Text

Draft - Section B Operating
	ML030220459
Person / Time
Site:	Beaver Valley
Issue date:	12/16/2002
From:	Hynes C; FirstEnergy Nuclear Operating Co
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-412/03-302 50-412/03-302
	Download: ML030220459 (120)
	v • d • e

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 F Facility:

FENOC BVPS Unit 2 Date of Examination:

12/2002 Exam Level:

RO I SRO (I)

Operating Test No.:

2002-01 B.1: Control Room Systems System JPM Description Type Safety Code*

Function

$1 001 Realign a Mispositioned Control Rod D, S 1

Rod Control S2 013 Respond to a Shutdown LOCA M, A, S, L 2

ESF Actuation S3 068 Respond to Radiation Monitor Alarm - Leak D, A, S 9

Liquid Radwaste Collection Tank (Repeat)

S4 002 Initiate a Natural Circulation Cooldown - ES-0.2 D, A, S, E 4

RCS (Repeat)

S5 026 Manual Initiation of Quench Spray D, A, S, E 5

Containment Spray S6 064 Shutdown No. 1 Diesel Generator N, S 6

EDG S7 015 Respond To Failed Power Range Channel N-44 D, S 7

NI (Repeat)

B.2 Facility Walk-Through P1 033 Respond to a SFP Low Level Alarm N, R 8

SFP Cooling P2 061 Reset the Terry Turbine Trip Throttle Valve D, E 4

AFW P3 012 Place SSPS Train in Service D, L 7

I RPS Type Codes:

(D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, RCA, (E)OPIAB NOTES BVPS2 - NRC RO/SROI JPM Outline.doc

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 Facility:

FENOC BVPS Unit 2 Date of Examination:

12/2002 Exam Level:

SRO (U)

Operating Test No.:

2002-01 B1.: Control Room Systems System JPM Description Type Safety Code*

Function S2 013 Respond to a Shutdown LOCA M, A, S, L 2

ESF Actuation S5 026 Manual Initiation of Quench Spray D, A,S, E 5

Containment Spray S7 015 Respond To Failed Power Range Channel N-44 D, S 7

NI (Repeat)

B.2 Facility Walk-Through P1 033 Respond to a SFP Low Level Alarm N, R 8

SFP Cooling P2 061 Reset the Terry Turbine Trip Throttle Valve D, E 4

AFW NOTES BVPS2 - NRC SROU JPM Outline.doc Type Codes:

(D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, RCA, (E)OP/AB

Appendix C Job Performance Measure Form ES-C-1 Worksheet BVPS Unit 2 Respond to RCCA Misalimnment Task No.:

0011-019-01-013 JPM No.:

2002 NRCS1 K/A

Reference:

001A2.03 (3.5/4.2)

NRC Examiner:

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom Simulator Actual Performance:

X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

"* The plant is in Mode 1, 48% power.

"* An incore flux map has determined that Control Bank "D" rod B-8 is at 155 steps. Bank "D" is at 170 steps.

"* Control rods are in manual.

"* Tavg and Tref are matched.

"* The reason for the misalignment has been determined and corrected.

"* The General Manager Nuclear Operations and Reactor Engineering personnel have been notified.

"* Permission is granted to realign the rod.

The rod realignment is complete with all Bank "D" rods at 170 steps and proper rod movement is verified.

None 20M-1.4.P, RCCA Or RCCA Group Misalignment, Rev. 4 20M-1.4.P, Rev. 4 The Unit Supervisor directs you to realign control rod B-8 to 170 steps in accordance with 20M-1.4.P,Section IV.D.Section IV.A has been completed.

No 15 minutes NUREG 1021, Revision 8, Supplement 1 Facility:

Task

Title:

Date:

X BVPS-2 NRC JPM #S1

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC SI1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Place the Rod Control Selector Switch to the 'Bank D' position.

Locates the Rod Control Bank Selector switch and rotates to the

'Bank D' position.

Comment:

Performance Step: 2 Standard:

Place the lift coil disconnect switches for all control bank "D" rods with EXCEPTION of rod B-8 to 'Rod Disconnect' position.

Locates lift coil disconnect switches for bank "D" rods EXCEPT rod B-8 and places them in the 'Rod Disconnect' position.

Comment:

Performance Step: 3 Standard:

Record Bank "D" group position and rod B-8 position.

Records 170 steps for Bank "D" and 155 steps for rod B-8.

Comment:

Performance Step: 4 Standard:

Set the Control Bank "D" step counters to the position of rod B-8.

Sets step counters at 155 steps.

Comment:

Performance Step: 5 Standard:

Comment:

Consult General Manager Nuclear Operations and Reactor Engineer to determine rate of control rod movement.

Candidate simulates contacting the GMNO and Reactor Engineer to determine the rate of allowable control rod movement.

Cue: Inform candidate to move control rods at 5 step increments or less.

NUREG 1021, Revision 8, Supplement 1 BVPS-2 NRC JPMV #S1

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S1 Performance Step: 6 Standard:

Standard:

Comment:

Performance Step: 7 Standard:

Comment:

Performance Step: 8 Standard:

Standard:

Withdraw rod B-8 to bank demand position in 5 step increments or less.

Locates the rod motion lever and moves it to the 'OUT' position.

Verifies rod motion occurs in 5 step increments or less.

URGENT FAILURE alarm will occur when demand signal is present for the group with all rods disconnected. This is an expected alarm.

Maintain Tavg-Tref as necessary during rod movement.

Maintains Tavg-Tref.

CUE: Inform Candidate that any turbine load adjustments will be handled by the Examiner.

Verify outward motion of rod B-8.

Locates rod direction lamp and verifies that 'UP' arrow is illuminated.

Locates individual DRPIs for Bank "D" and verifies outward motion of rod B-8.

Comment:

Performance Step: 9 Standard:

Standard:

Comment:

Performance Step: 10 Standard:

Standard:

Comment:

Withdraw rod B-8 in 5 step increments or less until it matches Bank D rods recorded demand position.

Stops outward motion when rod B-8 indicates to be at the same position as Bank D demand as verified by reading step counters.

Verifies DRPI indication is the same for all Bank "D" rods.

Clear the URGENT FAILURE alarm on the Power Cabinet by depressing the Rod Control Alarm Reset pushbutton.

Locates Rod Control Alarm Reset pushbutton and depresses it.

Verifies [A4-8A], Urgent Failure Alarm clears.

NUREG 1021, Revision 8, Supplement 1 BVPS-2 NRC JPM #S1

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S1 Performance Step: 11 Standard:

Comment:

Performance Step: 12 Standard:

Reset the P/A Converter.

Dispatches operator to reset P/A converter.

CUE: Another operator will reset the PIA Converter.

Verify core power distribution is normal.

Verifies Step 13 actions concerning core power distribution.

Comment:

Performance Step: 13 Standard:

Comment:

Performance Step: 14 Standard:

Comment:

Performance Step: 15 Standard:

Place Bank Selector Switch to 'Auto/Manual' position.

Locates and places the Bank Selector switch in 'MANUAL'.

Cue: Place Rod Control in 'MANUAL'.

Reset Bank D rod position in accordance with 2OM-5A.4.A.50 Resets bank D rod position.

Cue: Place Rod Control in 'MANUAL'.

The requirement for 20ST-1.1, "Control Rod Assembly Partial Movement Test" is performed.

Informs the US of the requirement for the test.

Comment:

Terminating Cue:

When the candidate informs the US of the requirement to perform 20ST-1.1, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I BVPS-2 NRC JPM #S1

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC S1 Job Performance Measure No.:

2002 NRC S1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS-2 NRC JPM #S1

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET 2002 NRC S1 INITIAL CONDITIONS:

INITIATING CUE:

"* The plant is in Mode 1, 48% power.

"* An incore flux map has determined that Control Bank "D" rod B-8 is at 155 steps. Bank "D" is at 170 steps.

"* Control rods are in manual.

"* Tavg and Tref are matched.

"* The reason for the misalignment has been determined and corrected.

"* The General Manager Nuclear Operations and Reactor Engineering personnel have been notified.

"* Permission is granted to realign the rod.

The Unit Supervisor directs you to realign control rod B-8 to 170 steps in accordance with 2CM-1.4.P,Section IV.D.Section IV.A has been completed.

NUREG 1021, Revision 8, Supplement 1 BVPS-2 NRC JPMV #S1

Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 20M-1.4.P RCCA OR RCCA GROUP MISALIGNMENT Revision 4 Prepared by Date Pages Issued Effective Date A. J. Ochs 11123199 1 through 5 Reviewed by Date Validated by Date J. E. Burnecke 11124/99 NIA OSC Meeting No.

Date Approved by Date Non-Intent 11/24/99

Beaver Valley Power Station Unit 2 20M-1.4.P Reactor Control and Protection Revision 4 Operating Procedures FOR TRAINING USE ONLY' ge2 of 15 RCCA OR RCCA GROUP MISALIGNMENT I.

PURPOSE To provide the necessary instructions for aligning Control Rod(s) in the event a Control Rod(s) is determined to be misaligned from its respective Control Rod Bank. This procedure may be entered from an AOP.

II.

PRECAUTIONS & LIMITATIONS A.

Positive reactivity additions, initiated by the operators, shall be limited to one method during subcritical operations and power operation below 20% power. Concurrent dilution and rod withdrawal below 20% power is prohibited.V.C.2 B.

Continuous control rod withdrawals, above the point of adding heat, shall be limited to 5 step increments and startup rate shall not exceed a sustained 0.5 dpm (disregarding prompt jump) unless authorized otherwise by procedure.V.C.2 C. The turbine shall be tripped if Tavg drops to 541 F.V.C.2 D. The reactor shall be tripped if Tavg has a sustained declining trend, greater than 10 degrees below Tref, whose cause cannot be readily determined and abated.V.C.2 Ill.

INITIAL CONDITIONS A.

One or more of the following symptoms may indicate Control Rod(s) misalignment:

1.

One or more of the individual Digital Rod Position Indicators (DRPI's) in disagreement with the associated group step counter or with other position indicators for rods in the same bank by more than 12 steps when no rods are in motion. (Confirmed by AOP 2.1.7.)

2.

Rod deviation alarm. Deviation by more than 12 steps when no rods are in motion (computer printout/Ann. Window A4-8G).

3.

Power range nuclear instrumentation axial offset indication.

4.

The incore thermocouples and/or incore flux map indicates rod out of alignment.

5.

An abnormal variation between loop Tavg or Delta-T measurements.

6.

One control rod has been dropped.

Beaver Valley Power Station Unit 2 2Mio.4.P Reactor Control and Protection FT NU IIL\\!aRevision 4 Operating Procedures FOR TRAINING USE O,-

Page3of 15 RCCA OR RCCA GROUP MISALIGNMENT IV.

INSTRUCTIONS A.

Determine the Position of the Misaligned Control Rod(s) and appropriate Action as follows:

1. Transfer Rod Control to manual by placing the Auto-Manual Selector switch in MAN.

CAUTION:

ROD MOTION SHOULD BE AVOIDED EXCEPT AS SPECIFIED IN SUBSEQUENT OPERATOR ACTIONS.

I

2.

If the reactor power is greater than 75%, THEN perform the following:

a.

Within one hour, reduce reactor power to less than or equal to 75% by increasing the boron concentration. Refer to 20M-52.4.B, "Load Following".

3.

Stabilize the plant as follows:

a.

Adjust turbine load and/or boron concentration to maintain Tavg AND Tref within +/- 4F.

b.

Maintain stable plant conditions until rod misalignment cause can be determined and corrective action initiated.

4.

Check compliance with T.S. 3.1.3.1.c.3 by ensuring the following has been performed within one hour of the rod inoperability:

a.

Declare the rod inoperable.

b.

Verify SHUTDOWN MARGIN requirements of T.S. 3.1.1.1.

c.

POWER OPERATION may continue provided that:

1) THERMAL POWER is reduced to less than or equal to 75% of RATED THERMAL POWER within the hour.

2) Within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , reduce the high neutron flux trip setpoint to less than or equal to 85% of RATED THERMAL POWER.

3)

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , verify the SHUTDOWN MARGIN requirement of T.S. 3.1.1.1.

4)

Request Reactor Engineering perform an incore movable flux map. Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , verify FQ(Z) and FNAH within their limits.

5)

Within 5 days, re-evaluate each accident analysis of T.S. Table 3.1-1.

5.

When Reactor Power has been reduced to less than or equal to 75% and is stable, verify QPTR is less than 1.02.

a.

If Reactor Power is less than 50%, GO TO Step 5.

Beaver Valley Power Station Unit 2 20M-1.4.P Reactor Control and Protection u

E Revision 4 Operating Procedures FOR TRAINING USE ONLY Page 4 of 15 RCCA OR RCCA GROUP MISALIGNMENT

b.

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

c.

If QPTR is greater than 1.02, take action in accordance with T.S. 3.2.4.

6.

Investigate the cause of the problem and correct before attempting re-alignment.

7.

Carefully monitor the Power Range nuclear instrumentation for the occurrence of abnormal nuclear flux tilts throughout all subsequent maneuvers. DO NOT increase reactor power more than 1% (not to exceed 75%) during recovery.

8.

Prior to moving rod(s) to correct the misalignment, notify the General Manager, Nuclear Operations and consult the cognizant Reactor Engineering Group personnel concerning the rate of control rod movement.(v-c.1)

CAUTION:

DURING THE SUBSEQUENT MANEUVERS INVOLVING BANK MOVEMENT, DO NOT VIOLATE THE PRESCRIBED BANK OVERLAP SEQUENCE, BANK ROD INSERTION LIMIT, SHUTDOWN MARGIN REQUIREMENTS, OR DELTA FLUX TECH. SPEC. ACTION STATEMENTS.

9.

Request Reactor Engineering obtain a power distribution map from the movable incore detectors.

B.

If a Single RCCA is high with respect to its associated bank, perform the following:

1.

Place Rod Control Selector Switch to the bank with the misaligned rod.

2.

Place all Lift coil disconnect switches for the Bank with the misaligned Rod to ROD DISCONNECT (Up Position), except the switch for the misaligned rod which is left in ROD CONNECT (Down position), (Behind VB-B).

3.

Record the following data below and in the Daily Journal.

Bank Group I steps Group II steps Misaligned Rod Designation Misaligned Rod position has been determined to be positioned at steps.

(As determined by AOP 2.1.7)

Beaver Valley Power Station Unit 2 20M-1.4.P Reactor Control and Protection Revision 4 Operating Procedures FOR TRAINING USE 0NLY'age 8 of 15 RCCA OR RCCA GROUP MISALIGNMENT

e.

If recommended by Reactor Engineering, perform an incore flux map.

f.

If Reactor Power is greater than 50%, perform 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation".

g.

Verify the following annunciators are NOT lit:

"* A4-3C, "TAVG DEVIATION FROM TREF"

"* A4-3F, "LOOP TAVG DEVIATION"

"* A4-4C, "LOOP DELTA-T DEVIATION"

11. Adjust the affected Bank to the original Bank position recorded in Step IV.C.4, THEN verify that the Bank position display counter, corresponds to this position.

a.

If it is not desirable to raise the Bank, THEN reset the Bank position display counter to correspond to the existing Bank position.

12. Return Bank Selector Switch to AUTO or MANUAL as appropriate for current plant operation.

13. Perform 20ST-1.1, "Control Rod Assembly Partial Movement Test".

D.

If a Single RCCA is lower than its associated Bank OR Dropped Rod AND lowering the Bank to the misaligned Rod height may violate Bank Overlap Sequence, Rod Insertion Limit, or Delta Flux Tech. Spec. action, then restore as follows:

1.

Place Rod Control Selector Switch to the Bank with the misaligned/ dropped rod.

2.

Place all lift coil disconnect switches for the bank with the misaligned/dropped rod to ROD DISCONNECT (Up position), except the switch for the misaligned/dropped rod, which is left in ROD CONNECT (Down position), (Behind VB-B).

3.

Record the step position(s) for the misaligned/dropped rod bank group step counters below and in the Daily Journal.

Bank Group I steps Group II steps Misaligned/dropped Rod Designation Misaligned/dropped Rod position has been determined to be positioned at steps.

Beaver Valley Power Station Unit 2 20M-1.4.P Reactor Control and Protection T AIIRevision 4

Operating Procedures FOR TRAININGO LSE ONLY Page 9 of 15 RCCA OR RCCA GROUP MISALIGNMENT

4.

Set the Group Step Counter for the misaligned/dropped rod group to the position of the misaligned/dropped rod.

CAUTION:

PRIOR TO MOVING ROD(S) TO CORRECT THE MISALIGNMENT, THE GENERAL MANAGER, NUCLEAR OPERATIONS MUST BE NOTIFIED AND THE REACTOR ENGINEER MUST BE CONSULTED CONCERNING THE RATE OF CONTROL ROD MOVEMENT.(v-c-')

5.

Move the Rod Motion lever to OUT (in 5 step increments or less) while adjusting Turbine load to maintain Reactor AND Turbine load equal (Tavg-Tref).

a.

If the Turbine is not in operation, THEN maintain (Tavg-Tref) by adjusting Steam Dump OR Boron Concentration as appropriate to maintain Tavg.

Note:

Annunciator A4-8A ROD CONTROL SYSTEM URGENT ALARM will appear on the annunciator and the Urgent Alarm on the Power Cabinet for the group with all the lift coils disconnected. This Group will be locked out and rod motion inhibited.

6.

Verify the rod OUT direction lamp is ON AND DRPI for the misaligned/dropped rod is moving in the proper direction.

7.

Move the misaligned/dropped rod (in 5 step increments or less) until the Group step counter indicates the position recorded for the affected Group in Step IV.D.3

8.

Verify the misaligned/dropped rod is at the same position as the other rods in the bank DRPI.

9.

Place all disconnect switches for the affected Bank to ROD CONNECT, (Down position).

10. Clear the Urgent Failure Alarm on the Power Cabinet by depressing the Rod Control Alarm Reset pushbutton.

11. Verify Annunciator A4-8A, ROD CONTROL SYSTEM URGENT ALARM is OFF.

12. If the misaligned/dropped rod was in a control bank, THEN reset P/A converter as follows: (P/A Cont Cab, Elev 755, Rod Control Area, Key 128)

a.

Place the bank position display selector switch on the P/A converter to the affected Control bank position.

Note:

The Down pushbutton should be pushed the same number of steps the misaligned/dropped rod was moved.

I

b.

Hold the Auto-Manual switch (spring retum to AUTO) in MANUAL position AND push the Down pushbutton the required number of times to return the P/A converter display to the position corresponding to the affected bank height.

Beaver Valley Power Station Unit 2 20M-1.4.P Reactor Control and Protection Revision 4 Operating Procedures F 0 R Page 10 of 15 RCCA OR RCCA GROUP MISALIGNMENT

c.

Release the Auto-Manual switch AND verify it spring returns to AUTO.

Note:

Reactor power should not be increased without verifying normal flux distribution.

The Reactor Engineer should be consulted to determine if a Flux Map is needed prior to increasing reactor power.

13. After the rods have been realigned, check core power distribution normal.

a.

Verify operable power range indications with +/-2% of each other.

Verify CHANNEL DEVIATION light on N46 (Comparator and Rate drawer) is NOT lit.

Verify Annunciator A4-4F, "NIS POWER RANGE COMPARATOR DEVIATION" is NOT lit.

b.

Verify delta flux indications within target band.

c.

Verify control rod positions are greater than minimum rod insertion limit.

d.

Check incore thermocouples for any unusual or unexpected values.

e.

If recommended by Reactor Engineering, perform an incore flux map.

f.

If Reactor Power is greater than 50%, perform 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation".

g.

Verify the following annunciators are NOT lit:

"* A4-3C, "TAVG DEVIATION FROM TREF"

"* A4-3F, "LOOP TAVG DEVIATION"

"* A4-4C, "LOOP DELTA-T DEVIATION"

14. Return the Rod Bank selector switch to MANUAL or AUTO as appropriate for current plant conditions.

15. Reset rod position for affected bank in accordance with 20M-5A.I.A.50, "Rod Bank Position (Function 50)". Otherwise take action in accordance with T.S. 3.1.3.2.

16. Perform 2OST-1.1, "Control Rod Assembly Partial Movement Test".

E.

If Rod Group Misaligned with Group in Same Bank (by less than 12 steps), then restore as follows:

Note:

If two groups within the same bank differ in position, THEN the high group should be moved down for alignment OR, IF the misaligned group is in a shutdown group, THEN the lower group should be manually withdrawn.

1.

Place The Rod Control Selector Switch to the bank with the misaligned group.

Appendix C Job Performance Measure Form ES-C-1 Worksheet BVPS Unit 2 Respond to a Shutdown LOCA Task No.:

0535-056-04 013 JPM No.:

2002 NRC S2 K/A

Reference:

Examinee:

009 EA1.13 (4.4/4.4)

NRC Examiner:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom Date:

Simulator Actual Performance:

X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

S S

S The plant was in Mode 4, on RHS, when a LOCA occurred.

The RCP's have been secured.

The Shift Manager has decided to enter AOP-2.6.5, Shutdown LOCA to stabilize plant conditions.

2CHS*P21A and P21B, Charging Pumps are out of service.

SI Accumulators are isolated.

Equipment aligned to establish HHSI flow.

Shorting Bar 20M-53C.4.2.6.5, Shutdown LOCA, Rev. 11 AOP-2.6.5, Rev. 11 The Unit Supervisor directs you to perform the first 6 steps of AOP 2.6.5, Shutdown LOCA to establish HHSI flow.

No 15 minutes NUREG 1021, Revision 8, Supplement 1 Facility:

Task

Title:

X BVPS NRC JPM #S2

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S2 (Denote Critical Steps with an asterisk)

Check Safety Injection NOT actuated.

Checks Safety Injection annunciators. Determines Safety Injection is NOT actuated.

Comment:

Performance Step: 2 Standard:

Standard:

Isolate RCS letdown.

Closes or verifies closed letdown orifice isolation valves

[2CHS*AOV200A, B, C].

Closes or verifies closed Regen Heat Exchanger Letdown Inlet valves [2CHS*LCV460A, B].

Closes RHS Train A Cross connect Isol Valve [2RHS*MOV750A and/or B] (if open).

Comment:

Performance Step: 3 Standard:

Standard:

Check if charging flow is adequate.

Opens [2CHS*FCV122] in 'Manual'.

Checks PRZR level greater than 17%.

Checks PRZR level stable or rising.

Verifies PRZR level < 17% and dropping.

Comment:

Performance Step: 4 Standard:

Standard:

Comment:

Alert plant personnel of the Shutdown LOCA.

Sounds standby alarm.

Announces Unit 2 Shutdown LOCA.

Nonessential personnel from containment.

Notifies SHIFT MANAGER/US to evaluate EPP.

CUE:

SHIFT MANAGER/US will evaluate EPP. If asked, no one is inside containment.

NUREG 1021, Revision 8, Supplement 1 Performance Step: 1 Standard:

BVPS NRC JPM #S2

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S2 Note: The following steps represent the alternate path for this JPM.

Performance Step: 5 Standard:

Comment:

Performance Step: 6 Standard:

Standard:

Comment:

Terminating Cue:

Check SI equipment status:

Check two charging/HHSI pumps available.

Determines only one Charging/HHSI pump available.

CUE: Operator has been dispatched to restore 2CHS*P21A and 2CHS*P21C.

Establish alternate SI flowpath.

Verifies only one Charging/HHSI pump running.

Verifies [2CHS*LCV115B and/or D] open.

Verifies [2CHS*LCV115C and/or E] closed.

Inserts shorting bar for [2SIS*MOV836].

Opens [2SIS*MOV836].

Immediately closes [2CHS*MOV289].

NOTE:

Terminate the JPM at this point.

When the Candidate has established the alternate SI flowpath, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S2

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC S2 Job Performance Measure No.:

2002 NRC S2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #S2

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC S2 INITIAL CONDITIONS:

INITIATING CUE:

"* The plant was in Mode 4, on RHS, when a LOCA occurred.

"* The RCP's have been secured.

"* The Shift Manager has decided to enter AOP-2.6.5, Shutdown LOCA to stabilize plant conditions.

"* 2CHS*P21A and P21B, Charging Pumps are out of service.

"* SI Accumulators are isolated.

The Unit Supervisor directs you to perform the first 6 steps of AOP-2.6.5, Shutdown LOCA to establish HHSI flow.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S2

Record Type EA9.350C Beaver Valley Power Station UNIT 2 FOR TRAINING USE ONLY 20M-53C.4.2.6.5 Shutdown LOCA Revision 11 Prepared by Date Pages Issued C. Eberle 04/02/02 1 through 55 Reviewed by Date Validated by Date W. Giffrow 04/29/02 N/A OSC Meeting No.

Date OSC Not Required DRR-02-01748

,AF'- n- 02-294

CONTINUOUS ACTION STEPS STEP DESCRIPTION 1

Check Safety Injection - NOT ACTUATED 10 Check If RCPs Must Be Stopped

"* Number 1 seal differential pressure - LESS THAN 200 PSID

-OR

"* Number 1 seal leakoff flow - LESS THAN 0.2 GPM

-OR

"* Loss of CCP flow to RCP motor coolers 11 Check If Second Charging/HHSI Pump Should Be Started PRZR level -

LESS THAN 17% [38% ADVERSE CNMT]

-OR RCS subcooling - LESS THAN ATTACHMENT 3 12 Check If Low Head SI Flow Required RCS subcooling -

LESS THAN ATTACHMENT 3 14 Check If One Charginq/HHSI Pump Should Be Stopped

"* PRZR level - GREATER THAN 27% [47% ADVERSE CNMT]

"* RCS subcooling - GREATER THAN ATTACHMENT 6 24 Check RWST Level

- GREATER THAN 460 INCHES 25 Check SG Levels - GREATER THAN 12% r31% ADVERSE CNMT1 26 Check If OPPS Should Be Placed in Service 45 Check If Letdown Can Be Established FOR TRAINING USE ONLY Revision 11

20M-53C.4.2.6.5 FOR TRAINING USE ONLY A. PURPOSE This procedure provides instructions for protecting the reactor core in the event of a Loss of Coolant Accident (LOCA) that occurs during either Mode 3 (after the accumulators are isolated) or Mode 4.

B.

SYMPTOMS OR ENTRY CONDITIONS The following symptoms may be indicative of a Loss of Coolant Accident (LOCA) during Mode 3 (after the accumulators are isolated) or Mode 4:

1. Uncontrolled drop in PRZR level.

2. Uncontrolled drop in RCS subcooling.

3. Uncontrolled drop in RCS pressure.

C. AUTOMATIC ACTIONS Letdown isolation.

2A0P265 4/29/02 1 of 55 BVPS - AOP 1 of 55 2AOP265 4129/02'

20M-53C.4.2.6.5 STEP7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Due to the possibility of overpressurizing the RCS, Safety Injection must not be manually actuated.

fetv Injection -

NOT GO TO EOP E-O, "Reactor Trip Or Safety injectionu.

2.

Isolate RCS Letdown

a. Close all Letdown Orifice 21,22,23 Isol Vlvs.

2CHS*AOV2OOA]

2CHS*AOV20OBJ 2CHS*AOV200C]

FOR TRAINING USE ONLY

b. Close Regenerative Heat Exch Letdown Inlet Vlvs.

[2CHS*LCV46OA]

[2CHS*LCV46OB]

(step continued next page) 2A0P26S 4/29/02 2 of 55 NMTE

If a reactor trip occurs during the performance of this procedure, recovery should be accomplished by continuing with AOP 2.6.5, "Shutdown LOCA".

ADVERSE CNMT conditions are defined as:

CNMT pressure - GREATER THAN 1.5 PSIG

-OR CNMT radiation -

GREATER THAN IE+5 R/HR

-OR Integrated CNMT radiation - GREATER THAN 1E+6 R inCheck Sa ACTUATED 0

BVPS - AOP 2 of 55 2AOP265 4/29/02

20M-53C.4.2.6.5 Number Title 2.6.5 Shutdown LOCA Revision 11 FSTEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.

(continued from previous page)

c. Close RHS Train A,B Cross Connect Isol Vlvs.

[2RHS*MOV750A]

[2RHS*MOV750B]

3.

Check If Charging Flow Is Adequate

a. Adjust [2CHS*FCV122],

Charging Pumps Disch Flow Control Vlv as necessary to maintain PRZR level.

b. Check PRZR level:

"* GREATER THAN 17% [38% ADVERSE CNMT]

"* STABLE OR RISING

c.

RCS subcooling based on core exit TCs - GREATER THAN 41F [59F ADVERSE CNMT]

d.

[2CHS*FI122A],

Charging Line Flow d.

- OFF SCALE HIGH

c. Close [2CHS*HCV142],

Outlet Flow Control.

RHR Hx

b. GO TO Step 4.

c. Check RCS subcooling based on core exit TCs - GREATER THAN SUBCOOLING LISTED ON ATTACHMENT 3 I.E subcooling less than required subcooling listed on Attachment 3, THEN GO TO Step 4.

IF PRZR level and RCS subcooling can be maintained, ITHE RETURN TO procedure and step in effect.

FOR TRAINING USE ONLY 2A0P265 4/29/02 3 of 55 BVPS - AOP 2AOP265 4/29/02 3 of 55

20M-53C.4.2.6.5 FSEP]

ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

4.

Alert Plant Personnel Of The Shutdown LOCA

a. Sound the standby alarm.

b. Announce "Unit 2 Shutdown Loss of Cool ant Accident".

c. Evacuate non-essential personnel from containuient.

d. Evaluate if EPP should be initiated.

5.

Check SI Equipment Status

a. Check Charging/HHSI Pumps - TWO AVAILABLE

b. High Head SI Cold Leg Isol Vlvs NONE ENERGIZED

[

[2SIS*MOV867A(B)]

[2SIS*MOV867C(D)]

a. Restore Charging/HHSI Pump(s) available status.

to

b. IF [2SIS*MOV867A(B)]

AND

[2SIS*MOV867C(D)] are energized, THEN GO TO Step 7.

6.

Establish Alternate SI Flowpath

a. Charging/HHSI Pump - ONLY ONE RUNNING

a. Stop Charging/HHSI Pump to establish only one pump running.

FOR TRAINING USE ONLN (step continued next page) 2A0P265 4/29/OZ 4 of 55 NOTE In the following instruction, [2CHS*MOV289] should be closed immediately after the alternate SI flowpath starts to align.

BVPS -

AOP I

4 of 55 2AOP265 4/29/02

20M-53C.4.2.6.5 STEP I ACTION/EXPECTED RESPONSE I

RESPONSE NOT OBTAINED

6.

(continued from previous page)

b. Align Charging/HHSI Pump suction to RWST by performing the following:

1) Open Charging Pumps Suct From RWST.

[2CHS*LCV11SB]

F2CHS*LCV115D]

2) Close Charging Pumps Suct From Volume Control Tank.

[2CHS*LCV115C]

S2CHS*LCV115E]

c. Align an alternate SI flowpath by performing one of the following:

Perform the following:

1) Insert shorting bar into

[2SIS*MOV836],

High Head SI Cold Leg Isol Vlv jack.

2) Open [2SIS*MOV836].

d. Immediately close [2CHS*MOV289],

Normal Charging Hdr Isol Vlv.

e. Dispatch an operator to re-energize valves:

[2SIS*MOV867A] -

[MCC*2-E03]

Cub 7A, (Aux Bldg - 755')

[2SIS*MOV867B] - [MCC*2-EO4]

Cub 6D, (Aux Bldg - 755')

FOR TRAINING USE ONLY (step continued next page) 2A0P265 4/29/02 5 of 55 BVPS - AOP 5 of 55 2AOP265 4129/02

20M-53C.4.2.6.5 iSTjI jIACTION/EXPECTED RESPONSE I

RESPONSE NOT OBTAINED (continued from previous page)

f. Dispatch an operator to re-energize valves:

"* [2SIS*MOV867C] -

[MCC*2-EO5]

Cub 1OA, (Rod Control Bldg 735')

"* [2SIS*MOV867D] -

[MCC*2-EO6]

Cub 4A, (Rod Control Bldg 735')

g. Continue to inject using the alternate SI flowpath.

WHEN

[2SIS*MOV867A,C(B,D)] become available, THEN simultaneously perform the following:

Open [2SIS*MOV867AC(B,D)],

High Head SI Cold Leg Isol Vlvs

Isolate alternate SI flowpath

h.

GO TO Step 8.

FOR TRAINING USE ONLY 2A0P265 4/29/az 6 of 55 6.

BVPS -

AOP 6 of 55 2AOP265 4/29/02

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

BVPS Unit 2 Respond to a Radiation Monitor Alarm Leak Collection Tank (Faulted) 073 A4.02 (3.7/3.7)

Task No.:

0431-028-01-013 JPM No.:

2002 NRC S3 Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

Simulator Actual Performance:

X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The plant is at 48% power. Annunciator A4-5C has just been received.

Radiation monitor automatic actions have been verified.

None 20M-43.4.AAC, Radiation Monitoring Level High, Issue 4, Rev. 0 20M-43.4.AEB, Local-Leak Collection Ventilation [2RMR-RQI301] High Alarm Level, Issue 1, Revision 5 20M-43.4.AAC, Rev. 0 & 20M-43.4.AEB, Rev. 5 The Unit Supervisor directs you to respond to the alarm using the alarm response procedures.

No 20 minutes NUREG 1021, Revision 8, Supplement 1 X

BVPS NRC JPM #S3

Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S3 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Verify or depress the grid six pushbutton and determine which radiation monitor is in alarm at the RM-1 1 console.

Locates the grid six pushbutton and depresses it, OR verifies that the grid is already displayed.

Comment:

Performance Step: 2 Standard:

Standard:

Comment:

Performance Step: 3 Standard:

At RM-1 1 console type in the four digit numerical code for the monitor in alarm and press the 'SELECT' pushbutton.

Locates the four digit code for 2RMR-RI301.

Enters the four digit code and presses the 'SELECT' pushbutton.

NOTE:

Candidate may press 'SELECT' only to access monitor alarm.

Depress the 'STATUS' pushbutton.

Locates and depresses the 'STATUS' pushbutton.

Comment:

Performance Step: 4 Standard:

Comment:

Performance Step: 5 Standard:

Comment:

Silence the alarm console.

Depresses the 'SYSTEM ACK' pushbutton to silence the alarm.

NOTE:

The audible alarm may be defeated and not sound.

Check if radiation level is at or approaching 1000 times background.

Compares reading against background or notifies Shift Manager.

CUE: The Shift Manager is aware of the alarm level.

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #S3

Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S3 Performance Step: 6 Standard:

Comment:

Performance Step: 7 Standard:

Candidate determines that [2RMR-RQI301] Leak Collection Ventilation Radiation Monitor is in alarm and then refers to local alarm response procedure for the corrective actions.

Determines 2RMR-RQI301 is in alarm.

NOTE:

Candidate may verbalize monitor in alarm or may just use the correct procedure. Either action satisfies the critical step.

CUE: Provide Candidate a copy of 20M-43.4.AEB.

At the RM-1 1 console, verify the indicating box turns red and moves to the right of 'CHANNEL IN HIGH ALARM'.

Verifies that the red box moves to the right.

Comment:

Performance Step: 8 Standard:

Standard:

Depress the 'CHANNEL ITEMS' pushbutton and verify that the actual level is higher than the high alarm setpoint.

Depresses the 'CHANNEL ITEMS' pushbutton.

Compares actual level to high alarm setpoint.

Comment:

Performance Step: 9 Standard:

Comment:

Notify the US/Shift Manager and obtain directions.

Notifies Shift Manager of the HIGH radiation monitor alarm and asks for direction.

CUE: The Shift Manager is aware of the alarm and has notified RADCON.

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #S3

Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S3 NOTE: The following steps represents the alternate path for this JPM.

Performance Step: 10 Verify 2HVS*MOD201A & B are closed, and that 2HVS*MOD202A & B are open.

Standard:

Locates 2HVS*MOD201A & B and 2HVS*MOD202A & B on BSP.

Standard:

Verifies that 2HVS*MOD201A & B are closed and that 2HVS*MOD202A & B are open.

Standard:

Verifies that the damper green or red lights are lit.

Comment:

Performance Step: 11 Standard:

Standard:

Comment:

Terminating Cue:

CUE:

If asked for guidance, act as Supervisor and direct Candidate to place the dampers in their required position.

Position dampers by placing either or both control switch(es) to

'FILT' position.

Locates Train "A" and Train "B" control switches on the Building Service Panel.

Places either or both control switches to the 'FILT' position.

Verifies that the damper green and red lights are lit.

NOTE:

If Candidate continues with procedure, conclude JPM at this point.

When the Candidate verifies the damper green and red lights are lit, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S3

Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC S3 Job Performance Measure No.:

2002 NRC S3 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S3

Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET 2002 NRC S3 INITIAL CONDITIONS:

INITIATING CUE:

The plant is at 48% power. Annunciator A4-5C has just been received.

The Unit Supervisor directs you to respond to the alarm using the alarm response procedures.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S3

Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 20M-43.4.AAC RADIATION MONITORING LEVEL HIGH Revision 0 Prepared by Date Pages Issued Effective Date R. Plummer 10/29/96 1 through 4 Reviewed by Date Validated by Date C. O'Neill 10/30196 N/A OSC Meeting No.

Date Approved by Date Non-Intent 10/30/96

DESCRIPTION CRT NO. COMPUTER ADDRESS A. HIGH RADIATION FOR TRAINING USE ONLY Beaver Valley Power Station Unit 2 20M-43.4.AAC Radiation Monitoring System Revision 0 Operating Procedures Page 2 of 4 RADIATION MONITORING LEVEL HIGH A4-5C RADIATION MONITORING LEVEL HIGH A4-5C PAGE 2

R0004D AAC;

Beaver Valley Power Station Unit 2 20M-43.4.AAC Radiation Monitoring System Revision 0 Operating Procedures Page 3 of 4 RADIATION MONITORING LEVEL HIGH A4-5C A. HIGH RADIATION SETPOINTS: Refer to RMS Log DISCONNECT SWITCH: 594 INITIATING DEVICE: K-1 (Relay in Rm-11)

PROBABLE CAUSE A high radiation condition being detected by any radiation monitor.

CORRECTIVE ACTIONS 1.

Perform the following at the RM-1 1 operators console:

a.

Press the grid 6 pushbutton AND Determine which radiation monitor in alarm (blinking and has turned red).

Note:

The four digit number is the radiation monitor number less the letters (i.e.

1 PA234 will be 1234).

b.

Type in the 4-digit numerical code number of the alarming monitor AND Press the SEL pushbutton.

c.

Press the STATUS pushbutton.

d.

Press SYSTEM ACK to silence the console alarm.

e.

If any radiation monitor is at OR approaching, 1000 times normal background, Immediately notify the NSS AND Refer to 1/20M-57, "Emergency Preparedness Plan" for further actions.

f.

Refer to local alarm response procedures 20M-43.4.ACN through 20M 43.4.AEJ for corrective actions.

FOR TRAINING USE ONLY

Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 20M-43.4.AEB(ISSI)

LOCAL-LEAK COLLECTION VENTILATION [2RMR-RQI301] HIGH ALARM LEVEL Revision 5 Prepared by Date Pages Issued Effective Date R. Plummer 10/13195 1 through 3 Reviewed by Date Validated by Date C. O'Neill 10/13195 N/A OSC Meeting No.

Date Approved by Date Non-Intent 10/13195

Beaver Valley Power Station Unit 2 20M-43.4.AEB(ISS1)

Radiation Monitoring System O

TRAINING U ONLY Revision 5 Operating Procedures FO*'

TRAIING USE Page 2 of 3 LOCAL-LEAK COLLECTION VENTILATION [2RMR-RQi301] HIGH ALARM LEVEL A4-5C Computer Pt. R0004D Setpoint Device See Setpoint Log

[2RMR-DAU301]

PROBABLE CAUSE

1.

Radioactive gases and/or particulates in the Safeguards area, Cable Vaults, or Equipment Hatch Area.

CORRECTIVE ACTIONS

1.

If radioactive gases ANDIOR particulates in the Safeguards area, Cable Vaults, OR Equipment Hatch are suspected:

a.

At the RM-1 1 operators console, Verify the indicating box turns red AND moves to the right of CHANNEL IN HIGH ALARM.

b.

Press CHANNEL ITEMS AND Verify the actual radiation level (top right hand corner) is greater than line item 9 (HIGH setpoint).

c.

Notify the NSS and at his direction, Perform any of the following steps.

d.

Notify Health Physics of the activity level.

e.

Verify [2HVS*MOD201A and B] Contiguous Area Normal Unfiltered Leak Coll.

Dampers, are Closed (2BSC).

1)

If dampers are NOT Closed, Place control switch in the FILT position.

f.

Verify [2HVS*MOD202A and B], Contiguous Area Normal Filtered Leak Collection Dampers, are Open (2BSC).

1)

If dampers are NOT Open, Place control switch in the FILT position.

g.

Instruct all affected personnel to report to Health Physics for possible dose assessment AND decontamination.

h.

Investigate to locate the source of the activity, IF possible.

i.

Refer to 1/20M-57, "Emergency Preparedness Plan", for further actions.

REFERENCES Note:

All references used prior to Issue I Revision 2 are located in Section 5.

1.

OMDR 2-88-1239 (Rev. 2).

2.

OMDR 2-88-1790 (Rev. 3).

3.

OMDR 2-91-0962 (Rev. 4).

Appendix C Job Performance Measure Form ES-C-1 Worksheet BVPS Unit 2 Initiate a Cooldown ier ES-0.2 Task No.:

0061-009-01-013 0061-011-01-013 JPM No.:

2002 NRC S4 K/A

Reference:

Examinee:

002 A4.02 (4.3/4.5)

EA 1.1 (3.5/3.5)

NRC Examiner:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom Date:

Simulator Actual Performance:

X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

The reactor was manually tripped due to a CCP leak that required stopping all RCPs.

The plant is now in natural circulation cooldown mode.

E-0, ES-0.1, and ES-0.2 through Step 5 have been completed.

The plant is stable with condenser steam dumps in automatic in the Steam Pressure Mode and the bypass feedwater regulating valves in automatic maintaining SG levels.

Natural circulation cooldown established at a rate of < 250F/hr.

None 20M-53A-ES-0.2, Natural Circulation Cooldown Issue 1C, Rev. 0 20M-53A.1.A-4.1, RCS Cooldown Limits - Technical Specifications, Issue 1C, Rev. 0 20M-53A-ES-0.2, Issue 1C, Rev. 0 20M-53A.1.A-4.1, Issue 1C, Rev. 0 Initiating Cue:

Time Critical Task:

Validation Time:

The Unit Supervisor directs you to initiate a cooldown of the RCS in accordance with ES-0.2, Step 6.

No 20 minutes NUREG 1021, Revision 8, Supplement 1 Facility:

Task

Title:

X BVPS NRC JPM #S4

Appendix C Page 2 of 5 PERFORMANCE INFORMATION Form ES-C-1 2002 NRC S4 (Denote Critical Steps with an asterisk)

NOTE:

It may be necessary to reduce letdown, manually operate 2CHS-FCV122, or use a PRZR PORV to control pressure. Also, AFW starts are inhibited, so no actuation will occur if SG levels are low.

Performance Step: I Standard:

Standard:

Trend RCS temperature and pressure at 10 minute intervals.

Acknowledges report to trend RCS cold leg temperatures and RCS pressure.

Refers to Attachment A-4.1 and ensures the following cooldown rate does not exceed 250F/hr.

Comment:

Performance Step: 2 Standard:

Standard:

Comment:

Performance Step: 3 Standard:

Standard:

Maintain SG level between 30% and 50%.

Locates appropriate SG NR level indication.

Checks SG narrow range level indication.

NOTE:

SG levels may have to be adjusted. Inform the Candidate that the Examiner will be responsible for SG level control.

Dump steam to condenser.

Checks MSIV's open.

Checks Annunciator A12-4C "Condenser Unavailable (C-9)"

NOT LIT.

Comment:

Performance Step: 4 Standard:

Standard:

Set steam header pressure setpoint to initiate dumping steam.

Sets 'STEAM HEADER' pressure setpoint on [2MSS*PK464]

MAIN STM MANIFOLD pressure control above existing steam header pressure.

Places 2MSS*PK464 in 'MANUAL'.

Verifies demand on 2MSS*PK464 at zero.

Places/verifies the "Steam Dump Control Mode" selector switch in the 'STM PRESS MODE'.

Comment:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S4

Appendix C Page 3 of 5 PERFORMANCE INFORMATION Form ES-C-1 2002 NRC S4 NOTE: The following steps represent the alternate path for this JPM.

Performance Step: 5 Standard:

Depresses raise pushbutton to open the steam dump valves.

Notes failure of condenser steam dumps and informs Supervisor.

CUE:

As Supervisor, acknowledge condenser steam dump failure and direct Candidate to use 2SVS*HCV1 04 to dump steam.

Standard:

Comment:

Performance Step: 6 Standard:

Refers to RNO and manually dumps steam using [2SVS*HCV104],

Residual Heat Release Valve.

Slowly opens 2SVS*HCV104.

Comment:

Performance Step: 5 Standard:

Standard:

Comment:

Terminating Cue:

Establish desired cooldown rate.

Monitors cooldown rate.

Adjusts cooldown rate as necessary to establish a cooldown rate less than 25°F/hr.

NOTE:

A final stable cooldown rate is NOT critical to the performance of the JPM.

When the candidate begins manually dumping steam using 2SVS*HCV1 04, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #S4

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC S4 Job Performance Measure No.:

2002 NRC S4 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #S4

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC S4 INITIAL CONDITIONS:

INITIATING CUE:

"* The reactor was manually tripped due to a CCP leak that required stopping all RCPs.

"* The plant is now in natural circulation cooldown mode.

"* E-0, ES-0.1, and ES-0.2 through Step 5 have been completed.

"* The plant is stable with condenser steam dumps in automatic in the Steam Pressure Mode and the bypass feedwater regulating valves in automatic maintaining SG levels.

The Unit Supervisor directs you to initiate a cooldown of the RCS in accordance with ES-0.2, Step 6.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S4

Record Type A9.350C Beaver Valley Power Station UNIT 2 FOR TRAINING USE ONLY 20M-53A.1.ES-O.2(ISSIC)

Natural Circulation Cooldown Issue 1C Revision I Prepared by Date Pages Issued M. P. Flynn 11/14101 1 through 17 Reviewed by Date Validated by Dale C. Eberle 11/14/01 N/A OSC Meeting No.

Date OSC Not Required DRR-01-04436

20M-53A.I.ES-O.2(ISS1C)

Number Title ES-0.2 Natural Circulation Cooldown Issue IC Revision 1 FOR TRAINING USE ONLY A. PURPOSE This procedure provides actions to perform a natural circulation RCS cooldown depressurization to cold shutdown, with no accident in progress, under requirements that will preclude any upper head void formation.

B.

SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from:

1. ES-O.1, "Reactor Trip Response", Step 19 when it has been determined that a natural circulation cooldown is required.

2. ECA-O.1.

"Loss Of All AC Power Recovery Without SI Required", Step 21 after the plant conditions have been stabilized following the restoration of AC emergency power.

3. ES-1.1, "SI Termination", Step 32 when it has been determined that a natural circulation cooldown is required.

C-APPLICABLE MODES ES-0.2, "Natural Circulation Cooldown", is applicable in Modes 1, 2 and 3.

Refer to 1/20M-53B.2, "User's Guidew,Section V, "Modes Of Applicability Of The EOPs', for a detailed discussion of this subject.

ZESO2 11/15/01 1 of 17 BVPS -

EOP 2,ES02 11/15/01 I of 17

SYMPTOMATIC RESPONSE/UNEXPECTED CONDITIONS ES-0.2 (Issue IC, Revision 1)

1. SI ACTUATION CRITERIA Actuate SI and GO TO E-O, "Reactor Trip Or Safety Injection", Step 1, if either condition listed below occurs:

"* RCS subcooling based on core exit TCs - LESS THAN 41F (If less, refer to Attachment A-5.1)

"* PRZR level - CANNOT BE MAINTAINED GREATER THAN 5%

2. AFW SUPPLY SWITCHOVER CRITERION Monitor PPDWST [2FWE*TK210] level for AFW pumps supply.

Upon reaching low level alarm, 85 INCHES, refer to Attachment A-1.8 for makeup.

FOR TRAINING USE ONLY

20M-53A.1.ES-O.2(ISSIC)

Number Title ES-O.2 Natural Circulation Cooldown Issue 1C Revision 1 Fs1T ] I ACTION/EXPECTED RESPON4SE]

RESPONSE NOT OBTAINED

6.

Initiate RCS Co01down To Cold Shutdown

a. Trend RCS Tcold and pressure on the main computer at 10 minute intervals.

1) Initial the trend every half-hour.

2) Ensure cooldown in RCS cold legs does not exceed 25F/HR.

3) Refer to Attachment A-4.1.

b. Maintain SG narrow range level BETWEEN 30% AND 50%

a. Verify cooldown rate in RCS cold legs less than 25F/HR and initial

[2RCS*TR410] RCS Temperature Recorder every half-hour.

b. Control feed flow to restore level.

FOR TRAINING USE ONLY (step continued next page) 2E502 11/15/01 5 of 17 BVPS -

EOP 2ES02 11/15/01 5 of 17

Reord TypeMA.3500 Beaver Valley Power Station UNIT 2 FOR TRAINING USE ONLY 20M-53A.1.A-4.1(ISSIC)

RCS Cooldown Umits - Technical Specifications Issue IC Revision 0 Prepared by Date Pages Issued Effective Date C. O'Neill 06126/00 1 of I MAR 2 9 2001 Reviewed by Date Validated by Date M. P. Flynn 0626100 NI n

OSC Meeting No.

Date ved b Date BV-OSC-02-0 1 01/09/01 c& '..

O

20M-53A. 1.A-4. 1 (ISSIC)

FOR TRAINING USE ONLY BV-2 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS (APPLICABLE FOR THE FIRST 15 EFPY) 0 III it I I i liii: Il IlL lIlt I{ III II UNACCEPTABLE OPERATION 60FM ACCEPTABLE 00FA*i OPERATION

- -1 t -

t -

I -

4 -

50 100 150 RCS TEMPERATURE (F) 200 250 2500 2250 2000 1750 f1250 a:

0) 1000 0

750 500 250 0

2A4]

3/20/01 I of 1 I -

BVPS -

EOP II 1loflI 2A41 3/20/01

Appendix C Job Performance Measure Form ES-C-1 Worksheet BVPS Unit 2 Manual Initiation of Quench Spray Task No.:

0531-005-05-013 JPM No.:

2002 NRC S5 K/A

Reference:

026A2.03 (4.1/4.4) 026K4.03 (3.7/4.1) 026A2.04 (3.9/4.2)

NRC Examiner:

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom Simulator Actual Performance:

X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

"* A reactor trip and safety injection have occurred.

"* The actions of E-0 have been completed through Step 7.

"* Steamline isolation has actuated due to high containment pressure and all indicating lights that have yellow SLI markers are energized.

CIB and Containment Spray requirements are satisfied in accordance with A.0.11, Step 6.

None 20M-53A. 1.E-0, Reactor Trip Or Safety Injection, Issue 1C, Rev. 3 20M-53A.1.A.0.11, Verification Of Automatic Actions, Issue 1C, Rev. 2 Attachment A-0.11, Issue 1C, Rev. 2 The Unit Supervisor directs you to verify Containment Isolation Phase "B" and Containment Spray requirements are satisfied according to Step 6 of Attachment A-0.1 1.

No 5 minutes NUREG 1021, Revision 8, Supplement I Facility:

Task

Title:

Date:

X BVPS NRC JPM #S5

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S5 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Standard:

Check CIB and Containment Spray status.

Checks whether annunciator "CONTAINMENT ISOLATION PHASE B" [AI-2H] is LIT.

Locates [2LMS*PR950], Containment Pressure Recorder.

Checks whether containment pressure has remained less than 8 psig (at least one pen).

Comment:

Performance Step: 2 Standard:

Verify Containment Isolation Phase "B" has occurred.

Determines BLUE CIB marked indicating lights are NOT energized.

Comment:

Performance Step: 3 Standard:

Standard:

Comment:

Manually initiate CIB (both switches for both trains).

Locates switches (2 per train) for Train "A" Spray Actuation.

(Benchboard Section A).

Turns both switches (2 of 2) to the 'ACTUATE' position.

Locates switches (2 per train) for Train "B" Spray Actuation (Benchboard Section A).

Turns both switches (2 of 2) to the 'ACTUATE' position.

NOTE:

Order of switch manipulation may be reversed.

Only one set of switches is required to be actuated.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S5

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S5 Note: The following steps represent the alternate path for this JPM.

Performance Step: 4 Standard:

Standard:

Check all indicating lights with BLUE CIB marks LIT.

Determines 21A and 21B Quench Spray pumps are not running.

Locates control switches for Quench Spray pumps.

Places control switches to the 'START' position (both pumps).

Verifies red lights are energized (both pumps).

Comment:

Terminating Cue:

When the Candidate has started the Quench Spray pumps, the evaluation for this JPM is complete NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S5

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC S5 Job Performance Measure No.:

2002 NRC S5 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S5

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC S5 INITIAL CONDITIONS:

INITIATING CUE:

"* A reactor trip and safety injection have occurred.

"* The actions of E-0 have been completed through Step 7.

"* Steamline isolation has actuated due to high containment pressure and all indicating lights that have yellow SLI markers are energized.

The Unit Supervisor directs you to verify Containment Isolation Phase "B" and Containment Spray requirements are satisfied according to Step 6 of Attachment A-0. 11.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S5

Record Type RA9 350D Beaver Valley Power Station UNIT 2 FOR TRAINING USE ONLY 20M-53A.1.A-0.1 1 (ISSl C)

Verification Of Automatic Actions Issue IC Revision 2 Prepared by Date Pages Issued C. Eberle 04/19/02 1 through 8 Reviewed by Date Validated by Date W. Giffrow 04/19/02 N/A OSC Meeting No.

Date OSC Not Required DRR-02-02136

20M-53A.I.A-O.11(ISSlC)

FOR TRAINING USE ONLY A.

PURPOSE To verify the automatic actions of E-O, "Reactor Trip Or Safety Injection".

This will reduce the time to perform the actions in E-O and allow quicker transition for inadvertent SI scenarios.

B.

SYMPTOMS OR ENTRY CONDITIONS This attachment is entered from E-O, "Reactor Trip Or Safety Injection", Step 8 and should be performed as time permits.

2a011 4/19/02 BVPS -

EOP I of 8

20M-53A.l.A-O.11(ISSIC)

Number Title A-O.11 Verification Of Automatic Actions Issue 1C Revision 2 STEP ACTION/EXPECTED RESPONSE I

RESPONSE NOT OBTAINED UIE The RSS pumps will not start until 10.5 MINUTES after the CIB signal is initiated.

6.

Check CIB And CNMT Spray Status e Containment pressure (at least one pen) - HAS REMAINED LESS THAN 8 PSIG ON [2LMS*PR950] REACTOR CNMT PRESS RECORDER Verify CIB initiated:

a. Check all indicating lights with BLUE CIB mark - LIT E NKUT.

IMHE manually initiate CIB (both switches for both trains). Check all indicating lights with BLUE CIB mark -

LIT IH CIB NOT actuated, TMEN manually align equipment.

b. Stop all RCPs.

c. Request BV-1 operator verify CREBAPS equipment actuation.

FOR TRAINING USE ONLY ZaUll 4/19/1J2 5 of 8 BVPS -

EOP 5of 8 24011 4/11i02

Appendix C Job Performance Measure Form ES-C-1 Worksheet BVPS Unit 2 Shutdown No. 1 Diesel Generator Task No.:

0362-007-01 013 JPM No.:

2002 NRC S6 K/A

Reference:

064A4.06 (3.9/3.9)

NRC Examiner:

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom Actual Performance:

Simulator X

Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The 2-1 Emergency Diesel Generator is running and supplying Emergency 4KV Bus "2AE" due to a spurious trip of ACB "2A1 0".

"2A10" has been checked by Electrical Maintenance and the relays are reset.

2EGS*EG2-1 is shutdown in accordance with 20M-36.4.E None 20M-36.4.E, Transferring 4KV Emergency Bus 2AE To Bus 2A, Rev. 8 20M-36.4.E, Rev. 8 (markup copy)

The Unit Supervisor directs you to transfer 4KV Bus "2AE" to Bus "2A" in accordance with 20M-36.4.E Step IV.A. The Initial Conditions are satisfied.

No 20 minutes NUREG 1021, Revision 8, Supplement 1 Facility:

Task

Title:

Date:

X BVPS NRC JPM #S6

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S6 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Close [ACB-2A10], 4KV Bus 2A to Emer Bus 2AE.

ACB-2A1 0 closed.

Comment:

Performance Step: 2 Standard:

Place 2-1 Emer Gen Synchronizing Selector Switch to Bus 2A position.

Selector Switch in Bus "2A" position.

Comment:

Performance Step: 3 Standard:

Adjust [2EGS*EG2-1], Emergency Diesel Generator 2-1 speed with the 2-1 Emerg Gen Governor Control such that the 2-1 Emergency Generator Synchroscope (VB-C) needle rotates slowly in the FAST direction.

Synchroscope needle rotating slowly in the fast direction.

Comment:

Performance Step: 4 Standard:

Adjust [EGS*EG2-1], Emergency Diesel Generator 2-1 output voltage as indicated on 2-1 Emer Gen Volts to read slightly higher than the 4KV Bus 2A Volts (VB-C) using Emer Gen 2-1 Voltage Adjust.

Voltage adjusted.

Comment:

Performance Step: 5 Standard:

With the synchroscope rotating slowly in the FAST direction, WHEN both synchronizing lights are completely dark AND the synchroscope needle is at the 12 o'clock position, place [ACB 2E7], 4KV Emer Bus 2AE to Bus 2A in the CLOSE position.

ACB-2E7 closed.

Comment:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S6

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S6 Performance Step: 6 Standard:

Place 2-1 Emer Gen Synchronizing Selector switch to 'OFF'.

Selector Switch in 'OFF' position.

Comment:

Performance Step: 7 Standard:

Maintain generator power factor between.8 and 1.0 lagging by adjusting 2-1 Emer Gen Voltage Adjust.

Power factor between 0.8 and 1.0 lagging.

Comment:

Performance Step: 8 Standard:

Reduce [EGS*EG2-1], Emergency Diesel Generator 2-1, load UNTIL < 100 KW is indicated on 2-1 Emergency Generator Watts by placing 2-1 Emer Gen Governor Control to 'LOWER'.

2EGS*EG2-1 load < 100 KW.

Comment:

Performance Step: 9 Standard:

Open [ACV-2E10], 2-1 Emer Gen Output Breaker.

ACB-2E10 open.

Comment:

Terminating Cue:

When the Candidate opens the diesel generator output breaker, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S6

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC S6 Job Performance Measure No.:

2002 NRC S6 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #S6

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC S6 INITIAL CONDITIONS:

INITIATING CUE:

The 2-1 Emergency Diesel Generator is running and supplying Emergency 4KV Bus "2AE" due to a spurious trip of ACB "2A10".

"2A10" has been checked by Electrical Maintenance and the relays are reset.

The Unit Supervisor directs you to transfer 4KV Bus "2AE" to Bus "2A" in accordance with 20M-36.4.E Step IV.A. The Initial Conditions are satisfied.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S6

A9.330B Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 20M-36.4.E TRANSFERRING 4KV EMERGENCY BUS 2AE TO BUS 2A Revision 8 Prepared by Date Pages Issued Effective Date W. K. Giffrow 09119101 1 through 6 Reviewed by Date Validated by Date F. J. Schaffner 09119101 N/A OSC Meeting No.

Date Approved by Date OSC Not Required

Beaver Valley Power Station Unit 2 20M-36.4.E 4KV Station Service System Revision 8 Operating Procedures FOR TR NINGU SE ONLYPage 2 of 6 TRANSFERRING 4KV EMERGENCY BUS 2AE TO BUS 2A Io PURPOSE This procedure describes the steps for transferring 4KV Emergency Bus 2AE to Bus 2A from the [2EGS*EG2-1], Emergency Diesel Generator 2-1. This procedure may be entered from an EOP.

I1.

PRECAUTIONS & LIMITATIONS A.

The emergency diesel generator should be manually tripped if a loss of offsite power is experienced while the emergency diesel generator is paralleled on the Bus. If the emergency diesel generator trips first on electrical protection, then the electrical protection relay (PNL 243 for DG 2-1, Emerg Swgr) should be reset manually as soon as possible (not to exceed one hour) to ensure that the emergency diesel generator will be available for an Auto start.

B.

At no time should the diesel generator be operated if the lube oil pressure is below 70 psi.

C. The emergency diesel generators should not be paralleled with offsite power when anticipating a loss of offsite power because it would increase the potential for a loss of all AC power.

D.

Voltage on [4KVS*2AE(2DF)] should be maintained within the limits listed in 20M-36.2.A, "Precautions And Limitations". If 4KV emergency bus voltage drops below 3885V (111V on VB-C), the 90-second degraded bus undervoltage timer will start. Bus voltage must be raised to > 3990V (1 14V on VB-C) to reset the timer.

If 480V emergency bus voltage drops below 450V, the 90-second degraded bus undervoltage timer will start. Bus voltage must be raised to > 460V to reset the timer.

480V emergency bus voltage can be read on the SPDS computer.

E.

If the diesels are solely supplying the emergency busses due to a loss of offsite power, re-alignment of the emergency busses to the offsite sources shall not be performed until confirmation of grid stability is obtained from system operations and permission received from Operations management. This will avoid returning to an unstable grid and possible challenges to the onsite emergency power system. (C.2)

II1.

INITIAL CONDITIONS A.

[2EGS*EG2-1], Emergency Diesel Generator 2-1, is supplying the Emergency Bus 2AE.

B.

Normal 4KV Bus 2A is being supplied by either USST-2C or SSST-2A.

C.

[ACB-2E7], 4KV Emer Bus 2AE to 4KV Bus 2A, is open.

D.

If the diesels are solely supplying the emergency busses due to a loss of offsite power, confirmation of grid stability has been received from system operations, and permission to return to the grid has been granted by Operations management. (C.2)

IV.

INSTRUCTIONS Note:

All switches, controls and meters are located on BB-C unless otherwise noted.

A.

Parallel the 4KV Bus 2A and Emergency 4KV Bus 2AE as follows:

1.

Close [ACB-2A10], 4KV Bus 2A to Emer Bus 2AE.

(1)

I Initial I Date (2)

I Initial I Date SNote:

When Synchronizing Selector switch is placed in the Bus 2A position, diesel speed will drop due to introduction of speed droop.

2.

Place 2-1 Emer Gen Synchronizing Selector switch to Bus 2A position.

3.

Adjust [2EGS*EG2-1], Emergency Diesel Generator 2-1 speed with the 2-1 Emer Gen Governor Control to cause the 2-1 Emergency Generator Synchroscope (VB C) needle to rotate slowly in the fast direction.

4.

Adjust [2EGS*EG2-1], Emergency Diesel Generator 2-1 output voltage, as indicated on 2-1 Emer Gen Volts, to read slightly higher than the 4KV Bus 2A Volts (VB-C), using Emer Gen 2-1 Voltage Adjust.

1N:

THERE IS NO OUT-OF-PHASE PROTECTION RELAYING TO PREVENT AN OUT-OF-PHASE SYNCHRONIZATION ATTEMPT. AN OUT-OF-PHASE ATTEMPT WILL JEOPARDIZE AND/OR DAMAGE THE EMERGENCY POWER SYSTEM.

5.

With the synchroscope rotating slowly in the fast direction (VB-C), WHEN both synchronizing lights are completely dark AND the synchroscope needle is at the 12 o'clock position, place [ACB-2E7], 4KV Emer Bus 2AE to Bus 2A (BB-C), in the CLOSE position.

(1)

I Initial I Date (2) 1 Initial I Date

6.

Place 2-1 Emer Gen Synchronizing Selector switch to OFF.

(1)

I Initial I Date (2)

I Initial I Date

7.

Maintain generator power factor between.8 and 1.0 lagging by adjusting 2-1 Emer Gen Voltage Adjust.

Beaver Valley Power Station Unit 2 2OM-36.4.E 4KV Station Service System O

R A

USE Revision 8 Operating Procedures TRAINING ONLY Page 3 of 6 TRANSFERRING 4KV EMERGENCY BUS 2AE TO BUS 2A

B.

Remove the [2EGS*EG2-1], Emergency Diesel Generator 2-1, from service as follows:

1.

Reduce [2EGS*EG2-1], Emergency Diesel Generator 2-1, load UNTIL < 100 KW is indicated on 2-1 Emergency Generator Watts (VB-C) by placing 2-1 Emer Gen Governor Control to LOWER.

2.

Open [ACB-2E10], 2-1 Emer Gen Output Bkr.

3.

Verify 4KV Bus 2AE Volts is within the limits listed in 20M-36.2.A, "Precautions And Limitations".

(1) 1 Initial I Date (2) 1 Initial I Date

4.

Shutdown [2EGS*EG2-1], Emergency Diesel Generator 2-1, in accordance with 20M-36.4.AF, "Emergency Diesel Generator [2EGS*EG2-1] Start-up And Shutdown,,.(C-1)

Performed By Verified By Reviewed By Date NSSIANSS Route the completed copy of this procedure to document control via the Operations clerk's daily transmittal.

Beaver Valley Power Station Unit 2 20M-36.4.E 4KV Station Service System LY Revision 8 Operating Procedures FOR TRAINING USE ON Page 4 of 6 TRANSFERRING 4KV EMERGENCY BUS 2AE TO BUS 2A

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom BVPS Unit 2 Task No.:

0535-010-04-013 0021-004-01-013 Respond to Failed Power Range Channel N-44 JPM No.:

2002 NRC S7 051A2.01 (3.5/3.9) 015A2.02 (3.1/3.5)

NRC Examiner:

Date:

Simulator Actual Performance:

X Plant X

READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The plant is operating at 46% power following the failure of a power range channel.

The actions required to stabilize the plant following the failure have been taken.

Reactor power, turbine power and Tavg are all stable at their current values.

"* Tavg is within one degree of Tref, and the control rods are in

'Manual'.

"* The bypass feedwater regulating valves are in 'Manual'.

"* All other systems are operating normally.

The failed power range channel is bypassed per AOP-2.2.1C.

None 20M-53C.4.2.2.1C, Power Range Channel Malfunction, Issue 1A, Rev. 6 20M-53C.42.2.1C, Rev. 6 The Unit Supervisor directs you to bypass the failed power range channel in accordance with AOP-2.2.1C.

No 15 minutes NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #S7

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S7 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Standard:

Check if malfunction of one power range channel has occurred.

Candidate verifies N-44 has failed high.

Candidate determines no other power range channel has failed.

Comment:

Performance Step: 2 Standard:

Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months remove control power fuses from Drawer "A" of channel N-44.

Removes control power fuses from N-44 Drawer "A".

Comment:

Performance Step: 3 Standard:

Standard:

Place "Rod Stop Bypass Switch" in 'N-44' position.

Places "Rod Stop Bypass Switch" in 'N-44' position.

Verifies Overpower Rod Stop Bypass Status Light is lit.

Comment:

Performance Step: 4 Standard:

Check reactor power greater than 50%.

Locates NIS channels and verifies power is less than 50%.

Comment:

Performance Step: 5 Standard:

Place "Comparator Channel Defeat Switch" in 'N-44' position.

Places "Comparator Channel Defeat Switch" in N-44 position.

Comment:

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #S7

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC S7 Performance Step: 6 Standard:

Ensure Vertical Board recorders are selected to monitor only operable detectors.

Checks NIS vertical board recorders to ensure N-44 is not selected.

Comment:

Performance Step: 7 Standard:

Comment:

Terminating Cue:

Refer to T.S. 4.2.1.1.b.

Reports N-44 bypassed and states that axial flux needs to be monitored per T.S. 4.2.1.1.b.

CUE:

As Supervisor, inform Candidate that another Operator will be asked to monitor axial flux and refer to Technical Specifications.

When the Candidate reports that N-44 is bypassed refers to the T.S. actions, evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S7

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC S7 Job Performance Measure No.:

2002 NRC S7 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S7

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC S7 INITIAL CONDITIONS:

INITIATING CUE:

"* The plant is operating at 46% power following the failure of a power range channel.

"* The actions required to stabilize the plant following the failure have been taken.

"* Reactor power, turbine power and Tavg are all stable at their current values.

"* Tavg is within one degree of Tref, and the control rods are in 'Manual'.

"* The bypass feedwater regulating valves are in 'Manual'.

"* All other systems are operating normally.

The Unit Supervisor directs you to bypass the failed power range channel in accordance with AOP-2.2.1C.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #S7

Recoid TI* A.350C DUQUESNE LIGHT COMPANY Beaver Valley Power Station UNIT 2 FOR TRAINING USE ONLY 20M-53C.4.2.21C(ISSIA)

Power Range Channel Malfunction Issue IA Revision 6 Prepared by Date Pages Issued Effective Date M. P. Flynn 09/06/96 1 through 6 SEP 2 3 1996 Reviewed by Date Validated by Date C. O'Neill 09106196 N/A OSC Meeting No.

Date Appromvd by Date BV-OSC-38-96 09/18196 67**

."i*/

20N-53C.4.2.2.IC(ISSIA)

"Number Title 2.2.1C Power Range Channel Malfunction Issue UA Revision 6 FOR TRAINING USE A. PURPOSE This procedure provides instructions for power range channel malfunctions in Modes 1 and 2.

B. SYMPTOMS OR ENTRY CONDITIONS Failure of channel may be evidenced by any of the following:

1. Erratic indication

2. Loss of indication

3. Drift of indication or trip settings

4. Unexplained trips

5. Loss of supply voltages

6. Annunciator alarms C. AUTOMATIC ACTIONS Depending on type of failure, any of the following may occur:

1. Reactor trip

2. Rod withdrawal stop AOP221C g16196 1 of 6 BVPS - AOP Ilof 6 A0P221C 9/6/96

BVPS - AOP 20M-53C.4.2.2.1C(ISS1A)

Number Title 2.2.1C Power Range Channel Malfunction Issue 1A Revision 6 TEP J

ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

1.

Check If Malfunction Of One Power IE malfunction of more than one Ranae Channel (N-41.

N-42, N-43, Power Range Channel, TIEN refer to N-44) Has Occurred T.S. 3.3.1.1, "Reactor Trip System Instrumentation".

a. Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , trip nuclear bistables by removing control power supply fuses from drawer A of failed channel.

b.

.E Power Range Channel 4 (N-44)

fails, HJUN perform the following:

1)

Place Control Rod Group Selector switch in MAN.

2)

Place [2FWS*FCV479,489,499],

21A(B) (C) SG Feedwater Bypass Control Vlvs in MANUAL.

c. At NIS Rack N50, "Detector Current Comparator," turn Rod Stop Bypass Switch to BYPASS on the failed channel.

1)

Verify appropriate Status Light, "Overpwr Rod Stop Bypass" (Status Light Panel 308, A-14, B-14. C-14, D-14)

- LIT FOR FAILED CHANNEL

d. Check reactor power - GREATER

d. GO TO Step 1.g.

THAN 50-.

e. Determine if Power Range Channel upper and lower detector inputs to QPTR are operable in accordance with 20ST-2.4A, "Quadrant Power Tilt Ratio Manual Calculation".

FOR TRAINING USE 0 LN (step continued next page)

AOP22IC 9/6/96 2 of 6 I

2 of 6 AOP221C 9/1/96

20N-53C.4.2.2.1C(ISSIA)

Number Title 2.2.1C Power Range Channel Malfunction Issue IA Revision 6 STEPJ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1.

(continued from previous page)

f. All Power Range Channel upper and f. Perform the following:

lower detector inputs to QPTR OPERABLE

1)

Turn Upper Section Comparator Defeat Switch to failed channel (NIS Rack).

2)

Turn Lower Section Comparator Defeat Switch to failed channel (NIS Rack).

g. At NIS Rack N37/N46, "Comparator and Rate", turn Comparator Channel Defeat Switch to failed channel.

h. Ensure vertical board recorders are selected to monitor only, operable detectors.

i. For failure of Power Range Channels N-41, N-42, N-43. place appropriate Delta T protection bistable switches in tripped position as follows:

1)

Obtain Keys 117(118) for process rack doors.

2)

Refer to Attachment 1, "Delta T Protection Bistable Switch List".

j. Check reactor power - GREATER

j.

GO TO Step 1.1.

THAN 50%.

FOR TRAINING USE ONLY (step continued next page)

AOP221C 9/6196 3 of 6 BVPS -

AOP 3 of 6 A0P221C 9/6/96

20M-53C.4.2.2.IC(ISSIA)

Number Title 2.2.1C Power Range Channel Malfunction Issue 1A Revision 6 ISTEP1 I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

1.

(continued from previous page)

k. Perform one of the following (refer to T.S. 3.3.1.1):

"* If 4 power range channel inputs to QPTR remain operable, perform Technical Speci fi cation Surveillance Requirement 4.2.4.a.

- OR With THERMAL POWER greater than 75% RATED THERMAL POWER AND less than 4 power range channel inputs to QPTR operable, perform Technical Specification Surveillance Requirement 4.2.4.b.

- OR Reduce THERMAL POWER to less than or equal to 75% RATED THERMAL POWER within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of placing failed channel In trip MAN perform Technical Specification Surveillance Requirement 4.2.4.a.

- OR

"* Place plant in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of channel mal functi on.

1. Refer to T.S. 4.2.1.1.b.

1) Monitor and trend Axial Flux Difference in accordance with O

USE 201M-49.4.C, "Axial Flux FOR TRAINING LE Difference Monitoring".

END -

AOP221C 916/96 4 of 6 BVPS -

AOP AOP221C 916/96 4 of 6

2o0-53C.4.22. 1C(ISSIA)

Number Title 2.2.1C Power Range Channel Malfunction Issue 1A Revision 6 Attachment I Delta T Protection Bistable Switch List

1. Power Range Channel I (N-41)

Protection - Channel 1 Protection Cabinet No. 1 C1-421 BS-3 and BS-4

"* 2TS/412C-1 (BS-3) Protection Rack Cl CF-4 Slot 21 Over Temp Delta T Rx Trip

"* 2TS/412C-2 (BS-4) Protection Rack C1 CF-4 Slot 21 Over Temp Delta T Rod Stop

2. Power Range Channel 1I (N-42)

Protection - Channel 2 Protection Cabinet No. 2 C2-421 BS-3 and BS-4

"* 2TS/422C-1 (BS-3) Protection Rack C2 CF-4 Slot 21 Over Temp Delta T Rx Trip

"* 2TS/422C-2 (BS-4) Protection Rack C2 CF-4 Slot 21 Over Temp Delta T Rod Stop

3. Power Range Channel III (N-43)

Protection - Channel 3 Protection Cabinet No. 3 C3-721 BS-3 and BS-4

"* 2TS/432C-1 (BS-3) Protection Rack C3 CF-7 Slot 21 Over Temp Delta T Rx Trip

"* 2TS/432C-2 (BS-4) Protection Rack C3 CF-7 Slot 21 Over Temp Delta T Rod Stop FOR TRAINING USE ONL AOPZ2IC 9/6196 5 of 6 BVPS - AOP 5 of 6 AOP221C 9/6/96

Appendix C Page 1 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P1 BVPS UNIT 2 Respond to a SFP Low Level Alarm Task No.:

0201-004-01 013 JPM No.:

2002 NRC P1 K/A

Reference:

033A2.03 (3.1/3.5)

NRC Examiner:

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

X Classroom Actual Performance:

Simulator Plant X

READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

The plant is in Mode 1 and the Spent Fuel Pool Level Low alarm is LIT.

Spent Fuel Pool level indicates less than 172". The cause of the Spent Fuel Pool low level is normal evaporation.

The running and standby Fuel Pool Purification Pumps have been placed in Pull-To-Lock.

Respond to a Spent Fuel Pool Level Low alarm, performing corrective actions until makeup can begin using the RWST cooling water pump.

None 20M-20.4.AAB, Spent Fuel Pool Level High/Low, Rev. 2 2OM-20.4.G, Makeup To the Spent Fuel Pool, Rev. 7 20M-20.4.G, Revision 7 The US directs you to coordinate with the PO and perform the actions of procedure 20M-20.4.G, Makeup To The Spent Fuel Pool to add water to the Spent Fuel Pool from the RWST.

NO 15 minutes (Denote Critical Steps with an asterisk)

BVPS NRC JPM #P1 Facility:

Task

Title:

Date:

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P1 (Denote Critical Steps with an asterisk)

Performance Step: 1 Standard:

Comment:

Performance Step: 2 Standard:

Obtain the Power Station key for [2QSS-26], Refueling Water Cooling Pumps Discharge to Fuel Pool Cooling.

Obtains key.

CUE: Simulate providing Candidate with key.

If necessary, Secure Fuel Pool Purification.

No action required. Task already performed.

Comment:

Performance Step: 3 Standard:

Check Open [2FNC-40(41)], Purif Pump [2FNC-P24A(B)] to Ion Exch [2FNCIOE21] Isol.

Locates valve(s) in Fuel Bldg 733' and checks open.

Comment:

Performance Step: 4 Standard:

Comment:

Open [2QSS-26] (LS), Refueling Wtr Cooling Pump Disch to Fuel Pool Cool Sys, (SFGDS North 718') to begin makeup to the Spent Fuel Pool.

Locates and opens [2QSS-26].

CUE: After the valve has been opened, inform the candidate that the desired quantity of water has been added.

BVPS NRC JPM #P1

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P1 Performance Step: 5 Standard:

Comment:

Terminating Cue:

Close AND Lock [2QSS-26], Refueling Water Cooling Pumps Disch to Fuel Pool Cool Sys, (SFGDS North 718').

Closes [2QSS-26] and secures lock in place.

Requests a second operator verify lock is in place. (Not critical)

CUE: Inform the candidate that an independent verification will be performed as requested.

When the candidate requests an independent verification for 2QSS-26, the evaluation for this JPM is complete.

BVPS NRC JPM #P1

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC P1 Job Performance Measure No.:

2002 NRC P1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

BVPS NRC JPM #P1

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC P1 INITIAL CONDITIONS:

INITIATING CUE:

The plant is in Mode 1 and the Spent Fuel Pool Level Low alarm is LIT. Spent Fuel Pool level indicates less than 172". The cause of the Spent Fuel Pool low level is normal evaporation.

The running and standby Fuel Pool Purification Pumps have been placed in Pull-To-Lock.

The US directs you to coordinate with the PO and perform the actions of procedure 20M-20.4.G, Makeup To The Spent Fuel Pool to add water to the Spent Fuel Pool from the RWST.

BVPS NRC JPM #P1

A9.330B Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 20M-20.4.G MAKEUP TO THE SPENT FUEL POOL Revision 7 Prepared by Date Pages Issued C. R. Kuhn 03/21/02 1 through 8 Reviewed by Date Validated by Date J. L. Popp 03125/02 N/A OSC Meeting No.

Date OSC Not Required DRR-01-04008

Beaver Valley Power Station Unit 2 2OM-20.4.G Spent Fuel Pool Cooling/Purification System Revision 7 Operating Procedures FOR TRAINING USE P

8 MAKEUP TO THE SPENT FUEL POOL

1.

PURPOSE This procedure provides the steps necessary to makeup to the Spent Fuel Pool using the CHS Blender or the RWST cooling water pumps supplying water from the RWST.

II.

PRECAUTIONS & LIMITATIONS A.

During makeup to the spent fuel pool from the CHS blender, automatic makeup, boration, dilution and alternate dilution of the volume control tank/reactor coolant system will not be available.

Ill.

INITIAL CONDITIONS A.

Makeup using the CHS blender

1.

The Boric Acid Blender [2CHS*BL21] is aligned for automatic operation in accordance with 20M-7.4.J, "Blender Automatic Makeup Operation".

2.

The boric acid tanks contain sufficient boric acid solution to perform a makeup to the spent fuel pool without reducing the inventory below Licensing Requirements 2.7 OR 2.8 requirements.

3.

The CHS blender is not required for other usage during the operation of this procedure.

B.

Makeup from the RWST using the RWST cooling water pump

1.

The RWST contains sufficient inventory to fill the spent fuel pool without violating Technical Specification 3.1.2.8 OR Licensing Requirement 2.7 requirements.

2.

The RWST cooling portion of the quench spray system is available for service with a RWST cooling pump operating.

3.

The boron concentration of the RWST has been checked to ensure that makeup will not dilute the spent fuel pool boron concentration below the minimum requirements.

C.

The purification portion of the fuel pool cooling/purification system is lined up for operation in accordance with section A of either 20M-20.4.A, "Spent Fuel Pool Cooling/Purification System Startup", OR 20M-20.4.D, "Refueling Cavity Purification".

D.

Color coded T-handle wrenches are available in the Auxiliary Building, Elev. 718', for valve operations.

IV.

INSTRUCTIONS A.

Makeup Using Primary Grade Water Note:

e Refer to Tech. Spec. 3.9.15 for minimum boron concentration requirements in the Spent Fuel Pool.

"* A one foot level change in the spent fuel pool is 8000 gallons. A one foot level change in the spent fuel pool and cask area is 10,000 gallons. (Ref.

Unit 2 Curve Book)

"* Each 1000 gallons of primary grade water added to the fuel pool reduces the boron concentration by approximately 7.5 ppm assuming a 2400 ppm initial concentration.

"* Selection of makeup source should be based upon the results of the most recent Chemistry boron analysis results.

1.

Verify at least one Spent Fuel Pool cooling pump [2FNC*P21A and/or 2FNC*P21 B]

is in service.

2.

Obtain BV-2 key.

3.

Inform Unit 1 that PG water will be used for spent fuel pool makeup and the approximate volume to be used.

4.

Throttle Open [2FNC-1 18], PG Water Supply To Spent Fuel Pool (Fuel Bldg 735').

5.

When the spent fuel pool level reaches 765'10" Close AND Lock [2FNC-1 18], PG Water Supply To Spent Fuel Pool (Fuel Bldg 735').

a.

Independently Verify that [2FNC-1 18], PG Water Supply To Spent Fuel Pool, is Locked Closed AND Document in the Daily Journal.

6.

Inform Chemistry of the time and volume of PG Water addition.

B.

Makeup Using the CHS Blender r2CHS-BL21

1.

Obtain the RBIX key from the NSS/ANSS for access to the blender cubicle.

2.

If operating, Secure fuel pool purification flow as follows:

a.

If necessary, Place the control switch for the standby [2FNC-P24B (A)], Fuel Pool Purif Pump, in PULL-TO-LOCK (BB-B).

b.

Stop the running [2FNC-P24A (B)], Fuel Pool Purif Pump, by placing its control switch in PULL-TO-LOCK (BB-B).

Beaver Valley Power Station Unit 2 20M-20.4.G Spent Fuel Pool Cooling/Purification System Revision 7 Operating Procedures FOR TRAINING USE ON3 o8 MAKEUP TO THE SPENT FUEL POOL

3.

Verify Closed, the following valves:

a.

[2FNC-47], Supply to Refueling Water Storage Tank Isol, (MSVA & CV Pen A 718').

b.

[2FNC-28 (29)], Filter [2FNC-FLT21A (B)] to Spent Fuel Pool Isol, (Aux Bldg 718').

c.

[2FNC-35 (36)], Filter [2FNC-FLT21A (B)] to Refueling Cavity Isol, (Aux Bldg 718').

d.

[2FNC-84 (24)], Filter [2FNC-FLT 21B (A)] Inlet Isol, (Aux Bldg 718').

4.

Place the control switch for [2CHS*FCV1 13B], Boric Acid Blender Disch to Chg Pumps, in the CLOSE position, (BB-A).

a.

Verify that its green (closed) indicating light is ON.

5.

Place the control switch for [2CHS*FCV1 14B], Blender Outlet to Volume Control Tank, in the CLOSE position, (BB-A).

a.

Verify that its green (closed) indicating light is ON.

6.

Verify Open the following valves:

a.

[2CHS*87], Blender to Refueling Cavity Isolation (Aux Bldg 710' Blender Rm).

b.

[2CHS*89], Blender to RWST Isolation (Aux Bldg 710, Blender Rm).

c.

[2FNC-36 (35)], Filter [2FNC-FLT21 B (21A)] to Refueling Cavity Isol (Aux Bldg 718').

d.

[2FNC-29 (28)], Filter [2FNC-FLT21 B (A)] to Spent Fuel Pool, (Aux Bldg 718').

7.

Refer to 20M-7.4.N, "Blender Manual Makeup Operations" and carry out the steps for Manual Blended Makeup with the following exceptions:

a.

Use spent fuel pool boron concentration instead of the RCS boron concentration.

b.

DO NOT open [2CHS*FCV113B], Boric Acid Blender Disch to Chg Pumps.

Makeup to the spent fuel pool will start when the Boric Acid Makeup Blender Control Switch is placed in the START position.

8.

When makeup is complete, Close the following valves:

a.

[2CHS*87], Blender to Refueling Cavity Isolation (Aux Bldg 710' Blender Rm).

1) Independently Verify that [2CHS*87], Blender to Refueling Cavity Isolation, is Closed AND Document in the Daily Journal.

Beaver Valley Power Station Unit 2 20M-20.4.G Spent Fuel Pool Cooling/Purification System Revision 7 Operating Procedures Page 4 of 8 FOR TRAINING USE ONLY MAKEUP TO THE SPENT FUEL POOL

b.

[2CHS*89], Blender to RWST Isolation (Aux Bldg 710' Blender Rm).

1)

Independently Verify that [2CHS*89], Blender to RWST Isolation, is Closed AND Document in the Daily Journal.

9.

Place the makeup control system in automatic in accordance with 20M-7.4.J, "Blender Automatic Makeup Operation".

10. Place OR Verify fuel pool purification valves in the specified positions as follows:

a.

Open [2FNC-28], Filter [2FNC-FLT21A] to Spent Fuel Pool Isol, (Aux Bldg 718').

b.

Open [2FNC-29], Filter [2FNC-FLT21 B] to Spent Fuel Pool Isol, (Aux Bldg 718').

c.

Open [2FNC-24], Filter [2FNC-FLT 21A] Inlet Isol, (Aux Bldg 718').

d.

Open [2FNC-84], Filter [2FNC-FLT 21B] Inlet Isol, (Aux Bldg 718').

e.

Close [2FNC-35], Filter [2FNC-FLT21A] to Refueling Cavity Isol (Aux Bldg 718').

f.

Close [2FNC-36], Filter [2FNC-FLT21 B] to Refueling Cavity Isol (Aux Bldg 718').

11. If desired, Resume operation of the fuel pool purification system in accordance with 20M-20.4.A, "Fuel Pool Cooling/Purification System Startup", OR 2OM-20.4.D, "Refueling Cavity Purification".

C.

Makeup From the RWST Using the RWST Cooling Water Pump

1.

Obtain the power station key for [2QSS-26], Refueling Water Cooling Pumps Discharge to Fuel Pool Cooling.

2.

If operating, Secure fuel pool purification flow as follows:

a.

If necessary, place the control switch for the standby [2FNC-P24B (A)], Fuel Pool Purif Pump, in PULL-TO-LOCK (BB-B).

b.

Stop the running [2FNC-P24A (B)], Fuel Pool Purif Pump, by placing its control switch in PULL-TO-LOCK (BB-B).

3.

Check Open [2FNC-40 (41)], Purif Pump [2FNC-P24A (B)] to Ion Exch

[2FNC-IOE21] Isol (Fuel Bldg 733').

4.

Open [2QSS-26](LS), Refueling Wtr Cooling Pump Disch to Fuel Pool Cool Sys, (SFGDS North 718'), to begin makeup to the spent fuel pool.

Beaver Valley Power Station Unit 2 20M-20.4.G Spent Fuel Pool Cooling/Purification System Revision 7 Operating Procedures FOR TRAINING USge5of8 MAKEUP TO THE SPENT FUEL POOL USE ONLY

5.

When the spent fuel pool reaches the desired level, Close AND Lock [2QSS-26],

Refueling Water Cooling Pumps Discharge to Fuel Pool Cool Sys, (SFGDS North 718').

a.

Independently Verify that [2QSS-26], Refueling Wtr Cooling Pump Disch to Fuel Pool Cool Sys, is Locked Closed AND Document in the Daily Journal.

6.

If desired, Resume operation of the fuel pool purification system in accordance with 20M-20.4.A, "Fuel Pool Cooling/Purification System Startup", OR 20M-20.4.D, "Refueling Cavity Purification".

Beaver Valley Power Station Unit 2 20M-20.4.G Spent Fuel Pool Cooling/Purification System Revision 7 Operating Procedures Page 6 of 8 MAKEUP TO THE SN FL P FOR TRAINING USE ONLY

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task No.:

0241-024-01 043 JPM No.:

2002 NRC P2 K/A

Reference:

061A2.04 (3.4/3.8)

Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

X Classroom NRC Examiner:

Date:

Actual Performance:

Simulator Plant X

READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

S 0

S S

The plant is in Mode 1 at 50% power.

The turbine driven auxiliary feedwater pump has tripped due to an overspeed condition.

The problem has been corrected.

A Plant Operator has verified that the trip and throttle valve is closed.

No start signal exists for 2FWE*P22 and the pump is stopped.

The pump is not required to feed the steam generators.

2FWE*P22 trip and throttle valve reset per 2OM-24.4.

None 20M-24.4.R, Resetting And Opening TDAFW Pump Trip And Throttle Valve, Rev. 15 20M-24.4.R, Rev. 15 The Unit Supervisor directs you to reset the trip and throttle valve for 2FWE*P22.

No 10 minutes NUREG 1021, Revision 8, Supplement 1 Facility:

Task

Title:

BVPS Unit 2 Reset the Terry Turbine Trip/Throttle Valve BVPS NRC JPM #P2

Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P2 (Denote Critical Steps with an asterisk)

Performance Step: I Standard:

Comment:

Performance Step: 2 Standard:

Standard:

Verify tripped or manually trip overspeed mechanism.

Locates manual emergency trip lever and simulates pressing it.

CUE:

The steam supply valves 2MSS*SOV105A, (B), (C),

(D), (E) and (F) are closed.

To open the trip and throttle valve, turn the handwheel in the clockwise direction until it is fully down (CLOSED).

Locates the trip and throttle valve handwheel.

Simulates turning it in the clockwise direction to raise the latch to engage the valve.

Comment:

Performance Step: 3 Standard:

Reset overspeed trip device.

Candidate simulates resetting overspeed trip device by:

"* Holding overspeed trip connecting rod to the left.

"* Ensuring overspeed tappet washer flat side line up with the overspeed trip lever (scribe mark on washer is aligned with punch mark on tappet housing).

"* Release connecting rod, allowing spring tension to maintain reset condition.

"* Ensuring washer flat edge is flush against vertical side of overspeed trip lever.

Comment:

Performance Step: 4 Standard:

Standard:

Comment:

Verify the valve is latched by observing the latch on the right side of the valve.

Locates the latch on the right side of the valve.

Verifies that it has engaged the latch hook.

Calls US to tell him that this requires an independent verification.

CUE:

The US will assign another Operator to perform independent verification.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #P2

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P2

"* Performance Step: 5 Standard:

Standard:

Comment:

Performance Step: 6 Standard:

Standard:

Reopen the trip throttle valve by turning the handwheel counterclockwise.

Locates throttle valve handwheel.

Simulates turning it counterclockwise.

Continues turning until the valve stops in the full open position.

Informs US of need for independent verification.

CUE: The US will assign another Operator to perform independent verification.

To prevent thermal binding of Trip Throttle valve, crack valve off its back seat by % turn.

Locates trip throttle valve.

Simulates 1/4-turn clockwise to prevent thermal binding.

Comment:

Performance Step: 7 Standard:

Standard:

Comment:

Terminating Cue:

Push both pushbuttons to dump oil from the governor to preclude overspeed of the Terry Turbine on a restart. Observe governor linkage until movement ceases or hold for 15 seconds.

Locates pushbuttons for governor oil dump.

Simulates depressing both pushbuttons simultaneously.

Holds pushbuttons until linkage movement ceases or 15 seconds has elapsed.

CUE: All governor linkage movement has stopped. (15 seconds has elapsed, if asked).

CUE: 2FWE*P22 is not needed to control steam generator level.

When the candidate has verified that linkage movement stops, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #P2

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC P2 Job Performance Measure No.:

2002 NRC P2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #P2

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET 2002 NRC P2 INITIAL CONDITIONS:

INITIATING CUE:

"* The plant is in Mode 1 at 50% power.

"* The turbine driven auxiliary feedwater pump has tripped due to an overspeed condition.

"* The problem has been corrected.

"* A Plant Operator has verified that the trip and throttle valve is closed.

"* No start signal exists for 2FWE*P22 and the pump is stopped.

"* The pump is not required to feed the steam generators.

The Unit Supervisor directs you to reset the trip and throttle valve for 2FWE*P22.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPMV #P2

A9.330B Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 20M-24.4.R RESETTING AND OPENING TDAFW PUMP TRIP AND THROTTLE VALVE Revision 15 Prepared by Date Pages Issued Effective Date W. K. Giffrow 09117101 1 through 12 Reviewed by Date Validated by Date J. Bumecke 09118101 N/A OSC Meeting No.

Date Approved by Date OSC Not Required

Beaver Valley Power Station Unit 2 20M-24.4.R Steam Generator Feedwater System TRAIING I

Xevision 15 Operating Procedures FOR TRAINING USE

?lage 2 of 12 RESETTING AND OPENING TDAFW PUMP TRIP AND THROTTLE VALVE PURPOSE This procedure provides instructions to perform the following:

"* Reset the [2FWE-P22], Steam Driven Auxiliary Feedwater Pump, overspeed trip device.

"* Relatch and Open [2FWE-TTV22], Trip and Throttle Valve for 2FWE*P22.

"* Close and Open [2FWE*T-V22], Trip and Throttle Valve for 2FWE*P22, to support testing.

This procedure may be entered from an EOP or an AOP.

I1.

PRECAUTIONS AND LIMITATIONS A.

WHEN resetting the overspeed trip device tappet assembly, the FLAT SIDE of the overspeed tappet washer must be flush against the vertical side of the overspeed trip lever (Figure 1). If the overspeed mechanism is NOT in this configuration when reset, it may result in bowing of the tappet, which could render the overspeed trip device inoperable.

B.

If [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, is being reset following a trip, the valve should be opened slowly to ensure any trapped pressure does not cause an overspeed trip.cl C.

Opening [2MSS*SOV1 05A or B], Turb Driven AFW Pump Stm Hdr A(B) Supply Isol, will cause isolation of steam generator blowdown and blowdown sample lines.

D.

Relieving the governor oil pressure prior to opening [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, will preclude an overspeed condition during a startup within 15-20 minutes of a pump shutdown.

Ill.

INITIAL CONDITIONS A.

[2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, AND/OR the Overspeed Trip Device, is required to be restored to its normal configuration.

OR B.

It is necessary to close [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, to support testing.

OR C.

The overspeed trip device is suspected of being NOT properly reset ANDIOR

[2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, is suspected of being NOT properly latched.

Beaver Valley Power Station Unit 2 2OM-24.4.R Steam Generator Feedwater System tUkuI pvision 15 Operating Procedures FOR T INING USl. LPIge3of 12 RESETTING AND OPENING TDAFW PUMP TRIP AND THROTTLE VALVE IV.

INSTRUCTIONS A.

Resetting The Overspeed Trip Device SNote:

"Initial/Date" Verification signoffs in Part A may be left blank if Part A is not performed.

1.

If [2FWE*P22], Turbine Driven Aux Feed Pump, is being placed in standby, Close or Verify Closed the following valves:

a.

[2MSS*SOV105A], Turbine Driven AFW Pump Stm Hdr A Supply Isol.

b.

[2MSS*SOV105B], Turbine Driven AFW Pump Stm Hdr B Supply Isol.

c.

[2MSS*SOV105C], Turbine Driven AFW Pump Stm Hdr C Supply Isol.

d.

[2MSS*SOV105D], Turbine Driven AFW Pump Stm Hdr A Supply Isol.

e.

[2MSS*SOV105E], Turbine Driven AFW Pump Stm Hdr B Supply Isol.

f.

[2MSS*SOV105F], Turbine Driven AFW Pump Stm Hdr C Supply Isol.

2.

Verify tripped OR manually trip the Overspeed Trip Mechanism by performing one of the following:

a.

To perform a trip locally, press the Manual Emergency Trip Lever.

OR

b.

To perform a trip from the Unit 2 Control Room, depress the Turbine Driven AFW Pump Trip pushbutton. (BB-C)

3.

Verify [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, is unlatched.

4.

If [2FWE*P22], Turbine Driven Auxiliary Feedwater Pump, will be restarted within the next 15 to 20 minutes, Relieve the governor oil pressure by performing the following:

a.

Loosen wingnuts and remove cover for access to [2FWE-CSSOV101],

Governor Oil Dump pushbuttons.

b.

Depress AND Hold [2FWE-CSSOV101], Governor Oil Dump pushbuttons simultaneously for at least 15 seconds.

c.

Release the pushbuttons and replace the cover for [2FWE-CSSOV101].

Note:

Refer to Figure 1, for detailed view of the overspeed trip device.

5.

Reset the Overspeed Trip Mechanism by performing the following:

a.

Hold the overspeed trip connecting rod to the left.

Beaver Valley Power Station Unit 2 2OM-24.4.R Steam Generator Feedwater System Revision 15 Operating Procedures FOR TRAINING USE ONL ge 4 of 12 RESETTING AND OPENING TDAFW PUMP TRIP AND THROTTLE VALVE

b.

Verify the overspeed tappet washer flat side directly faces the overspeed trip lever.

c.

Gently release the connecting rod and allow the spring tension to maintain the reset condition.

d.

Verify that the flat side of the washer is flush against the vertical side of the overspeed trip lever.

6.

Latch [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, by turning the handwheel in the clockwise direction UNTIL the sliding nut and trip lever raise AND engage with the trip hook.

Note:

The following instruction will start [2FWE*P22], Turbine Driven Aux Feed Pump, if steam is aligned from [2MSS*SOV105F and C(E and B)(D and A)],

Turb Driven AFW Pump Stm Hdr Supply Isol Valves.

The pump will accelerate when [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, is opened, regardless of whether steam is aligned. Residual pressure in the steam supply line is sufficient to cause acceleration after the steam supply has been isolated.

7.

Slowly Open [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, by turning the handwheel counterclockwise AND Verify pump does NOT accelerate in an uncontrolled manner.

Note:

Concurrent verification of [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, shall be completed with 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of completion of adjustment in the following instruction.

8.

Perform the following:

a.

Adjust [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, / turn off of the backseat.

b.

Verify the overspeed trip mechanism is reset.

c.

Verify PCS Computer Point Y5172D, "TURB DR AFW PP TRIPPED FWE*P22", indicates OPER.

9.

If not previously performed, Relieve the governor oil pressure by performing the following:

a.

Loosen wingnuts and remove cover for access to [2FWE-2CSSOV101],

Governor Oil Dump Pushbuttons.

Beaver Valley Power Station Unit 2 2OM-24.4.R Steam Generator Feedwater System FTNU I!

9 vision 15 Operating Procedures FOR TRAINING USE ONLPve5of 12 RESETTING AND OPENING TDAFW PUMP TRIP AND THROTTLE VALVE

b.

Depress AND Hold [2FWE-2CSSOV101], Governor Oil Dump Pushbuttons (2) simultaneously.

c.

WHEN 15 seconds has passed AND all governor linkage movement has ceased, Release the pushbuttons.

d.

Replace cover and tighten wingnuts on access cover for [2FWE-2CSSOV1 01],

Governor Oil Dump Pushbuttons.

10. Notify the Unit 2 Control Room Operator that [2FWE*P22], Turbine Driven Aux Feed Pump, is available.

11. WHEN the plant is stable and operators are available, perform the following:

a.

Adjust and Concurrently Verify [2FWE*TTV22], Trip and Throttle Valve for 2FWE*P22, 1/4 turn off of the backseat.

(1)

I Initial I Date (2)

I Initial I Date

b.

Verify the overspeed trip mechanism is reset.

(1)

I Initial Date (2) 1 Initial I Date

c.

Verify PCS Computer Point Y5172D, "TURB DR AFW PP TRIPPED FWE*P22", indicates OPER.

I Initial I Date

12. Verify the following:

a.

[2MSS*SOV105A], Turbine Driven AFW Pump Stm Hdr A Supply Isol, is Closed.

(1) 1 Initial I Date (2) 1 Initial I Date

Beaver Valley Power Station Unit 2 20M-24.4.R Steam Generator Feedwater System V

USE a

i~evision 15 Operating Procedures FOR TRAINING UILlRage6of12 RESETTING AND OPENING TDAFW PUMP TRIP AND THROTTLE VALVE

b.

[2MSS*SOV105B], Turbine Driven AFW Pump Stm Hdr B Supply Isol, is Closed.

(1) 1 Initial I Date (2)

I Initial I Date

c.

[2MSS*SOV105C], Turbine Ddven AFW Pump Stm Hdr C Supply Isol, is Closed.

(1)

I Initial I Date (2)

I Initial / Date

d.

[2MSS*SOV105D], Turbine Driven AFW Pump Stm HdrA Supply Isol, is Closed.

Initial Date (2)

I Initial I Date

e.

[2MSS*SOV105E], Turbine Driven AFW Pump Stm Hdr B Supply Isol, is Closed.

(1),

1 Initial I Date (2)

I Initial I Date

f.

[2MSS*SOV105F], Turbine Driven AFW Pump Stm Hdr C Supply Isol, is Closed.

(1)

I Initial I Date (2) 1 Initial I Date

FIGURE 1 SDAFW OVERSPEED RESET FIGURE 1 Beaver Valley Power Station Unit 2 2OM-24.4.R Steam Generator Feedwater System AIIGision15 Operating Procedures tOR INIUSE v.N, lTl-pae9of12 RESETTING AND OPENING TDAFW PUMP TRIP AND THROTTLE VALVE

FIGURE 2 TERRY TURBINE TRIP VALVE LATCH FIGURE 2 Beaver Valley Power Station Unit 2 20M-24.4.R Steam Generator Feedwater System T A IG PIeyision 15 Operating Procedures FOR TRAINING USE O YI 10 of 12 RESETTING AND OPENING TDAFW PUMP TRIP AND THROTTLE VALVE

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Task

Title:

K/A

Reference:

BVPS Unit 2 Place SSPS Train in Service 012A4.02 (3.3/3.4)

Task No.:

JPM No.:

0011-059-01-013 2002 NRC P3 Examinee:

Facility Evaluator:

Method of testing:

Simulated Performance:

Classroom NRC Examiner:

Date:

X Simulator Actual Performance:

Plant X

READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Task Standard:

Required Materials:

General

References:

Handouts:

Initiating Cue:

Time Critical Task:

Validation Time:

"* The plant is in Mode 5.

"* The Unit Supervisor has determined that Train "A" of SSPS is to be placed in service.

"* Train "B" of SSPS is already in service. The initial conditions of 20M-1.4.1, have been satisfactorily completed.

"* No ESF instrumentation is being tested.

Train "A" of SSPS returned to service per 2CM-1.4.1.

Simulated Keys 2CM-1.4.1, Solid State Protection System Alignments, Issue 4, Rev. 13 2CM-1.4.1, Rev. 13 (markup copy)

The Unit Supervisor directs you to place Train "A" of SSPS into service by performing 2CM-1.4.1, Attachment "D", Steps 3 through 14.a.

NO 15 minutes NUREG 1021, Revision 8, Supplement I N-BVPS NRC JPM #P3

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P3 (Denote Critical Steps with an asterisk)

CAUTION Performance Step: 1 Standard:

Standard:

Inform Candidate that ONLY the Cabinet Doors are to opened, all other manipulations are to be SIMULATED.

Place SSPS Train "A" Multiplexer Test Switch in 'NORMAL'.

Locates [RK*2RC-PRT-A] Logic Cabinet.

Places Train "A" Multiplexer Test Switch in 'NORMAL'.

Comment:

Performance Step: 2 Standard:

Standard:

Place SSPS Train "B" Multiplexer Test Switch in 'NORMAL'.

Locates [RK*2RC-PRT-B] Logic Cabinet.

Places Train "B" Multiplexer Test Switch in 'NORMAL'.

Comment:

Verify the following status lights are illuminated (BB'B).

PRZR LOW PRESS SI BLOCK PERM-CHAN I

PRZR LOW PRESS SI BLOCK PERM-CHAN II

PZRZ LOW PRESS SI BLOCK PERM-CHAN III Locates and verifies illuminated:

PRZR LOW PRESS SI BLCIK PER-CHAN II

PRZR LOW PRESS SI BLOCK PERM-CHAN II

PZRZ LOW PRESS SI BLOCK PERM-CHAN III Comment:

Performance Step: 4 Standard:

Verify all status lights are extinguished on Safeguards System Status Panel (464).

Contacts Control Room to verify all status lights are extinguished.

CUE:

Act as the RO and inform the Candidate that all status lights are extinguished.

NUREG 1021, Revision 8, Supplement I Performance Step: 3 Standard:

Standard:

Comment:

BVPS NRC JPM #P3

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P3 Performance Step: 5 Standard:

Standard:

At [RK*2RC-PRT-A] Logic Cabinet, place the Input Error Inhibit Switch to the 'INHIBIT' position.

Locates [RK*2RC-PRT-A] Logic Cabinet.

Places Input Error Inhibit Switch to 'INHIBIT'.

Comment:

Performance Step: 6 Standard:

Standard:

At [RK*2RC-PRT-A] Output Cabinet, place the Mode Selector Switch to the 'OPERATE' position.

Locates [RK*2RC-PRT-A] Output Cabinet.

Places the Mode Selector Switch to the 'OPERATE' position.

Comment:

Performance Step: 7 Standard:

Standard:

Comment:

Performance Step: 8 Standard:

Comment:

Verify the green light above the Mode Selector Switch has illuminated.

Locates the green light above the Mode Selector Switch.

Verifies it is illuminated.

CUE:

Green light is illuminated.

Place the following switches to the 'BLOCK' position:

PRZR Press SI Train "A".

Steam Line SI Train "A".

Candidate asks RO to place PRZR Press SI Train "A" and Steam Line SI Train "A". switches to Block.

CUE:

Act as the RO and inform the Candidate that the switches were placed in the 'BLOCK' position.

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #P3

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P3 Performance Step: 9 Standard:

Comment:

Performance Step: 10 Standard:

Comment:

Performance Step: 11 Standard:

Depress the following pushbuttons:

Safety Injection Signal Train "A" Reset

SI Recirc Mode Reset Train "A" Candidate asks RO to depress the Safety Injection Signal Train A Reset and SI Recirc Mode Reset Train A pushbuttons.

CUE: Act as the RO and inform the Candidate that the pushbuttons have been depressed.

Verify SI signals are blocked.

Candidate checks or ask RO to check:

"* PRCS point Y3190D, PRZR SI Blocked Train "A" shows

'BLOCK'.

"* PCS point P0402D SLI/SI BIk Train "A" shows 'SET'.

CUE:

Computer point Y3190D shows block and P0402D shows set.

At [RK*2RC-PRT-A] Logic Cabinet, place the Input Error Inhibit Switch to 'NORMAL'.

Candidate:

Locates [RK*2RC-PRT-A] Logic Cabinet.

Places the Input Error Inhibit Switch to 'NORMAL'.

Comment:

NUREG 1021, Revision 8, Supplement I BVPS NRC JPM #P3

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION 2002 NRC P3 Performance Step: 12 Standard:

At [RK*2RC-PRT-A] Logic Cabinet, place the Multiplexer Test Switch to the 'A+B' position.

Candidate places the Multiplexer Test Switch to the 'A+B' position.

Comment:

Terminating Cue:

When the candidate has completed the alignment through step C. 14.a, the evaluation for this JPM is complete.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPMV #P3

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION 2002 NRC P3 Job Performance Measure No.:

2002 NRC P3 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result:

SAT UNSAT Examiner's Signature:

Date:

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #P3

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET 2002 NRC P3 INITIAL CONDITIONS:

INITIATING CUE:

"* The plant is in Mode 5.

"* The Unit Supervisor has determined that Train "A" of SSPS is to be placed in service.

"* Train "B" of SSPS is already in service. The initial conditions of 20M-1.4.1, have been satisfactorily completed.

"* No ESF instrumentation is being tested.

The Unit Supervisor directs you to place Train "A" of SSPS into service by performing 20M-1.4.1, Attachment "D", Steps 3 through 14.a.

NUREG 1021, Revision 8, Supplement 1 BVPS NRC JPM #P3

A9.330B Beaver Valley Power Station Unit 2 FOR TRAINING USE ONLY 20M-1.4.1 SOLID STATE PROTECTION SYSTEM ALIGNMENTS Revision 13 Prepared by Date Pages Issued J. E. Bumecke 12109101 1 through 43 Reviewed by Date Validated by Date J. L. Popp 12/101 N/A OSC Meeting No.

Date OSC Not Required DRR-01-04592

PURPOSE To provide the steps necessary to remove from service or place in service a train of the Solid State Protection System (SSPS), or to align for Instrument and Control testing, in Modes 5 or 6 without inadvertent safeguards actuation.

This procedure may be entered from an Abnormal Operating Procedure.

List of Attachments in this Procedure:

Attachment A: Removing Train A SSPS from Service Attachment B: Removing Train A Output Relay Power Fuses Attachment C: Reinserting Train A Output Relay Power Fuses Attachment D: Returning Train A SSPS to Service Attachment E: Removing Train B SSPS from Service Attachment F: Removing Train B Output Relay Power Fuses Attachment G: Reinserting Train B Output Relay Power Fuses Attachment H: Returning Train B SSPS to Service Attachment J: Removal of SSPS Demultiplexer Relays for I&C Testing Attachment K: Restoration of SSPS Demultiplexer Relays after I&C Testing Attachment L: Input Error Inhibit Switch Continuity Checks II.

PRECAUTIONS & LIMITATIONS A.

Placing the SSPS Mode Selector switch in the TEST position will reset (remove) steamline and pressurizer safety injection signal blocks and in Modes 5 and 6 generate a reactor trip signal to the breakers. ESF actuations are prevented by another function of this switch which is to remove 120VAC power from the output (slave) relays.

B.

Placing any of the following switches out of their normal position will cause a General Warning and alarm ANN A5-2A (3A), 'REACTOR PROTECTION SYSTEM TRAIN A(B)

TROUBLE":

"* Mode Selector Switch (Output Cabinet)

"* Multiplexer Test Switch (Logic Cabinet) (white)

"* Input Error Inhibit Switch (Logic Cabinet) (red)

Beaver Valley Power Station Unit 2 20M-1.4.1 Reactor Control and Protection System FO R INN Ssion 1

Operating Procedures rOR TRAINING USE SOLID STATE PROTECTION SYSTEM ALIGNMENTS

Beaver Valley Power Station Unit 2 UOM-1.4.1 Reactor Control and Protection System i

TR IN N Qsion13 Operating Procedures Tage 3 of 43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS C. CREBAPS manual actuation from the Chlorine Detection CR Isolation Train A and B pushbuttons on 2BSC will be unavailable with both trains of Unit 2 SSPS out of service.

Manual Control Room isolation on a toxic gas release (ref. AOP 1/2.44A.1) is available from the Unit 1 Control Room 1 BSP, independent of Unit I or Unit 2 SSPS status.

D.

Placing the Source Range HV Manual ON/OFF switch in the HV ON position will prevent de-energizing the Source Range instrumentation when the Input Error Inhibit switch is placed in INHIBIT. The Source Range High Flux At Shutdown alarm is not affected by placing the Mode Selector Switch in TEST or by removing the Output Relay Power Fuses.

E. OPPS and the RHS Valve Pressure interlocks will not be affected when the Train A Output Relay Test Mode Selector switch is placed in TEST, provided the 120VAC Output Relay Power fuses remain installed.

F.

Placing the Input Error Inhibit Switch in INHIBIT will cause any non-latching output relay held in by 15 VDC present in "TEST" to drop out.

Beaver Valley Power Station Unit 2 20M-1.4.1 Reactor Control and Protection System R

ision 13 Operating Procedures FOR TRAINING USE ONI 4 of43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS III.

INITIAL CONDITIONS A.

Plant Status Changes

1.

Made INOPERABLE (Technical Specification Items)

a.

If a Solid State Protection System Train is to have its output fuses removed, the Over Pressure Protection System PORVs [2RCS*PCV455C, 456] are INOPERABLE (T.S. 3.4.9.3).

2.

Removed From Service (Non-Technical Specification Items)

NONE

3.

Placed in Failed Condition (Technical Specification Items)

a.

If a Solid State Protection System Train is to be removed from service, THEN:

1)

All Safeguards and Reactor Trip signals from the affected Train are defeated.

2)

CREBAPS initiation from Unit 2 Containment Isolation Phase B will be defeated.

4.

Alignments Affected NONE

5.

Special Considerations NONE B.

NSS/ANSS Sign-on

1.

Unit 2 is in Mode 5, 6 or an undefined mode.

2.

RTA and RTB, Reactor Trip breakers, AND BYA and BYB, Bypass Trip breakers, are open.

3.

Unit 2 NSS/ANSS verifies the following:

a.

Section Ill.A, Plant Status Changes, has been reviewed.

b.

Requirements of Section Il.B, NSS/ANSS Sign-on have been verified.

c.

Performance of this procedure is authorized.

Beaver Valley Power Station Unit 2 20M-1.4.1 Reactor Control and Protection Systemo T

USE ion 13 Operating Procedures rvn TRAIINGP4 S

OJI' e5 of 43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS

d.

Indicate in the NSS/ANSS COMMENTS Section, which attachment(s) is to be performed.

DATE:

/TIME:

CURRENT PLANT MODE:

NSS/ANSS COMMENTS:

UNIT 2 NSS/ANSS SIGNATURE

4.

Unit I NSS/ANSS verifies the following:

a.

If Unit I is in Mode 1, 2, 3 or4, the Unit I CREBAPS initiating signal from Containment Isolation Phase B is OPERABLE OR the applicable action is satisfied.

b.

Requirements of Section Ill.B, NSS/ANSS Sign-on, have been verified.

c.

Performance of this procedure is authorized.

UNIT I NSS/ANSS SIGNATURE C. Reactor Operator Sign-on

1.

Reactor Operator acknowledge procedure performance.

Reactor Operator Signature DATE:

[TIME:

ICURRENT PLANT MODE:

NSS/ANSS COMMENTS:

Beaver Valley Power Station Unit 2 20M-1.4.1 Reactor Control and Protection System TRIRvsion 13 Operating Procedures FOR TRAINING USE ONa 6 of 43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS D. Procedure Performer Initial Conditions

1.

The operator(s) performing this test have reviewed this procedure.

I Initial I Date I

Initial I Date I

Initial I Date I&C I

Initial i Date

IV.

INSTRUCTIONS A.

Preparations

1.

Obtain the following for the performance of this procedure:

Key No. 79, SSPS Train A.

Key No. 126, SSPS Train B.

I Initial I Date

2.

If performing Attachment A(E), "Removing SSPS Train A(B) From Service", perform the following: (Otherwise N/A)

a.

Verify [TRS-1VS-01,02,03,04 and 05], CREBAPS Transfer Switches,are in the UNIT 1 position by checking the following:

"* Transfer Switch placard in Unit I NSS Office. ([TRS-1VS-01 and 02] only)

"* Most recent performance copy of 1/20ST-44A.1, "Unit 2 Control Room Emergency Habitability Check".

I Initial I Date Note:

Blocking out of Attachments which are not used is not required. When preparing procedure for transmittal to Document Control, do not include pages which have not been used.

3.

Indicate the Attachment(s) to be performed by initialing the associated instruction(s) below and marking the remaining instructions "N/A":

a.

Attachment A: Removing Train A SSPS from Service.

I Initial I Date

b.

Attachment B, Removing Train A Output Relay Power Fuses.

I Initial I Date

c.

Attachment C: Reinserting Train A Output Relay Power Fuses.

I Initial I Date Beaver Valley Power Station Unit 2 20M-1.4.1 Reactor Control and Protection System*.*

TRAININ,

N p vision 13 Operating Procedures i

i lTlAINING USE J Lge7 of 43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS

ATTACHMENT D Returning Train A SSPS to Service CAUTION:

WITH SSPS IN OPERATION, LOSS OF POWER TO 2/3 PRESSURIZER PRESSURE TRANSMITTERS 2RCS-PT455, 456,457 OR PLACING THE CHANNEL BISTABLES IN TEST FOR AN MSP WILL REMOVE THE SI BLOCK AND RESULT IN A SAFETY INJECTION.

Note:

[2SIS*MOV867A and C] are maintained closed and de-energized to prevent an RCS overpressure condition from an inadvertent SIS signal. Ref 20M-51.4.D.

1.

Verify the following MCC breaker operating handles are in the OFF position:

a.

[MCC*2-E03] Cub 7A for [2SIS*MOV867A].

/

Initial I Date

b.

[MCC*2-EO5] Cub 10A for [2SIS*MOV867C].

/

Initial / Date

2.

If SSPS Train A was de-energized, perform the applicable portions of 20M-1.4.A, "Reactor Protection System Startup". (Otherwise N/A)

/

Initial I Date

3.

Verify or Place SSPS Train A white Multiplexer Test Switch in NORMAL.

([RK*2RC-PRT-A], Logic Cabinet)

I Initial I Date

4.

Verify or Place SSPS Train B white Multiplexer Test Switch in NORMAL.

([RK*2RC-PRT-B], Logic Cabinet)

I Initial I Date

5.

Verify the following status lights are ON: (BB-B, Status Panel 308)

a.

A3, "PRZR LOW PRESS SI BLOCK PERM CHAN I".

I Initial I Date ATTACHMENT D Beaver Valley Power Station Unit 2 20M-1.4.1 Reactor Control and Protection System, visiOn 13 Operating Procedures FOR TRAINING USE ONU

,le 15 of 43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS

Beaver Valley Power Station Unit 2 2OM-1.4.1 Reactor Control and Protection Systerj.mOR Revision 13 Operating Procedures TRAINING USE ONL e 16 of 43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS

b.

B3, "PRZR LOW PRESS SI BLOCK PERM CHAN I'".

I InitialI Date

c.

C3, "PRZR LOW PRESS SI BLOCK PERM CHAN II".

I Initial I Date

6.

Verify all status lights on Safeguards System Status Panel 464 are OFF. (BB-A)

I Initial I Date

7.

Verify that no greater than one ESF instrument is being tested (MSP, ICP, LCP) for any instrument group which actuates an ESF function (example: Pressurizer pressure, steamline pressure, chlorine).

I Initial I Date

8.

Place the SSPS Train A red Input Error Inhibit Switch in INHIBIT.

([RK*2RC-PRT-A], Logic Cabinet)

(1)

I Initial I Date (2)

I Initial I Date CAUTION:

THE RED INPUT ERROR INHIBIT SWITCH MUST BE IN THE "INHIBIT" POSITION BEFORE PLACING THE MODE SELECTOR SWITCH IN THE "OPERATE" POSITION.

9.

Place the SSPS Train A Mode Selector Switch in OPERATE. ([RK*2RC-PRT-A],

Output Cabinet)

I Initial I Date

a.

Verify the Mode Selector switch green light is ON.

I Initial I Date ATTACHMENT D

Beaver Valley Power Station Unit 2 20M-1.4.1 Reactor Control and Protection System.L TRAIN IN U

f, i!evision 13 Operating Procedures t0R TRAINING USE J,,ge 17 of 43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS

10. Reinstate memory circuit blocks by placing the following switches to the BLOCK position: (BB-B)

a.

Przr Press SI Train A Block/Reset switch.

I Initial I Date

b.

Stm Line SI Train A Block/Reset switch.

I Initial I Date

11. Reinstate memory circuit blocks by depressing the following pushbuttons: (BB-A)

a.

Safety Injection Signal Train A Reset pushbutton.

I Initial I Date

b.

SI Recirc Mode Reset Train A pushbutton.

/

Initial I Date

12. Verify Safety Injection automatic actuation is blocked by checking the state of the following:

a.

Y3190D, "PRZR SI BLOCKED TRN A", indicates BLOCK. (N/A if PCS is not available)

I Initial I Date

b.

P0402D, "SLI/SI BLK TRN A" indicates SET. (N/A if PCS is not available)

I Initial I Date

c.

If the PCS is not available, Verify Blocks by performing the applicable portion of 2MSP-1.04-1, "Solid State Protection System Train A Bi-Monthly Test". (N/A if PCS is available)

I Initial I Date ATTACHMENT D

13. Place the SSPS Train A red Input Error Inhibit Switch in NORMAL.

([RK*2RC-PRT-A], Logic Cabinet)

I Initial I Date

14. If both Train A AND Train B of SSPS have been returned to service, perform the following: (Otherwise N/A)

a.

Place white Multiplexer Test switch in "A+B". ([RK*2RC-PRT-A], Logic Cabinet)

I Initial I Date

b.

Remove Caution Tags from the following switches that state "Notify I&C prior to Changing Switch Position" OR that state "Restore to OPERATE position using 20M-1.4.1 only":

1)

Train A red Input Error Inhibit Switch I

Initial I Date

2)

Train A white Multiplexer Test Switch I

Initial I Date

3)

Train A Output Mode Selector Switch I

Initial I Date

4)

Train B red Input Error Inhibit Switch I

Initial I Date

5)

Train B white Multiplexer Test Switch I

Initial I Date

6)

Train B Output Mode Selector Switch I

Initial I Date ATTACHMENT D Beaver Valley Power Station Unit 2 20M-1.4.1 Reactor Control and Protection System on 13 Operating Procedures rOR TRAINING USE ONLV18of43 SOLID STATE PROTECTION SYSTEM ALIGNMENTS

ML030220459

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