-36.1, "Emergency Diesel Generator [2EGS*EG2-1] Monthly Test", Rev 62, place kept up to step 21.

20M-36.4.ACS, "Diesel Gen 2-1 Electrical Fault", Issue 1, Rev. 9 (AFTER ALARM OCCURS)

RTL#A5.640U 1/2-ADM-130 l.F04 Page 50fli Revision 1 OPERATIONS JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to synchronize and load Emergency Diesel Generator 2-1.

INITIAL CONDITIONS: The plant is in Mode 1 with 20ST-36.1 being performed. The test has been completed up to step VII, Part B, step 21. All steps up to this point have been completed satisfactorily.

INITIATING CUE: Your supervisor directs you to perform Section VII, Part B, steps 21 through 35 of20ST-36.L You are responsible to respond to all alarms on Annunciator panel A8.

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

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

Simulate performance or perform as directed the required task D Point to any indicator or component you verify or check and announce your observations.

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1!2-ADM-130 l.F04 Page 6 of II Revision I OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-524 JPM REVISION: 1

JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator STEP STANDARD I

( !Ie" Denotes CRITICAL STEP) (Indic(;l~e "S" FOR SAT or "U" FOR UNSAT)=> . S/U Simulator Setup: Initialize an Ie.,

Ensure simulator is setup for OST-36.1 conditions up to step 21 as follows:

DG in EXERCISE & running @ 514 RPM

DG voltage at ~ 122 volts Tum on Annuc AI1-4B, YO 186D, C02 in Lockout.

Set Trigger 1 to actuate when DG Load reaches 600 KW and actuates Annunciator A8-4C, Y2955D to support Alternate Path JPM.as follows:

Select Even Triggers

Enter HWXC8014M = 600 into event tab

Enter imf A8-4C-Y2955D 0 into command tab STARTTIME: ______________

1. Check EDG speed at ~514 1.1 Verifies EDG 1 Diesel Generator Speed at ~514 RPM. RPMonBB-C.

COMMENTS:

EVALUATOR CUE: Digital voltmeter readings are not required.

2. Obtain EDG voltage and 2.1 Records 2-1 EDG Output Voltage using frequency readings. benchboard indication in Step 22a.

2.2 Records 2-1 EDG Output Frequency using benchboard indication in Step 22a.

COMMENTS:

RTL#A5.640U 1/2-ADM-1301.F04 Page 7 of 11 Revision 1 OPERATIONS JOB PERFORMANCE NJEASURE JPM NlJMBER: 2CR-S24 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPMREVISION: 1 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ SIU EVALUATOR CUE: Motor Operated Potentiometer Test Not Required.

3.C Places 2-1 EMERG GEN 3.1 C Places 2-1 EMERG GEN MOTOR OPERATED MTR OPERATED GROUND GROUND DISCONNECT control switch to CLOSE.

DISCONNECT switch in the CLOSE position and verifies 3.2 Releases switch when Green light - NOT LIT and correct indication. Red light LIT.

3.3 Acknowledges Annunciator A8-4B, "DIESEL GEN2-1 M.O. GROUND SWNOTFULLY ENGAGED".

COMMENTS:

4.C Position the 1 EMERG 4.1C Places the 2-1 EMERG GEN SYNCHRONIZING GEN SYNCHRONIZING SELECTOR switch to the BUS 2AE position.

SELECTOR switch to the BUS 2AE position. COMMENTS:

S. C Adjust EDG speed using 2-1 S.lC Raise or lowers 2-1 EMERG GEN GOVERNOR EMERG GEN GOVERNOR control switch to adjust EDG 2-1 speed until the switch until EDG 2-1 EDG 2-1 synchroscope is rotating slowly in the fast Synchroscope needle is direction.

rotating slowly in the FAST direction. COMMENTS:

i

RTL#A5.640U 1I2-ADM-1301.F04 Page 8 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-S24 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "u" FOR UNSAT)~ S/U

6. Record voltage reading from 6.1 Records voltage from 2-1 EMERG GEN Voltmeter 2-1 EMERG GEN Voltmeter. on BB-C in Step 27a.

(BB-C)

COMMENTS:

7. Record voltage reading from 7.1 Records voltage from 4160V BUS 2AE Voltmeter 4160V BUS 2AE on BB-C in Step 27b.

Voltmeter. (VB-C)

COMMENTS:

8. If aligned to the SSST, Place 8.1 Determines NOT aligned to SSST and N/As Bus 2A Load Tap Changer in procedure step.

MANUAL.

COMMENTS:

9. Using the 2-1 EMERG GEN 9.1. Compares/verifies voltage between the EDG 2-1 VOLTAGE ADmST switch, and the Bus 2AE within 1 volt or adjusts EDG 2-1 match EDG voltage with the voltage to within that tolerance using the 2-1 voltage on Bus 2AE within 1 EMERG GEN VOLTAGE ADmST switch.

VAC.

COrvllVlENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 9 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASLTRE JPM NUMBER: 2CR-524 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 STEP STANDARD

( "e" Denotes CRlTICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ S/U 1O.C While observing both EDG 1O.1C Places 2-1 EMERG GEN OUTPUT BKR ACB-2-1 synchroscope and 2E 10 control switch to CLOSE position when synchronizing lights perform synchronizing needle is at 12 o'clock and lamps the following: are dark.

When synchronizing lamps 10.2 Verifies 2E 10 Red Light - LIT and White Light are completely dark and NOT LIT and releases switch.

synchroscope needle is at 12 0' clock position, place the 2- COMMENTS:

1 EDG Output Breaker ACB 2E 10 control switch in the CLOSE position and when the red light above switch turns ON, release the switch.

l1.C Increase load on EDG 2-1 to Il.1C Increases load on EDG 2-1 by turning 2-1 approximately 450 KW using EMERG GEN GOVERNOR Control switch EMERG GEN GOVERNOR intermittently to RAISE.

control switch.

11.2 Observes increasing EDG 2-1 watts and amps.

2-1 Emergency Generator Watts 2-1 Emer Gen 4KV Bus 2AE AMPS COMMENTS:

12. Place the 2-1 EMERG GEN 12.1 Places 2-1 EMERG GEN SYNCHRONIZING SYCHRONIZING SELECTOR switch in the OFF position.

SELECTOR switch in the OFF position. COMMENTS:

RTL#A5.640U l/2-ADM-I30 I.F04 Page 11 of 11 Revision 1 OPERATIONS JOB PERFORMANCE l\1EASURE JPM N1JMBER: 2CR-S24 JPM TITLE: Synchronize and Load 2-1 Emergency Diesel Generator JPM REVISION: 1 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT):::::> S/U FAULT STATEMENT: At this point the JPM alternate path begins. Annunciator A8-4C, "DIESEL GEN 2-1 ELECTRICAL F AUL T" will annunciate when EDG 2-1 loading reaches 600 KW. Computer alarm DG 2-1 DIFF will also be received. Candidate should respond to ARP and Trip the 2-1 EDG and open ACB 2E 10 which failed to automatically occur.

IS. C Annunciator A8-4C, IS. 1 Acknowledges the alarm and responds by "DIESEL GEN 2-1 reviewing the ARP for A8-4C.

ELECTRICAL FAULT",

alarms due to 2-1 DG DIFF, lS.2 Determines the alarm is indicative of an EDG Trip.

(Y29SSD) lS.3C Manually Trips EDG 2-1 and opens ACB 2E10 output breaker.

EVALUATOR CUE: Terminate the JPM after the candidate trips the EDG and opens the output breaker.

COM1!IENTS:

STOP TIl\1E: ----------------

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of l3 Revision 1 JPM NUMBER: 2CR-157 ,'JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 0 Test KJA

REFERENCE:

008 A4.01 3.3/3.1 TASK ID: 0151-012-01-012 JPM APPLICATION: I2?J REQUALIFICATION I2?J INITIAL EXAM D TRAINn~G D FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

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

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

Time 0 Yes Allotted 15 minutes Actual minutes Critical: I2?J No Time: Time:

JPM RESlJLTS:

0 SAT 0 UN SAT (Comments required for UNSAT evaluation)

Comments: - - - - ..

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

I

RTL#A5.640U 112-ADM-130 l.F04 Page 4 of 13 Revision 1 JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 0 I Test EVALUATOR DIRECTION SHEET TASK STANDARD: Transfer 2CCP*DCVI 00-1 and 100-2 between automatic and manual operation without invalidating test data. Determine TS 3.7.7 entry is required AND determine acceptance criteria is met> .98 for reverse flow test of2CCP*4, "21 A Discharge Check VIv.".

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: Yau are to perform 20ST-15.1, "Primary Component Cooling Water Pump (2CCP*P21A) Monthly Test".

INITIAL CONDITIONS: The plant is in Mode 3 on hold to perform a reactor startup.

2CCP*P21B is running and 2CCP*P2IA is in standby. (BOTH Pumps are OPERABLE)

All test preparations for 20ST-15.1, "2CCP*P21A Monthly Operability Test" are completed and the procedure is signed ready to begin at Step VII.B.2.

An NLO has been briefed and is standing by to support this OST.

INITIATING CUE: The Unit Supervisor directs you to perform 20ST-15.1, "Primary Component Cooling Water Pump (2CCP*P21A) Monthly Test", Steps VILB.2 through 4.

Determine if acceptance criteria in Step VII.B.4.1 is met.

REFERENCES:

20ST-15.I, "Primary Component Cooling Water Pump [2CCP*P21A]

Test", Rev. 44 TOOLS: None HANDOUT: 20ST-15.1, Primary Component Cooling Water Pump [2CCP*P21A]

Test Rev. 44, place kept up to step VII.4.B.2.

RTL#A5.640U 1I2-ADM-1301.F04 Page 5 of 13 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: You are to perform 20ST-15.1, "Primary Component Cooling Water Pump (2CCP*P21A) Monthly Test".

INITIAL CONDITIONS: The plant is in Mode 3 on hold to perform a reactor startup.

2CCP*P21B is running and 2CCP*P21A is in standby. (BOTH Pumps are OPERABLE)

All test preparations for 20ST-15.1, "2CCP*P21 A Monthly Operability Test" are completed and the procedure is signed ready to begin at Step VII.B.2.

An NLO has been briefed and is standing by to support this OST.

INITIATING CUE: The Unit Supervisor directs you to perform 20ST-15.1, "Primary Component Cooling Water Pump (2CCP*P21A) Monthly Test", Steps VII.B.2 through 4.

Determine if acceptance criteria in Step VII. B. 4.1 is 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.

RTL#A5.640U 1!2-ADM-130 I.F04 Page 6 of 13 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP *P21 A]

JPM REVISION: 0 Test STEP STANDARD

( "c" Denotes CRlTICAL STEP) (!ndicate "S" FOR SAT or "U" FOR UNSAT)=> I SiU I START TIME: _ _ _ _ _ _ __

SIMULATOR SETUP:

Select any Mode 3 steady state Ie.

Ensure 2CCP*P21B is in operation and 2CCP*P21A is in standby.

Verify 2CCp*nCV100-1 and 100-2 in AUTO.

EVALUATOR NOTE:

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

I

1. Review procedure. 1.1 Reviews procedure provided.

COMMENTS:

2. Verify 2CCP*P21A, 2.1 Requests NLO to verify 2CCP*P21 A bearing oil "Component Cooling Water level NORMAL on local constant level oiler.

Pump" bearing oil level is normal on local constant EVALUATOR CUE: Role play NLO and report level oiler. 2CCP*P21A local bearing oil level is NORMAL.

COMMENTS:

RTL#A5,640U 1I2-ADM-130LF04 Page 7 of 13 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 I JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 0 I Test "C" Denotes CRITICAL STEP Record 2CCP-PI150A, 3.1 Request NLO to report 2CCP-PI150A local suction "Primary Component pressure reading.

Cooling Water local suction pressure. EVALUATOR CUE: The NLO reports 2CCP-PI150A is reading 19A psig.

3.2 Records 2CCP-PI150A in step VII.B.3.

COMMENTS:

Verify 2CCP*4, "Component 4.1 Records 2CCP-PI145B, "21 B CCP Pump Disch Cooling Water Pump 21A Press" in step VII.BA.a, Disch Check Vlv" CLOSED, 4.2 N/A 2CCP-PI145C, "2IC CCP Pump Disch Press" in step VII.BA.a (pump is not running).

COMMENTS:

RTL#A5.640U I12-ADM-1301.F04 Page 8 of 13 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 Ii JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVIS[ON: 0 Test STEP I STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)==> SIU 5.C Verify 2CCP*DCV 100-1 5.lC Places 2CCP*DCVIOO-l in MAN by depressing AND 2CCP-DCVIOO-2 , MAN pushbutton.

"Pri Camp Cooling Pump Recirc Vlvs" are in MAN. 5.2 Verifies Red MAN light LIT and Red AUTO light NOTLlT 5.3C Places 2CCP*DCV 100-2 in MAN by depressing MAN pushbutton.

5.4 Verifies Red MAN light LIT and Red AUTO light

-NOTLlT.

5.5C Does NOT operate 2CCP*DCV100-1 or 100-2 while in MANUAL until pressure data is recorded in procedure step VII.B.4.f EVAULATOR NOTE: If2CCP*DCVlOO-l or 100-2 are operated in MANUAL prior to recording pressures in step VII.B.4.f, this will invalidate the data and will be considered UNSAT COMMENTS:

I I i

RTL#A5.640U l/2-ADM-130 1.F04 Page 9 of 13 Revision]

OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 0 Test 6,C If in MODEs 1-4 AND 6,1 C Determines that since the plant is in MODE 3 and 2CCP*P21A is required to be TWO (2) train of CCP are required to be operable, notify SMIUS to OPERABLE, that TS 3.7.7 entry is required.

make entry in the Narrative Log that TS 3.7. 7 condition 6.2 Requests SMIUS make TS 3.7,7 narrative log entry.

and required action will apply.

EVALUATOR CUE: When requested, role play the SNVUS and acknowledge that TS 3.7.7 entry and associated narrative log entry have been made.

COMMENTS:

7. Ifin MODEs 1-4, perform 7.1 Determines Mode 3 applies and either directs an either of the following:

operator stationed at 2CCP*7 with specific instructions to open 2CCP*7 if directed by control

Station an operator at room staff OR make a narrative log entry that 2CCP*7, "Component 2CCP*P21A is to be declared unavailable for Cooling Pump P21A Disch documentation of Maintenance Rule Availability, Iso1." With specific instructions to open 2CCP*7 EVALUATOR CUE: Role play either the if directed by control room NLO or SMIUS based on which choice is taken staff. by the candidate and acknowledge the request.

OR COMMENTS:

Record date and time below AND in narrative log that 2CCP*P21A is to be declared unavailable for documentation of Maintenance Rule Availabilit .

RTL#A5,640U 1I2-ADM-1301.F04 Page 10 of 13 Revision I OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: 2CR-I57

JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 0 I Test STEP

( "e" Denotes CRITICAL STEP 8,C Close 2CCP*7, "Component 8.1C Directs the NLO stationed in the Aux Building to Cooling Pump P21 A Disch CLOSE 2CCP*7, Iso1.".

EVALUATOR NOTE: 2CCP*7 is not modeled therefore 2CCP* 151 will be closed. Coordinate with the simulator operator and CLOSE 2CCP* 151 by selecting Primary Component Cooling Water Drawing (CCP2), clicking on 2CCP* 151, Enter 0 into remote value with a 10 second ramp time and ensure 2CCP

151 CLOSES.

EVALUATOR CUE: Once closed, Role Play NLO and report 2CCP*7 is CLOSED.

COMMENTS:

9, Record 2CCP-PI145B, "21B 9,1 Records 2CCP-PI145B, "21B CCP Pump Disch CCP Pump Disch Press", Press" in Step VII.BAr.

10,2 Marks 2CCP-I45C, "21C CCP Pump Disch Press" Nt A" in Step VIl.B.4.f. (Pump is NOT operating)

COMlVIENTS:

RTL#AS.640U 112-ADM-130 l.F04 Page 11 of 13 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPMNUMBER: 2CR-157 I JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPMREVISION: 0 ! Test

! STEP 1 STANDARD

. ( "C" Denotes CRlTICAL STEP) (Indicate "s" FOR SAT or "{I" FOR UNSA1)=> SIU

~pen 2CCP'7, "Component 1O.l Directs the NLO stationed in the Aux Building to REOPEN 2CCP*7.

Cooling Pump P21 A Disch Isol." .

EVALUATOR NOTE: Coordinate with the simulator operator and REOPEN 2CCP* 151 by clicking on 2CCP

151, Enter I into remote value with a 10 second ramp time and ensure 2CCP*151 OPENS.

EVALUATOR CUE: Once opened, Role Play the NLO and report 2CCP*7 is OPEN.

I COMMENTS:

11. IF 2CCP*P21 A was declared II 1 If 2CCP*P2l A was declared unavailable in previous unavailable in Step VII.BAd step AND IF desired to return pump to "available",

AND IF desired to return record date and time below in the Narrative Log pump to "available", record AND declare 2CCP*P21 A available for operation. If date and time below in the NOT applicable, mark step NI A.

Narrative Log AND declare 2CCP*P21 A available for

, EVALUATOR CUE: If applicable, it is desirable to operation.

I return 2CCP'P21A to available status. Narrative Log entries will be made.

COMMENTS:

I

RTL#A5.640U 1I2-ADM-130 l.F04 Page 12 of 13 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-157 I JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A)

JPM REVISION: 0 I Test "e" Denotes EVALUATOR CUE: It is NOT desirable to maintain 2CCP*DCVIOO-l and 100-2 in MANUAL.

12. IF manual operation of 12.1 This step will be marked N/A 2CCP*DCV 100-1 and 100-2 is desired, adjust valves as COMMENTS.

necessary UNTIL 2CCP-DII 00-1 AND 2 indicate 93 to 97 psid.

IF automatic operation of 13.1 C Places 2CCP*DCV100-1 in AUTO by depressing 2CCP*DCV100-1 and 100-2 AUTO pushbutton.

is desired, place valves in AUTO. 13.2 Verifies Red AUTO light LIT and Red MAN light

-NOTLlT.

13.3C Places 2CCP*DCV100-2 in AUTO by depressing AUTO pushbutton 13.4 Verifies Red AUTO light - LlT and Red MAN light

-NOTLlT.

COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page l3 of l3 Revision 1 OPERATIONS JOB PERFORMANCE lVIEASURE JPM NUMBER: 2CR-157 I JPM TITLE: Primary Component Cooling Water Pump [2CCP*P21A]

JPM REVISION: 0 I Test I STEP I STANDARD

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

14, IF in MODEs 1-4, Notify 14,1 Notifies SMllJS to make an entry in Narrative Log SMIUS to make an entry in that TS 3.7,7 condition no longer applies, Narrative Log that TS 3,7.7 condition no longer applies. EVALUATOR CUE: Role Play SMIUS and ~

acknowledge Narrative Log Entry that TS 3,7.7 no I longer applies. I COMMENTS:

15,C Calculate the ratio between 15.1 C Calculates the ratio between operating pump operating pump discharge discharge pressure with standby pump discharge pressure with standby pump valve closed and open as follows:

discharge valve closed and open RATIO = Indicated nress with 2CCP*7 onen (sten VILB.4.a)

Indicated press with 2CCP*7 shut (step VII.B.4,f) 15.2C Determines that the ratio for 2CCP*P21 B is >,98 acceptance criteria and records ratio in step VII,B.4J 15,3 NI A's ratio for 2CCP*P21 C.

15.4 Requests a second check for acceptance criteria.

EVALUA TOR CUE: Upon calculating acceptance criteria inform the candidate, "This JPM is COMPLETE".

COMMENTS:

I STOP TIME:

RTL#A5,640U l/2-ADM-130 l.F04 Page 3 of 11 Revision 1 JPM NUMBER: 2CR-599

]PM TITLE: Verify CREVS Actuation

]PM REVISION: 0 KJA

REFERENCE:

060 AAL02 2,9/3,1 TASK ID: 0441-007-01-013

]PM APPLICATION: L8J REQUALIFICATION L8J INITIAL EXAM o TRAINING L8J FAULTED JPM o ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

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

0 Training 0 Other:

EVALUATION RESULTS Performer Name: Performer SSN:

~

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

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

i

RTL#A5.640U 1I2-ADM-1301.F04 Page 4 of 11 Revision 1 JPM NUMBER: 2CR-599 JPM REVISION: 0 I .

JPM TITLE: Venfy CREVS ActuatIon EVALUATOR DIRECTION SHEET TASK STANDARD: MANUALLY closes 2HVC*MOD201B which failed to AUTO close.

MANUALLY starts 2HVC*FN241B due to 2HVC*FN241 A and 2HVC*FN241B failing to start.

RECOMMENDED Simulator ST ARTING LOCATION:

DIRECTIONS: You are to verify CREVS Actuation.

INITIAL CONDITIONS: A Large Break LOCA has occurred.

A transition to E-l, "Loss of Reactor or Secondary Coolant" has just been made.

CIB has actuated.

INITIATING CUE: The Unit Supervisor directs you to perform Step 1 RJ"JO actions ofE-I, "Loss of Reactor or Secondary Coolant".

REFERENCES:

20M-53A1.E-l, "Loss of Reactor or Secondary Coolant", Issue IC, Rev. 12.

1120M-44A4AA, "Post Control Room Habitability System ActuationJRecovery", Rev. 15 TOOLS:

HANDOUT: 20M-53A I.E-1, "Loss of Reactor or Secondary Coolant", Issue] C, Rev.12.

1I20M-44A.4AA, "Post Control Room Habitability System ActuationJRecovery", Rev. 15

RTL#A5.640U l/2-ADM-130 l.F04 Page 5 of 11 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK:

INITIAL CONDITIONS: A Large Break LOCA has occurred.

A transition to E-I, "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 ofE-I, "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.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 6 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASLTRE JPM NUMBER: 2CR-599 JPM REVISION: 0 I .

JPM TITLE: Venfy CREVS ActuatIon START TIME: - -...- - - - - -

~------------I-----------"'--"--'--'--'----+--1 SIMULATOR SETUP:

Begin with any power I C.

Insert aLB LOCA Malfunction (MALF RCS03A(B,C>>

on either loop.

Perform actions ofE-O, up to step 1 of E-l.

FaiI2HVC*MOD201B from AUTO closing (can manually close) as follows:

Select VL V-MSC029 (I-Fail Open)

Select Event Trigger, Select Event #, Enter Event XBSI065C == 1, Enter command DMF VLV-MSC029 Fai12HVC*FN241A from AUTO and MANUAL Start:

Enter BST-MSCOI4 (0- Actuate)

Enter lOR XBS 1077T - OFF

Enter lOR XBS 1077C - ON Fail 2HVC*FN241B from AUTO Start ONLY:

Enter BST-MSC013 (O-Actuate)

Freeze and take a snap.

EVALUATOR NOTE:

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

1. Review procedure. 1.1 Reviews procedure (E-l Step 1 RNO) provided.

COMMENTS:

Actuate both trains using 1 Actuates BOTH trains ofCREVS using the CONTROL ROOM .LJHJL.J...... '.'-J CONTROL ROOM EMERG AIR SUP AIR SUP ACTUATION ACTUATION pushbuttons located on Building pushbuttons. Services Panel.

RTL#A5.640U 1I2-ADM-1301.F04 Page 7 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-S99 I' J'PM l-ITLE V 'fy CREVS A .

JPM REVISION: 0 : en ctuatlOn

r'-j ISTEP I STANDARD i ( .. C .. Denotes CRITICAL STEP) I (Indicate "S" FOR SAT or "u" FOR UNSAT)=> I Stu J

, EVALUATOR NOTE:

I The following step can be done in any order.

3C. Verify CREVS actuation: 3.1 Verifies 2HVC*MOD201A, "Control Room ACU Control Room Air Intake Outside Air Intake" CLOSED.

Dampers CLOSED.

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

3.3 Verifies 2HVC*MOD20IC, "Control Room ACU Outside Air Exhaust" CLOSED.

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

3.SC Verifies 2HVC*MOD201B, "Control Room ACU Outside Air Intake" CLOSED. Recognizes 2HVC*MOD20IB did NOT AUTO close and manually places 2HVC*MOD201B control switch to CLOSE.

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

3.7. Verifies 2HVC*MOD201D, "Control Room ACU Outside Air Exhaust" CLOSED.

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

COMMENTS:

_' ~_,. _ _ _ _ _ _ _ _ _ _ _.......l-_ _ _ _ , _ _

RTL#A5.640U 1I2-ADM-130 l.F04 Page 8 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-599 I JPM TITLE V of CREVS A ° JPM REVISION: O . : en y ctuatlOn STEP STANDARD I

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

EVALUATOR CUE: When requested, role play and acknowledge request for Unit 1 Control Staff verification ofCREVS actuation.

4. Request Unit 1 Control 4. Requests Unit 1 Control Room staff to verify CREVS Room staff to verify CREVS actuation.

actuation COMMENTS:

5. C Verify one control room 5.1 Recognizes that neither 2HVC*FN241A or pressurization fan starts. 2HVC*FN241B AUTO started. (Green Lights LIT (2HVC*FN241 A or 241B) and Red Lights - NOT LIT.

5.2 Places 2HVC*FN241A control switch to START.

5.3 Recognizes 2HCVC*FN241A did NOT start: Green Light - LIT and Red Light - NOT LIT.

5.4C Places 2HVC*FN241B control switch to START.

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

EVALUATOR NOTE: Candidate may opt to attempt a start of a fan prior to going to 1i20M-44A4AA, which is acceptable. Operation Managers Expectation is to manually perform I actions which should have automatically occurred.

COMMENTS:

I I

RTL#A5.640U l/2-ADM-130 l.F04 Page 9 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-599 I JPM TITLE' V 'f CREVS A .

JPM REVISION: 0 !..... en y.. ctuatlOn SAT or "U" EVALUATOR NOTE:

Once located, provide candidate a copy of 1I20M-44.4AA, "Post Control Room Emergency Habitability System ActivationlRecovery, Part A".

6. Refer to 1I20M-44.4A.A, 6.1 Locates and references 1I20M-44.4AA, "Post "Post Control Room Control Room Emergency Habitability System Emergency Habitability ActivationlRecovery, Part A".

System ActivationlRecovery, Part A".

COMMENTS:

7. If CREVS was initiated as a 7.1 N/A 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 1I20M-53CAA44AA, "Toxic Gas COMMENTS:

Release".

8. Verify 2HVC*FN241 A, 8.1 Recognizes 2HVC*FN241 A failed to start: Green "Control Room Emer Vent Light LIT and Red Light NOT LIT.

Fan", has auto started AND 2HVC*MOD204A, "Control COMMENTS:

Room Emer Outside Air Intake Damper has opened.

RTL#A5.640U 112-ADM-130l.F04 Page 10 of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2CR-599 I. *

JPM REVISION: 0 : JPM TITLE: Venfy CREVS ActuatIon UNSATL~~!!J STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" F0it EVALVA TOR NOTE: Some of these critical steps may have been previously performed.

9.C If 2HVC*FN241 A failed to 9.1 Places 2HVC*FN241 A control switch to STOP.

start, perform the following:

9.2C Places 2HVC*FN241B control switch to START.

Place 2HVC*FN241A, "Control Room Emer Vent 9.3 Verifies 2HVC*MOD204B OPEN.

Fan" control switch to OFF.

If2HVC*FN241B, "Control 9.4 Verifies Red Light - LIT and Green Light NOT Room Emer Vent Fan" has LIT.

NOT started automatically, START 2HVC*FN241B. 9.5 Verifies annunciator AIO-3E, "CONTROL ROOM

Verify,2HVC*MOD204B, SUPPL Y AIR FLOW LOW" is NOT in alarm.

"Control Room Emerg Outside Air Intake Damper" COMMENTS:

OPEN.

Verify OFF annunciator AlO-3E, "CONTROL ROOM SUPPLY AIR FLOW LOW".

10. If annunciator Al 0-3E, 10.1 Recognizes Annunciator AIO-3E is NOT ON: N/A's "CONTROL ROOM EMER this step and does NOT proceed to step IY.A6.

SUPPL Y AIR FLOW LOW" is ON, proceed to step COMMENTS:

IY.A6.

I i i i

RTL#A5.640U 112-ADM-1301.F04 Page II of 11 Revision 1 OPERATIONS JOB PERFORMANCE MEASllRE JPM NUMBER: 2CR-599 JPM TITLE: Verify CREVS Actuation JPM REVISION: 0 EVALUA TOR NOTE/CUE: If the candidate decides to leave the control room to obtain DP indications, inform the candidate that an NLO will obtain this information.

11. Observe the following 11.1 Requests an NLO to observe the following indicators:

indicators and verifies the

2HVC-PDIS21A(B), DP for 2HVC*FLTA251A(B).

combined differential

2HVC-PDIS22A(B), DP for 2HVC*FLT A252A(B).

pressure on 2HVC-

2HVC-PDIS23A(B), DP for 2HVC*FLTA253A(B).

PDIS21A(B), 22A(B) AND 23A(B) is < 5.6 in. WG. EVALUATOR CUE: NLO reports 2HVC-PDIS21B is reading 1.3 in W.G. 2HVC-

2HVC-PDIS21A(B), DP for PDIS22B is reading 1.2 in W.G. and 2HVC-2HVC*FLT A251A(B). PDIS23B is reading 1.1 in W.G.

2HVC-PDIS22A(B), DP for 2HVC*FLT A252A(B).

2HVC-PDIS23A(B), DP for 11.2 Determines the combined differential pressure on 2HVC*FLTA253A(B). 2HVC-PDIS21A(B), 22A(B) AND 23A(B) is < 5.6 in. WG.

I EVALUATOR CUE:

I This JPM is COlv'IPLETE.

-~

COMMENTS:

STOP TIME: _ _ _ ~_~~~_~. ___ ~

BVPS - EOP 20M-53A.1.E-1(ISS1C)

Number Title E-l Loss Of Reactor Or Secondary Coolant Issue Ie Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION 1£ both trains of Service Water are in operation and one train is subsequently lost, flow in the train that is out of service should NQI be reinitiated without the concurrence of the TSC. Initiating flow with one train already in service could cause a water hammer of the Recirc Spray Hx discharge piping.

~ Check If CREVS Should Be Actuated

a. Control Room Radiation Monitor - Actuate both trains using the NOT IN HIGH ALARM CONTROL ROOM EMERG AIR SUP ACTUATION pushbuttons.

[2RMC*RQ201,202] (1069,1072)

Verify CREVS actuation:

b. CIS - HAS NOT OCCURRED a) Control Room Air Intake and Exhaust Dampers - CLOSED b) Request Unit 1 Control Room staff to verify CREVS actuation.

c) Verify one control room pressurization fan starts. Refer to 1/20M-44A.4A.A, "post Control Room Emergency Habitability System Activation/RecoveryU, Part A.

2E1 5/27/10 2 of 17

RTL#A5.640U 1I2-ADM-1301.F04 Page 3 of8 Revision 1 JPM NUMBER: 2PL-061 JPM REVISION: 7 I. JPM TITLE: Transferring Power for 2RHS*MOV702A KIA

REFERENCE:

005 K4.07 3.2/3.5 TASK ID: 0101-022-01-042 JPM APPLICATION: [g] REQUALIFICATION [g] INITIAL EXAM o TRAINING o FAULTED JPM o ADMINISTRATIVE JPM EV ALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

0 Perform 0 Plant Site 0 Annual Requal Exam 0 BVT 0 Simulate 0 Simulator 0 Initial Exam 0 NRC 0 Classroom 0 OIT/TPE 0 Other:

0 Training 0 Other:

EV ALUATION RESULTS Performer Name: Performer SSN:

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

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

RTL#A5.640U 1/2-ADM-130 l.F04 Page 40f8 Revision 1 EVALUATOR DIRECTION SHEET

[2RHS*MOY702A] is powered from [2MCC*EOS].

TASK STANDARD:

RECOMMENDED In-Plant STARTING LOCATION:

You are to simulate transferring power for [2RHS*MOY702A].

DIRECTIONS:

INITIAL CONDITIONS:

The Control Room has been evacuated due to a fire.

The Alternate Safe Shutdown panel has been activated.

A plant cooldown is in progress and nearing the point where the Residual Heat Removal System can be placed into service.

Your supervisor directs you to transfer power for [2RHS *MOY702A]

INITIATING CUE:

from [MCC*2-E06] to [MCC*2-EOS] in accordance with 20M-S6C.4, Subprocedure F -12. The use of any required keys is to be simulated.

20M-S6CA.F-12, "Transferring Power For [2RHS*MOY702A] From

REFERENCES:

Normal Power [MCC*2-E06] To Alternate Power [MCC*2-EOS]",

Issue 1 Revision S TOOLS: Keys (simulated).

HANDOUT: 20M-S6C.4.F-12, "Transferring Power For [2RHS*MOY702A] From Normal Power [MCC*2-E06] To Alternate Power [MCC*2-EOS]",

Issue 1 Revision S

RTL#A5.640U I12-ADM-130 I.F04 Page 5 of8 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

You are to simulate transferring power for [2RHS*MOV702Al TASK:

INITIAL CONDITIONS:

The Control Room has been evacuated due to a fire.

The Alternate Safe Shutdown panel has been activated.

A plant cool down is in progress and nearing the point where the Residual Heat Removal System can be placed into service.

Your supervisor directs you to transfer power for [2RHS*MOV702A]

INITIATING CUE:

from [MCC*2-E06] to [MCC*2-EOS] in accordance with 20M-S6C.4, Subprocedure 12. The use of any required keys is to be 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.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEAS"LTRE JPM NUMBER: 2PL-061 I. JPM TITLE: Transferring Power for 2RHS*MOY702A JPM REVISION: 7 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)~ S/U START TIME:

1. Reviews procedure 20M 1.1 Reviews procedure provided.

56C.4.F-12, "Transferring Power For [2RHS*MOY702A] From COMMENTS:

Normal Power [MCC*2-E06] To Alternate Power [MCC*2-E05]"

2.C Ensure the following breakers 2.lC Removes lock and energizes [MCC*2-E05] cubicle are energized: 8A by turning the switch handle to the ON position.

[MCC*2-E05] cubicle 8A EVALUATOR CUE:

[2CAB*RCPBP-04] cubicle Breaker is in the ON position.

R4A 2.2 Locates [2CAB*RCPBP-04] cubicle R4A and verifies cubicle R4A in ON position.

EVALUATOR CUE:

Breaker is ON.

I I COMMENTS:

3.C At [2RHS*TRSMOY702A] 3.1C Inserts the key into the upper lock for switch handle insert key into the upper lock [MCC*2-E06-7A] and turns it to release the switch on the normal power supply handle.

[MCC*2-E06] to release the switch handle. EVALUATOR CUE:

Key is INSERTED and TURNED.

COMMENTS:

RTL#A5.640U 1I2-ADM-130 1.F04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-061 JPM TITLE: Transferring Power for 2RHS*MOV702A JPM REVISION: 7 UNSAT)~ I StU STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR r-- .....

4.C De-energize normal power 4.1C Pulls the [MCC*2-E06-7A] switch handle to the OFF

[MCC*2-E06]. position (handle down).

EVALUATOR CUE:

Handle is in OFF position.

COMMENTS:

5.C Lock the normal power in the 5.1 C Turns the key in the lower lock to lock [MCC*2-E06 OFF position. 7A] power OFF and remove the key.

EVALUATOR CUE:

Key is TURNED and REMOVED.

COMMENTS.

6.C Place the released key into the 6.1 C Places the released key in the lower lock of alternate lower lock on the alternate power [MCC*2-EOS-8A] and turn it to release the power supply [MCC*2-E05]. switch handle.

EVALUATOR CUE:

Key is INSERTED and TURNED.

COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 8 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-061 JPM TITLE: Transferring Power for 2RHS*MOV702A JPM REVISION: 7 STEP STANDARD

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

7.C Energize the alternate power 7.1C Places [MCC*2-E05-8A] switch handle to the ON supply. position (handle up).

EVALUATOR CUE:

Handle is in ON position.

COMMENTS:

8. Lock the alternate power in the 8.1 Turns and removes the key in the upper lock to lock ON position. [MCC*2-E05-8A] power ON.

EVALUATOR CUE:

Key is TURNED and REMOVED.

COMl\lIENTS:

EVALUATOR CUE:

That Completes this JPM STOP TIME:

I

RTL#A5.640U 1/2-ADM-130 l.F04 Page 3 of8 Revision 1 JPM NUMBER: 2PL-150 JPM TITLE: Locally Throttle Open AFW Valve During ECA-O.O JPM REVISION: 0 KIA

REFERENCE:

061A2.05 3.1/3.4 TASK ID: 0534-010-05-042 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM D TRAINING D FAULTED JPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EVALUATION RESULTS Performer Name: Performer SSN:

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

JPM RESULTS:

0 SAT 0 UNSAT (Comments required for IJNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR

Evaluator (Print): Date:

i I Evaluator SIgnature.

RTL#A5.640U 112-ADM-130 1.F04 Page 4 of8 Revision 1 EVALUATOR DIRECTION SHEET 2FWE*HCVIOOF is OPEN.

TASK STANDARD:

RECOMMENDED In-Plant STARTING LOCATION:

You are to simulate MANUALLY opening 2FWE*HCVlOOF.

DIRECTIONS:

INITIAL CONDITIONS:

The plant has tripped from 100% and has experienced a loss of all AC power.

The crew has entered ECA-O.O, "Loss Of All AC Power".

Total AFW flow to the Steam Generators is less than 340 gpm.

The Steam Driven AFW Pump is running and aligned to the "B" Header.

2IA SG AFW Throttle valve 2FWE*HCVlOOF is CLOSED.

Your supervisor directs you to OPEN 21 A SG AFW Throttle valve INITIATING CUE:

2FWE*HCVIOOF by performing 20M-53 A. l.A-1. 1 I, "Manual Handpump Operation Of Hydraulically Actuated Valves". The valve is to be left in the full open position.

20M-53A.I.A-I.Il, "Manual Handpump Operation Of Hydraulically

REFERENCES:

Actuated Valves", Issue I C Rev. 5.

TOOLS: None 20M-53A.l.A-l.ll, "Manual Handpump Operation Of Hydraulically HANDOUT: Actuated Valves", Issue IC Rev. 5.

RTL#A5.640U 1I2-ADM-130LF04 Page 5 of8 Revision 1 CANDIDATE DIRECTION SHEET

THIS SHEET TO BE GIVEN TO CANDIDATE

D Read:

You are to simulate MANUALL Y opening 2FWE *HCVl OOF.

TASK:

INITIAL CONDITIONS:

The plant has tripped from 100% and has experienced a loss of all AC power.

The crew has entered ECA-O.O, "Loss Of All AC Power".

Total AFW flow to the Steam Generators is less than 340 gpm.

The Steam Driven AFW Pump is running and aligned to the "B" Header.

21A SG AFW Throttle valve 2FWE*HCVIOOF is CLOSED.

Your supervisor directs you to OPEN 21A SG AFW Throttle valve INITIATING CUE:

2FWE*HCVlOOF by performing 20M-53A.1.A-l.11, "Manual Handpump Operation Of Hydraulically Actuated Valves". The valve is to be left in the full open position.

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

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

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1/2-ADM-130 1.F04 Page 6 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-150 JPM REVISION: 0 , JPM TITLE: Locally Throttle Open AFW Valve During ECA-O.O

, STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I Stu START TIME: ----------------

1. Reviews procedure 20M 1.1 Reviews procedure provided.

53A 1.A-I.ll, "Manual Handpump Operation Of COMMENTS:

Hydraulically Actuated Valves".

EVALUATOR NOTE: It may take the candidate several minutes to proceed to step 4 due to procedure awkwardness.

2. Refer to the two lists in step 1 2.1 Determines 21 A SG AFW Throttle valve for "Fail-Closed" vs. "Fail-As- 2FWE*HCVI00F is a "Fail-As-Is" actuator.

Is" actuators. AND Proceeds to step 4 of the procedure.

COMMENTS:

3. Open supply breaker for 3.1 N/A 2FWE*HCVlOOF EVALUATOR CUE:

[MCC*2-EI4 Cub 3D (East Role-play the Unit Supervisor and report that another Cable Vault 735')] operator was dispatched to OPEN MCC*2-EI4 Cub 3D, and it is OPEN.

COMMENTS:

RTL#A5.640U 112-ADM-130LF04 Page 7 of8 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-lSO I JPM TITLE: Locally Throttle Open AFW Valve During ECA-O.O JPM REVISION: 0 .

STEP STANDARD

( "c" Denotes CRlTICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> I SIU 1 I EVALUATOR NOTE: Valve is NSA OPEN I

4.C Place the three position pump 4.1C Rotates the three position pump control valve to control valve to OPEN OPEN position.

position.

I EVALUATOR CUE:

. Pump control valve is in the OPEN position.

COMMENTS:

S. C Insert the pump handle into the S. 1 Locates the locally mounted hand pump handle.

hand-pump socket.

S.2C Inserts the pump handle into the hand-pump socket.

EVALUATOR CUE:

Pump handle INSERTED.

COMMENTS:

I I EVALUATOR NOTE: Valve position is located on I back side of valve.

6.C Pump the hand pump until the valve reaches the desired 6.1C Pumps the hand pump (up and down) until the valve position. is full OPEN.

6.2 Verifies valve stem is moving towards the OPEN position.

I EVALUATOR CUE: I I Valve is FULL OPEN or AS INDICATED.

I COMMENTS:

I

RTL#A5.640U 112-ADM-130 1.F04 Page 3 of 22 Revision I JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 KJA

REFERENCE:

064 K1.01 4.114.4 TASK ID: 0362-005-06-013 JPM APPLICATION: ~ REQUALIFICATION ~ INITIAL EXAM TRAINING

~ FAULTEDJPM D ADMINISTRATIVE JPM EVALUATION METHOD: LOCATION: TYPE: ADMINISTERED BY:

D Perform D Plant Site D Annual Requal Exam D BVT D Simulate D Simulator D Initial Exam D NRC D Classroom D OJT/TPE D Other:

D Training D Other:

EV ALUATION RESULTS Performer Name: Performer SSN:

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

JPM RESlJLTS:

0 SAT 0 UNSAT (Comments required for UNSAT evaluation)

Comments:

OBSERVERS Name/SSN: Name/SSN:

Name/SSN: Name/SSN:

EVALUATOR Evaluator (Print): Date:

Evaluator Signature:

i

RTL#A5.640U 1/2-ADM-130 l.F04 Page 4 of22 Revision 1 JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 EVALUATOR DIRECTION SHEET TASK STANDARD: Relay 27-VE2200(VF2200) and 27-VE2200X(VF2200X) are tested and reset.

RECOMMENDED In-Plant STARTING LOCATION:

EVALUATOR NOTE: This JPM is designed for either train. Perform for Train A relays if Protected Train B, and Train B relays if Protected Train A. Steps 1-18 of the JPM are for Train A performance. Steps 19-36 of the JPM are for Train B performance. Sign key out ahead of time and notify Shift manager that the JPM will be performed. Give key to student during reading of the initiating cue.

DIRECTIONS: You are to simulate the task Test the EDG UV Start Relay.

INITIAL CONDITIONS: The plant is in Mode 5. 20ST-36.15 A( 15B) is in progress. The Initial Conditions and Part A, Test Preparation, are complete. Steps 1 through 14 of Part B, Shutdown Mode Testing, are complete.

INITIA TING CUE: Your supervisor directs you to review the Initial Conditions and Precautions and Limitations, then perform Part B, Steps 15 through 24 of20ST-36.15A (15B).

REFERENCES:

20ST-36.15A(15B), Revision 3 TOOLS: Key 33 (34) forPNL*2UV-T-A(B)

HANDOUT: 20ST-36.15A(15B), Revision 3 Filled out through step Y.B.14

RTL#A5.640U l/2-ADM-130 l.F04 Page 50f22 Revision 1 CANDIDATE DIRECTION SHEET Use This Sheet if Protected Train "A"

THIS SHEET TO BE GIVEN TO CANDIDATE

DRead:

TASK: T est the EDG UV Start Relay INITIAL CONDITIONS: The plant is in Mode 5. 20ST-36.15B is in progress. The Initial Conditions and Part A, Test Preparation, are complete. Steps 1 through 14 of Part B, Shutdown Mode Testing, are complete.

INITIATING CUE: Your supervisor directs you to review the Initial Conditions and Precautions and Limitations, then perform Part B, Steps 15 through 24 of20ST-36.15B.

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

D When satisfied that you understand the assigned task, announce til am now beginning the JPMtI.

Simulate performance or perform as directed the required task.

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

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

D Then hand this sheet to the evaluator.

RTL#A5.640U 1I2-ADM-130 l.F04 Page 7 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP STANDARD

( "e" Denotes CRITICAL STEP) (Indicate "S" FOR SAT or "U" FOR UNSAT)~ S/U START TIME:

EVALUA TOR NOTE:

This is a "FAULTED" JPM, read cues carefully to ensure alternate path situation is presented to candidate.

EVALUATOR NOTE:

This JPM is setup for either Train.

If Train A is to be performed, follow JPM steps 1-18.

If Train B is to be performed, follow JPM steps 19-36.

1. Review the OST. 1.1 Reviews initial conditions, P&Ls and instructions.

COMMENTS:

2. Obtain Key 33. 2.1 NIA provided by evaluator.

COMNlENTS:

3. Open the door on the Train A 3.1 Uses key to unlock and open panel door. (PNL

UV Test Panel. 2UV-T-A)

COMMENTS:

RTL#A5.640U 112-ADM-130 l.F04 Page 9 of22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3

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

SIU *

7. Verify white (Push-to-Test) 7.1 Verifies white test pushbutton for [TEST: 27 pushbutton Test: [27 VE2200X CONTACT] is OFF.

VE2200X] Contacts is OFF (lB-ENSAB). EVALUATOR CUE:

White test pushbutton light is NOT LIT.

COMMENTS:

8. At cubicle 2E6 verify red trip 8.1 At [4KVS*2AE] Swgr, Cubicle 2E6, Verifies red trip target displayed on [27 target is displayed on relay [27-VE2200l VE2200l EVALUATOR CUE:

Red trip target is DISPLAYED.

COMMENTS:

RTL#A5.640U 1I2-ADM-130 l.F04 Page 10 of22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 II JPM REVISION: 3 JPM TITLE: Test the EDG UV Start Relay STEP STANDARD I* ("e" Denotes CRITICAL STEP)

I (Indicate "S" FOR SAT or "U" FOR UNSAT)~ *SIU !

I

9. Verify control room alarms 9.1 Establishes communications with Control Room.

A8-4H and computer point

[Y5714D] are active. 9.2 Requests Control room operator to verify annunciator A8-4H, 4KV EMER BUS 2AE12DF UV CKT "IN TEST" in alarm.

AND Computer point [Y5714D] 4KV EMERBUS 2AE UV TEST is active.

EVALUATOR CUE:

Role-play the control room operator and report Annunciator A8-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is IN ALARM and computer point

[Y5714D] 4KV EMER BUS 2AE UV TEST is ACTIVE.

COMMENTS:

] O.C Depress white pushbutton 10.1 C Depresses [TEST: 27-VE2200X CONTACT] white and verify lamp ON when pushbutton.

depressed and OFF when released to verify continuity 1O.2C Verifies light is ON when pushbutton is depressed.

through the trip circuit (Test

[27-VE2200X]). 1O.3C Verifies light goes OFF when pushbutton released.

I EVALUATOR CUE:

. Light is LIT when button depressed and NOT LIT I when button released.

COMMENTS:

" I I

RTL#A5,640U l/2-ADM-130LF04 Page 13 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 I STEP STANDARD I ( "e" Denotes CRITICAL STEP) (lnnic::lte "S" FOR SAT or "U"FOR UNSAT)=? S/U

15. Verify white indicating light 15.1 Verifies white light for [TEST: 27-VE2200 for [27-VE2200] and red CONTACT] is ON, indicating light for [27 VE2200X] are ON. 15.2 Verifies red light for [TEST: 27-VE2200X COIL] is ON.

EVALUATOR CUE: I Both lights are LIT.

COMMENTS:

i 16, Verify circuit is reset by 16,1 Verifies [TEST: 27-VE2200X CONTACT] white checking white light on test pushbutton light is ON.

pushbutton is ON when not depressed and OFF when EVALUATOR CUE:

depressed. White light is LIT.

I I 16.2 Depresses [TEST: 27-VE2200X CONTACT] white pushbutton light and verifies light goes OFF when depressed.

EVALUATOR CUE:

White light is NOT LIT when depressed, 16.3 Releases [TEST: 27-VE2200X CONTACT] white pushbutton light and verifies light comes ON when released.

EVALUATOR CUE: !

White light is LIT when released, I

COMMENTS:

i i

RTL#A5.640U l/2-ADM-1301.F04 Page 140f22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-S49 JPM REVISION: 3 I JPM TITLE: Test the EDG UV Start Relay STEP STANDARD

( "c" Denotes CRlTICAL STEP) (Indicate "s" FOR SAT or "U" FOR UNSAT)=> SIU I

17. Verify control room alarms 17. 1 Establishes communications with Control Room.

AS-4H and computer point

[YS714D] are reset. 17.2 Requests Control room operator to verify annunciator AS-4H, 4KV EMER BUS 2AE/2DF LTV CKT "IN TEST" is NO LONGER IN ALARM.

AND Computer point [YS714D] 4KV EMERBUS 2AE UV TEST is normal.

EVALUATOR CUE:

Role-play the control room operator and report Annunciator AS-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is NO LONGER IN ALARM AND Computer point [YS714D] 4KV EMER BUS 2AE UV TEST is NORMAL.

COMMENTS:

18. At 4KV cubicle 2E6, reset 18.1 At [4KVS*2AE] Swgr, Cubicle 2E6, Depresses the the red trip target on [27 relay target reset pushbutton for relay [27-VE2200].

VE2200].

EVALUATOR CUE:

Red trip target is NOT FLAGGED (BLACK).

COMMENTS:

EVALUATOR CUE:

That completes this JPM. (For Train A)

STOP TIME: - - - - - - - -

RTL#A5.640U l/2-ADM-1301.F04 Page 15 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 .

JPM REVISION: 3 I JPM TITLE: Test the EDG UV Start Relay STEP STANDARD I

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

EVALUATOR NOTE:

Steps 19-36 are for Train B performance.

19. Review the OST. 19.1 Reviews initial conditions, P&Ls and instructions.

COMMENTS:

20. Obtain Key 34. 20.1 N/A provided by evaluator.

COMMENTS:

I

21. Open the door on the Train B i 21.] Uses key to unlock and open panel door. (PNL

UV Test Panel. 2UV-T-B)

COMMENTS:

RTL#A5.640U l!2-ADM-130LF04 Page 16 of22 Revision l OPERATIONS JOB PERFORMANCE MEASURE JPM 1'<1JMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP . STANDARD I

( "C" Denotes CRITICAL STEP) I (Indicate "s" FOR SAT or "U" FOR lJl'l~AT):::;, I SIU I 22.C Place [1B-ENSBB] in TEST. 22.1C Turns 4KV Bus 2DF Test [lB-ENSBB] switch to the TEST position and allows it to spring return to normal.

I EVALUATORCUE:

I Test switch was placed in TEST and allowed to

. spring return to NORM.

COMMENTS:

I i

23. Verify red indicating light for 23.1 Verifies red indicating light for [TEST: 27-VF2200X

[27-VF2200X] is OFF. COIL] is OFF.

EVALUATOR CUE:

Red light is NOT LIT.

COMMENTS:

I

.. ~

24. Verify white indicating light 24.1 Verifies white indicating light for [TEST: 27-VF2200 for [27-VF2200] is OFF. CONTACT] is OFF.

EVALUATOR CUE:

White light is NOT LIT.

COMMENTS:

I i

1

RTL#A5.640U l/2-ADM-1301.F04 Page 17 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP STANDARD

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

25. Verify white (Push-to-Test) 25.1 Verifies white test pushbutton for [TEST: 27 pushbutton Test: [27 VF2200X CONTACT] is OFF.

VF2200X] Contacts is OFF (lB-ENSBB). EVALUATOR CUE:

White test pushbutton light is NOT LIT.

COMMENTS:

26. At cubicle 2F6 verify red trip 26.1 At [4KVS*2DF] Swgr, Cubicle 2F6, Verifies red trip target displayed on [27 target is displayed on relay [27-VF2200l VF2200].

EVALUATOR CUE:

Red trip target is DISPLAYED.

COMNIENTS:

RTL#A5,640U 1/2-ADM-130LF04 Page 18 of22 Revision 1 OPERATIONS JOB PERFORMANCE lMEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3 STEP STANDARD *

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

27. Verify control room alarms 27.1 Establishes communications with Control Room, AS-4H and computer point

[Y5715D] are active, 27.2 Requests Control room operator to verify annunciator A8-4H, 4KV ElMER BUS 2AE12DF UV CKT "IN TEST" in alarm.

AND Computer point [Y5715D] 4KV EMER BUS 2DF UV TEST is active, EVALUATOR CUE:

Role-play the control room operator and report Annunciator A8-4H, 4KV ElMER BUS 2AE/2DF UV CKT "IN TEST" is IN ALARM and computer point

[Y5715D] 4KV ElMER BUS 2DF UV TEST is ACT[VE, COMlMENTS:

I I 28,C Depress white pushbutton 28.1C Depresses [TEST: 27-VF2200X CONTACT] white and verify lamp ON when pushbutton.

depressed and OFF when released to verify continuity 28,2C Verifies light is ON when pushbutton is depressed.

through the trip circuit (Test

[27-VF2200X]). 28.3C Verifies light goes OFF when pushbutton released.

EVALUATOR CUE:

Light is LIT when button depressed and NOT LIT when button released.

COMlMENTS:

RTL#AS.640U 1I2-ADM-130 l.F04 Page 20 of 22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 i JPM REVISION: 3 I JPM TITLE: Test the EDG UV Start Relay STANDARD n(IJf:llTf' "S' FOR SAT or 'un FOR UNSAT):::;> I SIU

31. Verify circuit is reset by 31.1 Verifies [TEST: 27-VF2200X CONTACT] white checking white light on test pushbutton light is ON.

pushbutton is ON when not depressed and OFF when EVALUATOR CUE:

depressed. White light is NOT LIT.

31.2 Determines that the indications do not support verification that the relay was RESET and determines that the relay reset should be attempted a second time.

EVALUATOR NOTE:

If the candidate does depress the button, cue that the light remains NOT LIT.

COMMENTS:

32.C Reset relay [27-VF2200] by 32.1C Places and holds for 5 seconds switch IB-ENSBB in placing switch IB-ENSBB in the RESET position.

the RESET position for five seconds minimum. 32.2C Allows it to spring return to NORM.

EVALUATOR CUE:

Switch was held to RESET for 5 seconds and then returned to NORM.

COMMENTS:

RTL#A5,640U 1/2-ADM-130 l.F04 Page 22 of22 Revision 1 OPERATIONS JOB PERFORMANCE MEASURE JPM NUMBER: 2PL-549 JPM TITLE: Test the EDG UV Start Relay JPM REVISION: 3

35. VeritY control room alarms 35.1 Establishes communications with Control Room.

AS-4H and computer point

[Y5715D] are reset. 35.2 Requests Control room operator to verify annunciator AS-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is NO LONGER IN ALARM.

AND Computer point [Y5715D] 4KV EMER BUS 2DF UV TEST is normal.

EVALUATOR CUE:

Role-play the control room operator and report Annunciator AS-4H, 4KV EMER BUS 2AE/2DF UV CKT "IN TEST" is NO LONGER IN ALARM AND Computer point [Y5715D] 4KV EMER BUS 2DF UV TEST is NORMAL.

COMMENTS:

-- -~'~- - --

36. At 4KV cubicle 2F6, reset 36.1 At [4KVS*2DF] Swgr, Cubicle 2F6, Depresses the the red trip target on [27 relay target reset pushbutton for relay [27-VF2200],

VF2200l EVALUATOR CUE:

Red trip target is NOT FLAGGED (BLACK). I I COMMENTS:

f-- -

EVALUATOR CUE:

That completes this JPM. (For Train B)

STOP TIME:

I

A ppen d'IX 0 . 0 utrme 5 cenarlo Form ES-0 1 Facility: FENOC BVPS Unit 2 Scenario No.: 1 Op Test No.: 2LOT7NRC Examiners: Candidates: SRO ATC BOP Initial IC 211: 61% power, MOL, Equ. Xe Conditions, CB "0" 152 steps, RCS boron 1044 Conditions: ppm, Condensate Polishing Air Compressor - OOs.

. Turnover: Maintain current power level.

Critical Tasks: E-O.A, Auto Rx Trip failure E-O.H, Start LHSI Pumps E-O.E, Manually Initiate CIB I Event Malf. No. Event Type Event Description No.

I 1 XMT-RCS054A I(ATC/SRO) Loop 1 Tcold RTD fails low SROTS 2 PMP-CFW004 C(BOP/SRO) 2FWS*P2IA pump trip.(Power reduction required) 3 R(ATC) Power reduction to <50%

N(SRO/BOP) 4 FLX-CCP34 C(ALL) CCP supply leak to 2RCS*P2IB (10 minute ramp to 450 gpm PMP-RCP003 SROTS leads to an automatic RCP trip).

5 PPLOIA C(ATC) Auto Reactor Trip failure (manual available)

PPLOIB (SRO) 6 RCS03B M(ALL) B Loop Large break LOCA 7 PPL07A C(ATC) Both low head SI pumps fail to auto start (manual start PPL07B (SRO) available).

8 PPL09A C(BOP) Auto CIB failure (manual available)

PPL09B (SRO)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev 1

Appendix D Scenario Outline Form ES-D-1 The crew will take the shift at 61% power, MOL at Equilibrium Xe, Bank D control Rods at 152 steps and RCS ooron is at 1044 ppm. Crew instructions are to maintain current stable plant conditions.

Loop 1 Tcold RTD will fail low, requiring implementation of20M-6.4.IF, attachment 4. The ATC will have to accurately determine failed channel and select a non-failed channel and the SRO will evaluate TS.

2FWS-P21A will then trip requiring the crew to enter AOP 2.24.1 and rapidly reduce power to less than 50%.

When plant conditions have begun to stabilize, a leak develops on the CCP supply line to 2RCS-P21B, "B" RCP. The leak will ramp to 450 gpm over ten minutes. First indication is annunciator A2-2B for UIL HIGH, ARP 20M-9.4.AAL will be entered at which point dropping CCP surge tank level indication will require entry into AOP 2.15.1. The US will evaluate TS 3.7.7 applicability. The "B" RCP will degrade and eventually trip with a failure of the reactor to trip automatically. The Unit Supervisor should direct a manual reactor trip and enter E-O.

Immediately following the reactor trip, a large break LOCA occurs. After completing E-O immediate actions, all RCPs should be manually tripped due to the loss of component cooling.

Additional failures that occur following the LOCA, the ATC operator will identify that both low head SI pumps failed to start automatically and will manually start them. During the performance of EOP attachment A-O.II, the BOP will identify that Containment Isolation Phase "8" (CIB) failed to actuate automatically and will manually initiate CIB. The Unit Supervisor will progress through E-O to E-I at the "Check if the RCS is Intact" "tep, E-l will be implemented until the crew determines that ES-l.2 transition is not appropriate in E-l step 19 Jased upon RCS pressure being less than 225 psig.

The drill is terminated at step 20 of 1 when the crew evaluates if Transfer to Cold Leg Recirculation is required.

Expected procedure flow path is E-O ~ E-l.

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

BEAVER VALLE::. POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 61 % Power, CBD 152, EQU XE MOL, 1044 PPM Boron, IC-2l1

-~

ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2SAS-C22 in PTL YCTon CS None EQUIPMENT STATUS DATEITIME OOS TECHNICAL SPECIFICATION(Sl 2SAS-C2200S 2 days ago None j

SHIFT TURNOVER INFORMATION

1. 61 % Power, CBD 152, EQU XE MOL, 1044 PPM Boron, ROD's in AUTO

2. Protected Train is Train "8"

3. Maintain steady state power level for confidence run on 2FWS-P21 B which was just returned to service at the end of last shift from a pump bearing replacement outage.

4. 2SAS-C22, Condensate Polishing Air Compressor OOS for overhaul.

SCENARIO SUPPORT MATERIAL REQUIRED

1. Reactivity plan placard for MOL

2. Placard for 2FWE*P22 position stating 2FWE*P22 is aligned to "A" header

3. Place plaque on wall for Protected Train "8" BVPS - 2 Scenario 1 1 of 20

BEAVER VALLEy rlOWER STATION 1/2 ADM - 1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Initialize IC Set 211, and establish Reactor plant at 61 % power, MOL, equilibrium initial plant conditions. conditions. RCS boron 1044 PPM, CBD 152 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the drill Setup section of the HTML File for this drill:

TRGSET 1 'JPPLP4(1)' Set trigger 1 on Reactor trip IMF PPLOIA (00) 0 TRN "A" Auto Reactor trip failure IMF PPLOIB (0 0) 0 TRN "B" Auto Reactor trip failure IMF PPL07 A (0 0) 4 2SIS*P21 A auto start failure IMF PPL07B (0 0) 4 2SIS*P21B auto start failure IMF PPL09A (0 0) TRUE TRN "A" CIB Auto Actuation failure IMF PPL09B (0 0) TRUE TRN "B" CIB Auto Actuation failure IMF RCS03B (1 0) TRUE BLoop LBLOCA occurs on reactor trip IMF FLX-CCP34 (3 0) 1 450 gpm leak on CCP supply line to "B" RCP lOR XB40001R (3 0) 1 FaiI2CCP*MOVI03B red light on.

IMF VL V-CCP042A (3 120) 15 420 Reduced CCP flow to 2RCS-P21B IMF PMP-RCP003 (3 720) 1 Trip of"B" RCP in 12 minutes TRG 4 'IMF PMP-RCP003 l' OPTIONAL action to allow booth operator to manually trip the "B" RCP.

BVPS - 2 Scenario 1 2 of 20

BEAVER VALLEY POWER STATION 1/2 ADM - 1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ~

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

When the shift turnover is completed, Simulator running. Crew assumes control of the place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 1 3 of 20

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training r INSTRUCTIONAL GUIDELINES c=. PLANT STATUS OR RESPONSE~* EXPECTED STUDENT RESPONSE Revision 7 EVENT #1:

Loop 1 Tcold fails low 2RCS-TE412D IMF XMT-RCS054A (0 0) 510 240 IMMEDIATE PLANT RESPONSE:

A4-4C, - 'LOOP AT DEVIATION' - LIT ATC acknowledges alarms, informs Crew.

A4-3F, - 'LOOP TAVG DEVIATION' - LIT BOP refers to ARP's.

SRO directs entry into Instrument Failure procedure, 20M-6.4.IF ATT 4.

ATC/SRO diagnoses Loop 1 Tcold as failed low.

ATC selects an unaffected loop on OTDT recorder selector switch.

SRO reviews TS TS 3.3.1, functions 6 & 7, Both are Condition trip Bistables w/in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

TS 3.3 function 8c, Condition K, verify P-12 in correct position wlin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Contacts I&C to trip OTDT Bistables.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action to verify P-12 in correct position.

Proceed with next event at LE discretion BVPS - 2 Scenario 1 4 of 20

BEAVER VALLEY r-uWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENTS 2 and 3:

2FWS-P21 A Trip IMMEDIATE PLANT RESPONSE:

A6-10A, - 'SG FEED PUMP 21A/B AUTO-STOP' BOP recognizes feed pump trip and informs US IMF PMP-CFW004 (0 0) 1 -LIT Refers to ARPs as time permits.

A6-9E, A6-10E, A6-11E, - 'S/G 21A, B, C LEVEL As necessary, BOP controls SG level with manual DEVIA TION FROM SETPOJNT' control of the Main Feed Regulating valves.

BRIGHT white light for 2FWS-P21A SRO refers to AOP-2.24.1, Loss of Main Feedwater.

A TC verifies reactor power < 80%.

Turbine load reduction to < 50%. SRO refers to AOP-2.24.1 and directs load decrease to < 50% at desired reduction rate.

BOP decreases turbine load at rate designated by SRO.

In AUTO mode, Rods begin to step inward in ATC performs RCS boration to maintain response to Turbine Load Reduction. Tavg-Tref.

A TC maintains rods in Auto SRO places calls to Ops Management & Electrical maintenance.

BOP notifies turbine operator to check Aux oil pump for 2FWS-P21A Proceed with next event at LE discretion BVPS - 2 Scenario 1 5 of 20

BEAVER VALLEY POWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE 1-** EXPECTED STUDENT RESPONSE ~

EVENT 4:

IMMEDIATE PLANT RESPONSE:

CCP leak on supply line to "B" RCP Decreasing CCP Surge Tank level on with automatic RCP trip. 2CCP*LII00A and 2CCP*LII00B. Crew determines CCP header leak inside containment.

IMF FLX-CCP34 (3 0) 450 600 PMP-RCS003 SRO may initially enter AOP 2.6.7, 'Primary Plant Increasing containment sump levels. Leakage' due to containment sump alarms.

A2-2B, - 'UNIDENTIFIED LEAKAGE SYSTEM TROUBLE' - LIT SRO refers to AOP-2.15.1, 'Loss of Primary AI-2G, - 'UNIDENTIFIED LEAKAGE FLOW> Component Cooling Water'.

60 GALLONS' - LIT A2-3B, - 'INCORE INSTR ROOM/CNMT SUMP Crew may dispatch an operator to verify CCP LEVEL HIGH/VALVE NOT RESET' - LIT makeup valve(s) unisolated.

Decreasing 21B RCP motor CCP flow indication.

Increasing 21B RCP motor and bearing temperatures.

1 CCP pump operating. ATC/BOP checks CCP system status.

NOTE: Level control in manual with maximum makeup. ATC/BOP places surge tank level control valve in Dependant on timing and progression manual and adjusts control signal to maximize through AOP 2.15.1, CCP surge tank makeup to surge tank.

level may initially rise if makeup is quickly established, however as the ATC attempts to identify leak using AOP 15.1, leak continues to get larger, level will either Attachments 1 or 2 dependant upon timing.

then drop again.

BVPS - 2 Scenario 1 6 of 20

BEAVER VALLE'r r'OWER STATION 1/2 -ADM - 1357 Conduct of Simulator Training Revision 7 L_- INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE A2-5F, - 'RCP COOLING WATER TROUBLE' SRO enters AOP 2.6.8.

LIT Crew monitors RCP motor bearing upper and lower temperatures for RCPs.

Non-essential loads isolated. Crew attempts to locate the leak.

NOTE: Surge tank continues to decrease. Crew monitors to determine if any RCP If crew is preparing to pre-emptively temperatures are approaching limits OR operating trip the reactor before the RCP trip Cavitation of CCP pumps possible. CCP pumps discharge pressure and current times out, insert the following indicates cavitation, or if leakage is determined to command to trip the RCP immediately. Leakage excessive. be excessive:

TRG4 'IMF PMP-RCP003 l' IAW AOP-2.l5.1 the crew will Trip the Rx, THEN Go to E-O and perform IMA's, THEN Stop all RCP's Isolate Letdown Transfer CHS suct to R WST Stop ALL CCP pumps NOTE: The "B" RCP condition will continue to degrade Crew recognizes Automatic Reactor trip failure and The Reactor will trip manually. and trip, however an automatic reactor trip will ATC manually trips the reactor using a Benchboard NOToccuL control switch.

A5-3F, - 'REACTOR COOLANT PUMP AUTO STOP' - LIT A5-2G, - '113 REACTOR COOLANT PUMP LOOP FLOW LOW REACTOR TRIP' - LIT BVPS - 2 Scenario 1 7 of 20

BEAVER VALLEy r'OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES

'---- I PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: SRO Applies TS; Due to the sequence of events, the SRO TS 3.7.7, Condition Immediately initiate actions may not identify applicable TS. to restore one train of CCW to operable status.

follow-up question, "If CCP Surge Tank levels dropped to 0%, What, if any TS entries would be required?"

EVENTS 5,6,7 & 8 Automatic Reactor Trip failure (preloaded)

TRGSET 1 '.JPPLP4(1)' Set trigger 1 on Reactor trip SRO directs the A TC to manually trip the reactor, IMF PPLOI A (0 0) 0 TRN "A" Auto Reactor trip failure perform 1MAs and trio all RCPs.

IMF PPLOIB (0 0) 0 "B" Auto Rcactor IMF PPL07A (0 0) 4 2SIS*P21A auto start failure IMF PPL07B (0 0) 4 2SIS*P21B auto start failure IMF RCS03B (10) DBA LOCA on reactor trip IMF PPL09A (0 0) TRN "A" Auto CIB failure IMF PPL09B (0 0) TRN "B" Auto cm failure CRITICAL TASK: A TC manually trips the reactor.

E-O.A - Crew manually trips the reactor from the control room before performing the mitigation strategy of FR-S.1.

Crew enters E-O, performs immediate operator Crew performs IMAs of E-O.

actions BVPS - 2 Scenario 1 8of20

BEAVER VALLEy I ,OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I. EXPECTED STUDENT RESPONSE Rod bottom lights lit. Neutron flux dropping, First Out: A5-2G, - '113 REACTOR COOLANT PUMP LOOP FLOW LOW REACTOR TRIP' LIT Steps 1 - 4 of E-O are Immediate A5-6D, - 'TURBINE TRIP DUE TO REACTOR ATC verifies reactor trip.

Actions, TRIP' - LIT Power range indication - LESS THAN 5%

Neutron flux - DROPPING Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency Buses.

ENERGIZED Check SI ACTUATED ATC checks SI status.

CNMT Pressure - > 5PSIG PZR Pressure - < 1860 PSIG SG Steam Pressure - < 500 PSIG CREW DETERMINES SI REQUIRED Crew continues E-O Manually actuate SI (both trains) ATC manually actuates SI both trains.

E-O Immediate Actions completed, Manual reactor trip resulted in a DBA LOCA on SRO directs manual trip of all RCPs.

RCS Loop R A TC trips all RCPs.

BVPS - 2 Scenario 1 9 of 20

BEAVER VALLEy rOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Revision 7 em INSTRUCTIONAL GUIDELINES PLANT STATUS OBRESPONSE I EXPECTED STUDENT RESPONSE Alert Plant Personnel ATC/BOP sound Standby Alann, announce reactor trip and safety injection.

Leak collection filtered exhaust fan status SAT. Crew verities leak collection filtered exhaust fan 2HVS-FN204A or B running.

CRITICAL TASK: ATC verifies SI System status.

E-O.H - Crew manually starts at least Charging Pumps - TWO 2CHS*P2IA & 2CHS*P2IB running.

one low head ECCS pump before HHSI Flow INDICATED HHSI Flow indicated on 2SIS-FI943.

transition out of E-O. LHSI Pumps NONE RUNNING ATC manually starts 2SIS*P2tA & 2SIS*P2tB.

Motor-driven AFW Pumps - BOTH RUNNING BOP verities AFW System status.

Turb Driven AFW Pump Stm Supply Isol Valves OPEN AFW Throttle Vlvs - FULL OPEN Total AFW Flow GREATER THAN 340 GPM SRO directs an operator verify automatic actions by performing Attachment A-O.II when time pennits.

Attachment A-O.ll included with List of Attachment A-O.tt Discrepancies:

scenario beginning on Pg 18. Operator assigned to perform Attachment A-O.II Both LHSI pumps failed to auto start and were reports status of attachment to the SRO and any manually started. actions taken when completed.

CIB failed to auto actuate and was manually actuated.

BVPS 2 Scenario 1 10 of 20

BEAVER VALLEY POWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE RCPs OPERATING - MONITOR Tavg ATC/BOP checks RCS Tcold stable at or trending RCPs STOPPED - MONITOR Tcold to 547°F.

Plant rapidly cooled down due to DBA LOCA ATC reports RCS eold leg temperature and cool down caused by LOCA.

Check CIB - ACTUATED A TC checks Recirc Spray Pump status.

Recirc Spray HXs - SERVICE WATER FLOW ATC verifies 2SWS*MOVI03A(B) OPEN and TO ALL 4 HXs 2SWS*MOV106A(B) CLOSED.

Check Recirc Spray Pumps ANY RUNNING ATC checks no Recirc Spray pumps are running.

Check Recire Spray Pumps - ALL RUNNING Check Recirc Spray Pumps NOT CAVITATING If CIB was not previously actuated, the Crew will recognize CIB is required and manually actuate CIB - Both Trains.

PORVs CLOSED(not leaking). ATC verifies PZR isolated.

Spray Valves - CLOSED Safety relief valves (PSMS Detailed Data Page 1)

-CLOSED Check PRT conditions - CONSISTENT WITH EXPECTED VALUES Power to at least one block valve A VAILABLE Block valves - AT LEAST ONE OPEN BVPS - 2 Scenario 1 11 of 20

BEAVER VALLEY rOWER STATION 1/2 ADM-1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES

"----=-"----=-"----=---'---

PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE DIP between RCS pressure and highest SG pressure ATC checks if RCPs should be stopped.

- LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

AND HHSI Flow INDICATED Stop All RCPs If not previously stopped, ATC stops RCPs.

Pressures in all SGs ANY DROPPING IN AN BOP determines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED Check all SG levels - NONE RISING IN AN Crew determines all SG tubes are intact.

UNCONTROLLED MANNER Check Secondary Radiation - CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQ 100] Air Ejector Discharge (1007)

[2SSR-RQIOO] SG Blowdown Sample (1062)

[2MSS*RQIOIA,B,C] Main Steamline Discharge (1005,3005,5005)

BVPS - 2 Scenario 1 12 of 20

BEAVER VALLEY ,OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 C INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check the following consistent with pre-event Crew checks if RCS is intact.

values:

CNMT Pressure CREW DETERMINES THAT RCS IS NOT CNMT Sump Level INTACT, TRANSITIONS TO E-l STEP 1.

CNMT Radiation Transition to E-l, US directs transition to E-1.

NOTE:

After transition to E-l, crew may enter FR-P.l due to the excessive cooldown, however FR-P.l will be exited as soon as adequate LHSI flow is verified.

Crew checks if CREVS should be actuated If Auto Actuation of CREV s did not occur, BOP actuates both trains of CREVS using Control Room radiation monitor [2RMC*RQ20 1, CONTROL ROOM EMERG AIR SUP 202] (1069,1072) NOT IN HIGH ALARM ACTUATION pushbuttons.

CIB HAS OCCURRED DiP between RCS pressure and highest SG pressure A TC checks if RCPs should be stopped.

LESS THAN 205 PSID [220 PSID ADVERSE CNMT]

AND HHSI Flow - INDICATED RCPs STOPPED If not previously stopped, A TC stops RCPs.

BVPS - 2 Scenario 1 13 of 20

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE CIB - ACTUATED ATC checks Recirc Spray Pump status.

Recirc Spray Hxs SERVICE WATER FLOW TO ATC verifies 2SWS*MOVI 03A(B) OPEN and ALL 4 HXS 2SWS*MOVI06A(B) CLOSED.

RWST Level ::; 381 inches ATC checks RWST level> 38] inches.

Verify Recirc Spray Pumps NOT CAVITATING Pressures in all SGs - ANY DROPPING IN AN BOP determines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED SGs are NOT faulted Narrow Range Levels GREATER THAN 12% BOP checks intact SG levels.

[31 % ADVERSE CNMT]

BOP controls feed flow to intact SGs to maintain NR level between 12% [31% ADVERSE CNMT]

and 50%.

BVPS - 2 Scenario 1 14 of 20

BEAVER VALLE'Y rOWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check all SG levels - NONE RISING IN AN Crew determines SG tubes are intact.

UNCONTROLLED MANNER Check Secondary Radiation CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQ100] (1007) Air ejector discharge

[2SSR-RQ100] (1062) SGBD sample

[2MSS*RQlOIA,B,C] Main Steamline discharge (1005,3005,5005)

Power to the Block Vlvs A V AILABLE ATC checks PRZR PORVs and Block Valves:

PORVs - CLOSED All PORVS CLOSED.

Block Vlvs AT LEAST ONE OPEN All Block valves open and energized.

RCS Subcooling based on core exit TCs > 41 F ATC/BOP check if SI flow can be reduced.

[59F ADVERSE CNMT]

Secondary heat sink: Crew determines RCS subcooling is:s required Total feed flow to intact SGs GREATER THAN from Attachment A-5.l.

340GPM OR SI FLOW CANNOT BE REDUCED Narrow range level in at least one intact SG GREATER THAN 12% r3l-% ADVERSE CNMT]

RCS pressure STABLE OR RISING PRZR level GREATER THAN 17% [38% SI TERMINATION CONDITIONS ARE NOT ADVERSE CNMT] SATISIFIED, SRO CONTINUES IN E-l.

BVPS - 2 Scenario 1 15 of 20

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Any Quench spray or recirc spray pump ATCIBOP check ifCNMT Spray should be RUNNING stopped.

SRO continues STEP 10.

SI & CIA - RESET ATC resets SI and CIA.

RCS Pressure - > 225 PSIG [250 PSIG ADVERSE ATC checks ifLHSI pumps should be stopped.

CNMT]

RCS Pressure - STABLE OR RISING ATC determines RCS pressure is NOT stable or rIsmg.

Pumps stopped and in auto ATC determines RCS pressure < 225 psig, LHS[

pumps to remain running.

ATC/BOP checks RCS and SG Pressures.

Check pressures in all SGs - STABLE OR RISING BOP determines SG pressures are stable or rising.

Check RCS Pressure - STABLE OR DROPPING ATC determines RCS pressure is dropping.

Verify AC emergency busses energized from BOP checks ifEDGs should be stopped.

offsite Stop any unloaded EDG by performing 20M Crew initiates actions to STOP EDGs.

36.4.AF(AG)

Verify Cold Leg Recirculation Capability US directs operators to perform Att A-O.6 and verify cold leg recirculation capability.

ATC/BOP verifies all components in Attachment A-0.6 are available and dispatches an operator to energize valves per Step 4 of Attachment.

BVPS - 2 Scenario 1 16 of 20

BEAVER VALLEY POWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check Aux building and Safeguards radiation Crew recognizes that Rad Mon indications are CONSISTENT WITH PRE-EVENT consistent and leak is NOT outside containment.

ROLEPLAY: SM consults with TSC Staff to determine whether TSC is not yet activated, crew is to continue with If SRO requests TSC status - Report samples can be obtained next step.

TSC not yet activated.

Crew performs ATT A-1.l SRO directs crew to perform additional actions as required to aid in plant recovery per ATT A-I.I.

RCS Pressure - > 225 PSIG [250 PSIG ADVERSE A TC checks if cooldown and depressurization is CNMT] required:

Determines RCS pressure is < 225 psig and LHSI flow is > 1050 GPM.

Crew determines transition to ES-I.2 is not appropriate at this time.

Terminate drill when crew determines Check if Transfer to Cold Leg Recirculation is that ES-l.2 is not appropriate, Required. - Check RWST level < 400 inches.

continues with procedure and checks RWST level to determine if Transfer to Cold Leg Recirculation is necessary.

Classify Event SRO evaluates EPP and declares an ALERT either due to Loss of RCS Barrier (TAB 1.2.3) or Failure of Rx Protection (Tab 2.3)

BVPS - 2 Scenario 1 17 of 20

BEAVER VALLEy r'OWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES ,n_ PLANT STATUS OR RESPONSE ,... EXPECTED STUDENT RESPONSE ~

Attachment A-O.l1 'Verification of SRO directs an operator to perform Automatic Actions' performed as time Attachment A-O.ll as time & manpower permit.

& manpower permit.

Diesel generators BOTH RUNNING Check both EDGs running.

Ensure Reheat Steam Isolation Verifies 2MSS-MOVI00A,B closed.

Depresses reheater controller RESET pushbutton.

CNMT pressure - GREATER THAN 7 PSIG Check if MSLI is required.

OR SG Steam Pressure - LESS THAN 500 PSIG If not required, go to step 4.

OR Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIT Verify steam line isolation.

Open 2CCS-AOV118 domestic water to station air BOP establishes domestic water system cooling to compressors. the station air compressors by opening 2CCS AOV118.

At least one Station Air Compressor RUNNING BOP starts 1 station air compressor as required.

CCP pumps AT LEAST 1 RUNNING Check CCP Pump status None running due to CIB.

2NME-NR45 Nuclear Recorder selected to Align neutron nux monitoring for shutdown.

operable source and intermediate range displays BVPS - 2 Scenario 1 18 of 20

BEAVER VALLEY r'OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE pressure HAS REMAINED < 11 PSIG Check CIB status.

NOT Actuate CIB if required.

CRITICAL TASK:

E~O.E - Crew manually actuates at Manually initiate CIB - BOTH SWITCHES FOR BOP Manually Actuates CIB both trains.

least the minimum required BOTH TRAINS complement of containment cooling equipment before an Extreme (red Manually align equipment as required path) challenge develops to the All RCPs - STOPPED Stop ALL RCPs.

Containment CSF. BV-1 operator verifies CREVS actuation and Service water flow established to RSS HX(s)

Service Water Pumps 2 RUNNING Verify Service Water System in service.

Service Water Header Pressure - GREATER THAN 55 PSIG SWS Seal Water Pressure - NOT LOW

[2HCS*SOVlOOA1, B1] CNMT Sample amber Verify both CNMT hydrogen analyzers running.

LIT BVPS - 2 Scenario 1 19 of 20

BEAVER VALLEy rOWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 C=INS-TRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Verify ESF Equipment status - Start/align equipment as required.

CRITICAL TASK: All Red SIS Marks - LIT E-O.H - Crew manually starts at least 2SIS*P21A and 2SIS*P218 failed to start ATC didn't previously start both LHSI pumps one low head ECCS pump before automatically. the BOP will start them now.

transition out of E-O. Orange CIA Marks - LIT All Green FWI Marks LIT Power available to both Emergency AC Busses Verify power to both AC Emergency busses.

Restore power as required.

Attachment A-O.l1 - COMPLETE Report any discrepancies to SRO.

BVPS - 2 Scenario 1 20 of 20

A~ppen d"IX D . 0 utrme S cenano Form ES D 1 -

Facility: FENOC BVPS Unit 2 Scenario No.: 2 Op Test No.: 2LOT7NRC Examiners: Candidates: SRO ATC BOP Initial IC 212: 10% power, BOL, Equ. XE Conditions, CB "D" @ 118 steps, RCS boron - 1854 Conditions: ppm, Condensate Polishing Air Compressor - ~OS.

Turnover: Raise power to 15% to S/U main turbine.

Critical Tasks: E-3.A, Isolate Ruptured SG E-3.B, Cooldown RCS E-3.C, Depressurize RCS Event Malf. No. Event Type Event Description No.

1 R(ATC) Normal power increase to 15% lAW 20M-52.4.A N(SRO/BOP) 2 RCS04B C(ALL) seT 21 B Tube Leak SROTS 3 CNHMSS03A C (ATC/SRO) B atmospheric dump valve fails open.

SROTS 4 NIS08A I(ALL) N41 Power Range Instrument fuse blown SRO TS) 5 RCP06B C (ATC/SRO) 21B RCP high vibration (Manual RCP trip required)

RCP01B Manual reactor trip 6 RCS04B M (ALL) 21 B SG Tube Rupture 7 CNHPCS07A I (BOP/SRO) Condenser steam dumps fail closed.(Requires cooldown with 21A and 2IC Atmospheric Steam Dumps

~

C (BOP/SRO) 2SDS-AOV129A failed open, requires RNO actions for S/G isolation.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021. Revision 9 Supplement 1 FENoe Facsimile Rev 1

Appendix D Scenario Outline Form ES-D-1

<\fter taking the shift, the crew will continue the startup to raise power to 15% in accordance with 20M-52.4.A,

/art IV A, Plant Startup, currently the plant is at 10% power and Step 7 is in progress. The A TC will withdraw control rods lAW the reactivity plan while the BOP will be required to manually control the "e" S/O level due to the AUTO level control function being OOS.

A SO Tube leak will occur as evidenced by Rad monitor indications, the Unit Supervisor will direct actions per AOP 2.6.4 and refer to TS 3.4.13 for Primary to Secondary leakage.

2SVS*PCV101B, 21B SO atmospheric steam dump valve will fail open and stick open, the valve will not close in Auto, Manual or Locally, requiring the crew to direct the local isolation. The Unit Supervisor will refer to TS 3.7.4 for Inoperable Atmospheric Steam Dumps.

An Instrument power fuse will blow for Power range Channel N41, requiring the use of AOP IC. The crew will take actions per AOP 2.2.1C and the SRO will evaluate TS 3.3.1.

When the AOP actions are completed for N41, a 21B RCP high vibration condition develops, the crew will respond using AOP 2.6.8. The high vibration will increase at> 1 mil/hr which requires the crew to trip the reactor, enter E-O and take the reactor coolant pump out of service.

Following the reactor trip, a 500 gpm SOTR occurs on the 21B SO resulting in a Safety Injection actuation.

The crew will transition to E-3 at the "Check if SO Tubes are Intact" step ofE-O.

When the cooldown is attempted in E-3 the condenser steam dumps will fail closed, requiring the BOP operator J use manual control of the atmospheric steam dump valves and/or 2SVS-HCVl 04.

The drill will be terminated when HHSI flow is isolated in E-3.

Expected procedure flow path is EO ~ E3.

NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev 1

BEAVER VALLEy r--OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 10% Power, CBD 118, XE BOL, 1854 12 ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2SAS-C22 in PTL YCT on CS None 2FWS-FCV 499 AUTO Pushbutton YCTon CS --------------

None EQUIPMENT STATUS DATEITIME OOS TECHNICAL SPECIFICATION(S) 2SAS-C22 OOS --------------------

2 days ago None 2FWS-FCV499 AUTO control OOS Yesterday, 1200 hrs None SHIFT TURNOVER INFORMATION

1. Plant is at 10% power, BOL, EQU CB "D" at 118 steps, RCS boron 1854 ppm.

Protected Train is Train "B"

3. Continue the plant startup to 100% JAW 20M-52.4.A, Step 7 2SAS-C22, Condensate Polishing Air Compressor OOS

5. AUTO control function of Bypass Feed Reg Valve, 2FWS-FCV499 is OOS, requires manual operation.

SCENARIO SUPPORT MATERIAL REQUIRED

1. Plant startup reactivity plan.

2. Placard for 2FWE*P22 position stating 2FWE*P22 is aligned to "A" header

3. Place plaque on wall for Protected Train "B"

4. 20M-52.4.A, Increasing Power From 5% Reactor Power And Turbine On Turning Gear To Full Load Operation, completed through Step 7.a.l SETUP Start wIIC-5, raise power to 10% lAW reactivity plan and 20M-52.4.A, then SNAP IC BVPS - 2 Scenario 2 1 of 25

BEAVER VALLEy ;,OWER STATION 1/2 - ADM 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Initialize IC Set 212, and establish Reactor plant at 10% power, BOL, equilibrium initial plant conditions. conditions. RCS boron 1854 PPM, CBD 118 steps.

Inserts to TRGSET 1 'JPPLP4(1)' Set trigger 1 on Reactor Trip TRGSET 4 'TPCSTAAU <=530' Set trigger 4 on Tavg < 530 degrees f IMF CNH-PCS07A (4 0) 0 2MSS-PK464 failed, closes Steam Dumps IMF VLV-MSS057A (00) 100 2SDS* AOV129A failed open TRGSET 6 'JMLRCP6B == l' Set trigger 6 when malfunction RCP06B is actuated TRG 6 'IMF RCP06B 2160015' Ramp RCP vibration to 21 mils over 10 minutes BVPS - 2 Scenario 2 2of25

BEAVER VALLEy rOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Assign shift positions SRO:_ _ _ _ _ _ _ __

ATC:_ _ _ _ _ _ _ _ __

BOP:_ _ _ _ _ _ _ __

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

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

place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 2 3 of 25

BEAVER VALLEY rOWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 1:

Normal Plant Startup, Reactor Power increase to 15% to support Turbine Startup.

20M-52.4.A, step 7 Crew commences power increase in accordance with reactivity plan.

Continue reactor startup Reactor at 1U'ro power.

commences raising reactor power to between 10 and 15%.

Status lights on Panel 308 actuate at 10%. ATC verifies P-I 0 bistables lit on Panel 308 ATC verifies A12-1G, 'P-I0 PERMISSIVE' AI2-2B, - 'NIS IR TRIP BLOCKED' - LIT. ATC blocks the IR High Flux Trip AND IR High Flux Rod Stop by placing the IR BLOCK TRAIN and TRAIN B control switches to the BLOCK position and verifies annunciator A12-2B is AI2-2C, - 'POWER RANGE LOW SETPOINT A TC blocks the Power Range Low Overpower Trip TRIP BLOCKED' - LIT. by placing the PR BLOCK TRAIN A and TRAIN B control switches to the BLOCK position and verifies annunciator A12-2C is AI2-1H, - 'NOT P-7' - NOT LIT. ATC verifies that annunciator Al IH, 'NOT P-7' is NOT LIT.

BVPS - 2 Scenario 2 4 of 25

BEAVER VALLEY r-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

~~~~~:I~:N~STRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE A4-5G, - 'NIS POWER RANGE HIGH/LOW SP ATC verifies that annunciator A4-5G is OFF.

NEUTRON FLUX HIGH' NOT LIT.

ATC selects highest power ranges on N-45.

"C" S/G level decreases during power increase. BOP controls S/G level at target using manual controlof2FWS-FCV499.

Proceed next event at LE discretion BVPS - 2 Scenario 2 5 of 25

BEAVER VALLEY ,uWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 L INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 2:

After Crew has raised reactor power to 15% Insert TRG! 3 IMMEDIATE PLANT RESPONSE:

A4-5A; - 'RADIAnON MONITORING SYSTEM ATC reports Alarms to the SRO.

IMF RCS04B (3 0) 0.048 TROUBLE' - LIT (pre-loaded) A4-5C, - 'RADIATION MONITORING LEVEL BOP checks DRMS panel and determines that HIGH' - LIT 2MSS-RQI02B is indicating a 70 gpd tube leak 70 gpd tube leak "B" S/G. the "B" S/G.

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

SRO refers to AOP-2.6.4 Estimate initial pri-sec leakrate SRO determines that the leak rate is> 30 gpd due to the HIGH alarm on 2MSS-RQI02B actuated.

Check PZR level- DROPPING ATC determines value and trend for PZR level PZR Level is stable SRO monitors SG Tube leak by performing ATTACHMENT 1 of AOP 2.6.4.

BVPS - 2 Scenario 2 6of25

BEAVER VALLEY ..OWER STATION 1/2-ADM-1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ATTACHMENT 1, >5 gpd tube leak ATC opens 2SSR* AOVlI7A,B,C prior to obtaining Blowdown samples.

BOP to report leak rate from 6 monitor every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SRO Notifies Chemistry of entry into AOP-2.6.4, requests them to identify S/G, and quantity leakrate and report every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SRO Notifies RP of entry into AOP-2.6.4, requests them to quantify leakrate and report every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and to obtain grab samples every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and calculate leakrate based upon samples.

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

BVPS - 2 Scenario 2 7 of 25

BEAVER VALLEY ,~0WER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXE:~CTED STUDENT RESPONSE n~

ACTION LEVEL 1, >30 gpd tube leak ATC opens 2SSR *AOVII?A,B,C prior to obtaining Blowdown samples.

BOP to report leak rate from 6 monitor every 15 minutes.

SRO Notifies Chemistry of entry into AOP-2.6.4, requests them to identify S/G, and quantify leakrate and report every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SRO Notifies RP of entry into AOP-2.6.4, requests to quantify leakrate and report every 15 minutes and to obtain grab samples every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and calculate leakrate based upon samples, and perform additional surveys as appropriate.

SRO determines sustained leakrate is < 75 gpd and does not enter ACTION LEVEL 2.

SRO references Technical Specification 3.4.13 for "RCS Operational Leakage", determines not applicable until leakage > 150 gpd.

Next event occurs 10 minutes from initiation of Tube Leak (pre-loaded)

BVPS - 2 Scenario 2 8 of 25

BEAVER VALLEy ,-'OWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 3:

IMMEDIATE PLANT RESPONSE:

10 minutes after tube leak occurs, STATUS ALARM PANEL on VB-C indicates 2SVS-PCVl OIB fails OPEN, requires SG 21B ATM STM DUMP, 2SVS-PCVIOIB is manual isolation 'NOT CLOSEl),

Red light illuminated for 2SVS-PCVlOlB IMF CNH-MSS03B (3 600) 100 RCS Tavg shows a slight decrease SRO directs ATC to takc manual control of open (Pre-loaded) ADV, (2SVS-PCVIOIB) and close it.

SG level dcviation alarms may actuate.

ADV will NOT close from BB control A TC places controller for 21 B SG AD V in manual and attempts to close ADV.

SRO requests I&C assistance.

Crew notifies Field operator to close 2SVS Valve requires manual isolation, valve PCVIOIB using 20M-21.4.J not close via either local manual Or locally isolate via 2SVS-24 or de-energize via operation or by de-energizing MCC ROLE PLAY:

IF requested to Isolate 2SVS-24, INSERT 'LOA-MSS017 0' then report to Control Room that 2SVS-24 is isolated SRO refers to TS 3.7.4, Condition for inoperable atmospheric dump valvc. Requires restoring 7 days.

BVPS - 2 Scenario 2 9 of 25

BEAVER VALLEY r~OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I EXPECTED STUDENT RESPONSE]

Continue with next event at r,E discretion EVENT 4 1 Instrument Power fuse blows IMMEDIATE PLANT RESPONSE:

A4-4F, 'NIS POWER RANGE COMPARATOR A TC notes associated Power Range alarms and IMF NIS08A (0 0) 0 DEVIATION' - LIT indications, reports this to SRO.

A4-4G, - 'NIS POWER RANGE NEUTRON FLUX RATE HIGH' - LIT SRO determines AOP 2.2.1 C is necessary due to A4-4H, 'NIS POWER RANGE HIGH indications of failed Power Range channel.

SETPOINT OVERPWR ROD STOP BLOCK ROD WID' - LIT A4-5G, - 'NIS POWER RANGE HIGH/LOW SP NEUTRON FLUX HIGH' - LIT BB-B Indication for N41 indicates downscale NIS Rack drawer 41 A, downscale indication and all Indicating lights illuminate.

Crew verifies malfunction of only 1 Power Range Channel has occurred.

BVPS - 2 Scenario 2 10 of 25

BEAVER VALLEy rOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PL~J\lJ STATUS OR RESPONSE EXPECTED STUDENT RESPONSE To comply with TS 3.3.1, functions 17.c, 17.d, &

17.e, within 1 hr, SRO directs A TC to verify P-8, P-9 and P-l 0 interlocks are in the required state for the existing Plant conditions.

ATC verifies A12-1G P-lO PERMISSIVE',

A12-2G - 'NOT P-8' and A12-3G - 'NOT P-9' ALL LIT and in the required state for the plant being at 15% power.

Within 72 hrs, SRO directs BOP to TRIP the Nuclear Bistables by removing the Control Power Fuses from Drawer N41A.

ALL STATUS lights on Drawer N41A extinguish. BOP removes Control Power Fuses from drawer N41A.

At NIS Rack N50, BOP turns the "Rod Stop Bypass Switch" to BYPASS for N41.

Status light A-14 on status panel 308 illuminates ATC verifies status light A-14 on status panel 308 A4-4H, 'NIS POWER RANGE HIGH illuminates.

SETPOINT OVERPWR ROD STOP BLOCK ROD WID' - CLEARS ATC verifies Reactor Power is < 50%

BVPS - 2 Scenario 2 11 of 25

BEAVER VALLEY ,-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE L EXPECTED STUDENT RESPONSE ~

At NIS Rack N371N46, BOP turns "Comparator Channel Defeat Switch" to N41 channel.

NIS Drawer N3 71N46 Status light indication for "CHANNEL DEVIAnON" clears and indication illuminates for "COMPARATOR DEFEAT" A4-4F, 'NIS POWER RANGE COMPARATOR DEVIAnON' - CLEARS ATC verifies Vertical board recorders are NOT selected to N41.

To comply with TS 3.3.1 functions 6 & 7, SRO contacts I&C and requests Bistables on Attachment 1 for N41 be tripped w/in 72 hrs.

ATC verifies Reactor Power is < 50%

SRO refers to TS 1 function and to SR 3.2.3.1 for applicability, determines they are not applicable due to being at 15% reactor power.

Continue with next event at r,E discretion BVPS - 2 Scenario 2 12 of 25

BEAVER VALLE'r i-OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 1

m INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT #5 B RCP High Vibration/Seal Failure Insert the following: IMMEDIATE PLANT RESPONSE:

21 B RCP seal leakoff rising as indicated on 2CHS ATC acknowledges RCP Hi vibration alam1, IMF RCPOI B (5 0) 4 30 FR154A. informs SRO, BOP refers to A2-5C ARP.

A2-5C, 'REACTOR COOLANT PUMP Crew notes 21 B RCP Shaft vibrations at 15 IMF RCP06B (5 0) 15 VIBRA TION ALERT/DANGER' - and trends.

IMF RCP06B 21 600 15 (inserted as 21 B RCP vibration rises to >20 mils.

pre-load on trg 6)

SRO enters AOP-2.6.8, Crew checks RCP parameters in Table 1 of AOP 2.6.8 to determine if Criteria is met for an Immediate RCP Shutdown.

NOTE:

Trend on RCP vibration will need to be SRO continues in AOP 2.6.8 observed before RCP trip criteria is met.

A TC verifies that EITHER Seal Injection Flow OR Thermal Barrier cooling flow is indicated to EACH RCP.

NOTE: SRO refers to Attachment 3 for RCP Vibration SRO May not enter Attachment 3 if Issue.

Trend of RCP vibration has identified Immediate RCP Trip Criteria has been met.

BVPS - 2 Scenario 2 13 of 25

BEAVER VALLEy I,OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 L_n I~STRLJCTjONAL~IJIDELINES I... PLANT STATUS OR RESPONSE 1 EXPECTED STUDENT RESPONSE Shaft vibration> 15 mils and rising at> 1.0 When it is determined that RCP vibration is> 15 mils/hr. mils rising at> 1 mil/hour, the SRO directs a reactor trip and the stopping of 21 B RCP after E-O Immediate Actions are completed.

EVENT 6 ATC manually trips reactor.

500 gpm B SGTR IMF RCS04B (1 0) 500 (preload) 500 gpm 21 B SGTR when the reactor is tripped. ATC informs SRO of a reactor trip.

Steps 1 4 of E-O are Immediate ATC/BOP commence IMA's ofE-O, SRO Actions. references E-O to verify IMA' s.

A5-6D, - 'TURBINE TRIP DUE TO REACTOR ATC verifies reactor trip.

TRIP' Power range indication - LESS THAN 5%

Neutron f1ux dropping.

Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output BIas - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency Buses.

ENERGIZED BVPS - 2 Scenario 2 14 of 25

BEAVER VALLEY .OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Due to SGTR; RCS pressure reducing PZR Level goes offscale low.

SG level and Feedflow ISteam flow mismatch BOP will continue to control "C" S/G level to alarms will occur. 2FWS-FCV 499 controller in manual.

NOTE: SI may not have actuated at Evaluate if SI is Actuated or Required this time however, RCS conditions are Check SI - ACTUATED degrading due to 21 B SGTR. If crew Pressure > 5PSIG ATC reports SI status, manually actuates SL transitions to ES-O.l at this time, they PZR Pressure - < 1860 PSIG will be required to manually actuate SI SG Steam Pressure < 500 PSIG and return here. This drill assumes SI is actuated at this time and the crew SI actuated on low PZR pressure.

continues with E-O.

E-O Immediate Actions completed.

SRO directs RO to secure 21 B RCP due to high vibrationlsealleakofT trouble.

21B RCP secured. ATC secures 21 B RCP.

Alert Plant Personnel ATC/BOP sound Standby Alarm, announce reactor trip and safety injection.

Leak collection filtered exhaust fan status SAT. Crew verifies leak collection filtered exhaust fan 2HVS-FN204A or B running.

BVPS - 2 Scenario 2 15 of 25

BEAVER VALLEY rOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7

[ INST~UCTIONAL GUIDELINES PLANT STATUS OR RESPONSE [ EXPECTED STUDENT RESPONSE Verify SI Status A TC verifies SI System status.

2CHS*P21 A & 2CHS*P2IB running.

HHSI flow indicated on 2SIS-FI943 Both LHSI pumps running.

Verify AFW Status BOP verifies 2FWE*P23A & B both running 2FWE*P22 steam supply valves all open AFW Throttle valves all full open And total AFW flow is > 340 gpm.

SRO directs an operator verify automatic actions performing Attachment A-O.II when time permits.

Attachment A-O.ll included with List of Attachment A-O.ll Discrepancies:

scenario beginning on 24. Operator assigned to perform Attachment A-O.II All Automatic actions of A-O.ll are SAT reports status of attachment to the SRO and actions taken when completed.

RCS temperature trending to 547°F. ATC reports Tavg status, SRO directs crew to RCPs OPERATING MONITOR Tavg control steam/feed flow as necessary to achieve desired status.

RCPs STOPPED - MONITOR Tcold Check cm - NOT ACTUATED ATC checks Recirc Spray Pump status, cm NOT actuated, Recirc spray pumps not running.

Recirc Spray HXs - SERVICE WATER FLOW TO ALL 4 HXs Check Recirc Spray Pumps ANY RUNNING Check Recirc Spray Pumps ALL RUNNING Check Recirc Spray Pumps - NOT CA VITATING BVPS - 2 Scenario 2 16 of 25

BEAVER VALLEY rOWER STATION 1/2 ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES U-PLANT STATUS OR RESPONSE I EXPECTED STUDENT RESPONSE PORVs CLOSED A TC verifies PZR isolated.

Spray Valves CLOSED Safety relief valves - (PSMS Detailed Data Page 1)

-CLOSED Check PRT conditions - CONSISTENT WITH EXPECTED VALUES Power to at least one block valve A V AILABLE Block valves - AT LEAST ONE OPEN 2IB RCP previously secured. ATC checks if RCPs should be stopped.

21A & 21 C RCPs running.

CCP flow normal.

Pressures in all SGs ANY DROPPING IN AN BOP determines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED 2IB SG level rising in an uncontrolled manner. S RO directs operator to check if SG tubes are Secondary rad monitors not consistent with pre intact.

event levels. BOP determines that the 21 B SG level is rising an uncontrolled manner.

Crew transitions to SRO makes transition to E-3 and informs crew.

SRO directs STA to monitor status trees.

BVPS - 2 Scenario 2 17 of 25

BEAVER VALLEy I-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training r- nINSTRUCTIQNAL GUIDELINES In Revision 7 PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Control room habitability system not required. BOP verifies control room habitability.

21B RCP previously secured. ATC/BOP checks ifRCPs should be stopped, 21 A & 2 I C RCPs running. determine 21 A & 21 C RCPs to remain running.

RCS - Highest SG Delta Pressure >205 psid CCP flow normal.

CRITICAL TASK 21 B SG level rising in an uncontrolled manner. Crew identifies SG 21 B as the ruptured SG.

E-3.A - Crew isolates feed flow into Secondary rad monitors not consistent with pre and steam flow from the ruptured event levels.

SG and directs operator to close isolations valve{s) operated from outside of the control room before a transition to ECA-3.1 occurs.

Crew isolates flow ruptured SG.

Adjust ruptured SG atmospheric stearn dump controller setpoint to 100% and verify Crew notes that 2SYS*PCYI01B was previously 2SYS*PCYI 01B closed. isolated.

ATC verifies 2SYS*HCYI04 closed IRF LOA-MSSOIO 0 Verify closed 21 B SG steam supply to 2SYS Crew dispatches an operator to close 2SYS*28 HCYI04,2SYS*28.

ROLEPLAY:

Notify crew that 2SYS*28 closed when requested.

BVPS - 2 Scenario 2 18 of 25

BEAVER VALLEY .-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE J Isolate 21 B SG stearn supply to 2FWE*P22 BOP verifies both motor driven AFW pumps runmng.

BOP closes 2MSS*SOVI05B and E Verify Blowdown and Steamline drains isolated ATC verifies 2BDG* AOV 1OOB 1 is closed ATC verifies 2SDS*AOVl11Bl is closed VL V -MSS057 A (pre-loaded) 2SDS*AOV129A - failed open BOP verifies 2SDS* AOV129A is not closed.

BOP identifies that 2SDS* AOV129A is failed open, and won't close from VB-C control switch.

Reports to SRO and closes 2SDS*AOVI29B.

Closes Ruptured SG main stearn lines isolation and bypass valves. BOP closes 2MSS* AOV 101 B and verifies 2MSS*AOVI02B is closed.

21 B SG narrow range level greater than 12% (31% BOP checks ruptured SO level.

adverse). When NR level is > 12%, BOP isolates feed flow to 21B SG by closing 2FWE*HCVlOOC & D.

Feed Water Isolation verified BOP confirms FWI was previously verified using Attachment A-O.ll.

Ruptured SO pressure> 240 psig. BOP verifies ruptured SG pressure> 240 psig.

BVPS - 2 Scen ario 2 19 of 25

BEAVER VALLEY rOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES In PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE CRITICAL TASK Based on ruptured SG pressure. SRO determines target temperature for cooldown, E-3.B - Crew establishes/maintains 1000 - 1084 = 505°F (480°F). uses NORMAL containment parameters.

an RCS temperature so that 900 - 999 = 492°F (467°F).

transition from E-3 does not occur because the RCS temperature is in either of the following conditions:

Too high to maintain minimum required subcooling for subsequent RCS depressurization, OR below the RCS temperature that causes a red or orange path challenge to Subcriticality or Integrity CSF.

ATC blocks low steam line pressure SI when PRZR pressure is less than 2000 psig.

Steam dump is available, Max rate cooldown. BOP attempts to dump steam at maximum rate using condenser steam dumps in steam pressure Mode. If not already in steam pressure mode, BOP Steam dumps fail closed Condenser steam dumps closed, does so now.

CNH-PCS07A BOP determines that the condenser steam dumps have failed closed and reports to SRO.

SRO directs BOP to use the 21A and 21C ADV's to initiate max rate cooldown.

STA monitors thermocouples.

BVPS - 2 Scenario 2 20 of 25

BEAVER VALLEY rOWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I** EXPECTED STUDENT RESPONSE BOP stops cooldown when core exit TCs < target temperature.

BOP places 21 A & 21 C atmospheric dump valve controllers in auto with pot setting corresponding to current intact SG pressure.

Intact SG levels> 12% (31 % adverse). BOP controls intact SG feed flow as required (340 gpm min) to achieve/maintain levels between 26%

and 50%.

Power to PORVs & block valves SAT. ATC verifies PORVlblock valve conditions as PORVs closed, not leaking. expected.

PORV/block alignment SAT.

Auto SI blocked Al2-1C ATC resets SI (both trains).

SI signal A12-1 D NOT lit.

Both trains of CIA reset. ATC resets CIA and CIB (both trains).

CIB not actuated.

Station air available. BOP verifies/reports status of station air system.

Instrument air established to CNMT. Crew establishes instrument air to CNMT.

BOP verifies 2IAC-MOV131 - open.

BOP opens 2IAC-MOV130.

BOP verifies Instrument air header pressure> 85 psig on VB-C.

RCS pressure> 225 psig (250 psig adverse). A TC verifies RCS pressure> 225 psig and stable, LHSI pumps stopped, in auto. stops LHSI pumps and places them in auto.

BVPS - 2 Scenario 2 21 of 25

BEAVER VALLEY ,OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I n_ EXPECTED STUDENT RESPONSE Ruptured SG pressure stable. BOP verifies ruptured SG pressure stable.

Subcooling> 61°F (79°F adverse). Crew verifies subcooling SAT at >61 OF.

CRITICAL TASK Depressurize RCS to minimize break flow and A TC depressurizes RCS to minimizc break flow E-3.C -Crew depressurizes RCS to refill PRZR and refill PRZR by; meet Sf termination criteria before Verifying 21A and 21C RCPS both running.

water release from the ruptured SG Opening both pzr spray valves, 2RCS*PCV455A safety or atmospheric relief valve. and 2RCS*PCV455B.

Opens one PORV Verifies RCS pressure is reducing.

Depressurization Termination ATC closes the PORV and spray valves when RCS pressure is < ruptured SG pressure AND PRZR level is > 17%.

Verify PORV closed. A TC verifies RCS pressure rising.

Check if SI Flow should be terminated. ATC verifies RCS subcooling> 41°F.

BOP verifies secondary heat sink, total AFW flow

> 340 gpm or one intact SG NR level> 12%

ATC verifies RCS pressure is stable or rising.

A TC verifies PRZR level is > 17%.

SRO determines above conditions support termination of SI.

BVPS - 2 Scenario 2 22 of 25

BEAVER VALLEy .-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE U]

Terminate SI flow. SRO directs A TC to stop all but one charging pumps.

ATC secures all but one charging pumps.

SRO directs A TC to close 2SIS*MOY867 A, B, C, D.

ATC closes 2SIS*MOY867 A, B, C, 0 from BB-A.

Terminate scenario when HHSI is isolated in E-3.

Classify Event:

ALERT due to Tab 1.2.4, LOSS of RCS Barrier, Primary to Secondary Leak.

BVPS - 2 Scenario 2 23 of 25

BEAVER VALLEY I-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I EXPECTED STUDENT RESPONSE ~

Attachment A-O.11 'Verification of SRO directs an operator to perform Attachment A Automatic Actions' performed as time 0.11 as time & manpower permit

& manpower permit Diesel generators - BOTH RUNNING Check both EDGs running Ensure Reheat Steam Isolation Verify 2MSS-MOVIOOA and B closed Depress Reheater Controller RESET push button CNMT pressure GREA TER THAN 7 PSIG Check if MSLI is required OR SG Steam Pressure LESS THAN 500 PSIG If not required, go to step 4 OR Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS YeHow SLI marks - LIT Verify steamline isolation Step 4 Open [2CCS-AOVl18] Domestic Water to Station Establish Domestic Water System Cooling to Air Compressor Station Air Compressors At least one Station Air Compressor RUNNING Start 1 Station Air Compressor as required CCP pumps ... AT LEAST 1 RUNNING Check CCP Pump status

[2NME-NR45] Nuclear Recorder selected to Align neutron flux monitoring for shutdown operable source and intermediate range displays BVPS - 2 Scenario 2 24 of 25

BEAVER VALLEY ,OWER STATION 1/2 -ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE CNMT pressure - HAS REMAINED LESS THAN Check CIB status 11 PSIG IF NOT Actuate CIB if required Manually initiate CIB - BOTH SWITCHES FOR BOTH TRAINS Manually align equipment as required RCPs STOPPED Stop ALL RCPs BV -1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps - 2 RUNNING Verify Service Water System in service Service Water I leader Pressure - GREATER THAN 55 PSIG SWS Seal Water Pressure NOT LOW

[2HCS*SOVI OOAl, Bl] CNMT Sample amber Verify CNMT hydrogen analyzers running light- LIT All Red SIS Marks LIT Verify ESF Equipment status Start/align All Orange CIA Marks - LIT equipment as required All Green FWI Marks Power available to both Emergency AC Busses Verify power to both AC Emergency busses Restore power as required Attachment A-O.ll COMPLETE Report any discrepancies to SRO BVPS - 2 Scenario 2 25 of 25

A,ppen d"IX D " 0 utrme S cenano Form ES-D 1 Facility: FENOC BVPS Unit 2 Scenario No.: 3 Op Test No.: 2LOT7NRC Examiners: Candidates: SRO ATC BOP Initial IC-213 MOL, 100 % power Equ Xe, Rods Bank D @ 230 steps, RCS Boron - 883 PPM, Conditions: Condensate Polishing Air Compressor - OOS.

Turnover: Maintain current plant conditions Critical Tasks FR-S.1.A, Crew isolates the main turbine from the SG's FR-S.l.c, Crew inserts negative reactivity into the core by inserting RCCAs E-2.A, Crew isolates/directs isolation of faulted SG Ir= 1 Malf. No.

XMT-MSS043A Event Type I(ALL)

Event Description 2MSS*PT447 fails LOW, Rods Auto insert, Rx power rises due to cold Feedwater, Power reduction required.

SRO TS.

2 R(ATC) Emergency Power reduction N(BOP/SRO) 3 XMT-RCS030A I(ATC/SRO) 2RCS*PT444 drifts HIGH, Pzr pressure decreases, manual SRO TS. control of Pzr pressure required.

4 FLX-CFW31 M(ALL) 4500 gpm Feedwater leak inside cnmt on "A" S/G 5 PPLOIA PPLOIB M(ALL) ATWS - Failure of auto/manual Rx trip 6 EHC03B C(BOP/SRO) Incomplete turbine trip, requires manual Steam line isolation actuation EHCOIB 7 VLV-MSS003A C(BOP/SRO) Auto MSLI Isolation actuation failure with 2MSS-AOVIOIA PPLlOA PPLIOB failing to close on a manual MSLI actuation. manual isolation required.

8 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev 1

Appendix 0 Scenario Outline Form ES-D-1

'T'he crew will assume the shift at 100% power, Equilibrium MOL conditions with instructions to maintain

-.:urrent power leveL 2MSS*PT447 will fail low, this will cause 2CNM-AOVIOO to open resulting in an overpower condition, causing the control rods to insert. The crew will respond by performing an Emergency Shutdown lAW AOP 2.51.1. Once the overpower condition has been corrected, 20M-24.4.IF, attachment 5 will be implemented to respond to 2MSS*PT447 failure. The SRO will evaluate TS 3.3.1 applicability and initiate required actions.

When the plant has stabilized, 2RCS*PT444 will drift high, requiring use of20M-6.4.IF, Attachment 2, the ATC will be required to manually control RCS pressure. The SRO will evaluate TS 3.4.1 applicability.

A 4500 gpm Feedwater leak on the "A" loop inside containment will begin to ramp in, I st indication of leak will be containment sump pumpout and Incore sump alarms. Based upon the sump alarms, the crew may enter AOP 2.6.7 to diagnose leak location. Feed flow to the "A" S/G will increase, however, S/G level will begin to drop.

Level will continue to drop to the Reactor trip setpoint, however, Auto and Manual Reactor trips have been inhibited. When the crew recognizes a reactor trip is necessary a manual reactor trip will be directed by the SRO and E-O will be entered.

When it is recognized that the reactor will not trip, the SRO will direct entry into FR-S.1, this will be complicated by TV -2 and GV -2 sticking open on a turbine trip. An automatic MSLI actuation is inhibited requiring the BOP to manually actuate a MSLI, this is further complicated by 2MSS-AOV101A failing to automatically close on the manual MSLI actuation, which will require manual closure. The ATC will be

nserting control rods and initiating emergency boration. An operator will be dispatched to locally trip the

.eactor, which will occur 2 minutes after being dispatched, at which time the crew will transition back to E-O.

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

When the crew has isolated the "A" S/G, in E-2, the drill will be terminated.

Expected Procedure flow path is E-O - FR-S.l - E-O- E-2 NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev 1

BEAVER VALLEY ,OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 100 % Power, CBD 230, XE MOL, 883 PPM Boron, IC-213 I ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2SAS-C22 in PTL

,~-~~---- -------

YCTon CS None

~EQUIPMENTSTATUS DATE/TIME OOS TECHNICAL SPECIFICATION(SJ 2SAS-C22 OOS

}. days ago None SHIFT TURNOVER INFORMATION

1. Power, CBD 230, EQU MOL, 883 PPM Boron Protected Train is Train "B"

.J. Maintain steady state power level.

4. 2SAS-C22, Condensate Polishing Air Compressor OOS for overhaul.

SCENARIO SUPPORT MATERIAL REQUIRED

1. Reactivity plan placard for MOL

2. Placard for 2FWE*P22 position stating 2FWE*P22 is aligned to "A" header

3. Place plaque on wall for Protected Train "B" BVPS - 2 Scenario 3 1 of 19

BEAVER VALLEY ,OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Initialize Ie Set 213, and establish Reactor plant at 100 % Power, MOL, equilibrium initial plant conditions. conditions, ReS Boron 883 PPM, eBD 230 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the drill Setup section of the HTML File for this drill:

TRGSET 1 'JPPLP4(1)' Set trigger 1 on Reactor Trip IMF PPLOIA (0 0) 1 Set ATWS condition TRN "A" IMF PPLOIB (0 0) 1 Set ATWS condition TRN "B" IMF EHC03B (0 0) 1000100 2 L TRGSET 2 'JPPLASO(I)' Set trigger 2 on Turbine Trip (auto stop oil low)

IMF EHCOIB (2 0) 740 ASIS GV 2 stuck in pre-trip position IMF PPLI0A (0 0) TRN "A" AUTO MSLI inhibited IMF PPLI0B (0 0) TRN "B" AUTO MSLI inhibited IMF VLV-MSS003A (0 0) 100 2MSS-AOVIOIA failed to auto close on MSLI TRGSET 3 'XC2I027C == l' Set trigger 3 on manual close attempt with TRN "A" 2MSS-AOV101A es TRG 3 'DMF VLV-MSS003A' Delete preventing 2MSS-AOVIOIA closure.

TRGSET 4 'XC2I028C == l' Set trigger 4 on manual close attempt with TRN "B" 2MSS-AOVIOIA es TRG 4 'DMF VLV-MSS003A' Delete MALF preventing 2MSS-AOVIOIA closure.

IMF PPL02A (30 120) Train A trip BKR open IMF PPL02B (30 130) B trip BKR open IRF LOA-CRF007 (30140) 1 ~ A rod drive MG set IRF LOA-CRF008 (30 150) 1 Trip B rod drive MG set BVPS - 2 Scenario 3 2 of 19

BEAVER VALLEY .-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training

--~~

Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Assign positions BOP:_ _ _ _ _ _ _ _~

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

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

place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 3 3 of 19

BEAVER VALLEY rOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENTS 1 & 2:

2MSS*PT447 fails LOW requires Emergency Power Reduction IMF XMT-MSS043A (0 0) 0 30 ASIS IMMEDIATE PLANT RESPONSE:

Rods begin stepping inward Automatically ATC observes Inappropriate Rod Movement and A4-3C, - 'TA V G DEVIAnON FROM TREF' performs Immediate Action Step of AOP 2.1 LIT ATC determines No Load Rejection is in progress A6-12G, 'AMSAC TROUBLE' - LIT and places Rod Control into Manual to stop rod movement.

Followed by; A6-5E, - 'CONDENSATE PUMP DISCH/SUCT PRESSURE LOW' - LIT A6-5D, - 'CONDENSATE PUMP AUTO START/AUTO STOP' ~ LIT 2CNM-P21 Auto Starts ~ Red light illuminated 2CNM-AOVIOO opens Red light illuminated SRO implements AOP 2.1.3 Checks First Stage Pressure indication BOP identifies 2MSS-PT447 is failing low.

Loop delta 1"s exceed 100% power indication Crew determines that Reactor Power is exceeding 1

SRO enters AOP 1.1 and directs an emergency power reduction.

BVPS - 2 Scenario 3 4 of 19

BEAVER VALLEY ,-OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: ATC initiates Emergency power reduction by 2CNM-AOVlOO will automatically close 4 minutes Depressing 151 stage in pushbutton, after opening. Setting EHC setter to ~5% below current power Setting load rate thumbwheel to 5%/min Depressing GO pushbutton A TC monitors Power level less than 100% and not rising. If necessary, SRO directs BOP to reduce additional turbine load.

ATC controls RCS Tavg via use of Control Rods manual and/or Boration of the RCS.

When power level is <100%, SRO implements 20M-24.4.IF BOP selects 2MSS*PT446 by placing "Main First Stage Press Sensor Select" CS to PM446 position on BB-C SRO directs BOP to remove the Arming signal to the condenser steam dumps by placing the "Steam Dump Control Mode Selector Switch" on BB-C to the RESET position.

Steam dump arming signal reset stm dumps close.

BOP verifies 2CNM-AOVI 00 closed BOP places Steam Dumps in Steam Pressure Mode of Operation with a control Setpoint of 1005 psig IA W SRO Direction per 20M-24.4.IF.

BVPS - 2 Scenario 3 5 of 19

BEAVER VALLEY ,-OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE SRO refers to TS 3.3. L Function 17.f, Condition P, verify P-13 interlock is in it's required State w/in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ATC determines A12-1F, 'P-13 PERMISSIVE' is Ii 1.

When the Crew has stabilized the plant at less than 100% power and the SRO has determined TS applicability, Proceed with next event at LE discretion EVENT 3:

2RCS-PT444 drifts high RCS Pressure control input PT IMF XMT-RCS030A (0 0) 2500 90 IMMEDIATE PLANT RESPONSE:

A4-1D, - 'PRESSURIZER CONTROL A TC notes/verifies alarms, informs SRO/Crew of PRESSURE HIGH/LOW' - LIT apparent instrument failure of2RCS*PT444.

A4-1E, - 'PRESSURIZER CONTROL PRESS DEVIATION HIGH/LOW' - LIT A4-2F, - 'PRESSURE RELIEF BLOCK' - LIT ATC takes manual control of Pressurizer pressure A2-4B, - 'REACTOR COOLANT SYSTEM control to restore pressure.

SUBCOOLING OFF NORMAL' - LIT BVPS - 2 Scenario 3 6 of 19

BEAVER VALLEY .-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE ,- EXPECTED STUDENT RESPONSE SRO enters 20M-6.4.IF Attachment 2 and directs ATC to place the CS for 2RCS*PCV455C to close.

SRO directs ATC to manually control pressurizer spray valves and heaters as necessary to restore/control RCS pressure.

ATC reports to SRO that Pressurizer pressure reduced low enough to require entry into DNB TS.

Per TS 3.4.1, SRO identifies that pressure must be restored within limit w/in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ATC continues to manually control Pressurizer pressure for the remainder of the scenario.

When ATC has stabilized pressure and SRO has addressed DNB TS.

Continue with next event at LE discretion BVPS 2 Scenario 3 7 of 19

BEAVER VALLEY ..OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE ,.. EXPECTED STUDENT RESPONSE EVENT 4:

4500 GPM Feedwater leak, "A" S/G inside Cnmt IMF FLX-CFW31 (00) 4500 600 0 IMMEDIATE PLANT RESPONSE:

Cnmt Sump Alarms, IMF CRFOIA A2-2B, - 'UNIDENTIFIED LEAKAGE SYSTEM TROUBLE' - LIT Al-2G, - 'INCORE INSTRUMENT ATC notes cnmt sump alarms and informs SRO.

ROOM/CNMT SUMP LEVEL HIGHlY AL VE BOP refers to ARP for A2-2B, checks CCP surge NOT RESET' - LIT tank levels stable and reports that ARP directs entry Cnmt Dewpoints rising into AOP 2.6.7.

NOTE: SRO enters AOP 2.6.7 It not likely that AOP 2.6.7 actions will be taken due to the degrading S/G parameters that will become evident.

A6-9E, - 'SG 21A LEVEL DEVIATION FROM BOP acknowledges alarm and informs SRO.

SETPOINT' LIT "A" SG level dropping wi increasing Feedwater BOP recognizes and informs the crew, that the A flow. SG level is dropping with an increase in Feedwater flow.

A2-3B, 'UNIDENTIFIED LEAKAGE FLOW ATC informs SRO that another Cnmt Sump alarm GREATER THAN 60 GALLONS' LIT has annunciated.

BVPS - 2 Scenario 3 8 of 19

BEAVER VALLEY r-OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE A6-9D, - 'SG 21A LEVEL HIGH/LOW' BOP reports to the crew that the A S/G low level 21 A S/G level continues to drop with an increasing alarm has annunciated and that level continues to Feedwater flow rate drop.

SRO directs the crew to perform a manual reactor trip and enter E-O EVENTS 5 - 7: (pre-loaded)

IMMEDIATE PLANT RESPONSE:

A TWS, Incomplete Turb Trip, MSLI Reactor NOT trip from the control room Actuation failure Crew enters E-O, performs Crew performs IMAs of E-O.

immediate operator actions.

A5-6D, - 'TURBINE TRIP DUE TO REACTOR ATC verifies reactor is NOT tripped.

TRIP' - NOT LIT Power range indication NOT LESS THAN 5% ATC attempts manual reactor trip from BB-B eutron flux - NOT DROPPING BB-A, reports reactor has NOT tripped US transitions to FR-S.l Reactor IS NOT tripped SRO/Crew determine FR-S.l entry conditions met, transitions to FR-S.l Step I Crew performs IMAs of FR-S.l BVPS - 2 Scenario 3 9 of 19

BEAVER VALLEY rOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 I** INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE n~

IMF EHC03B (0 0) 1000100 Turbine trip BOP manually trips the turbine by depressing both TRGSET 2 'JPPLASO(I)' Turbine Trip push buttons on BB-C.

IMF EHCOIB (2 0) 74 0 ASIS IMF PPLIOA (0 0) BOP identifies that TV-2 and GV-2 have not closed IMF PPLI0B (0 0) and the turbine has not tripped.

IMF VLV-MSS003A (0 0) 100 TRGSET 3 'XC21027C = 1' BOP manually initiates Main Steam Line Isolation.

TRG 3 'DMF VLV-MSS003A' TRGSET 4 'XC21028C == l' BOP identifies that 2MSS-AOVIOIA did not close TRG 4 'DMF VL V-MSS003A' and manually closes valve from BB-C.

above commands pre-loaded)

CRITICAL TASK FR-S.1.A Crew isolates the main turbine from the SGs before WR SG level is less than 10%

CRITICAL TASK ATC identifies that the control rods are not inserting in Auto, selects MANUAL and begins FR-S.1.C Crew inserts negative Control Rods are inserting in Manual inserting Control Rods.

reactivity into the core by inserting RCCAs before completing the immediate action steps of FR-S.1.

Verify AFW Status BOP verifies 2FWE*P23A & B both running 2FWE*P22 steam supply valves all open AFW Throttle valves all full open Crew initiates Emergency Boration A TC verifies at least 1 Charging Pump is running and SI is actuated with HHSI flow indicated.

ATC verifies PRZR pressure is < 2330 psig.

BVPS - 2 Scenario 3 10 of 19

BEAVER VALLE) ,-'OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7

[ INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I*** EXPECTED STUDENT RESPONSE PZR Pressure < 2330 PSIG ATC checks PZR pres < 2330 PSrG Plant personnel alerted of ATWS Crew alerts plant personnel by sounding the standby alarm and announcing Unit 2 reactor trip without SCRAM.

ROLE PLAY: Crew notifies and dispatches a field operator to locally trip the Unit 2 reactor by opening the When a crew member directs a field reactor trip breakers or open the rod drive MG sets operator to locally trip the Unit 2 output breakers.

Reactor, insert TRG! 30, this will initiate a timed sequence for the operator to get to the rx trip breakerslMG sets and open them.

Report to the control room when Actions have been completed.

Verify turbine tripped and reheat steam isolated. BOP reports that turbine is not completely TRIPPED, previously required a MSLI.

Verifies 2MSS-MOVlOOA and B closed Depresses Reheater Controller RESET push button Check sr signal status ATC determines SI is actuated.

SRO directs a crew member to complete the steps of E-O when time and manpower permit.

BVPS - 2 Scenario 3 11 of 19

BEAVER VALLE) . ,OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 r

~----.-

INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: Check if reactor is subcritical ATC verifies; Scenario assumes the reactor has been All power range channels indicate <5%

locally tripped by this time Both IR N I channels indicate a negative SUR Safety Injection actuated - Emergency Boration is not required.

SRO returns to E-O step 1 Crew enters E-O, performs immediate Crew performs IMAs ofE-O.

operator actions.

A5-6D, -' TURBINE TRIP DUE TO REACTOR ATC verifies reactor tripped.

TRIP' - LIT Power range indication - LESS THAN 5%

Neutron flux - DROPPING Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency Buses.

ENERGIZED Check SI - ACTUATED ATC checks SI status CNMT Pressure - > 5PSIG PZR Pressure - < 1860 PSIG SG Steam Pressure - < 500 PSIG CREW DETERMINES SI REQUIRED Crew continues E-O Manually actuate SI (both trains) ATC manually actuates SI, both trains.

E-O Immediate Actions completed.

BVPS - 2 Scenario 3 12 of 19

BEAVER VALLEy ,-OWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Alert Plant Personnel A TC/BO P sound Standby Alarm, announce reactor safety Leak collection filtered exhaust fan status SAT. Crew verifies leak collection filtered exhaust fan 2HVS-FN204A or B running.

Verify SI Status A TC verifies SI System status.

2CHS*P2IA & 2CHS*P2IB running.

HHSI flow indicated on 2SIS-FI943 Both LHSI pumps rUlIDing.

Verify AFW Status BOP verifies 2FWE*P23A & B 2FWE*P22 steam supply valves AFW Throttle valves all full open And total AFW flow is > 340 gpm.

SRO directs an operator verify automatic actions by performing Attachment A-O.II when time permits.

Attachment A-O.ll included with List of Attachment A-O.ll Discrepancies:

scenario beginning on Pg 18. Operator assigned to perform Attachment A-O.II MANUAL MSLI was required on initial trip reports status of attachment to the SRO and any 2MSS-AOVI0IA failed to close on MSLI signal. actions taken when completed.

RCS temperature trending to 547°F. ATC repolts Tavg status, SRO directs crew to RCPs OPERATING - MONITOR Tavg control steam/teed flow as necessary to achieve desired status.

RCPs STOPPED - MONITOR Tcold BVPS - 2 Scenario 3 13 of 19

BEAVER VALLEy r~OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Check CIB - NOT ACTUATED ATC checks Recirc Spray Pump status, CIB NOT actuated, Recirc spray pumps not running.

Recirc Spray HXs - SERVICE WATER FLOW TO ALL 4 HXs Check Recirc Spray Pumps - ANY RUNNING Check Recirc Spray Pumps - ALL RUNNING Check Recirc Spray Pumps - NOT CAVITATING PORVs - CLOSED(not leaking). A TC verifies PZR isolated.

Spray Valves - CLOSED Safety relief valves - (PSMS Detailed Data Page 1)

-CLOSED Check PRT conditions - CONSISTENT WITH EXPECTED VALUES Power to at least one block valve - AVAILABLE Block valves - AT LEAST ONE OPEN BVPS - 2 Scenario 3 14 of 19

BEAVER VALLEy ..OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE DIP between RCS pressure and highest SG pressure ATC checks if RCPs should be stopped LESS THAN 205 PSID [220 PSID ADVERSE CNMT] ATC determines RCP DIP trip criteria NOT met.

AND RCPs remain in service.

HHSI Flow-Stop All RCPs Pressures in all SGs ANY DROPPING IN AN BOP checks if any SGs are faulted.

UNCONTROLLED MANNER OR SG COMPLETELY DEPRESSURIZED "A" SG is faulted SRO determines transition to E-2 is necessary.

Crew transitions to E-2 STEP 1 SRO directs transition to E-2 As U-I operator, when requested, Check CREVS actuated: BOP verifies CREVS actuated, requests Unit 1 report proper CREVS actuation. Control room air intake and exhaust dampers CREVS verification.

CLOSED

[2HVC*FN241A(B)] - ONE RUNNING Request U1 operator to verify CREVS actuation Commence Control Room ventilation actions lAW ATT A-2.4 BVPS - 2 Scenario 3 15 of 19

BEAVER VALLEY t""OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES I mm pLANT STATUS ORI3ESPONSE EXPECTED STUDENT RESPONSE Check All yellow SLI marks - LIT Crew verifies steam line isolation.

Check all SG pressures ANY STABLE OR BOP checks for any non-faulted SG, determines that "B" and SG's are not faulted.

Check all SGs - ANY SG PRESSURE BOP identifies SG as faulted.

DROPPING IN AN UNCONTROLLED MANOR OR ANY SG COMPLETELY DEPRESSURIZED "A" SG pressure dropping uncontrollably.

Check PREVIOUSLY Crew SG (A) isolated 2FWS*HYY-157A closed BOP verifies "A" SG CNMT isolation closed.

(rno - close 2FWS-MOY154A, 155A) 2FWS*FCY478 closed. BOP verifies "A" MFRY closed.

(rno close 2FWS-MOY154A) 2FWS*FW479 closed. BOP verifies "A" BPFRY closed.

(rno close 2FWS-MOY155A) 2FWE*HCYIOOE, F closed. BOP closes 2FWE*HCYI00E, F.

Check Residual Heat Release valve CLOSED BOP verifies 2SYS*HCYI04 closed.

IRF LOA-MSS009 (0 0) 0 Check Residual Heat Release Valve from faulted Crew dispatches an operator to close 2SYS*27.

SG PREYIOUSL Y ISOLATED:

SG 21A [2SYS*27]

BVPS - 2 Scenario 3 16 of 19

BEAVER VALLEY rOWER STATION 1/2 ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE 1 REQUESTED: Close Turbine driven AFW pump steam supply BOP closes [2MSS*SOVlOSA,D]

isolation valves from faulted SG:

IRF LOA-AFW025 (0 0) 0 [2MSS*SOVlOSA,D]

To close [2MSS*lS] (rno close [2MSS

IS]

IF REQUESTED: Close atmospheric steam dump on faulted SG BOP closes "An SG atmospheric steam dump

[2SVS*PCV] OlA] [2SVS*PCV1 01 A]

IRF LOA-MSS016 (0 0) 0 (rno close [2SVS*23]

To close [2SVS*23]

Verify SG blowdown isolation valve from faulted BOP verifies SG blowdown isolated from "A" SG.

SGCLOSED:

[2BDG* AOV] OOA 1] OR

[2BDG* AOVlOIAl]

CRITICAL TASK Close [2SSR* AOVl17A] SG blowdown sample BOP isolates SG blowdown sample from "A" SG E-2.A Crew isolates the faulted SG outside CNMT isolation valves and directs operator to close isolation (rno close[2BDG* AOV 102A] ,A2]

valve(s) operated from outside the control room before transition out of E-2.

Terminate Drill upon completion of isolation of the faulted SG per E-2 Classify Event:

SITE AREA EMERGENCY due to Tab 2.3, Failure of Rx Protection.

BVPS - 2 Scenario 3 17 of 19

BEAVER VALLEY r-OWER STATION 1/2 - ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE ] EXPECTED STUDENT RESPONSE Attachment A~O.l1 'Verification of SRO directs operator to perform Attachment A-Automatic Actions' performed as time 0.11 as time & manpower permit

& manpower penn it Diesel generators - BOTH RUNNING Check both EDGs running CNMT pressure - GREATER THAN 7 PSIG Check if MSLI is required OR (MANUAL MSLI required on initial trip)

SG Steam Pressure - LESS THAN 500 PSIG If not required, go to step 4 OR Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIT Verify steamline isolation STEP 4 Open f2CCS-AOV118] Domestic Water to Station Establish Domestic Water System Cooling to Air Compressor Station Air Compressors At least one Station Air Compressor - RUNNING Start 1 Station Air Compressor as required CCP pumps AT LEAST 1 RUNNING Check CCP Pump status

[2NME-NR45] Nuclear Recorder selected to Align neutron flux monitoring for shutdown operable source and intermediate range displays BVPS - 2 Scenario 3 18 of 19

BEAVER VALLEY t-'OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE CNMT pressure HAS REMAINED LESS THAN Check CIB status 11 PSIG IF NOT Actuate CIB if required Manually initiate CIB BOTH SWITCHES FOR BOTH TRAINS Manually align equipment as required RCPs - STOPPED Stop ALL RCPs BV-1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps - 2 RUNNING Verify Service Water System in service Service Water Header Pressure - GREATER THAN 55 PSIG SWS Seal Water Pressure - NOT LOW

[2HCS*SOVI00Al, Bl] CNMT Sample amber Verify both CNMT hydrogen analyzers running LIT All Red SIS Marks - LIT Verify ESF Equipment status Start/align All Orange CIA Marks LIT equipment as required All Green FWI Marks LIT Power available to both Emergency AC Busses Verify power to both AC Emergency busses Restore power as required Attachment A-O.l1 - COMPLETE Report any discrepancies to SMfUS BVPS - 2 Scenario 3 19 of 19

Appendix D Scenario Outline Form ES-D-1 Facility: FENOC BVPS Unit 2 Scenario No.: 1: Op Test No.: 2LOT] NRC Examiners: Candidates: SRO

ATC

BOP

----~~ .. - ---~-------.- ..

Initial IC 214: Reactor power -E-6 amps, BOL, Equ. Xe Conditions, CB "D" @ 101 steps, RCS Conditions: boron - 1851 ppm, Condensate Polishing Air Compressor - ~OS.

Turnover: Raise power to above the POAH (3-5%)

Critical Tasks: E-1.C, Trip RCPs E-O.I, Manually Start HHSI Pump ECA-1.1.B, Makeup to RWST Event Malf. No. Event Type Event Description No.

R(ATC) Raise Reactor power to 3-5%

Ir-_-+__________~N(BOP-/S-R-O~)~~------------------------~---------~I 2 2RSS-P21D, Recirculation Spray Pump Seal failure

, BST-CSS035 C(A TC/SRO) 2RSS-P21D seal tank level low

,IBST-CSS036 SRO TS 2RSS-P21D seal tank level 10 10 Ir----+- --~-+----------~-------------------~-------~-~-------~

3 FLX-CSS05 C(BOP/SRO) 500 gpm suction leak to the "A" Quench Spray Pump. I SROTS 4 PMP-CAS003 C(BO)/SRO) Statio compressor Trip/auto start failure of standby

I---=**-*---------1----__~**_____- - _ r - - - - * - - * * - - - - - : - c * - -_____- * * - * * - _ : _ - - * - , - - - - 1 1

5 FLX-CAS 10 C(ALL) Air Header leak requires manual reactor trip I 6. RCS02C M(ALL) 5000 gpm SBLOCA on Loop C upon reactor trip h-*4--BK-R--H*~I-V-0-8--+--C-(-B-O-P-I-SR--O-)--+-In-a-d-v-ert-e-n-t-tr-ip-o*f 2DF feeder brk on Rx trip.

1 I I?SGOIB I' 2-2 EDG Auto start failure with sub~y'uent trip

,I 8: P~P--L-07-A----j-C-(ATC/SRO) Standby HHSI pump fails to auto start (manual start required).

! 9 i LOA-LOV072 II C(ALL) i Loss of2MCC-Ell, (Both Trains of Transfer to Cold Leg I. I . I Recirculation are unavailable - ECA-l.l entry required) Ii (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG*l021, Revision 9 Supplement 1 FENOC Facsimile Rev 1

Appendix D Scenario Outline Form ES-D-1

-rhe Crew will continue the reactor startup, raising reactor power to above the POAH, ~3%. The ATC operator will withdraw control rods and observe startup rate while the BOP controls RCS temperature by manually adjusting 2SVS-HCV 104. The BOP also controls SG level by manual(V controlling the bypass feed reg valves.

After the Crew has raised power to above the POAH, Al -3H will annunciate due to a low level in the seal tank for 2RSS*P21D. AI-3H will reflash in 5 minutes due to the seal tank for 2RSS-P21D level being LO-LO which indicates a seal failure for 2RSS*P21 D. lAW the ARP for Al-3H, the crew will dispatch an operator to fill the seal lAW 20M-13.4.F. The SRO will evaluate TS 3.5.2 & 3.6.7 A 500 gpm isolable leak develops on the suction line to 2QSS*P21A in South Safeguards. The South Safeguards sump Hi level annunciator will alarm followed by annunciator A6-1 D due to a low level in the RWST, the crew \-vill monitor RWST level and initiate actions to locate the leak and makeup to the RWST. The SRO will evaluate TS 3.5.4 (RWST level) and TS 3.6.6 for 2QSS*P2IA when leak is located)

The running station air compressor will trip requiring manual start of the standby station air compressor.

A slowly developing Instrument Air leak will occur. The air leak will continue to worsen, requiring the crew to determine that a reactor trip is appropriate lAW AOP 2.34.1.

Upon the reactor trip the crew will enter E-O, a 5000 gpm SBLOCA will occur on Loop C. When the reactor trips, one of the 4kv tie breakers, between the "D" and "DF" buses will trip open, 2D 10. The automatic start of the 2-2 EDG will fail and requires the BOP to manually start the 2-2 EDG, it will trip 90 seconds after starting.

"ince the "B" CHS/HHSI pump was in service it will no longer be running, the "A" CHS/HHSI pump will iequire the ATC to manually start it due to an automatic start failure. The crew will Transition to E-l based upon containment conditions when checking if the RCS is intact. 5 minutes after the reactor trip, the feeder breaker to 2MCC -Ell will trip When the crew performs EOP attachment A-0.6 to verify Cold Leg Recirculation capability, it will be determined that at least one train of recirculation capability cannot be verified requiring the SRO to transition to ECA-l.l. The crew will remain in ECA-l.l; after the crew has initiated actions to add makeup water to the RWST (step 9) the drill will be terminated.

Expected procedure flow path is E-O ~ E-l ~ ECA-l.l.

NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev 1

BEAVER VALLEY ruWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INITIAL CONDITIONS: 0% Power (~E-6 amps), CBD = 101, EQU XE BOL, 1851 PPM Boron, IC-214 ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2SAS-C22 in PTL YCTon CS None EOUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 2SAS-C22 OOS 2 days ago None SHIFT TURNOVER INFORMATION

1. 0 % Power (~E-6 amps), CBD = 101, CBC = 229, EQU XE BOL, 1851 PPM Boron

2. Protected Train is Train "B"

3. Raise power to above the POAH (3-5%) lAW 20M-50.4.D, Reactor Startup from Mode 3 to Mode 2, Part C Temperature control is via 2SVS-HCV1 04, with bypass feed reg valves in manual.

4. 2SAS-C22, Condensate Polishing Air Compressor OOS for overhaul.

SCENARIO SUPPORT MATERIAL REOUIRED

1. Plant Startup reactivity plan, Critical with Bank D at 101steps.

2. Placard for 2FWE*P22 position stating 2FWE*P22 is aligned to "A" header

3. Place plaque on wall for Protected Train "B"

4. Plant startup procedure - 20M-50.4.D completed up through Part B.

BVPS - 2 Scenario 4 1 of 24

BEAVER VALLEY ruWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 I INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE]

Initialize IC Set 214, and establish Reactor plant at 0% power (~E-6 amps), BOL, initial plant conditions. equilibrium conditions. RCS boron 1851 PPM, CBD 101 steps.

Insert the following per the Simulator Inserts all pre-loads required to support the drill Setup section of the HTML File for TRGSET 1 '.JPPLP4(1)' Set Trigger 1 on Reactor Trip IMF PPL07A (0 0) 0 Auto Start Failure of2CHS*P21A IMF BKR-HIVOS (I 0) 0 ACB-2DI0 trips on reactor IRF LOA-LOV072 (3300) 0 Trip of ACB 2N-6C, MCC*2-Ell Feeder bkr IMF AS-6F-Y3510D (3 300) 0 A8-6F alarm for trip ofMCC*2-Ell Feeder bkr IMFDSGOIE Auto start inhibit, EDG 2-2 TRGSET 3 'ODSG02RM > 20' Set trigger 3 on EDG 2-2 start IMF DSGOIB (3 90) TRUE EDG 2-2 trip 90 seconds after manual start IMF RCS02C (I 0) 5000 5000 gpm SBLOCA, Loop upon reactor trip IMF BST-CAS013 (0 0) 1 2IAS-PS 106B, station air compressor autostart inhibit IMF BST -CASO 10 (O 0) 1 2IAS-PS 108, stby diesel air compressor autostart inhibit IMF BST-CAS035 (2 0) 0 2RSS-LS156D, RSS*P21D Seal Tk lvl BELOW L0706D IMF BST-CAS036 (2 300) 0 2RSS-LSI56Dl RSS*P21D Seal Tk lvl LOLO L0707D BVPS - 2 Scenario 4 2 of 24

BEAVER VALLEy "OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE ~

Assign shift positions ATe:

BOP:_____________

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

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

place the simulator to RUN and commence the drill.

BVPS - 2 Scenario 4 3 of 24

BEAVER VALLE'r ..OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 c=JNSTRUCTIONAL GUIDELINES 1_.. PLANT STATUS OR RESPONSE In EXPECTED STUDENT RESPONSE EVENT 1:

Raise Reactor Power to 3-5% ATC withdraws Control rods to raise reactor power As control rods are withdrawn, reactor power rises being observant 0[0.1 dpm procedural SUR limit.

and then RCS temperature rises as power increases.

BOP manually controls RCS temperature using 2SVS-HCVI04.

BOP controls SG levels using manual control of the Bypass Feed reg valves.

Proceed with next event at LE discretion EVENT 2:

2RSS*P21D Seal Trouble I Failure IMMEDIATE PLANT RESPONSE:

AI-3H, - 'RECIRC SPRA Y SYSTEM TROUBLE' ATC responds with ARP which directs that Seal IMF BST-CAS035 (2 0) 0 - LIT, L0706D, BELOW System be filled lAW 20M-13.4.F.

IMF BST-CAS036 (2 300) 0 (pre-loaded) SRO dispatches an operator to fiIl2RSS*P2ID seal lAW 20M-13.4.F, part D.

Initiate by actuating TRG! 2 5 MINUTES LATER:

REFLASH of: ATC reports that lAW ARP, Seal is to be filled.

Al-3H, - 'RECIRC SPRAY SYSTEM TROUBLE' (Fill procedure should be already working by now)

- LIT. L0707D. LOLO BVPS 2 Scenario 4 4of24

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I** EXPECTED STUDENT RESPONSE~

ROLE PLAY:

5 minutes after being dispatched as SRO to review TS; field operator to fill the seal for TS 3.6.7, RSS Sys, Condition C, Restore in 72 hrs.

2RSS*P21D lAW 20M-13.4.F, Part D. TS 3.5.2, BCCS, Condition A, Restore in 72 hrs.

Call in to the Control Room SRO and TS 3.6.1, CNMT, Condition A, Restore in 1 hr.

report that "you have completed steps 1 through 5 of20M-13.4.F, Part 0, you ATC places the CS for 2RSS*P21D in PTL and can continue with step 6." closes 2RSS*MOV155D and 2RSS*MOV156D.

Field operator is notified to continue with Step 6.f.

Continue with next event at LE discretion BVPS - 2 Scenario 4 5 of 24

BEAVER VALLEY t"'OWER STATION 1/2 ADM-1357 Conduct of Simulator Training Revision 7 r INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE EVENT 3:

IMMEDIATE PLANT RESPONSE: BOP responds with ARP which directs that 500 gpm leak on suction line to All-lOG, - 'SAFEGUARDS AREA SUMP someone be dispatched to investigate leakage into 2QSS*P21A. LEVEL HIGH' - LIT, (L2963D), SOUTH South Safeguards.

IMF FLX-CSS05 (0 0) 500 SRO dispatches field operator to investigate South Safeguards to identify leakage.

ROLE PLAY:

As field operator report in that there is a SRO reviews system YOND and determines that leak on the suction piping for leak can be isolated by closing 2QSS*2 and 2QSS*P21A upstream of 2QSS*MOVIOOA.

2QSS*MOVIOOA.

Crew isolates 2QSS*P2IA by placing CS for 2QSS*P21A in PTL & closing 2QSS*MOVIOOA.

SRO directs field operator to close 2QSS*2.

SRO reviews TS 3.6.6 for 1 Train of Quench Spray, ROLE PLAY: Condition A, Restore in 72 hrs.

Insert command 'DMF FLX-CSS05' then as field operator report to SRO that you have closed 2QSS-2.

A6-ID, - 'REFUELING WATER STORAGE BOP reviews ARP; TANK LEVEL OFF NORMAL' LIT, (L2966D) Verifies actual low level in the R WST.

Determines makeup to RWST is necessary.

Dispatches operator to initiate R WST makeup lAW 20M-7.4.0.

SRO reviews TS 3.5.4 for RWST volume.

Condition B, restore level within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

BVPS - 2 Scenario 4 6of24

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I n_n EXPECTED STUDENT RESPONSE J Continue with next event at LE discretion EVENT 4:

Trip of2SAS-C21A IMMEDIATE PLANT RESPONSE:

A6-3D, - 'STATION AND CONDENSATE BOP determines 2SAS-C21A has tripped and IMF PMP-CAS003 (0 0) 1 POLISHING AIR SYSTEM TROUBLE' 2SAS-C21 B has failed to start, reports to (Y6464D) SROICrew.

SRO directs the BOP to start 2SAS-C21B.

BOP starts 2SAS-C21B.

SRO notifies maintenance of trip of2SAS-C21A.

Continue next event at LE discretion BVPS - 2 Scenario 4 7 of 24

BEAVER VALLEY ["'OWER STATION 1/2 -ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I .. EXPECTED STUDENT RESPONSE EVENT 5:

IMMEDIATE PLANT RESPONSE:

Instrument Air Header Leak Numerous air system alarms annunciate A6-3D, - 'STATION AND CONDENSATE BOP reports Air System alarms to the Crew/SRO.

IMF FLX-CASIO (0 0) 1200500 POLISHING AIR SYSTEM TROUBLE' - LIT (P08II D)

A6-3C, - 'STATION INSTRUMENT AIR RECEIVER TROUBLE' LIT (P0810D) SRO determines AOP 2.34.1, "Loss of Station A6-3C, - 'STATION INSTRUMENT AIR Instrument Air" is applicable, enters and directs RECEIVER TROUBLE' - LIT (P08I2D) actions of AOP.

A6-3C, - 'STATION INSTRUMENT AIR RECEIVER TROUBLE' LIT (P0815D)

A6-3D, - 'STATION AND CONDENSATE POLISHING AIR SYSTEM TROUBLE' - LIT (P0814D)

ATC sounds the Standby Alarm and announces "Loss of Station Instrument Air",

BVPS - 2 Scenario 4 8 of 24

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE NOTE: BOP verifies all available Station Air compressors 2SAS-C21 A previously tripped. are running.

2SAS-C21B running 2IAS-C21 Did not auto start Verifies 2SAS-C21 B is running.

2SAS-C22 OOS on turnover.

BOP dispatches turbine operator to locally start the ROLE PLAY: Diesel Air compressor, (2IAS-C21).

As turbine operator dispatched to start 2 IAS-C21, report back in 3 minutes that it appears as though the battery is dead, the Diesel Air compressor will not start.

ROLEPLAY: SRO dispatches operator to place the Instrument As operator dispatched to Bypass the Air Dryer Bypass tilters in service and to isolate the Instrument air dryers, report back in 3 Instrument Air Dryers.

minutes that the Bypass filters are inservice and the Dryers are isolated.

Additionally, report that there is an instrument air leak downstream of 2IAS-I026, right at the header.

NOTE: Station instrument air pressure continues to drop. BOP checks for Reactor trip criteria, checks Continuous Action Step, requires Instrument air header pressure not < 55 psig, tripping the Reactor if pressure is <55 however there is a decreasing pressure trend.

pSlg.

BVPS - 2 Scenario 4 90f24

BEAVER VALLEY rOWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 c=JNSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE ,- EXPECTED STUDENT RESPONSE ._J BOP checks Instrument Air header pressure is <86 psig.

BOP verifies 2SAS-AOVI 05 is closed.

SRO continues attempts to restore station instrument air.

Station instrument air pressure drops to < 55 psig BOP reports to crew that Instrument Air pressure is

< psig SRO directs the crew to Manually trip the reactor, perform Immediate Operator Action steps and report when ready to read.

BVPS - 2 Scenario 4 10 of 24

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 c-JNSTRUCTIONAL GUIDELINES PLANT STAlljS OR RE§PONSE I. EXPECTED STUDENT RESPONSE EVENTS 6,7,8,9:

5000 gpm Loop C SBLOCA with inadvertent trip of 2D 1a breaker, Auto start failure of2-2 EDG with trip 90 seconds after loading, Loss of 2MCC E11 5 minutes later.

TRGSET 1 'JPPLP4(1)'

IMF PPL07A (0 0) 0 IMF BKR-HIV08 (1 0) 0 IRF LOA-LOV072 (3300) 0 IMF A8-6F-Y3510D (3 300) 0 IMF DSGOIE TRGSET 3 'ODSG02RM > 20' IMF DSGOIB (3 90) TRUE IMF RCS02C (1 0) 5000 preloaded)

Crew enters E-O, performs immediate Crew performs IMAs of E-O.

operator actions.

A5-6D, - 'TURBINE TRIP DUE TO REACTOR ATC verifies reactor trip.

TRIP' - LIT.

Power range indication - LESS THAN 5%

Neutron flux dropping.

BVPS - 2 Scenario 4 11 of 24

BEAVER VALLEY ,OWER STATION 1/2 -ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE L__... EXPECTED STUDENT RESPONSE Throttle Valves - ALL CLOSED BOP verifies turbine tripped.

OR Governor Valves - ALL CLOSED Main Generator Output Bkrs - OPEN Exciter Circuit Bkr - OPEN AC Emergency Busses - AT LEAST ONE BOP verifies power to AC Emergency Buses.

ENERGIZED Check SI ACTUATED ATC checks SI status.

CNMT Pressure - > 5PSIG PZR Pressure - < 1860 PSlG SG Steam Pressure - < 500 PSIG CREW DETERMINES SI REQUIRED Crew continues E-O Manually actuate SI (both trains) A TC manually actuates SI, both trains.

E-O Immediate Actions completed.

Alert Plant Personnel ATC/BOP sound Standby Alarm, announce reactor trip and safety injection.

Leak collection filtered exhaust fan status SAT. Crew verifies leak collection filtered exhaust fan 2HVS-FN204A or B running.

CRITICAL TASK Charging Pumps TWO RUNNING ATC verifies SI System status E-O.I - Crew establishes flow from at ATC identifies that 2CHS*P21A did not Auto least one high head ECCS pump HHSI Flow INDICATED start on SI signal, and manually starts before transition out of E-O. LHSl Pumps TWO RUNNING 2CHS*P21A. Reports malfunction to the crew.

Both LHSI pumps running.

BVPS - 2 Scenario 4 12 of 24

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 L INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Verify AFW Status BOP verifies 2FWE*P23A & B both running 2FWE*P22 steam supply valves all open AFW Throttle valves all full open And total AFW flow is > 340 gpm.

SRO directs an operator to verify automatic actions by performing Attachment A-O.II when time permits.

Attachment A-O.l1 included with List of Attachment A-O.ll Discrepancies:

scenario beginning on Pg 22. Operator assigned to perform Attachment A-O.II 2CHS*P21A failed to auto start, manually reports status of attachment to the SRO and any started - SAT. actions taken when completed.

2-2 EDG failed to auto start, manually started and then subsequently tripped after loading, resulting in ALL "B" Train equipment being de energized.

RCS temperature trending to 547°F. ATC reports Tavg status, SRO directs crew to RCPs OPERATING - MONITOR Tavg control steam/feed flow as necessary to achieve desired status.

RCPs STOPPED MONITOR Tcold Check CIB NOT ACTUATED A TC checks Recirc Spray Pump status, CIB NOT actuated, Recirc spray pumps not running.

Recire Spray HXs - SERVICE WATER FLOW TOALL4HXs Check Recirc Spray Pumps ANY RUNNING Check Recirc Spray Pumps - ALL RUNNING Check Recirc Spray Pumps NOT CAVIT ATING BVPS - 2 Scenario 4 13 of 24

BEAVER VALLEY rOWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 L INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE PORVs - CLOSED(not leaking). A TC verifies PRZR isolated Spray Valves - CLOSED Safety relief val ves (PSMS Detailed Data Page 1)

-CLOSED Check PRT conditions CONSISTENT WITH EXPECTED VALUES Power to at least one block valve - AVAILABLE Block valves -- AT LEAST ONE OPEN DIP between RCS pressure and highest SG pressure ATC checks ifRCPs should be stopped

- LESS THAN 205 PSID [220 PSID ADVERSE CRITICAL TASK CNMT] ATC determines RCP DIP trip criteria met.

E-1.C - Crew trips all RCPs when A TC verifies HHSI flow.

ReS to highest SG DIP criteria is AND exceeded and SI flow verified prior to HHSI Flow- INDICATED ATC STOPS all RCPs.

exiting procedure E-l.

Stop All RCPs Pressures in all SGs - ANY DROPPING IN AN BOP determines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED BVPS - 2 Scenario 4 14 of 24

BEAVER VALLEY !-lOWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 LINSTRUCTIONAL GUIDELINES PLANT STATUS OR -RESPO-NSE----. EXPECTED STUDENT RESPONSE Check all SG levels - NONE RISING IN AN BOP determines all SG tubes are intact.

UNCONTROLLED MANNER Check Secondary Radiation CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQI00J Air Ejector Discharge (J 007)

[2SSR-RQI00J SG Blowdown Sample (1062)

[2MSS*RQl 0IA,B,C] Main Steamline Discharge (1005, 3005, 5005)

Check the following consistent with pre-event Crew checks if RCS is intact.

values:

CNMT Pressure CREW DETERMINES THAT RCS IS NOT CNMT Sump Level INTACT, TRANSITIONS TO E-1 STEP 1.

CNMT Radiation Crew transitions to E-l STEP 1 SRO directs transition to E-l SRO directs STA to monitor status trees.

Crew checks if CREVS should be actuated Crew checks if CREVS should be actuated Control Room radiation monitor [2RMC*RQ201, 202] (1069,1072) NOT IN HIGH ALARM CIB HAS NOT OCCURRED BVPS - 2 Scenario 4 15 of 24

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE DIP between RCS pressure and highest SG pressure ATC checks ifRCPs should be stopped.

- LESS THAN 205 PSID [220 PSID ADVERSE CNMT] All RCPs previously stopped.

AND HHSI Flow INDICATED Reps - STOPPED CIB ACTUATED ATC checks Recirc Spray Pump status Recirc Spray Hxs SERVICE WATER FLOW TO ATC verifies 2SWS*MOV103A(B) OPEN and ALL 4 HXS 2SWS*MOV106A(B) CLOSED RWST Level- ~ 381 inches ATC checks RWST level> 381 inches Verify Recirc Spray Pumps - NOT CAVlT ATING Pressures in all SGs ANY DROPPING IN AN BOP determines no SGs are faulted.

UNCONTROLLED MANNER OR ANY SG COMPLETELY DEPRESSURIZED SGs are NOT faulted Narrow Range Levels GREATER THAN 12% BOP checks intact SG levels

[31 % ADVERSE CNMT]

BOP controls feed flow to intact SGs to maintain NR level between 12% [31 % ADVERSE CNMTl and 50%

BVPS - 2 Scenario 4 16 of 24

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR-RE-SPO=-=N"'":-:S:-:-E---' EXPECTED STUDENT RESPONSE Check all SG levels NONE RISING IN AN Crew determines all SG tubes are intact UNCONTROLLED MANNER Check Secondary Radiation CONSISTENT WITH PRE-EVENT VALUES

[2ARC-RQ 100] (1007) Air ejector discharge

[2SSR-RQ 100] (1062) SGBD sample

[2MSS*RQ101A,B,C] Main Steamline discharge (1005,3005,5005)

Power to the Block Vlvs - AV AIT~ABLE ATC checks PRZR PORVs and Block Valves:

PORVs CLOSED All PORVS CLOSED.

Block Vlvs - AT LEAST ONE OPEN All Block valves open and energized.

RCS Subcooling based on core exit TCs > 41 F ATC/BOP check if SI flow can be reduced r59F ADVERSE CNMT]

Secondary heat sink: Crew determines RCS subcooling is required Total feed flow to intact SGs GREATER THAN from Attachment A-5. L 340GPM OR SI FLOW CANNOT BE REDUCED Narrow range level in at least one intact SG GREATER THAN 12% [31-% ADVERSE CNMT]

RCS pressure - STABLE OR RISING PRZR level- GREATER THAN 17% [38% SI TERMINATION CONDITIONS ARE NOT ADVERSE CNMT] SATISIFIED, SRO CONTINUES IN E-l.

BVPS - 2 Scenario 4 17 of 24

BEAVER VALLEY /-,OWER STATION 1/2 - ADM 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE ~-.----

EXPECTED STUDENT RESPONSE Any Quench spray or recirc spray pump ATC/BOP check if CNMT Spray should be RUNNING stopped.

SRO continues with STEP 10.

SI & CIA - RESET ATC resets SI and CIA RCS Pressure - > 225 PSIG [250 PSIG ADVERSE ATC checks ifLHSI Pumps should be stopped CNMT]

RCS Pressure ST ABLE OR RISING ATC determines RCS pressure is NOT stable or rising.

LHSI Pumps stopped and in auto ATC determines RCS pressure < 225 psig, LHSI pumps to remain running.

ATC/BOP checks RCS and SG Pressures.

Check pressures in all SGs ST ABLE OR RISING BOP determines SG pressures are stable or rising.

Check RCS Pressure STABLE OR DROPPING ATC determines RCS pressure is dropping.

Verify AC emergency busses energized from BOP checks ifEDGs should be stopped.

offsite Stop any unloaded EDG by performing 20M Crew initiates actions to STOP EDGs.

36.4.AF(AG)

BVPS - 2 Scenario 4 18 of 24

BEAVER VALLEY I-'OWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7

[ .. INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Verify Cold Leg Recirculation Capability. SRO directs operators to perform Att A-O.6 and verify cold leg recirculation capability Due to loss of 2DF 4KV bus along with loss of 2MCC-Ell, the BOP determines that at least one train of cold leg recirc capability can not be verified and reports to SRO that RECIRC CAPABILITY NOT AVAILABLE.

SRO determines entry into ECA-1.1 required.

Crew transitions to ECA-l.l STEP 1 SRO directs transition to ECA-l.1 Recirc Spray Pumps - NO SIGN OF A TC determines no Recirc Spray pumps are CAVITATION. runnmg.

ATC determines Transfer-to-Recirculation was not initiated.

Reset SI signal. ATC RESETS SJ, both trains.

Reset SI Recirc Mode. ATC RESETS SI RECIRC MODE, both trains.

Check Charging Pump Flow ATC verifies HIlSl flow on 2SIS-FI943.

BVPS - 2 Scenario 4 19 of 24

BEAVER VALLEY pOWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES L pLANfSfAfU§ OR RESPONSE n~ EXPECTED STUDENT RESPONSE Check Emergency Coolant Recirculation BOP performs Attachment A-O.8.

Equipment - AVAILABLE Along with unavailability of power to MCC-Ell and 2DF 4KV busses, the BOP determines RWST level is NOT less than 369 inches, therefore, Cold leg recirc alignment is not required at this time.

Crew continues attempts to restore at least one train.

Cheek RWST level GREATER THAN 30 ATC verifies RWST level is > 30 inches.

INCHES Determine Quench Spray Requirements. ATC determines that CIB is ACTUATED, however NO Quench Spray pumps are running, Quench Spray reduction is not necessary.

Check Recirc Spray System Status. ATC determines that CIB is ACTUATED, Verifies SWS flow established to "A" train RSS Heat Exchangers.

ATC verifies RWST level is not less than 381 inches, Transfer to Recirc not required at this time.

CRITICAL TASK Add Makeup to RWST as Necessary Crew initiates makeup from the Fuel pool to the ECA-1.1.B - Crew makes up to the RWST lAW 20M-7.4.0, "Makeup To The RWST and minimizes RWST Refueling Water Storage Tank".

outflow.

Terminate drill when crew initiates actions to Makeup to the R WST from the Blender in ECA-I.I.

BVPS - 2 Scenario 4 20 of 24

BEAVER VALLEY POWER STATION 1/2 -ADM -1357 Conduct of Simulator Training Revision 7 I-INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE EXPECTED STUDENT RESPONSE Classify Event SRO evaluates EPP and declares a SITE AREA EMERGENCY due to TAB 1.2.3, Loss of RCS Barrier and Tab 1.3.2, Potential Loss of Containment Barrier due to not having 1 complete Train of Containment Depressurization available BVPS - 2 Scenario 4 21 of 24

BEAVER VALLEY I-'OWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I. EXPECTED STUDENT RESPONSE Attachment A-O.ll 'Verification of US directs operator to perform Attachment A-O.lI Automatic Actions' performed as time as time & manpowcr permit

& manpower permit Diesel generators - BOTH RUNNING Check both EDGs running, BOP notes the 2-2 EDG did not auto start, BOP manually starts 2-2 EDG. EDG starts, loads and then trips 90 seconds later resulting in loss of power to the 2DF 4KV bus.

CNMT prcssure GREATER THAN 7 PSIG Check if MSLI is required OR SG Steam Pressure - LESS THAN 500 PSIG If not required, go to step 4 OR Steamline pressure high rate of change 100 PSIG DROP IN 50 SECONDS Yellow SLI marks - LIT Verify stcamline isolation STEP 4 Open [2CCS-AOVl18] Domestic Water to Station Establish Domestic Water System Cooling to Air Comprcssor Station Air Comprcssors At least one Station Air Comprcssor RUNNING Start 1 Station Air Comprcssor as required CCP pumps A T LEAST 1 RUNNING Check CCP Pump status BVPS - 2 Scenario 4 22 of 24

BEAVER VALLEY POWER STATION 1/2 - ADM - 1357 Conduct of Simulator Training Revision 7 I_~INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE r-~* EXPECTED STUDENT RESPONSE 2NME-NR45 Nuclear Recorder selected to Align neutron flux monitoring for shutdown operable source and intermediate range displays CNMT pressure HAS REMAINED LESS THAN Check CIB status 11 PSIG IF NOT Actuate CIB if required Manually initiate CIB - BOTH SWfTCHES FOR BOTH TRAINS Manually align equipment as required All Reps - STOPPED Stop AU RCPs J

BV-1 operator verifies CREVS actuation Service water established to RSS HX(s)

Service Water Pumps - 2 RUNNING Verify Service Water System in service Service Water Header Pressure - GREATER THAN 55 PSIG SWS Seal Water Pressure - NOT LOW

[2HCS*SOV100A1, B1] - CNMT Sample amber Verify both CNMT hydrogen analyzers running light LIT NOTE: All Red SIS Marks - LIT Verify ESF Equipment status - Start/align Due to 2DF 4KV bus being de All Orange CIA Marks LIT equipment as required energized, ALL train "B" All Green FWI Marks - LIT components will be de-energized with 2CHS*P21A did not auto start, BOP manually positions unable to be verified. starts 2CHS*P21A satisfactorily.

BVPS - 2 Scenario 4 23 of 24

BEAVER VALLEY POWER STATION 1/2 -ADM - 1357 Conduct of Simulator Training Revision 7 CINSTRUCTIONAL GUI DELINES L_. PLANT STATUS OR RESPONSE .-. EXPECTED STU[)E:;t'HBESPQjl.JSE_ _,

Power available to both Emergency AC Busses Verify power to both AC Emergency busses Restore power as required 2DF 4KV Bus de-energized Attachment A-O.ll COMPLETE Report any discrepancies to SM/US BVPS - 2 Scenario 4 24 of 24

v t e Letter Sequence Draft Other
TAC:U01821, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML102510196, ML102510217, ML102510235, ML102510316, ML102650433, ML102650445, ML102650459, ML111680049
MONTHYEAR2010-07-03 [Table View]

ML102520199

Text

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

4.2. COMMENTS

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

Conclusion:

Conclusion:

Conclusion:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

REFERENCE:

REFERENCES:

Navigation menu

Search