ML20149D289

Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970317

ML20149D289
Person / Time
Site:	Beaver Valley
Issue date:	07/14/1997
From:	Curley V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9707170075
Download: ML20149D289 (606)

Text

. .

July 14, 1997 NOTE T0: NRC Document Control Desk Mail Stop 0-5-0-24 FROM: Ireos/ Oonle v . Licensing Assistant OpetAting Licen ng Branch. R 7

SUBJECT:

OPERATORLICENSINGEXAMINATIONADMINISJEREDON Mu d h 17 t r11 . AT t%xe n valim W DOCKET #50-dJ//- /}

97f7e tdecPor J//1/97 Operator Licensing Examinations were administered

~

. at the refere/ iced facility. Attached, you will find the follcuing information for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR:

Item #1 - a) Facility submitted outline and initial exam submittal, designated for distribution under RIDS Code A070.

b) As given operating examination designated for distribution under RIDS Code A070.

=- d Da r 2, l

100023 llIlll.llll.lll.llll.llll.EI.!Illlll 9707170075 970714 .

PDR ADOCK 05000334 i V PDR  !

L

INDEX l JPMs l

1PL-092, Establish RCP CCR Cooling and Seal Injection.

IPL-094, Emergency Start Charging /HHSI Pump on Bus IAE During Blackout 1

IPL-095, Perform Warm Slow Start of Turbine Driven AFP IPL-096, Place CCR Heat Exchanger in Service 1PL-097, Lockout of Affected 4160V Emergency Bus i

AD-001, Manual QPTR Calculation I i

AD-003, Verify Clearance AD-004, Enter the Radiological Controlled Area AD-005, Classify Emergency Plan Event (Drill 1) l AD-006, Classify Emergency Plan Event (Drill 2) l AD-007, Classify Emergency Plan Event (Drill 3)

AD-008, Classify Emergency Plan Event (Drill 4)

AD-009, Classify Emergency Plan Event (Drill 5)

AD-010, Classify Emergency Plan Event (Drill 6)

)

AD-011, Fill Out An Operating Manual Change Notice S

0 R

\

. . . - . . . - . . . . . - . . . . . . . . . . ~ . . . . - - . - . . . . - . - . .

l RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual

. f. 1

j. l l 1 I

OJT CHECKLIST /JPM COVER PAGE l

l PROGRAM TITLE: Licensed Operator Training '

SUBDIVISION:

i On-the-Job Training l

I OJT CHECKLIST /JPM TITLE: ESTABLISH RCP CCR COOLING I, '

i. l

( JPM NO.: 1PL-092 i

COMPUTER CODE: N/A i Revision No. Date Revision No. Date ,

l t

t b

PREPARED BY: DATE:

l l

l l

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee i

l

f. 5 L

Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: 1PL-092, ESTABLISH RCP CCR COOLING Revision Anoroval No. Brief Description Revised by: Signature Date i

I i

l i.

Revision 9

i BEAVER VAL?.EY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET l JPM Number: 1PL-092 Rev: 0 System #: 008 Faulted: 0 JPM

Title:

ESTABLISH RCP CCR COOLING

, K/A

Reference:

008 000 G13 3.4/3.4 Task ID #: 301 006 0601

! JPM Designation: NO RO X SRO I

JPM Application: X NRC X Initial Exam Training i

l,

)<

Evaluation Method LOCATION TYPE

] Perform Plant Site Training l Simulate Simulator Annual Requal. Exam

,! [] Classroom OJT f Initial Operator Exam l Administered By: Other:

l BV-T I [3 NRC i

i Other:

}

l j Evaluation Results f Performer: Name: Employee No:

Results SAT Time (minutes)

I' UNSAT* Allotted: 20 Actual: 1 1 .

1 Time Critical: Yes x No

)

• Comments (Required for UNSAT Evaluation):

i l Evaluation Results [] Check here if same as above

] Observer 1: Name: Employee No:

l Observer 2: Name Employee No:

Observer 3

Name Employee No:

Obnerver 4: Name .

Employee No:

i Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

j Question #1 5 [3 j Employee No:

Question #2 [3 5

Employee No:

.

• Comments (Required for UNSAT Evaluation):

4 I -

s j Evaluator (Print) : Organization:

Evaluator Signature Date:

Revision 9

RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l

EVALUATOR DIRECTION SHEET JPM NUMBER: 1PL-092 l

l JPM TITLE:

L ESTABLISH RCP CCR COOLING RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to perform (simulate) the task establish RCP CCR cooling and seal i injection. l 1

INIT. CONDITIONS: A Loss of All Emergency AC Power occurred i approximately 40 minutes ago. AC power was  ;

restored to both emergency busses using the diesel generators approximately 20 minutes ago. ECA-0.1, Loss of All AC Power Recovery i Without SI Required, is in progress at this  !

time.

TASK STAN.: Actions taken outside the control room to restore RCP CCR and seal injection cooling, I in accordance with 10M-53.A.1.2.B.

(Attachment 2-B)

II . E:

Your supervisor directs you to take actions outside of the control room to re-establish RCP CCR and Seal Injection in accordance with 10M-53.A.1.2.B. (Attachment 2-B)

I

REFERENCES:

10M-53.A.1.2.B, Issue 1B, Rev 1 TOOLS: NONE HANDOUT: 10M-53.A.1.2.B, Establishing RCP CCR Cooling and Seal Injection, l

i 1

i i !

l Revision 9

RTL #AS.635.J i

NUMBER TITLE 1PL-092 ESTABLISH RCP CCR COOLING i

STEP STANDARD .

(Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

START TIME:

Candidate locates and reviews procedure.

Evaluator Cue: Provide candidate with copy of 10M-53A.1.2-B.

COMMENTS:

1. Align River Water to 1. Candidate determines Appropriate CCR Heat status of CCR Heat Exchanger. Exchanger River Water Cooling.

Evaluator Cue: The A Train of River Water has been aligned to CCR Heat Exchangers, steps 1.a.1,2,3 are complete.

~

COMMENTS:

Page 1 of 5 Revision: 0

_= _ _ . . . . _ -- _

l 1

! RTL #AS.635.J l

l NUMBER TITLE 1PL-092 ESTABLISH RCP CCR COOLING STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

2.C Establish CCR Flow to 2.1 Candidate requests CCR RCP Thermal 9arriers temperature reading and Motor Coolers from the control room.

Evaluator Cue: The control room reports that TI-1CC-100 is reading 92 degrees.

2.2.C Candidate locates and closes [1CCR-18).

Evaluator Cue: [1CCR-18] is closed.

COMMENTS: ,

1 1

1 l

Page 2 of 5 Revision: 0

RTL #AS.63F J l NUMBER TITLE 1PL-092 ESTABLISH RCP CCR COOLING STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

3. Close CCR isolation 3. Candidate request the valves. control room open the CCR isolation valves.

Evaluator Cue: The control room reports that the CCR isolation valves listed in Step 2.c are open.

COMMENTS: )

l l

l l

l l Page 3 of 5 Revision: 0 i

RTL #A5.635.J NUMBER TITLE 1PL-092 ESTABLISH RCP CCR COOLING STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

4.C Establish CCR Flow to 4.C Candidate establishes RCPs. communications with control room and slowly opens [1CCR-18]

while maintaining pressure as indicated on [PI-1CC-100) from dropping below 100 PSIG.

Evalv3 tor Cue: As candidate begins to open valve, control room reports pressure is 122 PSIG and dropping. When candidate slows valve opening report that pressure is recovering. After valve is full open report that pressure is steady at 121 PSIG.

COMMENTS:

l l

l Page 4 of 5 Revision: 0

-. .. .- - .. .-- -. . . . . - . . . - ~ _ _ . - - - . - .. _. .. . . - .

RTL #A5.635.J r.

NUMBER TITLE 1PL-092 ESTABLISH RCP CCR COOLING STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denot'es critical step) for Unsat.)

Evaluator Cue: Another operator will manipulate the valves to restore RCP seal l

injection. You can assume that he has completed this evolution. You are to inform the control room of the status

! of the attachment.

8. Report that RCP CCR and 8. Candidate reports RCP seal injection have CCR and seal injection been established. have been establi.shed. ,

! COMMENTS:

~

l l

l l STOP TIME:

I i

Page 5 of 5 Revision: 0

l. . , - - - . .

BEAVER VALLEY JOB PERFORMANCE MEASURE

(

l JPM QUESTION # 1 What is the expected CCR System Response to a rupture of an RCP thermal barrier heat

!- exchanger?

008 000 Kl.04 3.3/3.3

! Obj: LP-SQS-15.1 ELO-6

! Ref: lOM-15.1.D, Issue 4, Revision 1 ANSWER:

The thermal barrier return outlet trip valve would close on high flow, isolating the failed component from the rest of the system. .

Also acceptable: Initially CCR radioactivity and surge tank level would increase l

Comments:

l l

i

1 I

I

! I I

I l i

-l

?

IPI 092

.- _ _ . . _ _ _ _ _ _ . _ . . . _ _ _ _ _ _ . _ . _ . . . . . _ . . _ . ._ .. _.m . _ __.

l l BEAVER VALLEY JOB PERFORMANCE MEASURE

.i.

I ,

!~ JPM QUESTION # 2 l  :

~

What is the expected automatic response of CCR system components (specifically PCV-l ICC-100 and TCV-ICC-100) to restoring CCR flow to the RCPs? "

L i

008 000 A3.013.2/3.0 l Obj: LPS-SQS-15.1, ELO-5 Ref: lOM-15.1.D, Issue 4, Revision 1 i

ANSWER:

.The CCR system pressure control valve, PCV-ICC-100, should throttle closed to maintain constant CCR header pressure and the CCR system temperature control valve,

' TCV-lCC-100 should throttle closed to maintained constant CCR temperature.

. Comments:

l i

f IPIr092

. , . - . . -.. -.- - . . - . . . . . . . - . - - ~ . . . . . . . . - - . _ ..

l l BEAVER VALLEY JOB PERFORMANCE MEASURE 1 i i l

l l(

• THIS SHEET TO BE GIVEN TO CANDIDATE * )

1 JPM QUESTION # 2 l 1

What is the expected automatic response of CCR system components (specifically PCV- I l

ICC-100 and TCV-1CC-100) to restoring CCR flow to the RCPs? I

^

i l

l i

l 1

i l

-)

1 i

l l

k IPIr092

_ _ .. . . . - _ _ . ~ . . . . . . . . . . _ _ _ _ _ . . _ . _ . . _ . . . . . _ . _ . . _ _ __ _ _ ~ . - . .

I BEAVER VALLEY JOB PERFORMANCE MEASURE l

l l

• TEUS SHEET TO BE GIVEN TO CANDIDATE

• l l

l l

JPM QUESTION # 1 I

l' What is the expected CCR System Response to a rupture of an RCP thermal barrier heat

( exchanger?

i l

I J i i l

i 1

t i

i I

l I

4 I

i l

l l

l 1 PIA 92 l i

. _ _ _ . - . -.- - - . - - . .~

RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION. SHEET THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Task:

lESTABLISHRCPCCRCOOLING l

INITIAL A Loss of All Emergency AC Power occurred i Y CONDITIONS: appr ximately 40 minutes ago. AC power.was i

restored to both emergency busses using the

! diesel generators approximately 20 minutes ago.

ECA-0.1, Loss of All AC Power Recovery Without SI Required,-is in progress at this time.

TASK STAN.: lActionstakenoutsidethecontrolroomtorestore RCP CCR and seal injection cooling, in accordance with 10M-53.A.1.2.B. (Attachment'2-B)

INIT. CUE

lYoursupervisordirectsyoutotakeactions l outside of the control room to re-establish RCP' CCR and Seal Injection in accordance with 10M-

- 53.A.1.2.B. (Attachment 2-B) I I

l.

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

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

Simulate performance or perform as directed the required task.

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

l After completing the task, reread the Task Standard.

After determining the Task Standard has been met, announce "I ha.e completed the JPM". Then hand back this sheet to the evaluator.

i b-1 0

i Revision 9

I I

l I

s BVPS - E0P 10M-53 A. I .2-B(ISSIB)

.j

$- number Titie l

2-B Establishing RCP CCR Cooling And Issue 1B

[ Seal Injection Revision 1 i

i A. PURPOSE To establish CCR cooling and seal injection flow to the RCPs.

B. SYMPTOMS OR ENTRY CONDITIONS

1. Either of the following conditions can be met:

1

- CIB has NOT occurred l l

-0R-l

. CIB has occurred, only one train of River Water is needed to supply the Recirc Spray Heat Exchangers and it is desired to supply the CCR Heat Exchangers with the other train of River Water.

l 1

(

50R ' RMugMG OW L

( .

r l

. . . - - m _ -

0 BVPS - E0P 10M-53A.I.2-B(ISSIB)

J e, Number Title

I 2-B Establishing RCP CCR Cooling And Issue IB 4 -

Seal Injection Revision 1

1. Alian River Water To The Acoropriate CCR Heat Exchanaer I

a. IF the A Train of River Water is to be aligned to the CCR Heat Echangers, THEN perform the following:

1) Open [MOV-lRW-106A,ll4A] CCR Hx RW Series Isol Vivs.

2) Close [MOV-lRW-103A,B] 1A Hdr RPRW To Recirc Spray Hxs Isol Vivs.

3) Verify [PI-lRW-113Al CCR Heat Exchanger RW Pressure To The A Header

- GREATER THAN 20 PSIG

4) GO TO Step 2.

b. IF the B Train of River Water is to be aligned to the CCR Heat Echangers, THEN perform the following:

1) Open [M0V-1RW-106B,ll4B] CCR Hx RW Series Isol Vivs.

2) Close [MOV-1RW-103C,D] 1B Hdr RPRW To Recirc Spray Hxs Isol Vivs.  !

-g

3) Verify [PI-1RW-113B]IGCCR

- GREATER THAN 20 PS Heat Exchanger RW Pressure To The B Header l

I I

1 t0R TRAINING ~0NLY

.\ .

f I

l, BVPS - E0P 10M-53A.l.2-B(ISSIB) i

-i Number iitle

/ 2-B Establishing RCP CCR Cooling And Issue IB Seal Injection Revision 1 l

• * \

• 1 CAUTION

• - High steam pressure in thermal barrier may

• damage CCR return piping when opening valves *

• [TV-lCC-107A,B,C].

• CCR flow to the RCP thermal barrier should be *

• established prior to establishing seal *

• injection flow to prevent damaging the RCP *

• seal s.

• NOTE High steam pressures may exist in the thermal barrier piping due to loss of cooling flow. This high pressure valves to trip may closecause [TV-lCC-107A,B,C]

on high flow. Severa l

. attempts to open these valves may be needed before they remain open.

2. Establish CCR Flow To RCP Thermal Barriers And Motor Coolers As Follows

a. Ensure CCR water supply temperature less than 105F on [TI-lCC-100].

b. Close [lCCR-18], CCR Supply Header Isolation (Aux Bldg - 735').

4 g l (step continued next page)

_ w

l-I BVPS - E0P 10M-53A.I.2-B(ISSIB) l ,

! Number. Title 2-B Establishing RCP CCR Cooling And Issue IB Seal Injection Revision 1

2. (continued from previous page)

, c. Open containment CCR isolation valves:

1) [TV-1CC-103A and 103Al], lA RCP CCR Inlet CNMT Isol Vlv.

2) [TV-1CC-103B and 103Bl],1B RCP CCR Inlet CNMT Isol Viv.

3) [TV-1CC-103C and 103Cl],1C RCP CCR Inlet CNMT Isol Vlv.

4) [TV-1CC-107A,B,C], lA,B,C RCP Th Barr CCR' Outlet Isol Vlv.

5) [TV-1CC-105El and 105E2], lA RCP Motor CCR Outlet CNMT Isol Viv. 1

6) LF [1RC-P-1A1 thermal barrier cooling is needed, THEN open .

'[TV- 1 CC- 107 E' and 107E2], lA RCP Th Barr CCR Outlet CNMT Isol Vlv.  :

7) Check open [TV-ICC-107A], lA RCP Th Barr CCR Outlet Isol.

8) [TV-1CC-105D1 and 10502],1B & IC RCP Motor CCR Outlet CNMT lsol  ;

Viv.

t 9) J1 [1RC-P-1B and r' thermal barrier cooling is needed, THEN open

[TV-1CC-10701 c.ad IO7D2],1B & IC RCP Th Barr CCR Outlet CNMT Isol Viv.

10) Check open [TV-1CC-107B,C),18,1C RCP Th Barr CCR Outlet Isol.

d. Slowly open [1CCR-18), CCR Supply Header Isulation, (Aux Bldg - 735'), ,

to maintain CCR system pressure from dropping below 100' PSIG on

[PI-1CC-100).

50R M NINb

f BVPS - E0P 10M-53A.l.2-B(ISSIB)

Number Title 2-8 Establishing RCP CCR Cooling And Issue IB l Seal Injection Revision 1 CAUTION

• - RCP seal injection should be established *

• slowly to minimize RCP thermal stresses and

• l

• potential seal failure. *

• l Do not exceed a 1F/ MIN cooldown rate of the *

• RCP lower bearing (on in-Plant Computer) when *

• bearing temperature is greater than 225F as

• indicated on This will *

• preventdamag(TR-1RCS-448A].ing the RCP lower bearing. *

• • • • • • • • • • • k*********************************************.********************

3. Establish Seal Iniection Flow To The RCPs

a. Check closed ICH-178,179,180], RCP Seal Flow Throttles (SFGDS - 722',

Penetration A .

b. Ch.c.k open the following valves:

1) [H0V-1CH-308A,B,C], lA,B,C RCP Seal Inj isol Viv.

2) [HCV-lCH-186], RCP Seal Sup Viv.

c. Slowly open [lCH-178,179,180], RCP Seal Flow Throttles (SFGOS - 722',

Penetration A) until seal water flow is just indicated on

[F1-lCH-130A,127A and 124A] 0.R [F1-lCH-130B,127B and 124B].

Gradually raise flow. Do not exceed cooldown limits for RCP lower bearing.

d. WHEN RCP lower bearing temperature is less than 225F, THEN establish seal injection flow between 6 AND 9 GPM.

4. RETURN TO Procedure And Steo in Effect REFERENCES

1. Issue 1, Revision 1: OMDR 86-0238, 87-0082; Table-Top Validation.

2. Issue 1A, Revision 0: OM 1/2.538.1, Appendix A, "EOP Writers Guide."

3. Issue 1A, Revision 2: 0MDR l-89-1591.

4. Issue IB, Revision 0: 0MDR l-90-0912, 1170, 92-0144, 0544; Walkthrough Validation Comment (9/12/90). i I

- END - l l .

3 e0R TRAINING OriLY L

l

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training 1

SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Emergency Start HHSI Pump on Bus 1AE JPM NO.: IPL-094 COMPUTER CODE: N/A Revision No. Date Revision No. Date i

l I

PREPARED BY: DATE:

APPROVED FOR l IMPLEMENTATION: DATE:

l Director, Operations Training,

! or Designee I

t i Revision 9 f

-RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division ,

Training Administrative Manual  !

LESSON PLAN AND OJT REVISION APPROVAL SHEET i

DOCUMENT TITLE: 1PL-094. Emeroency Start HHSI Pumo on Bus 1AE i Revision Acoroval No. Brief Description Revised by: Signature Date t

?

4 h

i 1

l l

5 8

I i

k l

)

Revision 9.

, . i

... . ~ . . . - - - - - - - - - . , . - - - . . - . ~ . . - ~ . - . _ - . . . - . - . - - . _ . - . ~ . - . ~ . . .

RIL #A5.635.J . BEAVER VALLEY JOB PERFORMANCE MEASURE a EVALUATOR DIRECTION SHEET JPM NUMBER: 1PL-094 JPM TITLE:

Emergency Start HHSI Pump on Bus 1AE

• RECOMMENDED  !

STARTING LOCATION: CONTROL ROOM l

l DIRECTIONS: You are to perform (simulate) the task ,

emergency start HHSI Pump on Bus 1AE. '!

INIT. CONDITIONS: A Loss of All Emergency AC Power occurred  !

approximately 40 minutes ago. Offsite power could not be restored and the diesel  :

generators could not be started. Action is

• l being taken to establish power to Bus 1AE from BV-2 Cross Tie.

TASK STAN.: Actions outside of the control room taken to start Charging /HHSI pump 1A in accordance with 10M-53A.1.2-P-AE. t

-(Attachment 2-P-AE) l INIT. CUE: '

Your supervisor directs you to align systems for starting the 1A Charging /HHSI i pump on Bus 1AE during station blackout in l l

accordance with 10M-53A.1.2-P-AE.  ;

(Attachment 2-P-AE)  !

l l

REFERENCES:

10M-53A.1.2-P-AE Issue 1B, Rev 1 i

. TOOLS: NONE l

i  !

HANDOUT: 10M-53A.1.2-P-AE, Starting Charging /HHSI l Pump on Bus 1AE During Station Blackout.

l f

Revision 9 l' . .

1 l

1 i

j BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET t

l '

JPM Number: 1PL-094 Rev: O System #: 006 Faulted: O i JPM

Title:

Emergency Start HHSI Pump on Bus 1AE K/A

Reference:

006 000 G09 4.0/3.9 Task ID #: 301 006'0601 1

JPM Designation: NO [] RO UU SRO j JPM Application: X NRC X Initial Exam [3 Training

)

5

] Evaluation Method LOCATION TYPE Perform Plant Site Training l Simulate Simulator Annual Requal. Exam i

O Classroom O oat

] Initial Operator Exam

} Administered By: Other:

BV-T j NRC Other:

ll .

l Evaluation Results j Performer: Name: Employee No:

f Results SAT Time (minutes) j UNSAT* Allotted: 20 Actual:

l Time Critical: Yes X No j

• Comments (Required for UNSAT Evaluation) :

.i 4

Evaluation Results [] Check here if same as above j Observer 1: Name: __

Employee No:

Employee No:

2 Observer 2: Name i Observer 3: Name Employee No:

Employee No:

Observer 4: Name Time (minutes) Results q

Question ID Allotted Actual SAT UNSAT*

j Question #1 4

Employee No

J. Question #2 4

! Employee No:

l

• Comments (Required for UNSAT Evaluation) :

Evaluator (Print) : Organization:

4 Evaluator Signature Date:

Revision 9

1 RTL #AS.635.J  ;

I NUMBER TITLE 1PL-094 Emergency Start HHSI Pump'on Bus 1AE 1

STEP STANDARD  !

(Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

START TIME:

Candidate locates and reviews procedure.

Evaluator Cue: Provide candidate with copy of.10M-53A.1.2-P-AE.

1. Obtain Power Station 1. Candidate obtains Key. Power Station Key (PWR STA). I i

i l

COMMENTS: 1 1

l l

l l

l l

1 l

i 6

Page 1 of 7 Revision: 0 l

l

RTL #A5.635.J.

NUMBER TITLE 1PL-094 Emergency Start HHSI Pump on Bus 1AE STEP STANDARD (Indicate "S" for Sat, or "U"

("C" denotes critical step) for Unsat.)

2.C Place All Cubicles at 2.C Candidate places All

. [MCC1-E03 ] in OFF. Cubicles at [MCC1-E03]

in OFF.

I Evaluator Cue: All Cubicles at l [MCC1-E03] are in OFF.

COMMENTS:

3.C Ensure' power is 3.1.C Candidate places available to Cubicle J, [MOV-1CH-charging /HHSI pump 115B], RWST Discharge.

Suction valves, to Charging Pump Suction, in ON.

Evaluator Cue: Cubicle J is in the ON position.

i l

Page 2 of 7 Revision: 0 t

RTL #AS.635.J i

NUMBER TITLE 1PL-094 Emergency Start HHSI Pump on Bus 1AE STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

3.2.C Candidate places Cubicle K, [MOV-1CH-115C) VCT Outlet to Charging Pump Suction in ON.

Evaluator Cue: Cubicle K is in the ON position. Another operator has verified that 480v bus 1N cub N8 is closed.

COMMENTS:

4. Align Charging /HHSI 4. Candidates requests Pump Flow Path, the Control Room to align Charging /HHSI Pump Flow Path.

Evaluator Cue:'The Control Room reports that the Charging /HHSI pump flow path alignment, steps 5.a through 5.g are complete.

COMMENTS:

Page 3 of 7 Revision: 0

RTL #AS.635.J NUMBER TITLE 1PL-094 Emergency Start HHSI Pump on Bus 1AE STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

5. Ensure Attachment 2 5. Candidate asks Control AE, Starting River Room if Attachment 2-Water Pump During 0-AE is complete.

Station Blackout has been completed. Evaluator Cue: The Control Room reports that Attachment 2-0-AE is complete.

COMMENTS:

I 6.C Establish River Water 6.1.C Candidate opens [1RW-to Appropriate 160].

Charging /HHSI Pump. l Evaluator Cue: (1RW-160) is open.

l l

I l

Page 4 of 7 Revision: 0

RTL #A5.635.J i .

NUMBER TITLE 1PL-094 Emergency Start HHSI Pump on Bus 1AE STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

6.2.C. Candidate opens [1RW-172).

Evaluator Cue: [1RW-172] is g n.

COMMENTS:

7. Check if RCP Seal 7.1 Candidate checks Injection Throttle position of [1CH-178, Valves are closed. 179 end 180).

Evaluator Cue: Another operator has verified that

[1CH-178, 179 and 180] are closed.

1 1

COMMENTS:

Page 5 of 7 Revision: 0

I i

i RTL #AS.635.J l 1

l l

NUMBER TITLE 1PL-094 Emergency Start HHSI Pump on Bus 1AE l

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

Evaluator Cu : The control room reports that they are going to start the 1A charging pump and that you are to locally throttle SI by using

[1CH-25). The use of key 0.4 will be simulated. Call the control room when you are in position to throttle flow.

8.C Calls the control room 8.1 Candidate locates and to reports that the [1CH-25], simulates 1A Charging /HHSI pump unlocking valve.

flow can now be throttled.

Evaluator Cue: The control room reports that flow is too high and that you are to close

[1CH-25].

8.2.C Candidate throttles closed [1CH-25), to establish flow.

Page 6 of 7 Revision: 0 1

RTL #A5.635.J NUMBER TITLE 1PL-094 Emergency Start HHSI Pump on Bus 1AE I

STEP STANDARD (Indicate "S" for Sat. or "U" 1

("C" denotes critical step) for Unsat.)

I 1

l Evaluator Cue: The control I room reports that desired flow l is established. 1 l

COMMENTS:

STOP TIME:

l l

l i

i i

l l

Page 7 of 7 Revision: 0 l~

l

. . . . - ..-.~ . . - . . - - . - - . . - - . - , .. . - - . _. ..-

i BEAVER VALLEY JOB PERFORMANCE MEASURE JPM QUESTION # 1 ECA-0.0 directs the operator to choose the cross-tie path based on diesel generator  !

operability. Assuming the #1 diesel generator was known to be inoperable prior to the Blackout, determine the cross tie path that should be used and the explain the basis for this decision.

006 000 K2.013.6/3.9

• Obj: LP-SQS-53.3-3  ;

Ref: lOM-53.B.4.ECA-0.0, Issue IB, Revision 3 j

ANSWER: -

l t

1 With the #1 diesel generator known to be inoperable, Bus I AE should be used for the  ;

cross tie path. This allows the possible use of the " operable" diesel generator to be used to energize Bus IDF.

Comments:

i 4

l 1

l l

l

! i t-

IPL-094 -

i i

.c BEAVER VALLEY JOB PERFORMANCE MEASURE JPM QUESTION # 2 -

Why was seal injection flow isolated prior to starting the HHSI pump?

- 006 000 K1.08 3.6/3.9 '  ;

Obj: LP-SQS-53.3-3 Ref: lOM-53.B.4.ECA-0.0, Issue IB, Revision 3

]

l ANSWER:

During a station blackout, seal injection flow and CCR flow to thermal barrier heat l exchangers are lost causing the seal temperatures to increase. If the charging pump had I been staned, without first isolating seal injection flow, thermal shock could have further damaged the RCP seals.

Comments:

l l

i l

l.

{

j. IPIA94

. . ._, .~ _ -

f BEAVER VALLEY JOB PERFORMANCE MEASURE

(

• THIS SHEET TO BE GIVEN TO CANDIDATE * .

l JPM QUESTION # 1 l

l ECA-0.0 directs the operator to choose the cross-tie path based on diesel generator j operability. Assuming the #1 diesel generator was known to be inoperable prior to the ,

Blackout, determine the cross tie path that should be used and the explain the basis for this j decision.

l l

l-I l

i i

+

IPIA94

l: l l l i

l

. i BEAVER VALLEY JOB PERFORMANCE MEASURE l l

• THIS SHEET TO BE GIVEN TO CANDIDATE

• JPM QUESTION # 2 i -

l

. Why was seal injection flow isolated prior to starting the HHSI pump?  :

B 4

I l

l l

l l

l l >

IPL-094

.. _ _ . _ . . . _ _ _ _ _ _ _ _ _ _ _ . ~ . _ _ . _ . . . _ . _ . _ _ _ _ . . . . _ _ . . _ . . _ _ _ _ _ . _ - - _ . _ .

l~ RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET i- -

THIS SHEET TO BE GIVEN TO CANDIDATE

• 1 Read: 1 l

Tasb lEmergencyStartHHSIPump'onB'us.1AE I

i- 1 l i INITIAL A Loss of All Emergency AC Power occurred  !

CONDITIONS.

• aPProximately 40 minutes ago. Offeite power could .

l not be restored and the diesel generators could I not be started. Action is being taken to I establish power to Bus 1.AE from BV-2 Cross Tie. i

\. ,

l TASK STAN.: lActionsoutsideofthecontrolroomtakento start Charging /HHSI pump 1A in accordance with  ;

10M-53A.1.2-P-AE. (Attachment 2-P-AE) l INIT. CUE: Your supervisor directs you-to align systems.for starting the 1A Charging /HHSI pump on Bus 1AE during station blackout in accordance with 10M- ,

! 53A.1.2-P-AE. (Attachment 2-P-AE)

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

Simulate performance or perform as_ directed the required task.

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

l After completing the task, reread the Task Standard.

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

8

! ( '

I l

l l Revision 9

. l

. it BVPS - E0P 10M-53A.l.2-P-AE(ISSIB)

.unbe r Title l 2-P-AE Starting Charging /HHSI Pump On Bus lAE Issue 18 l During Station Blackout Revision 1 A. FJRPOSE To provide instructions for starting Charging /HHSI Pump on Bus lAE during a station blackout at BV-1. ,

B. SYMPTOMS OR ENTRY CONDITIONS ,

This procedure is entered from Attachment 2-M-AE, " Actions To Establish l BV-2 Cross-Tie To Bus lAE During Station Blackout", Step 17.

l l

1 l

l I

50R WW l

i

s BVPS - E0P 10M- 53 A. l .2-P- AE(ISSIB) kumber T it le 2-P-AE Starting Charging /HHS1 Pump On Bus lAE Issue IB During Station Blackout Revision 1

• CAUTION

• One charging pump should not be started if BV-2 *

• Diesel Generator load is greater than 3700 KW. *

• This could overload the cross-tied BV-2 Diesel *

• Generator.

• NOTE Additional BV-2 equipment should not be stopped to provide excess capacity on the BV-2 diesel generator to allow the BV-1 charging pump to be started. This could degrade the BV-2 recovery effort.

1. Obtain Power Station Key (Pwr Stal l

2. Place All Cubicles At IMCCl-E031 ( Aux Bldo - 735') In OFF

' Ensure Power Is Available To Charoina/HHSI Pump Suction Valves

a. Place the following cubicles at (MCCl-E03] (Aux Bldg - 735') in ON:

. J, 'M0V-lCH-ll5B' RWST Discharge To Charging Pumps Suction

. K, MOV-lCH-ll5C VCT Outlet To Charging Pumps Suction

4. Close 480V Emeroency Bus IN Cub N8, IMCCl-E031 (Service Blda - 713')

50R TRMuquG OC

l

.o BVPS - E0P 10M-53A.1.2-P-AE(ISS18)

'. Number Title f 2-P-AE Starting Charging /HHSI Pump On Bus lAE Issue IB During Station Blackout Revision 1 png If Si has occurred, it must be reset prior to realigning SI equipment.

5. Alian Charaina/HHSI pumo Flow Path

a. Close [MOV-1CH-ll5C), VCT Outlet To Chg Pumps Suct Vlv.

b. Close [MOV-1CH-289], Regen Hx/Chg Hdr Inlet Cnmt Isol Viv. I

c. Close [TV-1SI-884A], BIT Recirc To Boron Inj Surge TK Isol Viv.

d. Close [TV-lSI-884B], BIT Recirc To Boron Inj Surge Tk Isol Viv.

e. Open [MOV-lCH-ll5B], RWST Disch To Chg Pumps Suct Viv.

( f. Open [MOV-1SI-867A], BIT Inlet Isol Vlv.

g. Open [MOV ISI-867C), BIT Outlet Isol Viv.

6. Ensure Attachment 2-0-AE "Startina River Water Pumo Durina Station Blackout." Has Been Comoleted

7. Establish River Water To The Acoropriate Charaina/HHSI Pumo Cooler

a. IE [1CH-P-1A), Charging /HHSI Pump will be started, THEN perform the following (Aux Bldg - 735'):

1) Open [lRW-160], Charging Pump [1CH-E-7A] Supply A Hdr Isol.

2) Open [lRW-172], Charging Pump [1CH-E-7A] Outlet To Rtn Hdr.

3) GO TO Step 8.

b. J1 f1CH-P-lC], Charging /HHSI Pump will be started, THEN perform the following (Aux Bldg - 735'):

i 1) Open [1RW-162], Charging Pump [lCH-E-7C] Supply A Hdr Isol.

, 2) Open [1RW-174], Charging Pump [lCH-E-7C) Outlet To Rtn Hdr.

1' C0R TRAINING ONLY

,..t BVPS - E0P 10M-53A.I.2-P-AE(ISSIB) i '

humber Title 2-P-AE Starting Charging /HHSI Pump On Bus IAE Issue Ib During Station Blackout Revision 1

8. Check RCP Seal isolation Status

a. Check if [lCH-178,179 and 180], RCP Seal Injection Throttle Valves (SFGDS, Penetration A - 722') are closed.

JF valves are open OR position not known, THEN locally close

[lCH-178, 179 and 180] prior to starting a charging /HHSI pump.

9. Start flCH-P-1 A(C)l. Charaina/HHSI Pumo

a. As time permits, dispatch an operator to check pump operation.

10. Establish S1 Flow To Maintain PRZR Level Between 5% And 50% By Performina ONE Of The Followino Dependina On Plant Radioloaical Conditions

a. Throttle BIT valve by performing the following:

1) Dispatch an operator to the West Cable Vault Area and establish continuous communications. .

Initiate stroking [M0V-1SI-867A(C)), BIT Inlet (Outlet) Isol Viv to

-(' 2) the CLOSE position.

3) Immediately place cubicle for affected valve at [MCCl-E5 (West Cable Vault - 735') in 0FF when desired flow is obtained]:

- W, 'M0V-1SI-867A' Boron Injection Tank Inlet Isolation Valve

. X, 'MOV-1SI-867Ch Boron Injection Tank Outlet Isolation Valve

, locally throttle [lCH-25(27)) Charging /HHSI

b. With PumpKey 0.4(0.6)lation Charging Iso Valve (Aux Bldg, Reach Rods - 722').

c. Locally throttle BIT valve by performing either of the following.

1) Close one AND throttle the other [MOV-ISI-867A,B), BIT Inlet Isol Vivs (Aux Bldg, Blender Room - 722').

-0R-

2) Close one AND throttle the other (MOV-1SI-867C,0), BIT Outlet Isol Vivs (SFGOS, Penetration A - 722').

l l

l' c0R TRAIMtMG ONLY

...e l BVPS - E0P 10M-53A.I.2-P-AE(ISSIB)

Number Title l 2-P-AE Starting Charging /HHSI Pump On Bus 1AE Issue IB During Station Blackout Revision 1 RETURN TO Procedure And Steo in Effect 1

11.

l REFERENCES

1. Issue 1A, Revision 0: OCP 1698, NUMARC 87-00 " Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors"; Walkthrough Validation Comments - 1/20/93.

- END -

i l

l t0R TRAIN NG ONLY

I l

l RTL #A5.640E DUQUESNE LIGHT COMPANY j Nuclear Power Division Training Administrative Manual t

3 OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Warm Slow Start of Turbine Driven AFW Pump JPM NO.: 1PL-095 COMPUTER CODE: N/A Revision No. Date Revision No. Date PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

l Director, Operations Training, l or Designee i

Revision 9

i 1

l t

! RTL #AS.640E DUQUESNE LIGHT COMPANY I Nuclear Power Division Training Administrative Manual l

LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: 1PL-095. Warm Slow Start of Turbine Driven AFW l

Pumo l

Revision Accroval No. Brief Description Revised by: Signature Date 1

I I

Revision 9

- _ . . - - . . - . _ - . _ ~ _ . . - . . ~ . - . - - - - - . -

- - - . . - . . . ~ - . . - . . . . . _ _ . _

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: 1PL-095 Rev: 0 -System #: 061 Faulted: O JPM

Title:

Warm Slow Start of Turbine Driven AFW Pump K/A

Reference:

061 000 G09 3.8/3.9 Taek ID #: 061 003 0101 JPM Designation: O NO RO @ SRO JPM Application: X NRC X Initial Exam Training Evaluation Method LOCATION TYPE Perform ~ Plant Site Training Simulate Simulator Annual Requal. Exam Classroom OJT Initial Operator Exam Administered By: Other:

BV-T l NRC l Other:

Evaluation Results Performer: Name: Employee No:

Results O SAT Time (minutes)

O uNSAT* Allotted: 30 Actual: l Time Critical: 0 Yes X No

• Comments (Required for UNSAT Evaluation) :

Evaluation Results Check here if same as above

! Observer 1: Name: Employee No:

j Observer 2: Name Employee No:

j Observer 3: Name Employee No:

j Observer 4: Name Employee No:

j Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 s O Employee No:

Question #2 4 Employee No:

• Comments (Required for UNSAT Evaluation) :

Evaluator (Print) : Organization:

Evaluator Signature Date:

Revision 9

- ,...- - . - . - . . - . - . ~ . - ~ . - . . - . . . ~ - - - . . - . . - . - . . . - -

f-L RIL #A5.635.J. BEAVER VALLEY JOB PERFORMANCE MEASURE 1 EVALUATOR DIRECTION SHEET JPM NUMBER: 1PL-095-JPM TITLE-Warm Slow Start of Turbine Driven AFW Pump '

l l

RECOMMENDED .I STARTING LOCATION: CONTROL ROOM l

1 DIRECTIONS:

L You are to perform (simulate) the task '

perform warm slow start of Turbi'ne Driven i AFP. l INIT. CONDITIONS: The plant is operating in Mode'3. The NSS has decided to place the Turbine-Driven I Auxiliary Feedwater Pump in service. The  !

pump is to be run on recirc for this  ;

evolution. I TASK STAN.:

[1FW-P-2] placed in service-in accordance with 10M-24.4.X, Turbine-Driven Auxiliary '

Feedwater Pump Warm - Slow Start.

INIT. CUE: . +

Your supervisor directs you to perform -l warm-slow start of the Turbine-Driven l Auxiliary Feedwater Pump. 3 l

REFERENCES:

10M-24.4.X Issue 3, Revision 1.

10M-24.4.V Issue 3, Revision 1 TOOLS: NONE HANDOUT: 10M-24.4.X, Turbine-Driven Auxiliary Feedwater Pump Warm - Slow Start.

10M-24.4.V Issue 3, (1FW-P-2] Trip Throttle Valve Resetting i f l

l l  !-

i Revision 9 l

RTL #AS.635.J NUMBER TITLE 1PL-095 Warm Slow Start of Turbine Driven AFW Pump STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.) i START TIME: l l

Candidate locates and reviews I procedure. j l

Evaluator Cue: Provide candidate with copy of 10M-  ;

24.4.X.

i 1

1. Don glasses or face 1. Candidate dons glasses shield, ear protection, or face shield, ear.

and gloves. protection, and gloves. .

Evaluator Note: This step may l not be performed until

! actually ready to begin running pump. (or simulated)

COMMENTS:

i i i

l l

Page 1 of 15 Revision: 0

I l

l RTL #AS.635.J  ;

l l;

\

NUMBER TITLE 1

1PL-095 Warm Slow Start of Turbine Driven AFW Pump i l

1 l

i STEP STANDARD

.. (Indicate "S" for Sat. or "U" l'

I

("C" denotes critical step) for Unsat.)

r 2.C Obtain key for [1FW-36) 2.1.C Candidate obtains Key and copy of procedure No. 19.

10M-24.4.V. 1 2.2 Candidate obtains copy of 10M.24.4.V.

( Evaluator Cue: Provide I

candidate with copy of 10M-  ;

24.4.V.

~

COMMENTS:

3. Check that the oil pump 3.1 Candidate observes oil i

is primed. pump suction cross-tie sightglass.

Eyaluator Cue: The sightglass I appears dark inside.

COMMENTS: I l

l

[i i-Page 2 of 15 Revision: 0

t RTL #A5.635.J NUMBER TITLE 1PL-095 Warm Slow Start of Turbine Driven AFW Pump l

l l

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.) l

4. Perform lineup to 4.1. Candidate closes [1FW-prevent closing 352].  ;

blowdown isolation valves.

Evaluator Cue: [1FW-352] is Iclosed. j 4.2. Candidate closes instrument stop for

[PS-1FW-157-3].

Evaluator Cue: The instrument i stop for [PS-1FW-157-3] is  !

closed I I

l l

4.3. Candidate removes the I swage lock cap for l

[PS-1FW-157-1]. j l

I Evaluator Cue: Swage lock cap for [PS-1FW-157-1] has been removed.

l l Page 3 of 15 Revision: 0 I

1 I _,

RTL #AS.635.J NUMBER TITLE 1PL-095, Warm Slow Start of Turbine Driven AFW Pump STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

4.4. Candidate opens pressure switch drain for [PS-1FW-157-1].

! Evaluator Cue: The pressure l

switch drain for [PS-1FW-157-1] is open.

COMMENTS:

i i

l-l l Page 4 of 15 Revision: 0 l

, . _ _ ._ _.___.._.m .- ._ _ .-_. _ ~ . _ . _ . _ _ _ _ . _ _ _ . _ _ . _ _ . _ _ _ . . _ . . . _ _ _ . . - _

l l

RTL #AS.635.J ,

t NUMBER TITLE l

l 1PL-095 Warm Slow Start of Turbine Driven AFW Pump i

l l

l STEP STANDARD -)

(Indicate "S" for Sat. or "U" i .

! ("C" denotes critical step) for Unsat.)

l

5. Verify trip valve 5.1. Candidate observes l status. trip throttle valve.

I Evaluator Cue: The trip I throttle valve is latched and )

open. .

1 i

5.2. Candidate observes oil dump valve.

Evaluator Cue: The oil dump valve is latched.

i I

COMMENTS:

l Page 5 of 15 Revision: 0

. . . , _- -- - ...- -. -. .- ..._. .~. . . . . . ~ . - . - ~= . . - - . . - . . .

l I

RTL #AS.635.J NUMBER TITLE 1PL-095 Warm Slow Start of Turbine Driven AFW Pump '

t l i i STEP STANDARD

! (Indicate "S" for S.at. or "U" l .. ("C" denotes critical step) for Unsat.) ,

6. Verify proper 6. Candidate checks status of [1VS-D-4-15A ventilation.

and 15B] and [1VS-D ,

l- 12A,and 12B) with.

• l Control Room.

l l Evaluator Cue: The Control l Room reports that [1VS-D-4-15A i and 15B] and [1VS-D-4-12A and '

l _

12B] are open. l l

COMMENTS:

i i  ;

a

{

l l

l

~

l I~ l l

i Page 6 of 15 Revision: 0

I i

, RTL #AS.635.J l 1

I l

1 NUMBER TITLE '

i i

1PL-095 Warm Slow Start of Turbine Driven AFW Pump I l

l I

t STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

I

7. Establish 7. Candidate establishes communications with the communications with l Control Room, the Control Room. -

Evaluator Cue: Communications with the Control Room will be simulated.

4 COMMENTS:

8.C Unlock and close 8.C Candidate unlocks and  !

discharge isolation closes (1FW-3 6 (3 9) ) . l valve.

Evaluator Cue: [1FW-3 6 (3 9 ) ] is closed.

COMMENTS: .

l l

Page 7 of 15 Revision: 0

RTL #A5.635.J l

I !

NUMBER TITLE 1PL-095 Warm Slow Start of Turbine Driven AFW Pump i

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

9.C Check drain valves and 9.1 Candidate verifies traps. that the traps are in service.

Evaluator Cue: Another operator has verified that the traps are in service.

9.2.C Candidate opens [1MS-14 ) .

Evaluator Cue: [1MS-14] is open.

9.3.C Candidate checks [1MS-

13) open.

Evaluator Cue: [1MS-13] is open.

COMMENTS:

l l

l l i r

Page 8 of 15 Revision: 0

RTL #A5.635.J t

l NUMBER TITLE 1PL-095 Warm Slow Start of Turbine Driven AFW Pump i

l STEP STANDARD (Indicate "SO for Sat. or "U" {

("C" denotes critical step) for Unsat.) 1 1

l 10.C Manually close the trip 10.1.C Candidate closes trip throttle valve. throttle valve.

l Evaluator Cue: The trip throttle is. closed.

10.2 Candidate checks status of A7-7 I

! annunciator with. ')

I Control Room.

l Evaluator Cue: The Control

Room reports A7-7 is alarming.

o l

1  !

COMMENTS: I l

l l-l l-

\

l i

i Page 9 of 15 Revision: 0 i

.. - ~. - .- . . . ~ . - _ _ . - . . - - . - . . _ _. - -

i RTL #AS.635.J NUMBER TITLE 1PL-095, Warm Slow Start of Turbine ~ Driven AFW Pump STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

Evaluator Cue: Another operator will fail air and open [TV-1MS-105A or B].

Assume (TV-MS-105A] is now open.

l 11.C Crack open Trip 11.1.C Candidate cracks open Throttle Valve. Trip Throttle Valve.

Evaluator-Cue: The Trip Throttle. Valve is beginning to open.

l l

l 11.2. Candidate observes for steam or hot water issuing from casing.

Evaluator Cue: There is no more water flowing from casing. The casing is warmed up.

!. COMMENTS:

l l

t Page 10 of 15 Revision: 0 L

RTL #A5.635.J NUMBER TITLE 1PL-095 Warm Slow Start of Turbine Driven AFW Pump STEP STANDARD (Indicate "S" for Sat. or "U3

("C" denotes critical step) for Unsat.)

12.C Stop the Turbine-Driven 12.1.C Candidate closes [1MS- 1 Auxiliary Feedwater 14].

Pump.

Evaluator Cue: [1MS-14] is closed, l

12.2. Verifies air restored to (TV-1MS-105A to

{- close the valve.

Evaluator Cue: The air.has been restored to (TV-1MS-105A]

by another operator and has been idependently verified. J l

12.3 Candidate verifies position of [TV-1MS-105A AND B].

Evaluator Cue: The control room reports that (TV-1MS-105A L

t AND B] are closed.

COMMENTS:

I Page 11 of 15 Revision: 0

RTL #A5.635.J I NUMBER TITLE 1PL-095 Warm Slow Start of Turbine Driven AFW Pump STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

13.C Fully open Trip 13.1.C Candidate continues to Throttle Valve. open Trip Throttle Valve.

Evaluator Cue: The Trip Throttle is full open.

13.2 Candidate checks status of A7-7 annunciator with Control Room.

Evaluator Cue: The Control Room reports A7-7 alarm has cleared.

COMMENTS:

i Page 12 of 15 Revision: 0 I

l l RTL #AS.635.J i

NUMBER TITLE i

1PL-095 Warm Slow Start of Turbine Driven AFW Pump l

l l STEP STANDARD (Indicate "S" for Sat. or "U" l

("C" denotes critical step) for Unsat.) l

14. Start the Turbine- 14. Candidate requests the Driven Auxiliary Control Room start the Feedwater Pump. Turbine-Driven Auxiliary Feedwater Pump.

Evaluator Cue: The Control l Room reports [TV-1MS -10 5A] is open (the Turbine-Driven Auxiliary Feedwater Pump is running.)

COMMENTS:

15. Verify the Turbine- 15.1 Candidate requests Driven Auxiliary Control Room to report Feedwater Pump the status of [FCV-recirculation flow 1FW-102).

control valve is open.

Evaluator Cue: The Control Room reports [FCV-1FW-102 is open.

Page 13 of 15 Revision: 0

i l

[

RTL #A5.635.J l

l l

l NUMBER TITLE l 1PL-095 Warm Slow Start of Turbine Driven AFW Pump STEP STANDARD (Indicate "S" for Sat. or "U" t

("C" denotes critical step) for Unsat.) l 15.2 Candidate observes local valve stem position for (FCV-1FW-102].

Evaluator Cue: The stem for

[FCV-1FW-102] indicates the valve is open.

1 COMMENTS:

1 I

i l

5 l

Page 14 of 15 Revision: 0

RTL #A5.635.J i

NUMBER TITLE 1PL-095 Warm Slow Start of Turbine Driven AFW Pump i

STEP STANDARD (Indicate "S" for Sat, or "U" l

("C" denotes critical step) for Unsat.)

l

16. Observe pump for proper 16. Candidate observes, operation, local oil pressure indication, pump vibration, oil and water / steam leaks, no excessive bearing or packing gland temperatures, backward rotation of the motor-driven auxiliary feedwater pumps and lube oil temperature.

Evaluator Cue: The pump is operating normally COMMENTS:

l Evaluator Cue: The NSS wants the pump to be run on i

recirculation for 15 minutes.

(This completes the JPM).

l STOP TIME:

5

(

l Page 15 of 15 Revision: 0 i

i

I BEAVER VALLEY JOB PERFORMANCE MEASURE i

- JPM QUESTION # 1 Describe the purpose of the two recirculation flow paths associated with the turbine driven auxiliary feedwater pump.

061000 K4.08 2.7/2.9 Obj: LP-SQS-24.1, ELO-6 Ref: 10M-24.1.B, Issue 4, Revision 1 ANSWER:

The primary recirculation flowpath provides minimum flow protection. The secondary recirculation flowpath provides cooling for the pump's oil cooler. ,

Conunents:

l I

i i n' l

1PL-095

. . _ . _ . . _ _ , . . _ _ _ ~ . - . . . _ . .

i i

BEAVER VALLEY JOB PERFORMANCE MEASURE 1

JPM QUESTION # 2 l What would happen if the turbine driven AFP lost oil pressure while feeding the steam generators?

i 061000 A2.04 3.4/3.8 Obj: LP-SQS-24,1, ELO-4 Ref: lOM-24.1.C Issue 4, Revision 2 ,

1 ANSWER: I i

The trip throttle valve would fail closed. (Oil pressure holds the latch which allows the l valve to be opened against spring pressure.)

l i

Comments:

l l

I l

4 4 -

l f I

l 1 PIA 95 1

. - - . - . . . . - . - - . - . . . . . . . . . . . . . . ~ .

l l.

l BEAVER VALLEY JOB PERFORMANCE MEASURE l

' l

• THIS SHEET TO BE GIVEN TO CANDIDATE

• JPM QUESTION # 1 Describe the purpose of the two recirculation flow paths associated with the turbine driven  ;

auxiliary feedwater pump.

1 .

l h

i-i 1PIr095

_ _ - _ . . . _ _ _ . _ _ _ _ _ _ . . _ . _ . . .__. _ .. ~. . _ _ _ _ _ . . . .~_.

BEAVER VALLEY JOB PERFORMANCE MEASURE I

• THIS SHEET TO BE GIVEN TO CANDIDATE

• JPM QUESTION # 2 What would happen if the turbine driven AFP lost oil pressure while feeding the steam generators?

A 1

I I

l i

l l

l I i

a 1 PIA 95

-....- .- . . - . - . . . ~ . . _ - . - . _ . . . _ . . . . - . . - . . . . . ~ . . - - - _ - _ . . ~ . . - _ . - . .

l l

. RTL #A5.635.J' BEAVER VALLEY JOB PERFORMANCE MEASURE -

l CANDIDATE DIRECTION SHEET l THIS SHEET TO BE GIVEN TO CANDIDATE

• 1 Read:

Task: lWarmSlowStartofTurbineDrivenAFWPump i

i i

INITIAL The plant is operating in Mode 3. The NSS has i CONDITIONS: decided to place the Turbine-Driven. Auxiliary j Feedwater Pump in service. The pump is to be run'  !

on recirc for this evolution.-

TASK STAN.: [1FW-P-2] placed in service in accordance with 10M-24.4.X, Turbine-Driven' Auxiliary Feedwater- {

i Pump Warm - Slow Start.

l t

INIT. CUE: Your supervisor directs you to perform warm-slow- ,

start of the Turbine-Driven Auxiliary Feedwater i Pump.

l l

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

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

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and

.announce your observations.

After completing the task, reread the Task Standard.

-- After determining the Task Standard has been met, announce "I '

4 have completed the JPM". Then hand back this sheet to the

. evaluator.

a Revision 9

Record Type #A9.330B DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit 1 l

l l

l 10M-24.4.X(ISS3)

TURBINE-DRIVEN AUXILIARY FEED PUMP WARM - SLOW START

' I.

1 I

l

\

Issue 3 Revision 1 Prepared by Date Pagesissued Effective Date G. P. Smith 09/13/95 X1 thru X6 SEP 21 1995 Reviewed by Date Validated by Date J. E. Burnecke 09/13/95 gfg Unit 1 Manager Date OSC Meeting No. Date l N/A Non-intent 09/18/95 l

Unit 2 Manager Date Approved y Date N/A f(, m{ 7lf9lp(

i K

t0R TRAINING ONLY C_ONTROLLED

i l

Beaver Valley Power Station Unit 1 10M-24.4.X(ISS3)

Steam Generator Feedwater System Issue 3 Revision 1 i Operating Procedures Page X 1 of 6

( TURBINE-DRIVEN AUXILIARY FEED PUMP WARM - SLOW START PURPOSE This procedure provides instructions for normal warm up and start up of the Turbine-Driven Auxiliary Feedwater Pump [1FW-P-2] in situations where the cold fast start in accordance with 10ST-24.4 is not desired. {

PRECAUTIONS

1. Safety glasses or a face shield, ear protection and gloves shall be worn when working around the turbine-drivan AFW pump [1PN-P-2] while it is running.

2. During the operation of [1FW-P-2], a steady stream of hot water may flow from the turbine exhaust piping on to the area where the operator monitors cump performance.

l INITIAL CONDITIONS

1. The NSS/ANSS has approved the starting of [1FW-P-2], Turb AFW pump.

l

2. The Auxiliary Feedwater System is aligned for the present plant mode.

INSTRUCTIONS

{ 1. Obtain the following for this procedure performance:

a. Key No. 0.19 for [1FW-36], the [1FW-P-2] "A" Header Discharge isolation, if l

[1FW-P-2] is to be run on recirc.

b. A copy of procedure 10M-24.4.V. " Trip Throttle Valve Resetting" Note: A sightglass full of oil wil! appear dark inside, and an empty sightglass will appear clear inside.

2. Check that the oil pump is ' primed by verifying oil pump suction line cross-tee sightglass shows lube oil is at or above pipe center line.

3. In order to prevent closing blowdown isolation trip valves [TV-1BD-100A, B and C]

when [1FW-P-2] is started, perform the following:

a. Shut [1FW-352], the [PS-1FW-157-1] root stop valve, to isolate [PS-1FW-157-1]

and prevent closing blowdown isclation trip valves [TV-1BD-100A, B, and C].

j b. Shut Instrument stop for [PS-1FW-157-3] to isolate and prevent closing blowdown isolation trip valves [TV-1BD-100A, B, and C]

c. Remove swage lock cap for [PS-1FW-157-1].

i d. Open pressure switch drain for [PS-1FW-157-1].

,. 4. Verify that the following conditions exist or make the necessary changes to achieve l \., the desired condition:

a. Trip throttle valve latched and open.

b. Oil dump valve for trip throttle valve latched. COR TRAINING Orr" -/

Beaver Valley Power Station Unit 1 Steam Generator Feedwater System 10M-24.4.X(ISS3)

Issue 3 Revision 1 Operating Procedures Page X 2 of 6 TURBINE-DRIVEN AUXILIARY FEED PUMP WARM - SLOW START

5. Align proper ventilation by opening the following (1BSP): l

a. [1VS-D-4-15A and 15B], AFW Pump Area Exhaust Dmprs. I

b. [1VS-D-4-12A and 12B], Quench Spray Pump Area Outside Air Dmprs. l

6. Establish continuous communications with the Control Room while any normal (NSA locked-open) discharge isolation valve [1FW-36 (39)] is closed (Tech. Spec.

4.7.1.2.b.3).

/

initial / Date

7. Unlock and manually close the normal discharge isolation valve [1FW-36 (39)] in the Auxiliary Feed Pump Room.

8.

a. Check the following traps in service by cnecking open their respective inlet and outlet valves T47, T53, T54, T55 and T60.

b. Open [1MS-14] outboard casing drain valve. l

c. Check open [1MS-13] inboard casing drain valve. l

9. Manually close the unit trip throttle valve.

{

a. Verify alarm A7-7, "STM UNAVAILABLE TO TURB DRIVEN FEED PP [1FW-P-2]", 'I is ON.

10. Open [TV-1MS-105A or B], AFW Turb Steam Sup A or B Trn Trip Viv, by failing air supply to the valve locally in main steam valve room.

CAUTION: DURING THE OPERATION OF THE [1FW-P-2], A STEADY STREAM OF HOT WATER MAY FLOW FROM THE TURBINE EXHAUST PIPING ON TO THE AREA WHERE THE OPERATOR MONITORS PUMP PERFORMANCE.

11. Manually crack open the Unit Trip Throttle Valve until the turbine starts rolling then leave it in that position until all of the water in the casing is gone and the turbine casing is warm.

12. After the turbine casing has warmed up, perform the following:

a. Close [1MS-14] outboard casing drain.

b. Close [TV-1MS-105A or B] by unisolating normal air supply to it in Step 10.

(1) /

Initial / Date

! /

(2) initial / Date -

c. Verify [TV-1MS-105A and B], AFW Turb Steam Sup A & B Trn Trip Vivs, are in k'

l -

c0R TRAINING OrM

Beaver Valley Power Station Unit 1 10M-24.4.X(ISS3)

Steam Generator Feedwater System issue 3 Revision 1 Operating Procedures Page X 3 of 6 TURBINE-DRIVEN AUXILIARY FEED PUMP WARM - SLOW START Note: It is possible that the throttle valve may have to be reset before being taken to the FULL OPEN position.

d. Continue to open the Unit Trip Throttle Valve full open.

e. Verify alarm A7-7, "STM UNAVAILABLE TO TURB DRIVEN FEED PP [1FW-P-2]", j is OFF.

13. Start [1FW-P-2], Turb AFW Pump, by opening [TV-1MS-105A or 105B], AFW Turb Steam Sup A or B Trn Trip Viv.

14. Check [FCV-1FW-102] open by verifying:

a. Red open light on BB-C is ON. l

b. Local valve stem position.

15. After the pump has started, check the pump for proper operation:

a. Oil pump develops 2: 7 psig (Local [PI-1LO-3C]). l

b. No excessive vibrations.

c. No tube oil leaks.

d. No abnormal water or steam leaks.

e. No excessive bearing temperatures.

f. No excessive packing gland temperature (i.e., not too hot to touch stuffing box).

g. Inspect for steam leaks between the trip valves and the Terry Turbine casing fla nge.

h. Verify [1FW-P-3A and 3B] AFW Pumps,are not rotating backwards. .

l

i. Verify tube oil does not overheat.

16. Run [1FW-P-2] on recirc as desired by the NSS/ANSS.

17. Shut down [1FW-P-2], Turo AFW Pump, using one of the following methods: l

a. Manually trip the overspeed trip mechanism AND Perform either of the following: l

1) Close [TV-1MS-105A or B], AFW Turb Steam Sup A or B Trn Trip Viv.

OR

b. Shut off steam to [1FW-P-2] by closing [TV-1MS-105A or B], AFW Turb Steam Sup A or 5 Trn Trip Viv.

18. Manually close or verify the Unit Trip Throttle Valve is in the closed position. l

a. Verify alarm A7-7, "STM UNAVAILABLE TO TURB DRIVEN FEED PP [1FW-P-2]", g is ON.

t0R TRAINING On LY

l l

I I

l Beaver Valley Power Station Unit 1 Steam Generator Feedwater System 10M-24.4.X(ISS3)

Operating Procedures Issu'e 3 Revision 1 i

Page X 4 of 6 TURBINE-DRIVEN AUXILIARY FEED PUMP WARM - SLOW START

19. From the Control Room, BB-C:

l a. Place or verify selector switches for the following valves in the CLOSE position (green lights ON): {

1) [TV-1MS-105A], AFW Turb Steam Sup A Trn Trip Viv. l (1) /

Initial / Date (2) /

Initial / Date

2) [TV-1MS-105B], AFW Turb Steam Sup B Trn Trip Viv.

(1) /

Initial / Date '

(2) / j Initial / Date 1

20. Manually open AND Lock the normal discharge isolation valve [1FW-36 (39)] in the Auxiliary Feed Pump Room.

(1) /

Initial / Date (2) / (.

Initial / Date l

21. Reset the trip throttle valve in accordance with 10M-24.4.V. " Trip Throttle Valve Resetting" f (1) /

Initial / Date (2) /

Initial / Date

22. Verify that the turbine overspeed device is latched.

(1) /

Initial / Date (2) /

initial / Date

23. Unisolate [PS-1FW-157-1 and 3], Discharge Pressure Switches for [1FW-P-2] by Performing the following: {

l a. Close [PS-1FW-157-1] drain valve.

l (1) /

&, initial / Date

.(2) /

(

C0R TRAINING ONLY

Beaver Valley Power Station Unit 1 Steam Generator Feedwater System 10M-24.4.X(ISS3) issue 3 Revision 1

( Operating Procedures '

Page X 5 of 6 TURBINE-DRIVEN AUXILIARY FEED PUMP WARM - SLOW START

b. Replace swage lock cap.

(1) /

Initial / Date (2) /

Initial / Date

c. Open [1FW-352], Root Stop for [PS-1FW-157-1]. l (1) /

Initial / Date (2) /

Initial i Date

d. Open instrument stop valve for [PS-1FW-157-3]. l (1) /

Initial / Date (2) /

Initial / Date

24. , Verify closed [FCV-1FW-102], Turb Driven AFW Pump Recirc Viv, (green light ON)

(BB-C).

(1) /

Initial / Date (2) /

l Initial / Date

25. At Building Service Panel, place or verify the following dampers in " CLOSED" position.

a. [1VS-D-4-12A], Quench Spray Pump Area Outside Air Dmpr. l

/

Initial / Date

b. [1VS-D-4-12B], Quench Spray Pump Area Outside Air Dmpr.

l

/

Initial / Date

c. [1VS-D-4-15A], AFW Pump Area Exhaust Dmpr.

[ /

Initial / Date

d. [1VS-D-4-15B], AFW Pump Area Exhaust Dmpr.

{

initial / Date t0R TRAlu)NG 0

)

Beaver Valley Power Station Unit 1 10M-24.4.X(ISS3) ,

i Steam Generator Feedwater System issue 3 Revision 1 i

i Operating Procedures Page X 6 of 6 TURBINE-DRIVEN AUXILIARY FEED PUMP WARM - SLOW START

(

26. At Building Service Panel, place the following dampers in " AUTO" position:

a. [1VS-D-4-12A], Quench Spray Pump Area Outside Air Dmpr. l (1) /

Initial / Date (2) /

initial / Date

b. [1VS-D-4-12B], Quench Spray Pump Area Outside Air Dmpr. l (1) /

Initial / Date (2) /

Initial / Date

c. [1VS-D-4-15A], AFW Pump Area Exhaust Dmpr.

(1) /

Initial / Date (2) /

Initial / Date .

d. [1VS-D-4-158], AFW Pump Area Exhaust Dmpr. .!.

Initial / Date (2) /

initial / Date REFERENCES i

Note: All references used prior to 02/09/89 are located in Section 5.

1. OMDR 1-89-0038 (Issue 2, Revision 32).

2. OMDR 1-93-1072 (Issue 3, Revision 0).

3. TER 9707; OMCN 1-95-173 (Rev.1).

l l

? COR TRAINING ONLY .

b

g Record Type #A9.3308 l

DUQUESNE LIGHT COMPANY l Beaver Valley Power Station l

Unit 1 1

i 1

1ou-24.4.v(Issa)

[1FW-P-2] TRIP THROTTLE VALVE RESETTING

!( . .

I 1

l Issue 3 Revision 1 I

Prepared by Date Pages issued Effec;;ve Date L. R. Montanari ' 07/22/96 V1 thru V2 M 29 1996 I Reviewed by Date Validated by Date J. E. Burnecke 07/22/96 N/A OSC Meetmg No. Date Approv y ate OMCN 1-96-175 y ff 1 c0R TRAINING OnlLY cennone BVPS UN0T 1

Beaver Valley Power Station Unit 1 Steam Generator Feedwater System 10M-24.4.V(ISS3)

Operating Procedures Issue 3 Revision 1 Page V 1 of 2

[1FW-P-2] TRIP THROTTLE VALVE RESETTING PURPOSE To reset the Trip Throttle Valve and latch the mechanical overspeed trip device. This will ensure the overspeed protection and low oil pressure protection are available to [1FW-P-2].

PRECAUTIONS 1

1. Ensure no direct steam flow path to the valve before resetting the valve.

INITIAL CONDITIONS

1. No Automatic or Manual initiating signal is present to [1FW-P-2].

2. [1FW-P-2] has been stopped and its shaft is not rotating.

INSTRUCTIONS

1. Perform one of the following: i

a. Verify the following valves are closed at Benchboard Section C:

1) [TV-1MS-105A] AFW Turb Steam Sup A Trn Trip Viv.

2) [TV-1MS-1058] AFW Turb Steam Sup B Trn Trip Viv.

OR

b. Verify closed [MOV-1MS-105] AFW Turb Steam isol Viv at Benchboard Section A.

2. Latch the mechanical overspeed trip device with the oil pressure dump valve as  !

follows at [FW P-2] (refer to Figure 24-17):

a. Manually push the oil pressure dump valve cap down.

b. Then push the latch on the overspeed trip lever in to latch the cap.

i

3. Verify the trip throttle valve is in the shut position.  ;

4. Turn the handwheel in the clockwise direction until the sliding nut and latch lever raise to where they will engage with the trip hook (Refer to Figure 24-17).

5. Slowly open the trip throttle valve by turning the handwheel counterclockwise until it stops in the full open position.

l 1

I c0R M#

Beaver Valley Power Station Unit 1 l Steam Generator Feedwater System 10M-24.4.V(ISS3)

Operating Procedures issue 3 Revision 1 Page V 2 of-2

[1FW-P-2] TRIP THROTTLE VALVE RESETTING

(

Note: In an emergency situation, Step 6 does not need to be performed.

Note: If [MOV-1MS-105] is closed, Annunciator A7-7, STEAM UNAVAILABLE TO TURBINE DRIVEN FEED PUMP, will not be extinguished to verify proper operation of the trip-throttle alarm circuit.

G.

With the latch lever and trip hook engaged, verify the proper operation of the trip ,

throttle valve as follows: l

a. Turn the handwheel clockwise to close the valve.

b. Contact the Control Room operator to verify control room annunciator A7-7 (steam unavailable to Turbine Driven Aux. Feed pump) alarms.

c. Re-open the valve by turning the handwheel counterclockwise until it stops in full open position.

7. After opening the valve full open, turn the handwheel clockwise 1/4 turn to 1/2 turn to prevent locking of the valve in the open position from expansion of valve parts.

8. Close or verify closed the following valves at Benchboard Section C:

a. [TV-1MS-105A] AFW Turb Steam Sup A Trn Trip Viv.

(

b. [TV-1MS-105B] AFW Turb Steam Sup B Trn Trip Viv.

9. Open or verify open [MOV-1MS-105] AFW Turb Steam isol Viv at Benchboard Section A.

a. Independently Verify that [MOV-1MS-105], AFW Turb Steam isol Viv, is Open AND Document in 10M-54.2 S1-4(5)(6), Nuclear Control Operators Report. I

10. Verify control room annunciator A7-7 (steam unavailable to Turbine Driven Aux. ,

Feed Pump) has extinguished. l l

1 REFERENCES l

1. OMDR 86-1579 (Issue 2, Revision 23).

2. OMDR 87-248 (Revision 24),

3. OMDR 1-88-1604 (Revision 30). l l 4. OMDR 1-93-0835,1072 (Issue 3, Revision 0).

5. OMCN 1-96-175 (Revision 1). i l

t ('

\

l

l \

l B:iv:r Valley Pownr Station Unit i 10M-24.5 l Steam Generator Feedwater System issue 4 Revision 0 Figures and Tables l Page 1 of 1 '

FIGURES AND TABLES l

1 I

~

5 5 5

2 0-5 E

5 I I E3 ,

5 M  !

a o'

/ H

/

i E

a v ,,'  :

I!

90 F r i

li v :4 m

1

(' 11l_ a/N d

3 5{ D [d g% \j \ '

l l- / \ $

~

U 5 ) g 1_

e &

$ I i

1 55 A z i

<5

"" 5 '

e o

a  :- ;

I 5 _ s o "' >*# i l

IId I x

> o ,

l C'~~ V c. $ O cm B v, =! 1

-- ow s o l C_2 ~h w o uky

,4uu-

_o TRIP THROTTLE VALVE RESETTING FIGURE 24-17 QQY CQ i f

1 RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual i

l OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training  ;

OJT CHECKLIST /JPM TITLE: Place CCR Heat Exchanger in Service JPM NO.: 1PL-096 COMPUTER CODE: N/A I

Revision No. Date Revision No. Date l

l PREPARED BY: DATE:

l APPROVED FOR f IMPLEMENTATION: PATE:

l Director, Operations Training, or Designee B

l Revision 9 l

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: 1PL-096. Place CCR Heat Exchancer in Service Revision Acoroval No. Brief Description Revised by: Signature Date I

l l

i I

I l

l Revision 9

. . . - . . - . .-. - - - .-..-.-. ..... _. .._ _ - - .-..- -....~.- -. -

BEAVER VALLEY JOB PERFORMANCE MEASURE

EVALUATOR COVER SHEET -

i JPM Number: 1PL-096 Rev: 0 System #: 008 Faulted: O l

JPM

Title:

Place CCR Heat Exchanger in Service f K/A

Reference:

008 000 G09 3.4/3.3 Task ID #: 008 003 0121

JPM Designation

NO RO X SRO .

JPM Application: X NRC X Initial Exam l Training l

l Evaluation Method LOCATION TYPE l arform Plant Site Training l 0 .imulate Simulator Annual Requal. Exam Classroom OJT j Initial Operator Exam

! Administered By: Other:

O Bv-T 1

O NRC Other:

1 l Evaluation Results l Performer: Name: Employee No:

Results SAT Time (minutes) i UNSAT* Allotted: 40 Actual:

l Time Critical: 0 Yes x No

!

• Comments' (Required for UNSAT Evaluation) :

I

] 3 i Evaluation Results Check here if same as above

) Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

i Observer 4: Name Employee No:

j Time (minutes) Results l Question ID Allotted Actual SAT UNSAT*

I Question #1 4 0

) Employee No:

i Question #2 s O

} Employee No:

)

• Comments (Required for UNSAT Evaluation) :

4

! i 4 j'

Evaluator (Print) : Organization:

) Evaluator Signature Date:

Revision 9

. .~ _ _ _- _ _ _ _ _ . . . .

. _ . ~ . _ - . . _ _ . _ _ , _ - _ _

RIL liA5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR D,IRECTION SHEET JPM NUMBER: 1PL-096 JPM TITLE:

Place CCR Heat Exchanger in Service l RECOMMENDED ,

STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to perform (simulate) the task Place CCR Heat Exchanger in Service.

1 INIT. CONDITIONS: The 1B CCR Heat Exchanger has been isolated and drained due to suspected leakage. It has been determined that there is no .

leakage in this heat exchanger. The 1B CCR l Heat Exchanger is now ready to be returned 1 to service. The river water side of the heat exchanger is filled and vented. The ,

1A heat exchanger is in service, the 1C has '

river water aligned to it.

TASK STAN.:

[1CC-E-1B] filled and placed in service in accordance with 10M-15.4.E, Placing a CCR Heat Exchanger in Service.

INIT. CUE:

Your supervisor directs you to fill and l

vent the 1B-CCR Heat Exchanger and place it i

in service in accordance with 10M-15.4.E, Placing a CCR Heat Exchanger in Service.

j

REFERENCES:

10M-15.4.E Issue 4, Revision 4 TOOLS: NONE HANDOUT: 10M-15.4.E, Placing a CCR Heat Exchanger in

l. Service. Prints 15-1, 30-3, 8-5, 8-6.

l i

l Revision 9 i

. . - .. . . . . - . - . . . - . . - - - . - ~ . . ~ . . . - . - - ~ - . . - . . - . ~ . . . ...-..- ~.

~

RTL #AS.635.J.

1 1

1 NUMBER- TITLE i 1PL-096 Place CCR Heat Exchanger in Service i

STEP STANDARD (Indicate "S" for Sat. or "U"

.("C" denotes critical step) for Unsat.)

i i

1 l

START TIME: ,

l Candidate locates and reviews procedure.

i

l. Evaluator Cue: Provide

! candidate with copy of 10M-15.4.E. and system prints.

1.C ' Verify that heat 1.1.C Candidate verifies '

, exchanger inlet and [1CCR-13] is closed.

outlet CCR valves are  :

closed.

Evaluator Cue: [1CCR-13] is closed.

l i 1

1.2.C Candidate verifies l

[ [1CCR-16] is closed. J l

Evaluator Cue: [1CCR-16] is

closed.

l 1 1 j COMMENTS:

1

, a-s l

Page 1 of 12 Revision: 0

- - . . ~. , . _ . . . . . - . . . . - . - . . . -. . - ... _ . ... ~ .- . . . - . . . -

l-RTL #AS.635.J l

LI NUMBER TITLE I

1PL-096 Place CCR Heat Exchanger in Service L

, 1 i

i 1

1 STEP STANDARD l I

(Indicate "S" for Sat. or "U" 1

("C" denotes critical step) for Unsat.) I l

l l

.2. Check Primary Water 2.1 Candidate verifies i valve alignment. [1BR- 54 6] is closed. I Evaluator Cue: (1BR-546] is I closed.

2.2 Candidate verifies (1BR-548] is closed.

Evaluator Cue: [1BR-548] 10 closed.

2.3 Candidate verifies

[1BR-550] is closed.

1 Evaluator Cue: [1BR-550] is closed.

2.4 Candidate verifies

[1BR-551] is closed.

Evaluator-Cue: [1BR-551] is j closed, t

f-}

Page 2 of 12 Revision: 0 i

I RTL #AS.635.J

(

NUMBER TITLE l 1PL-096 Place CCR Heat Exchanger in Service l

l STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

l 2.5 Candidate verifies

[1BR-552) is closed.

Evaluator Cue: [1BR-552] il[

closed. l l

l COMMENTS:

l

, i i

3.C Install temporary fill 3.1 Candidate locates 1 hose, temporary hose.

L Evaluator Cue: The temporary

fill hose will be simulated, there are no flushing requirements.

! 3.2.C Candidate simulates connecting temporary hose downstream of i

[1BR-548].

i L

i a

I l

l Page 3 of 12 Revision: O

RTL #AS.635.J NUMBER TITLE iPL-096 Place CCR Heat Exchanger in Service L ..

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

3.3 Candidate notifies Chemistry that a CCR heat exchanger is being filled.

Evaluator Cue: Chemistry acknowledges report.

COMMENTS:

4.C Perform lineup in 4.1 Candidate checks preparation for filling (1CCR-168] closed.

heat exchanger.

Evaluator Cue: [1CCR-168] is closed.

4.2 Candidate checks (1CCR-169] closed.

Evaluator Cue: [1CCR-169] is closed.

(

i

{

Page 4 of 12 Revision: 0

I RTL #A5.635.J NUMBER TITLE 1PL-096 Place CCR Heat Exchanger in Service STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

4.3 Candidate connects temporary hose to

[1CCR-168 or 169].

Evaluator Cue: The hose will be simulated.

4.4 Candidate verifies

[1CCR-166 and 167) are open.

Evaluator Cue: Another operator will manipulate the vent valves. Both [1CCR-166 and 167) are open.

COMMENTS:

I l

i l l r

l I

Page 5 of 12 Revision: 0

RTL #A5.635.J l

l NUMBER TITLE l 1PL-096 Place CCR Heat. Exchanger in Service i STEP STANDARD '

(Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

i Evaluator Note: The following step will be performed by another operator. Give the following cue.

i 5

5. Align radiation monitor 5.1. Candidate closes (1BR-flush line. 839], opens (1BR-837],

(1BR-838] and (1BR-648].

Evaluater Cue: [1BR- 83 9] is closed. [1BR-837, 1BR-838, and 1BR-648] are open

• COMMENTS:

L b

i

) !

l 1

Page 6 of 12 Revision: 0 ,

1

RTL #A5.635.J NUMBER TITLE 1PL-096 Place CCR Heat Exchanger in Service STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

6.C Begin to fill heat 6.1.C Candidate slowly opens exchanger. [1BR-548].

Evaluator Cue: [1BR-548] is open. There are no leaks.

Another operator will standby and monitor the temporary fill hose 6.2.C Candidate opens [1CCR-168 or 169].

5 valuator Cue: [1CCR-168 (or 169)]is open.

Evaluator Cue: Water is now issuing from vent.

1 COMMENTS:

l l

I 1

i Page 7 of 12 Revision: 0

l l RTL #A5.635.J l

l l NUMBER TITLE 1PL-096 Place CCR Heat Exchanger in Service l STEP STANDARD l (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

7.C Stop filling heat 7.1. Candidate closes exchanger. [1CCR-166].

Evaluator Cue: The other operator has closed [1CCR-166) t

[ 7.2. Candidate closes

[1CCR-167).

Evaluator Cue: The other operator has closed [1CCR-167) 7.3.C Candidate clos;s (1BR-548).

Evaluator Cue: [1BR-548]is closed.

! 7.4.C Candidate closes l

[1CCR-168).

Evaluator Cue: [1CCR-168]is closed.

COMMENTS:

Page 8 of 12 Revision: 0

RTL #AS.635.J NUMBER TITLE 1PL-096 Place CCR Heat Exchanger in Service i

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

l I l 1

1 l

l I

i J

Page 9 of 12 Revision: 0

RTL #AS.635.J l l

NUMBER TITLE ,

1PL-096 Place CCR Heat Exchanger in Service I

STEP STANDARD I l (Indicate "S" for Sat. or "U" i -("C" denotes critical step) for Unsat.)

l l-i Evaluator Note: The following j step will be performed by l

another operator. Give the ,

following cue. '

8. Align radiation monitor 8. Candidate Closes [1BR-flush line. 837],-[1BR-838), and

[1BR-648] and opens  !

[1BR-839],,  ;

l I

Evaluator Cue: [1BR-837, IBR- '

838, and 1BR-648] are closed

[1BR-839]is open.

i i

COMMENTS:

. i l

I 1

l i

s l

I

,)

,' i Page 10 of 12 Revision: 0 l

. _ . . m-. . _ _ . . . . . _ _ _ _ . . . . - m _. - _ _ . - _ . _ _ _ _ . _ . _ _ . - . . _ . . . . . _ , . - - _ _ _ . _ _ _ . . . _ . _ . _ .

RTL #AS.635.J NUMBER- TITLE j 1PL-096 Place CCR Heat Exchanger in Service ,

b STEP STANDARD .

(Indicate "S" for Sat. or "U" [

("C" denotes critical step) for Unsat.)

9. Disconnect temporary 9. Candidate simulates hose from (1CCR-168] removing temporary (or [1CCR-169]). hose from [1CCR-168]

(or . [1CCR-169] ) .

Evaluator Cue: The temporary I hose is removed from [1CCR- t 168] ([or 1CCR-169]). '

-i i f i

COMMENTS:

e i

10.C Open heat exchanger 10.1.C Candidate opens [1CCR-inlet valve. 13].

Evaluator Cue: [1CCR-13] is open.

I 10.2 Candidate removes temporary hose from I

[1BR-548]. I I

Evaluator Cue:-Temporary hose is removed from [1BR-548).

?

. j 1

Page 11 of 12 Revision: 0

l RTL #AS.635.J NUMBER TITLE 1

1PL-096 Place CCR Heat Exchanger in Service l

l l

I 1

1 l

STEP STANDARD l (Indicate "S" for Sat. or "U" I

("C" denotes critical step) for Unsat.)

COMMENTS:

l l

l i

I I

l l

i <

4 t.

Page 12 of 12 Revision: 0

RTL #AS.635.J 4

NUMBER TITLE 1PL-096 Place CCR Heat Exchanger in Service STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

11.C Open heat exchanger, 11.C Candidate monitors River Water outlet river water pressure valve. and opens [1RW-189].

Evaluator Cue: Report slight drop in River Water pressure as candidate opens valve.

Report River Water pressure stable at 27 psig.

)

l COMMENTS: I l

l 12.C Open heat exchanger 12.C Candidate opens (1CCR-outlet valve. 16] .

Evaluator Cue: [1CCR-16) is open.

l COMMENTS:

4-f I

i Page 13 of 12 Revision: 0

..__. . _ _ _ . . .. _ _ _ _ _ - - . _ = . . _ _ . _ _ . _ - . . - . - _ _ _ _ _ . _ _

1 RTL #AS.635.J NUMBER TITLE 1PL-096 Place CCR Heat Exchanger in Service i

I STEP STANDARD (Indicate "S" for Sat. or "U"  !

("C" denotes critical step) for Unsat.)

l 13.C Align heat exchanger to 13.C Candidate opens [1RW-

radiation monitor. 441).

l Evaluator Cue: [1RW-441) is l open. l COMMENTS:

l

14. Report that the 1B CCR 14. Candidate reports that l heat exchanger has been the 1B CCR heat placed in service. exchanger has been '

placed in service.

l COMMENTS:

STOP TIME:

l l

l

{

l- i Page 14 of 12 Revision: 0 l . . _ _ - - - _,

l l l-l 1

( BEAVER VALLEY JOB PERFORMANCE MEASURE l

l l JPM QUESTION # 1 Explain the expected response of the CCR temperature control valve, TCV-CC-100, to j the actionjust taken.

l 008 000 A1.02 2.9/3.1 Obj: LP-SQS-15.1, ELO-5 1

! Ref: lOM-15.1.D, Issue 4, Revision 1 l

ANSWER: 1 TCV-CC-100 should throttle in the open direction, to allow more flow to bypass the inservice heat exchangers and to maintain a constant CCR temperature.

{

1 Comments:

l

I l

IPL-096

.- .. -. . . -. . . . . . - - . ~ . - - . . . . . . . . .

l  !

l 1

BEAVER VALLEY JOB PERFORMANCE MEASURE l 1

)

L -

]

l l l l JPM QUESTION # 2 How could an excessively high CCR temperature lead to a plant trip? (Assume full power .

operation.)

i 008 000 Kl.02 3.3/3.4 l Obj: LP-SQS-6.3 ELO-9 ,

Ref 10M-6.4. AAZ, Issue 4, Revision 3

. I

! 1

)

ANSWER:

High CCR temperatures would cause overheating of key components including the RCP bearings. The plant could be required to be tripped on high RCP bearing temperature.

i

! Comments:

l

(

I i

I l

IPL-096

BEAVER VALLEY JOB PERFORMANCE MEASURE l-

• THIS SHEET TO BE GIVEN TO CANDIDATE

• u l- JPM QUESTION # 1 l

Explain the expected response of the CCR temperature control valve, TCV-CC-100, to the actionjust taken.

l l.

l- 1

-l l

1 i-l'

\-

J

(

i 1PIr096 l

l

. -~ . , .

.. . -.- .. - - . . . . . . - . . - . _ . - - . . . _ . . . . - . - . . . _ . . - - . - ._ ._~ .-. . . - .

I l

BEAVER VALLEY JOB PERFORMANCE MEASUPS l

• THIS SHEET TO BE GIVEN TO CANDIDATE *

! 1 JPM QUESTION # 2 l 1

l i

E How could an excessively high CCR temperature lead to a plant trip? (Assume full power operation.)

I l

l i.

f I

a I

i l

l l J

,. i 1

l t

i l

l:

1 l

i e

t IPL-096

RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET l l

THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Task: lPlaceCCRHeatExchangerinService l

I l

l

! INITIAL The 1B CCR Heat Exchanger has been isolated and ONS:

drained due to suspected leakage. It has been determined that there is no leakage in this heat l

exchanger. The 1B CCR Heat Exchanger is now ready j to be returned to service. The river water side i of the heat exchanger is filled and vented. The  :

1A heat exchanger is in service, the 1C has river l water aligncA to it. l TASK STAN.: [1CC-E-1B] filled and placed in service in accordance with 10M-15.4.E, Placing a CCR Heat  ;

Exchanger in Service.

INIT. CUE: lYoursupervisordirectsyoutofillandvent the 1B-CCR Heat Exchanger and place it in service in accordance with 10M-15.4.E, Placing a CCR Heat Exchanger.in Service.

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

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

Simulate performance or perform as directed the required task.

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

l l

After completing the task, reread the Task Standard.

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

Revision 9

. . _ . - . . . . - _ . - - . - _ . . . . . . ~ . . . - . . . ~ _.

\

l Record Type #A9.330B

! DUQUESNE LIGHT COMPANY i Beaver Valley Power Station i Unit 1 10M-15.4.E l

PLACING A CCR HEAT EXCHANGER IN SERVICE Issue 4 Revision 4 v

Prepared by Date Pagesissued Effective Date C. Eberle 03/27/96 E1 thru E7 APR 0 91996 Reviewed by Date Validated by Date F. J. Schaffner 03/27/96 N/A OSC Meeting No. Date Approved by Date Non-Intent 9 T7 f4 c g c g77 gfj4 i

I c0R TRAINLNG ONLY cmmoLLs

Beaver Valley Power Station Unit 1 10M-15.4.E j Reactor Plant Component and Neutron Tank Cooling Water issue 4 Revision 4 l Operating Procedure Page E 1 of 7 PLACING A CCR HEAT EXCHANGER IN SERVICE l

1. PURPOSE I This procedure provides the steps necessary to place a CCR heat exchanger in service.

II. PRECAUTIONS & LIMITATIONS A. There should never be more pumps than heat exchangers in service.

B. The CCRS uses molybdates for chemistry control. Take all applicable precautions with spills and leaks.

C. An RPRW Pump may auto start when placing a CCR heat exchanger into service. This is an expected sequence and does not constitute a reportable event.

Ill. INITIAL CONDITIONS A. The river side of the CCR heat exchanger to be placed in service has been filled and

vented.

IV. INSTRUCTIONS Note: All valves and components in this procedure are located in the Aux Bldg,735, unless otherwise noted.

A. If the heat exchanger is in standby (filled and vented with the inlet isolation valve open), Verify the following:

1. The CCR heat exchanger to be placed in service has been filled AND vented in accordance with 10M-15.4.L " Filling and Venting the CCRS".

2. The CCR heat exchanger to be placed in service is pressurized AND the outlet

! isolation valve is shut.

B. If the heat exchanger has been isolated and drained, Perform the following:

1. Verify that the CCR heat exchanger inlet AND outlet CCR isolation valves are closed for the heat exchanger to be placed in service.

2. Check Closed the following valves:

l a. [1BR-546], Aux Steam Rtrn Water Monitor Flush, (Aux Bldg,735, Primary l

Sample Room).

I b. [1BR-548], Flush Isolation for [RM-1RW-101], (Aux Bldg,735).

c. [1BR-550], Low Level Waste Monitor Flush, (Aux Bldg,722, Above

[1 BR-P-28], 730').

I d. [1BR-551], Laundry Waste Monitor Flush, (Aux Bldg,722 By [1LW-TK-6B]).

e. [1BR-552), Pri Water to [RM-1CC-100] Isol, (Aux Bldg,722).

8 l t0R TRAINING OriLY l

L l .

i l Beaver Valley Power Station Unit 1 10M-15.4.E Reactor Plant Component and Neutron Tank Cooling Water issue 4 Revision 4 Operating Procedure Page E 2 of 7 PLACING A CCR HEAT EXCHANGER IN SERVICE

(' )

3. Install a temporary heat exchanger fill hose as follows: j

a. Obtain a temporary hose, rated for at least 150 psig, of sufficient length to connect from the hose connection downstream of [1BR-548], Flush Isolation for [RM-1RW-101], to the applicable CCR heat exchanger drain valve. l

b. Review the hose flushing requirements with Chemistry and flush the hose if l applicable.

c. Connect the temporary fill hose to the hose connection downstream of

[1BR-548], Flush Isolation for [RM-1RW-101]. ,

l

4. Notify Chemistry that a CCR heat exchanger is being filled with PG water AND to l expect a dilution of the CCR System. I l

C. If [1CC-E-1 A], Reactor Plant Component Cooling Water Heat Exchanger 1 A, has been drained, Fill AND Vent the heat exchanger as follows:

1. Check Closed [1CCR-164] AND [1CCR-165], CCR HX 1 A Drain Valves.

t

2. Connect the temporary fill hose to [1CCR-164(165)], CCR HX 1 A Drain Valve.

3. Check Open [1CCR-162] AND [1CCR-163], CCR HX 1 A Vent Valves.

4. Align the radiation monitors flush line as follows: (Aux Bldg 722 West)

Close [1BR-839], Flush Line Drain.

a.

b. Open [1BR-837], Flush Line Isol.

c. Open [1BR-838], Flush Line Isol.

d. Open [1BR-648], Rad Monitors Flush Water Sup Isol.

Note:

• An operator should be continuously stationed in the area of the temporary fill hose while [1BR-548] is open to monitor for leakage and/or spills.

• The heat exchanger vent effluent should be directed to the Aux Bldg 735' floor drains or a suitable container.

5. Perform the following to align the fill supply AND begin heat exchanger fill:

a. Slowly Open [1BR-548], Flush Isolation fer [RM-1RW-101], AND Check the temporary hose for leaks.

b. Open [1CCR-164(165)], CCR HX 1 A Drain Valve.

i

^

1 I

l Beaver Valley Power Station Unit 1 10M-15.4.E g Reactor Plant Component and Neutron Tank Cooling Water issue 4 Revision 4

=

Operating Procedure Page E 3 of 7 PLACING A CCR HEAT EXCHANGER IN SERVICE Note: When the second vent valve is closed, [1BR-548], Flush Isolation fut i

[RM-1RW-101], should be closed without delay to avoid prolonged periods of pressurizing the heat exchanger and temporary hose from PG water pressure.

6. Close the following valves when venting is complete:

a. [1CCR-162], CCR HX 1 A Vent Valve.

b. [1CCR-163], CCR HX 1A Vent Valve.

c. [1BR-548], Flush Isolation for RM-1RW-101.

d. [1CCR-164(165)], CCR HX 1 A Drain Valve.

7. Align the radiation monitors flush line as follows: (Aux Bldg 722 West)

a. Close [1BR-648], Rad Monitors Flush Water Sup Isol.

i b. C:ose [1BR-837], Flush Line Isol.

c. Close [1BR-838], Flush Line Isol.

d. Open [1BR-839], Flush Line Drain.

8. Disconnect the temporary hose from [1CCR-164(165)], CCR HX 1A Drain Valve.

9. Open [1CCR-12], CCR HX 1 A Inlet isolation Valve.

D. If [1CC-E-1B], Reactor Plant Component Cooling Water Heat Exchanger 18, has been drained. Fill AND Vent the heat exchanger as follows:

1. Check Closed [1CCR-168] AND [1CCR-169], CCR HX 18 Drain Valves.

l 2. Connect the temporary fill hose to [1CCR-168(169)], CCR HX 18 Drain Valve.

3. Check Open [1CCR-166] AND [1CCR-167], CCR HX 1B Vent Valves.

4. Align the radiation monitors flush line as follows:(Aux Bldg 722 West)

a. Close [1BR-839], Flush Line Drain.

b. Open [1BR-837], Flush Line isol.

c. Open [1BR-838], Flush Line Isol.

d. Open [1BR-648], Rad Monitors Flush Water Sup Isol.

c0R M

i i

I l

l Beaver Valley Power Station Unit 1 10M-15.4.E l

Reactor Plant Component and Neutron Tank Cooling Water issue 4 Revision 4 Operating Procedure Page E 4 of 7 PLACING A CCR HEAT EXCHANGER IN SERVICE (t Note:

• An operator should be continuously stationed in the area of the temporary fill

, hose while [1BR-548] is open to monitor for leakage and/or spills.

• The heat exchanger vent effluent should be directed to the Aux Bldg 735' floor l drains or a suitable container.

I

5. Perform the following to align the fill supply AND begin heat exchanger fill:

a. Slowly Open [1BR-548], Flush Isolation for [RM-1RW-101], AND Check the temporary hose for leaks.

b. Open [1CCR-168(169)], CCR HX 1B Drain Valve.

Note: When the second vent valve is closed, [1BR-548], Flush Isolation for

[RM-1RW-101], should be closed without delay to avoid prolonged periods of pressurizing the heat exchanger and temporary hose from PG water pressure.

6. Close the following valves when venting is complete:

a. [1CCR-166], CCR HX 1B Vent Valve.

b. [1CCR-167], CCR HX 1B Vent Valve.

c. [1BR-548], Flush Isolation for [RM-1RW-101].

d. [1CCR-168(169)], CCR HX 1B Drain Valve.

7. Align the radiation monitors flush line as follows: (Aux Bldg 722 West)

a. Close [1BR-648], Rad Monitors Flush Water Sup Isol.

b. Close [1BR-837], Flush Line isol.

c. Close [1BR-838], Flush Line Isol.

d. Open [1BR-839], Flush Line Drain.

8. Disconnect the temporary hose from [1CCR-168(169)], CCR HX 18 Drain Valve.

9. Open [1CCR-13], CCR HX 18 inlet isolation Valve.

E. If [1CC-E-1C], Reactor Plant Component Cooling Water Heat Exchanger 1C, has been l

drained, Fill AND Vent the heat exchanger as follows:

[ 1. Check Closed [1CCR-172] AND [1CCR 173], CCR HX 1C Drain Valves.

2. Connect the temporary fill hose to [1CCR-172(173)], CCR HX 1C Drain Valve.

! 3. Check Open [1CCR-170] AND [1CCR-171], CCR HX 1C Vent Valves. .

4. Align the radiation monitors flush line as follows:(Aux Bldg 722 West) (

a. Close [1BR-839), Flush Line Drain.

b. Open [1BR-837], Flush Line isol.

i t Beaver Valley Power Station Unit 1 10M-15.4.E Reactor Plant Component and Neutron Tank Cooling Water issue 4 Revision 4 I Operating Procedure Page E 5 of 7 PLACING A CCR HEAT EXCHANGER IN SERVICE

c. Open [1BR-838], Flush Line isol.

d. Open [1BR-648], Rad Monitors Flush Water Sup Isol.

Note:

• An operator should be continuously stationed in the area of the temporary fill hose while [1BR-548] is open to monitor for leakage and/or spills.

• The heat exchanger vent effluent should be directed to the Aux Bldg 735' floor drains or a suitable container.

5. Perform the following to align the fill supply AND begin heat exchanger fill:

a. Slowly Open [1BR-548], Flush Isolation for [RM-1RW-101], AND Check the l

temporary hose for leaks.

b. Open [1CCR-172(173)], CCR HX 1C Drain Valve.

Note: When the second vent valve is closed, [1BR-548], Flush Isolation for

[RM-1RW-101], should be closed without delay to avoid prolonged periods of  ;

pressurizing the heat exchanger and temporary hose from PG water pressure. l

6. Close the following valves when venting is complete:

a. [1CCR-170], CCR HX 1C Vent Valve. '

b. [1CCR-171], CCR HX 1C Vent Valve.

c. [1BR-548], Flush isolation for RM-1RW-101.

d. [1CCR-172(173)], CCR HX 1C Drain Valve.

7. Aliyn the radiation monitors flush line as follows:(Aux Bldg 722 West)

a. Close [1BR-648], Rad Monitors Flush Water Sup Isol.

I b. Close [1BR-837], Flush Line isol.

c. Close [1BR-838], Flush Line isol.

d. Open [1BR-839], Flush Line Drain.

8. Disconnect the temporary hose from [1CCR-172(173)], CCR HX 1C Drain Valve.

9. Open [1CCR-14], CCR HX 1C Inlet isolation Valve.

F. If temporary hose was used to fill the heat exchanger, Disconnect the temporary fill hose from the hose connection downstream of [1BR-548], Flush Isolation for

[RM-1RW-101].

t0R TRAINsMG Odd

Beaver Valley Power Station Unit 1 10M-15.4.E Reactor Plant Component and Neutron Tank Cooling Water issue 4 Revision 4 Operating Procedure Page E 6 of 7 PLACING A CCR HEAT EXCHANGER IN SERVICE (

CAUTION: THE STANDBY RPRW PUMP MAY AUTO START WHEN PLACING A CCR HEAT EXCHANGER INTO SERVICE.

Note: The following three steps are written to place a specific HX in service. Use the appropriate step for the HX to be placed in service.

G. Place [1CC-E-1 A], Reactor Plant Component Cooling Water Heat Exchanger 1 A, in service as follows:

1. Slowly open [1RW-188], Primary CCW HX 1 A Outlet isolation Valve.AND throttle as necessary to maintain river water inlet pressure 2 25 psig.

2. Slowly open [1CCR-15], CCR Heat Exchanger 1 A Outlet isolation Valve.

3. If additional cooling is required AND river water inlet pressure cannot be maintained, start another river water pump in accordance with 10M-30.4.M.

" Standby Reactor Plant River Water Pump Startup", prior to throttling open the river water outlet valve further.

4. Open [1RW-442], CCR HX 1 A Discharge to [RM-RW-101] Radiation Monitor Comp. l H. Place [1CC-E-1B], Reactor Plant Component Cooling Water Heat Exchanger 18, in (

service as follows:

1

1. Slowly open [1RW-189], Primary CCW HX 18 Outlet Isolation Valve AND throttle as necessary to maintain river water inlet pressure 2 25 psig. I

2. Slowly open [1CCR-16], CCR Heat Exchanger 1B Outlet Isolation Valve. ]

l

3. If additional cooling is required AND river water inlet pressure cannot be j maintained, start another river water pump in accordance with 10M-30.4.M.

" Standby Reactor Plant River Water Pump Startup", prior to throttling open the river water outlet valve further.

4. Open [1RW-441], CCR HX 1B Discharge to [RM-RW-101] Radiation Monitor Comp.

1. Place [1CC-E-1C], Reactor Plant Component Cooling Water Heat Exchanger 1C,in service as follows:

1. Slowly coen [1RW-190], Primary CCW HX 1C Outlet isolation Valve AND throttle as necessary to maintain river water inlet pressure 2 25 psig.

2. Slowly open [1CCR-17], CCR Heat Exchanger 1C Outlet isolation Valve.

l l 3. If additional cooling is required AND river water inlet pressure cannot be maintained, start another river water pump in accordance with 10M-30.4.M,

( " Standby Reactor Plant River Water Pump Startup", prior to throttling open the

river water outlet valve further. .

4. Open [1RW-440], CCR HX 1C Discharge to [RM-RW-101] Radiation Monitor Comp. ,

t0R TRAINING OriLY

Beaver Valley Power Station Unit 1 10M-15.4.E Reactor Plant Component and Neutron Tank Cooling Water issue 4 Revision 4

'- Operating Procedure Page E 7 of 7 PLACING A CCR HEAT EXCHANGER IN SERVICE V. REFERENCES A. TECHNICAL SPECIFICATIONS None B. UPDATED FINAL SAFETY ANALYSIS REPORT None C. COMMITMENTS None D. ADMINISTRATIVE None E. VENDOR INFORM ATION None F. DRAWINGS

1. 11700-RM-157A - VOND Component Cooling Water - Sheet 1.

2. 11700-RM-127A - VOND River Water System.

G. OPERATING MANUAL

1. 10M-15.4.L - Filling And Venting CCRS.

2. 10M-30.4.M - Standby Reactor Plant River Water Pump Startup.  :

H. PLANT MODIFICATION None

1. OTHER

1. OMDR 1-86-1850,1-90-1128 (Rev. 0).

2. OMDR 1-93-0806 (Rev.1).

3. OMCR 1-95-0610 (Rev. 2).

4. OMCR 1-95-0767, DCP 675 (Rev. 3).

5. OMCR 1-95-1011 (Revision 4).  !

I g

I

i l

4 m O O

• w "

__.7 i

~

, 8 5' ,  !!! I i 5 5 S

1 k-e!!i, u  ; 1,

$IIl sr  !!Il! ,  !!!l!+!

x !e i-

! I!! 5 ! $ h

,i j!g w

'l j!d"i 5 '

(  !

s d l ~3

?J . jf.'Q. es En;

. .... 4. .....fJ 3% P! z g g h8 s

lE -

1 i  : 6 '-  ;;

46tj::g -

o I m$l@ar1%s pJ 9

4

,h,ij

,, i 8-r O.

t ge .

o w , g4J ._

3 i

'at f aII :Iq s .

s; g, ,

i

...........rd ;g ,

3, s

3 i,s

=

, o i t t ',

Q, '

' Il = 6 I

{,. . . . . . ' . . .

a ,,

g s %i g h,eQA- ........ _ _

75

. o u_-

I du g;; ( b h{,', ;h0' , et [--)!

cs - ,

~

<-i,

,O t

'y

- [/1 g i

i'L.01 4y_!i[!i

5.~

3 7 l

s-8 ( l!'gf.! ,ig'

! N;

~

} [- $ jij l' . , _ _ ,Ni i' '

h i

,i:- <

- t

-- e li a a - e._ ,

I r II,. ,.

.g ( m.

5

,p....... A$.c -

3 a.-

I J ~k $ g . qT,5I I m

g

. =

i > > y n.

wi%

a <1

• J 5g. > i,> i 7.......g e  :

gb  ;,; -j gg,

{f 5.;.

g"J _

3-

j 1 .i e gm=a.I 1 la t -

5 .

'Y i!g!, '

J- > y

~~

' j ,,

• e 1 ,() 3 1

,Mx 1

g;5 dl na s is .

I i

t

!! T t f , ,

s s s 1.@

Aw

' [{ -

!  ; **.1; l ,  ; 9 i 9i 9 (

Ingi Lh,d3 lh,d3thd3 f 3 , I' ,, !i !lA If i..,.,

..__+ a.-_

. .ei. .

Ii .- g 4 -. 4 "8

~ '

. h "**" % ( h ,j,d.i 4

.:! ij ',( t,19>( l Fl_r g

, 1 ,; y , -

f

}i}. '

ii H$ ,,* m lt }; .Q .

9 / i r T*.sils  ! 4g Nh!j' g rg b iIEE

.M 1

l i i

,(5a. ( 9 b

i

c1).-) llli 6-m m

v o

w o

M -

(

4 _

m -

i l 's cyn us.:&;e.'Tii gTM,um AM...,curgrtarze,issua. ss.asuirm vymusens m o - n w e w w - r- -i

~

.+ v .; . g  ;

l 1 h e v e w u 3- ~ -

9 85 a e s ky e hi.e[g.

,o v

'd i'i!

I. p!!

g i i,e,,,,

i. i. i r t, ;a ,

ha I!! E 99 ,o e o :e: *d ., ;p'. ii: isi p, sjl e P e!!lM c c I? I:f 1 g l9l M . m t

!* vf15 fi - !> g  ; jd {'; les M Em 8

"ijrsj;g"inijr 0;;h3ll

' ' ' " =;

.. j 2 O' y %!

i r , .

+ .

,,a 4 l.)

g g. g g f .f 1

. , .. a.

[..q. .. _

,+ 1 s .  :  :  : . -

I .

c .3 2 t.t k. ,

,1 u' i

. 3,

.u .

e 1 I 9 I - i k M h O i_i > .

a 2 ,

11!

E"! ,< !

'l' p' liEI!i;%l 8

. f!.

O 3

(

• i1 ^

k3 U2 b?'.

. /

On 1

l' c' 'E;kQ1,'fY;"i) d, k' q!!" k  ;- r- -

Q .~,s

. w . .n, n ,a

)hi cp i

.% y> 2 9, - . i ,

l

.T '

====. -

L ,

u L '!!'*I-i (: l l

\

1. st d ESEun

[

M' a, e a a X2 te e !

W Y.#$

, ,,,g: . , , f 9. . _ JF _. ' . j - --- e- .:

I

%8 I,, 45 ". .. -

t,'I.b s

' f. s . ,'., 6 l. $. E . ' ' ', '

.. f 4, ,

18! I,,**II C, > C,I . > l ll U o "f II!f

" Ij!;; - l1; lI?,,) il

• U}

! ll c-l b,- p a:  !! 1;  ;

e 3

la -

! it h: l

~

!.  !* r- a

_,[!;

'i> ill y!

11

+

,-; , ge,- ge,-

( " n.= nl v v P

if 1 fl fir  ! };  ! }g O 5

• inisdM"4 3.: .d. 3 s i,Y y, ,1. 21l.

A.

)  !

V. J , .

" 1}q&.,u.

ll

(?

n 11 L E * ,- n k[

• ~1: k..

e 1-#,

c 1re Q3 r c i r, Q,], a Q,- rr e 6

t g ens l

L.

rii

,;r

'lr

,$ ,hr! ih i ..

3 e

, , , . 3 N

'I[w lw '

I k' '

N '

• 44 5 6-. -

k_ _

j

.'g hg~ "

f g

'l i g.

4 i n

{

A ,

. lh *** -

i g g t

• i 1 ..

\ F l

, r. ,s:

t . 8 g

i

, , , , ' m -

4 v o , m m o I

}l

• a

, w ;;..~, a i. ~ .a .~. .. . a . .. .. . n .u. . a . s a .n. . .m .,p

}

2 rl ,,e 3 i..;

t @ 4 ,ii 3ff i

>%- o .

e 8y e  !,. e. e g g)

-lt{.g', *) (G

• Id

aig , , .. .

s

.f -

l t;,

.' m.i li dii9 e"ml I  !

l! 7- **

• . ga'i ->. g

. ,- .u[

g,I}Q,.,h,: ( t 4x"!l -- 13 p, u %.,

p

' Q,J

1. ,f; lyt,, . ' y;jjg}l; EI,1!

t =3 1 .. ,; g,9 - .

f@ J uJ q pjj ,tj 9 '!,ig

.l - gigg 4m.

1-k (g_

g

- fiit  ;' g i  !!L,i 6 _H,--

. j, 3

=

h ..d P E' gz8e rf s i >

i T

,9; ,gi11 t[/g >

kyy f

o c,

4 t J y  ;..

,s i ron, 1 7 2 E- I' t.p ,!(<_ f

~

I -

i,9 F ar-

.f.i!!jy{

in v,!.'

it re@ a g .v t

t .

g

• g; t O 1

(

-@QPQliiis'>_

~

H- - -

4 19 t.f 'lld ,' r i <

r%

v. -

ao q,(, ;.

,s?

t ggh - q- ;  :;

.i-g 4,

, ,q.

al ag, i+g ,

i, __,.

,ii l,

o f..t..i

- q,. s c .

1 s ii. - ,1  !> ,

Mll t ' -

{di, ,a *i0

. g f{.d;!

- c

+ g ,p r 9e. ..,f_s g f, .

g > k t, , t g 9 i

, a -g gt (g L: Ort jg'

' -7 .

1. [L 7, h' Q' g' g ".(:q> t 2

[.,

~

g .

~1 i f, .p> . ,g16 ,

- ti -

7

7. '

7 v

_pTf;gt g.$.;

9

>N k

' Q.g

'~-4

/ I 9ff,i

! >: g.g Y9.li L$,, 16di -

g4 g!.;;ig y;h ' N,

[ \e. nhll , , ,

.qf';E...f!

fi p

I

,i

,f,i e, 7b. J..e 15.:2 ,

DI'

v. , , .

y. i k..t,

e._

~

lA.t.' .

' @ , p f- 1r I. -

a t.

" ~I

, j~ . . .

t q,1; AF (F. )3 13,9,[et ci . - g g$.4]_;r i . ., ~ s ~

- i- iii It odi t... .) M.

?. ua.w.... <. . . ., .4;  : .

g j ,

13li l' d I), ,y-r 'a '

i,,;_,,5 _

.u q

< m o o w m o 4

t I _ _ _

l ,

l v

l

- 1 m h tg {. .j. !f g e c e -r li A i s i f:W

)

i in

!r!I - -

~

i 1: n g: : s$e i~: u:

Irl 2  ! =$  !

t i

t} lci:

1i II i i; }; ;?

1l1Li,el% $! l l' i tr!?

.s. le r 1

!! i di l ei e o,

I t .

-- d ;

ty bl l lA g i.

x r c3 atn.,

1th .

(

' In I .3i . $. EL 1 n

'lN $ ~ ~*

h... '* ~*

[tz), .

.l .

"e ; .

L), ~

J), ... 3 ..

Lt 1 . -

~ '

Ni t

. g l' !!  : l%g4:L%q Tiq 4 :l49. '

is R g.

E' I f

_.e tg e cit e p 1

. . . , i 3 I 'Y i t lj ou' j h 4 ' h M f d I ! k M g !i ,U

~

]4u l "

>i j ~ ~

r

{;.- gltt- t as jj sj} as a}} s Qi

                                                                                                                                                             .                     ...                               ;            .                :;s 7..                                                                                                      .
                                                                                                                                                                                                                                                  , m, _

gy ,a,3i

                                           ,                 r                                              ~

m. I ~ m, I ~ m. I m.. I I It ' - T [ " j [.j,'i a, E(8 ,f t a  ;  : I

                                                                                                                                                                                                                                                  '.#K s

n ..., 7m ,s, - - sm , _m , j' r I'i fi t

                                                                                                                                                                                                                               ._it.1!!     "

.- {,s Y

                                                                                                                                                                                                                                                             i A                                                                  z' y   e it a     _.; .

i gg p ,'. X . n ,8

                                                                                                                                                                                                                         !                        d GE cy                                                                                                                                                                                                                    i;r :: f t                                             e t

lr @ t t

                                                                                                                                                                                                                                      ,            sa cp s

T..~i

                                                                                                                                                                                        !sg                                   l'i ;-              :st.

1 l h)4)' i t 5 y z sp. ,s

 --                                                                                                                        t    .

t . t b Q,4 *e ; a2 iw .1 1 " - vi w, er

                 ,,                                 p-                                                     18;                                                                                                                                       w mumb                                                                   i                   -

j 1. , sj n, 19 , n T. n 1. 4 T 4 6 ii n . -l. i v7 n 5 C Tsii. . ! sin ( 71, 1 '. 4d me o ~ d3-$'HliI$ia , i

                                                                                            ' tud :iC.is-                    ;9 s;, T                                     v:7 .1           -

l'$i  ; H , m1 > <317 s;Jr a=, u.. 9 9 w s  : . t, e - Q s-e s- e 9 _ , , i M 's h -

            .                                                                                                                            o                                   ,o s
                                                                                                                                                   ,~ ,.,.i                        p.

o o e s, ,3_g gs c  ; i t d

                                                                                                                                                            --h
                                                                                                                                                                                                                                       . ij j il;                                   ,-                                                                                                                              >

c a t; li n-i g si . s m j i i i '

t. -y -

g e , ' ' -

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Lockout of Affected 4160V Emergency Bus JPM NO.: 1PL-097 COMPUTER' CODE: N/A l

Revision No. Date Revision No. Date PREPARED BY: DATE: l APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, or Designee I Revision 9

RTL #AS.640E' DUQUESNE LIGHT. COMPANY Nuclear Power Division Training Administrative Manual

  .- {

LESSON PLAN AND OJT REVISION APPROVAL SHEET 1 DOCUMENT TITLE: 1PL-097, Lockout of Affected 4160V Emeroency Bus i Revision Accroval No. Brief Description Revised by: Signature Date t i f i l i i 1. I. l l-I Revision 9

           -     . . - . . - - . -               . . . . . . .      - .     . . . . .         --.-....-..---             -.~.  . - .

( _. -- l i l BEAVER VALLEY JOB PERFORMANCE MEASURE i EVALUATOR COVER SHEET q JPM Number: 1PL-097 Rev: O System #: 062 Faulted: O l JPM

Title:

Lockout of Affected 4160V Emergency Bus K/A

Reference:

062 000 G09 3.2/3.3 Task ID #: 062 007 0101 JPM Designation: NO RO X SRO j JPM Application: X NRC X Initial Exam Training ) l I

Evaluation Method LOCATION TYPE l j Perform Plant Site Training l Simulate Simulator Annual Requal. Exam Classroom OJT j Initial Operator Exam j Administered By

Other:

I BV-T l l NRC 4

Other

i { Evaluation Results I f Performer: Name: Employee No: l Results SAT Time (minutes) ! O UNSAr* Allotted: 2s Actual: Time Critical: Yes E No !

• Comments (Required for UNSAT Evaluation):

j . j Evaluation Results Check here if same as above j Observer 1: Name: Employee No: i Observer 2: Name Employee No: ! Observer 3: Name Employee No: l Observer 4: Name Employee No: i Time (minutes) Results l Question ID Allotted Actual SAT UNSAT* i Question #1 5 , Employee No: Question #2 7 '! Employee No: l

• Comments (Required for UNSAT Evaluation) :

i a

'  I i'

j Evaluator (Print): Organization: Evaluator Signature Date: j Revision 9 4

   . - - - .        ._ _    . . - _ . - . . - - ~ . ~ . - . - .               ~ . . . .- ~. - -   ........ - .. ~ . -

RIL $lAS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1PL-097 JPM TITLE: Lockout of.Affected 4160V Emergency Bus RECOMMENDED STARTING. LOCATION: CONTROL ROOM l l DIRECTIONS: You are to perform (simulate) the task lockout of affected 4160V Emergency Bus. INIT. CONDITIONS: Following a reactor trip and loss of offsite power, a fire has occurred in the AE Switchgear Room (ES-1). The fire is not , TASK STAN.: bVBusAElockedoutinaccordancewith 10M56B.4.2.D-3.  ! INIT. CUE: Your supervisor directs you to lockout s 4160V Bus AE. .

                                                                                                                      ]

i

REFERENCES:

10M-56B.4.2.D-3, Issue 3, Revision 0 l TOOLS: NONE l 1 HANDOUT: 10M-56B.4.2.D-3, Lockout of Affected 4160V Emergency Bus for Fire in ES-1 (AE) or ES-2 (DF) s 5 f Revision 9

     .._ m_   . . - . _ _ . _ _ _ . . _ . _ . _ . _ _ _ _ _ _ ,                   . - _ . - . _ . , .. -                . _ . ~ _~          . . . - _ . . _ .

l RTL #A5.635.J. I 4 NUMBER TITLE

j. 1PL-097 Lockout.of Affected 4160V Emergency Bus l

i l l STEP STANDARD l (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)  ! t-i START TIME: I Candidate locates and reviews , procedure. l Evaluator Cue: Provide l candidate with copy of.10M- [ 56B.4.2.D-3. l 1.C Turn off DC control 1.1. Candidate simulates '

. power-to Normal 4KV to opening cubicle for l Emergency Feeder 1A10.  ;

breaker. ' 1.2.C Candidate describes , how to place control . L power switch in the OFF position. l Evaluator Cue: The switch is in the OFF position.  ; l 1.3 Candidate simulates i closing cubicle for l 1A10. l COMMENTS: i

  .t f

Page 1 of 5 Revision: 0 f

                                                         ._-   - - ~ . .   . -

RTL #AS.635.J NUMBER TITLE 1PL-097 Lockout of Affected 4160V Emergency Bus STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

2. Check the Normal 4KV to 2.1 Candidate verifies Emergency Bus breaker 1A10 is open.

is open l Evaluator Cue: 1A10 is open.

                                                                         ~

COMMENTS: 3.C Take Local control of 3.C Candidate simulates the No. 1 Diesel placing Auto / Local Generator, switch on the Engine Control Cabinet in the LOCAL position. Evaluator Cue: The switch is in the LOCAL position. COMMENTS: Page 2 of 5 Revision: 0

  --  .-    -.~.- .      --. ,.. ..         .        .  . -    . . . - .-   . . . - . . - ~ . . ..

RTL #A5.635.J

   .I                                         _

NUMBER TITLE 1PL-097 Lockout of Affected 4160V Emergency. Bus ' STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 4.C Depress Stop 4.C Candidate depresses pushbuttons. both Stop pushbuttons. I f Evaluator NOTE: The stop push buttons must be depressed simultaneously. ! COMMENTS: i i 5.C Open the DC control 5.C Candidate opens the DC

circuit breaker, control circuit l breaker.

! Evaluator Cue: The DC control circuit breaker is open. i l l i COMMENTS: ! i Page 3 of 5 Revision: 0

RTL #A5.635.J I' NUMBER TITLE 1PL-097 Lockout of Affected 4160V Emergency Bus t STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 1 6.C Open the START 1 and 2 6.1.C Candidate opens the i circuit breakers. START 1 circuit breaker. Evaluator Cue: The START 1 circuit breaker is open. 6.2.C Candidate opens the START 2 circuit breaker. Evaluator Cue: The START 2 circuit breaker is open. COMMENTS: l l 1 t l l l 3 Page 4 of 5 Revision: 0 l l-

( i RTL #A5.635.J \ NUMBER TITLE l 1PL-097 Lockout of Affected 4160V Emergency Buc, 1 l l j i I STEP STANDARD I (Indicate "S" for Sat. or "U"  ! ("C" denotes critical step) for Unsat.) j

7. Report that 4160V 7. Candidate Report TO Emergency Bus AE has SUPERVISOR that 4160V been locked out. Emergency Bus AE has been locked out.  ;

1 COMMENTS: STOP TIME: l l l l l l O Page 5 of 5 Revision: 0

           . - - . .          .-     - .       _ .    - - . . . - .-   - . . - . . . . . ~ . - . . _ .   - - . - . . .

i BEAVER VALLEY JOB PERFORMANCE MEASURE l JPM QUESTION # 1 L What is the expected response of the Diesel Generator when the STOP pushbuttons are

. depressed? -

064 000 K4.02 3.9/4.2 Obj: LP-SQS-36.2, ELO-8 Ref: lOM-36.1.E, Issue 4, Revision 1 l ANSWER: The engine will slow to idle speed and idle for 11 1/2 minutes before coming to a complete stop. Comments:

                                                                                                                       )

1 1PL-097

 . . _ . . _ . ., . _ . . . _ . - _ _ . _ . _        . _... . . _ . . . ~ . ._ _   _.        _ . . _ .

BEAVER VALLEY JOB PERFORMANCE MEASURE JPM QUESTION # 2 > Explain the interlocks which prevent inadvertently paralleling Bus A with Bus AE when Bus AE is being supplied by the Diesel Generator, 062 000 K4.05 2.7/3.2 Obj: LP-SQS-36.2, ELO-10 Ref: lOM-36.1.E, Issue 4, Revision 1 ANSWER: . ACB's l A10 (I A to I AE) and IE7 (I AE to I A) cannot be closed unless the No.1 Diesel - Generator Syncronizing Switch is in the IE7 (I AE to I A) position [or the No.1 Diesel Generator breaker is open. ACB 1 A10 (I A to 1 AE) must be closed before IE7 (I AE to  ! 1 A) can be closed.] {not required for full credit} l Comments': l IPL-097

                                                                        .   - . . _ . . . . =. _ - _ . . _ _ . _ _ . . . . _ .

BEAVER VALLEY JOB PERFORMANCE MEASURE

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 1 What is the expected response of the Diesel Generator when the STOP pushbuttons are depressed? ,

l L F I l-4 i l i l l 1PL-097

l BEAVER VALLEY JOB PERFORMANCE MEASURE 1 l

  '1

• THIS SHEET TO BE GIVEN TO CANDIDATE
• I 1

JPM QUESTION # 2 l l Explain the interlocks which prevent inadvertently paralleling Bus A with Bus AE when Bus AE is being supplied by the Diesel Generator. 1 i R

                                                                                                                     )

I l l k l. 1 PIA 97

I i l- RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE 1 1 I CANDIDATE DIRECTION SHEET I l 1 t' .) - 1 ! *- THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Task: Lockout of Affected 4160V Emergency Bus l INITIAL Following a reactor trip and loss of offsite CONDITIONS. Power, a fire has occurred in the AE Switchgear l

• Room (ES-1). The fire is not out.

j i i TASK STAN.: 4160V Bus AE locked out in accordance with 10M56B.4.2.D-3. INIT. CUE: Your supervisor directs you to lockout 4160V Bus AE. At'this time,-ask the evaluator any questions you have on this l JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. l Point to any indicator or component you verify or check and I announce your observations. After completing the task, reread the Task Standard. l-After determining the Task Standard has been met, announce "I l have completed the JPM". Then hand back this sheet to the l~ evaluator. I i t-f- l l Revision 9 l _. _. -

 . -                    -    --  - = . _ .      .     . _ .   -- . -                          - . _ . .     - . . - . .

l l l l Record Type #A9.3308 l l l DUQUESNE LIGHT COMPANY Beaver Valley Power Station I 1

Unit 1 l l

l l l l l 10M-56B.4.2.D-3(ISS3) LOCKOUT OF AFFECTED 4160V EMERGENCY BUS FOR A FIRE IN ES-1 (AE) OR ES-2 (DF) l lasue 3 Revision 0

                                                                                                          ~

Prepared by Date .Pagesissued Effective Date R. Plummer 08/11/94 D-31 of 1 7 /p.cf /9 '/ 9eviewed by Date Validated by Date L. Montanari 09/09/94 gfg i Unit 1 Manager Date OSC Meeting No. Date N/A Non-Intent 09/12/94 Unit 2 Manager Date Approved by Date h f hY y , <i-( [x CONTROLLED BVPS UNIT 1 g Ot\@

Beaver Valley Power Station Unit 1 10M-568.4.2.D-3(ISS3) Fire Prevention and Control issue 3 Revision 0 Operating Procedures Page D-31 of 1 LOCKOUT OF AFFECTED 4160V EMERGENCY BUS FOR A FIRE IN ES-1 (AE) OR ES-2 (DF) INITIAL CONDITIONS For a fire in ES-1 or ES-2 that affects the emergency electrical systems (AE or DF Train) to preclude spurious operations of the particular train affected by the fire. INSTRUCTIONS

1. In the Normal Switchgear Room, turn OFF the DC control power on the Normal 4KV to Emergency Feeder breaker 1 A10(1D10) AND Check the breaker Open.

2. At the No.1 (No. 2) Diesel Generator, Shutdown / lockout the Diesel Generator by;

a. Placing the Auto / Local switch, on the Engine Control Cabinet, in the LOCAL position,

b. Depress bot shbunons

c. Open the C circuit breaker.

d. Open the 5. .tT 1wND START 2 circuit breakers.

REFERENCES Note: All references used prior to issue 3 Revision 0 are located in Section 5.

1. OMDR 1-94-0357 (Issue 3, Rev 0) l l

i i

          - .  .-      . . _ . . . ~ _ _        .  . - . . . - ~      . . . .   . . . -     -  . - - - . . . ,

l l RTLL#A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual ! i- _ OJT C!4CKLIST/JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training ! I SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Manual QPTR Calculation JPN NC.: 1AD-001 COMPUTER CODE: N/A l i Revision No. Date Revision No. Date . l l l !' l l PREPARED BY: DATE: l l' APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, , or Designee f i l Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: 1AD-001, Manual OPTR Calculation Revision Anoroval No. Brief Description Revised by: Signature Date l l l l l l l \ Revision 9

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

2 i j BEAVER VALLEY JOB PERFORMANCE MEASURE 1 EVALUATOR COVER SHEET i JPM Number: 1AD-001 Rev: 0 System #: 015 Faulted: O l JPM

Title:

Manual QPTR Calculation l K/A

Reference:

015 000 A1.04 3.5/3.7 Task ID #: 341 018 0302 JPM Designation: NO RO X SRO X X l j JPM Application: NRC Initial Exam Training l l ! Evaluation Method LOCATION TYPE US Perform Plant Site Training [3 Simulate Simulator Annual Requal. Exam X Classroom [] OJT l l EU Initial Operator Exam f Administered By: Other: BV-T li j NRC j Other:

Evaluation Results j Performer

Name: Employee No:

l Results SAT Time (minutes) UNSAT* Allotted: 15 Actual: l Time Critical: Yes x No l

• Comments (Required for UNSAT Evaluation):

1 ( Evaluation Results [] Check here if same as above l Observer 1: Name: Employee No: {- Observer 2: Name Employee No: j Observer 3: Name Employee No: 1 Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* I i Question #1 NA 1 Employee No: Question #2 NA , Employee No:

• Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization: Evaluator Signature Date: Revision 9

     ~ ..,.-~,           .      . - - . .        . . . . . - - - - . . . . - - . . - . - . . . . - . - . . . - . ._-

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE I l i-CANDIDATE DIRECTION SHEET THIS SHEET TO BE GIVEN TO CANDIDATE Read: i I L Task: Manual QPTR' Calculation J l

                                                  .                                                                  l INITIAL          The plant is operating at 60% power. N-42 has CONDITIONS:.      een removed from service due to an internal L                              circuit failure. The plant computer is unavailable 1

TASK STAN.: Quadrant Power Tilt Ratio manually calculated in accordance with 10ST-2.4.A. INIT. CUE: Your super. visor directs you to Perform 10ST-2.4.A. Quadrant Power Tilt Ratio Manual-Calculation. l  !

                 'At this time, ask the evaluator any questions you have on-this

! JPM. l 0 When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or. perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. After completing the task, reread the Task Standard. J After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. I i i + 1 L Revision 9 l -. - . .

                                             ..     . - -   - . . . . - - ._. -   .. - . - . - . .~

f .l i RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE

EVALUATOR DIRECTION SHEET r

l JPM NUMBER: 1AD-001 JPM TITLE: Manual QPTR Calculation I i 1  : , RECOMMENDED j l- STARTING LOCATION: CONTROL ROOM l i l DIRECTIONS: You are to perform the task perform a manual QPTR calculation. i INIT. CONDITIONS: The plant is operating at 60% power. N-42 q has been removed from service due to an i internal circuit failure. The plant j computer is unavailable. l l TASK STAN.: Quadrant Power Tilt Ratio manually , j calculated in accordance with 10ST-2.4A. l \

INIT. CUE

Your supervisor directs you to Perform  !

10ST-2.4A. Quadrant Power Tilt Ratio Manual. l Calculation. l l

REFERENCES:

10ST-2.4A, Issue 4, Revision 1 , 1 1 TOOLS: NONE I i HANDOUT: 10ST-2.4A. Quadrant Power Tilt Ratio Manual ' Calculation l Nuclear Instrument Current Readings j QPTR Normalization Factors I t i - + a Revision 9

                  -                              - - . . . . .. ~

RTL HA5.635.J NUMBER TITLE 1AD-001 Manual QPTR Calculation STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) START TIME: Candidate locates and reviews 10ST-2.4A, Quadrant Power Tilt Ratio Manual Calculation. EVALUATOR CUE: Provide candidate with copy of 10ST-2.4A with NSS/ANSS approval signature. I

1. Acknowledge performance of 1. Candidate signe procedure and sign on. procedure.

COMMENTS: l l , Page 1 of 10 Revision: 0

RTL #A5.635.J NUMBER TITLE I 1AD-001 Manual QPTR Calculation l I STEP STANDARD  ! (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.)

2. Verify reactor power is 2. Candidate verifies reactor l being maintained at steady power is being maintained l state value. at steady state value.

EVALUATOR CUE: Power is being maintained at steady state value. COMMENTS: l l

    =

Page 2 of 10 Revision: 0 l

  .    --  .-    .   . . . . ...       ..   - ..   . - . . ~ , - . .. . . .             -.. ..      . ..

I l l 1

i. i RTL.#A5.635.J i

i NUMBER TITLE 1AD-001 Manual QPTR Calculation L I l l l 1 l l I l STEP STANDARD  ; i (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) l l 1

3. Record power range 3. Candidate locates the detector QPTR normalization factors normalization factors. in the Reactor L Engineering Data Book i and records power l range detector QPTR normalization factors on Data Sheet 1.

l EVALUATOR CUE: Provide candidate with the following values: (Sheet One) N41A= 0.0557 N41B= 0.0462 N42A= 0.0511 N42B= 0.0465 l N43A= 0.0545 N43B= 0.0533 N44A= 0.0422 .N44B= 0.0460 COMMENTS: 1 i

g l

Page 3 of 10 Revision: 0 l

              . -. -   .-      -.   ~    . . . . . . - . _ - .              -.- .     .    . . - _ _ . . . -

j RTL #A5.635.J l NUMBER TITLE 1AD-001 Manual QPTR Calculation l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 4.C Record detector current 4.1. Candidate marks data values. entries for N-42 l ' ' N/A' ' . EVALUATOR CUE: It is not necessary to use DVM. I 4.2.C Candidate reads current meters located on NI drawers and , j records data on Data Sheet 1. EVALUATOR CUE: Provide candidate with the following values: (Sheet Two) l N41A= 94 N41B= 120 l N43A= 101 N43B= 106 l N44A= 124 N44B= 121 1 COMMENTS: l !i i Page 4 of 10 Revision: 0 l

h l j l RTL #AS.635.J-NUMBER TITLE 1AD-001 Manual QPTR Calculation l l

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.) S.C Multiply each detector 5.C Candidate multiplies l reading by its each detector reading normalized value. by its normalized value and records in the ' Current (Cor.) column on data cheet 1. j EVALUATOR CUE: The candidate should record the-following i values: N41A= 5.2358 N41B= 5.544 N43A= 5.5045 N43B= 5.6498 N44A= 5.2328 N44B= 5.5660 COMMENTS: I I 1 l l l l' 1 l i i. i i l Page 5 of 10 Revision: 0 f I

i RTL #A5.635.J NUMBER TITLE l 1AD-001 Manual QPTR Calculation l l l l l STEP STANDARD i (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

                       ~

l 6.C Determine tilt ratio 6.1.C. Candidate adds the for each upper values for the Current , detector. (Cor.) column and ' records the result in the space marked SUM: i l l EVALUATOR CUE: The candidate ' should record the following values: 15.9731 6.2.C Candidate divides the value in the SUM space by 3 and records the result in the space i marked AVG. ' EVALUATOR CUE: The candidate should record the following values: 5.3243 l n l Page 6 of 10 Revision: 0

i RTL #A5.635.J l l NUMBER TITLE 1AD-001 Manual QPTR Calculation ? STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) 6.3.C Candidate divides the value in the Current (Cor.) column for each detector by the value in the AVG space and records results in the

                                                Tilt Ratio column.

EVALUATOR CUE: The candidate should record the fcilowing values-N41A= 0.9833 N43A= 1.0338 N44A= 0.9828 1 I l COMMENTS: l l f Page 7 of 10 Revision: 0

l f RTL #A5.635.J NUMBER TITLE 1AD-001 Manual QPTR Calculation STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l

                                                                       )

7.C Determine tilt rat T 7.1.C. Candidate adds the for each lower values for the Current detector. (Cor.) column and records the result in the space marked SUM: EVALUATOR CUE: The candidate should record the following value: 16.7598 7.2.C Candidate divides the value in the SUM space by 3 and records the result in the space i marked AVG. EVALUATOR CUE: The candidate should record the following value: 5.5866 Page 8 of 10 Revision: 0

                 ~

l RTL #A5.635.J A- , NUMBER TITLE 1AD-001 Manual.QPTR Calculation L STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 7.3.C Candidate divides the value in the Current (Cor.) column for each detector by the value in the AVG space and records results in the

                                                   Tilt Ratio column.

EVALUATOR CUE: The candidate should record the following values: N41B= 0.9923 N43B= 1.0113 l l N44B= 0.9963 COMMENTS: i l

                                                                                  .l l

l 5 t' I Page 9 of 10 Revision: 0

l 1 RTL #A5.635.J h NUMBER TITLE 1AD-001- Manual QPTR Calculation , i t STEP STANDARD (Indicate "S" for Sat. or "U" (."C" denotes critical step) for Unsat.) , 8.C Consult test criteria 8.C Candidate identifies that i for acceptable N43A does meet acceptance performance. criteria. COMMENTS: f

9. Inform NSS/ANSS of test 9. Candidate informs completion, supervisor that test is complete and that the test acceptance criteria is not met. .

COMMENTS: l EVALUATOR CUE: It is not " necessary to complete the front cover sheet. i j STOP TIME: I I Page 10 of 10 Revision: 0

I c L l k SHEET ONE - QPTR NORMALIZATION FACTORS l l l l N41 A= 0.0557 N41B= 0.0462 l t  : N42A= 0.0511 N42B= 0.0465 i N43A= 0.0545 N43B= 0.0533 l N44A= 0.0422 N44B= 0.0460 i l l i f l l l 1 I' i

a., & a _ _ -= _ _J 4 m. J.A. - .h. SHEET TWO - DETECTOR CURRENT READINGS N41 A= 94 N41B= 120 N43A= 101 N43B= 106 N44A= 124 NA44B= 121 l 1 t l 1 [ l

i . Record Type #A9.3308 DUQU6SNE LIGHT COMPANY Beaver Valley Power Station - Unit 1 w. l I 10ST-2.4A l l

l. Quadrant Power Tilt Ratio Manual Calculation I

l l i

                               *                                                                                                                            'I 1 l

Issue 4 Revision 1 l l Prepared by Date Pagesissued $ffective Date l l J. E. Burnecke 08/27/96 1 through 10 SEP 0 51996 Reviewed by Date Validated by Date ,

             'J. P. Keegan                                    08/27/96   N/A                                                       .

OSC Meeting No. Date Approved by Date - Non-intent 08/28/96 (( g [g i r,' ." *, r  :* 3, , e ,, 4 . . . - ,- ..

                                                           $ %){7t - b                 ,          ,

li C_ONTROLLED .

I l- Beaver Valley Power Station Unit 1 10ST-2.4 A j issue 4 Revision 1

i Operating Surveillance Test Page 11 Quadrant Power Tilt Ratio Manual Calculation l Table of Contents l l. PURPOSE . . . . . . . . ................. ..:. .. .. ...... 3 i

! 11. DISCUSSION . . . . . . . . . ........ ...... . . . ...... . .. 3 1

111. ACCEPTANCE CRITERIA .... .......... .. . . . . .... 3 l

IV. EQUIPMENT AND MATERIALS ..... .... . . .. .... . .. 3 V. PRECAUTIONS AND LIMITATIONS . . . . . . .. ... ... ... . .. 3 ! VI. INITIAL CONDITIONS . .... .... . ... .. . . ... 3 t i Vll. INSTRUCTIONS . . . . .......... . . . ... . ....... . 5  ; Vlll. DATA SHEETS, TABLES, FIGURES AND ATTACHMENTS I (- . . 7 OATA SHEET 1 . . . . .. . .... .. . . .. 8 ATTACHMENT A .. .. ... .. . . . 9 IX. REFERENCES . . . . . . ..... .. ..... . . . 10 I l m 4

03 TRA N!NG USE ONLY .

l > I CONTROLLED

           .- --            --      ._           ._      . - .        . . .   -    . . . .    ~-            --       -

Beaver Valley Power Station Unit 1 10ST-2.4A issue 4 Revision 1 !' Operating Surveillance Test - Page 1 of 10 Quadrant Power Tilt Ratio Manual Calculation l Frequency: W 00 Surveillance Requirements: 4.2.4(a) , Required for Mode (s): 10 Date / Time Completed: ._

                                                                                                        /

Performed in Mode (s): 1 Total Manhours: TEST RESULTS: (Completed by Performer) PERFORMED BY: Name (Print) Initial or N/N ,- O est Completed SATISFACTORY l O Problems Encountered (See Problem Sheet) O Unscheduled / partial OST (explain) l l Reviewer Signature /Date i STA Review / NSS App'roval / COMMENTS: (include Date and initials) l 1 l O Comments continued on Problem Sheet O Above 50% of rated thermal power. O O Required at least once every 12 hours during steady-state operation when QPTR alarm

'i                   is inoperable.                                                                                    !

F

                                                               ?OR I'RANNG UCid CJLY L     _

CONTROLLED

Beaver Valley Power Station Unit 1 10ST-2.4 A l Issue 4 Revision 1

 -1  Operating Surveillance Test                        -

Page 2 of 10 Quadrant Power Tilt Ratio Manual Calculation ( ( OST PROBLEM SHEET l See Page and Step No, for problem desetiption. See below for corrective action, eg: MWR No., OMCN No., OMCR or Database change written or other. l PAGE NO. STEP NO. DESCRIBE CORRECTIVE ACTION INITIALS DATE l A. [ . l l cs l i l l l - l l  : 1

                      =

l l l

                                    ~

FOo TP ^!N!NG USE ON_Y , i l i I i

Beaver Valley Power Station Unit 1 10ST-2.4 A issue 4 Revision 1 Operating Surveillance Test Page 3 of 10 , Quadrant Power Tilt Ratio Manual Calculation

1. PURPOSE To determine by manual calculation the Quadrant Power Tilt Rdtio (QPTR) and verify that it does not exceed the limit given in Technical Specification 3.2.4.

11. DISCUSSION This OST is routinely performed on a weekly frequency, above 50% reactor power, when the QPTR alarms (ANN. A4-59(67), POWER RANGE LOW (HIGH) SETPOINT FLUX DEVIATION OR AUTO DEFEAT) are operable, as determined by 10ST-2.4," Quadrant Power Tilt Ratio Alarm _ Check". The required test frequency is increased to every 12 hours when a QPTR alarm}is inoperable.

Ill. ACCEPTANCE CRITERIA Note: An exception to the Acceptance Criteria exists for physics testing (Tech Spec 3.10.2). A. Quadrant Power Tilt Ratio (QPTR) does not exceed 1.02 (Data Sheet 1)(T.S. 4.2.4.a). IV. EQUIPMENT AND MATERIALS A. A digital voltmeter (DVM), if determined to be necessary during OST performance. V. PRECAUTIONS AND LIMITATIONS A. . Perform this OST every 12 hours with the QPTR alarm inoperable. B. If it is suspected that the meter indication on the power range drawers is erratic due to static in the meter face, a DVM should be used to determine current values. The DVM measurement should be taken at the test Jacks on the front of the power range drawers. i VI. INITIAL CONDITIONS A. Plant Status Channes This procedure does not affect plant status. , B. NSSIANSS Slan-on )

1. A QPTR' determination is desired to verify conformance to Technical Specification 3.2.4.

l i { c F03 TRANNG UE ONLY

l ). j Beaver Valley Power Station Unit 1 10ST-2.4A l Issue 4 Revision 1 Operating Surveillance Test - Page 4 of 10 ) Quadrant Power Tilt Ratio Manual Calculation , ( CAUTION: IF POWER IS 2:75% AND ONE POWER RANGE HIGH NEUTRON FLUX l CHANNEL INPUT TO QPTR IS INOPERABLE, QPTR'MUST BE VERIFIED AT l LEAST ONCE PER 12 HOURS IN ACCORDANCE WITH TECHNICAL l SPECIFICATION SURVEILLANCE 4.2.4.b USING 1RST-3.4, "lNCORE ANALYSIS i OF QPTR". I

2. If one power range high neutron flux channelinput to QPTR is inoperable, AND

                            thermal power < 75%, the remaining three power range high neutron flux
                          ,- channels may be used for calculating QPTR.

t

                         '8-    No other tests of the power range channels are being performed during this OST.                           I l                                                                                                                                          1 l                          4. NSS/ANSS verifies the following:                                                                          !

i

• Section VI.A Plant Status Changes, has been reviewed. l l l

! ~

• Requirements of Section VI.8, NSS/ANSS Sign-on have been verified.

l , I

• Performance of this procedure is authorized. I DATE: Toow TIME: yog CURRENT PLANT MODE: L NSS/ANSS COMMENTS: y e, %

l I l l l NSS I ANSS Signature $ C. Reactor Operator Stan-on l

1. Reactor Operator performs the following:

l .

• Acknowledge performance of this procedure.

Reactor Operator Signature I TAvaate>L D. Procedure Performer Initial Conditions l 1. Reactor power is being maintained at a steady-state value. l l l Initial / Date (

2. Operator (s) performing this procedure has reviewed this procedure.

                                                -                                                                               I       ;

initial / Date ' I I - Initial / Date FOR TRANNG JSE ONLY

l Beaver Valley Power Station Unit 1 10ST-2.4 A Issue 4 Revision 1 Operating Surveillance Test Page 5 of 10 Quadrant Power Tilt Ratio Manual Calculation Vll. INSTRUCTIONS A. Test Preparation '

1. Record the power range detector QPTR normalization factors, found in the Reactor Engineering Data Book, Data Sheet 3 of 1RST-2.3, " Nuclear Power Range Calibration", Data Sheet 5 of 1RST-2.4, " Alignment of Excore Instrumentation for

                   . Startup After Reload" OR Data Sheet 3 of 1RST-2.9,"NIS Single Point Calibration" l
                  . (NSS Office), on Data Sheet 1.

i. _f J Initial / Date B., QT5TR Determination Note: If one power range high neutron flux channelinput to QPTR is inoperable, AND thermal power < 75%, the remaining three power range high neutron flux channels may be used for calculating QPTR In this case, the entries on Data Sheet 1 for the OOS detector should be marked "N/A".

1. Record detector current values for each of the power range detectors in the

                        " Current (Uncor.)" column of Data Sheet 1, using either of the following methods:

a. Detector current meters located on the power range drawers.

I initial / Date Note: If uncertainty exists in reading the current meters, a DVM should be used to obtain the current readings.

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

I initial / Date

2. Multiply each of the detector current readings by its associated normalization factor AND Record the result in the " Current (Cor.)" column of Data Stieet 1.

I ! Initial / Date 1 ( 3. Perform the following for the Upper Detectors on Data Sheet 1: I l

a. Add the-values in the " Current (Cor.)" column AND Record the result in the [ I l

i space marked " SUM". , l y ng p i Initial / Date r OR 7irN ew, 'a." lu'".". u"J,m}} \/

l l ! 1 I l Beaver Valley Power Station Unit 1 10ST-2.4 A l l Issue 4 Revision 1 ! Operating Surveillance Test Page 6 of 10 Quadrant Power Tilt Ratio Manual Calculation ( l

b. Divide the value in the " SUM" space by 4(3) AND Record the result in the space marked " AVG". -

I initial / Date

c. Determine the Tilt Ratio for each of the upper detectors by dividing each l

value in the " Current (Cor.)" column by the value of " AVG" AND Record the results in the " Tilt Ratio" column.

                                                                                        ~

j

                       ~

Initial I Date k Perform the following for the Lower Detectors on Data Sheet 1:

a. Add the values in the " Current (Cor.)" column AND Record the result in the space marked " SUM". I I

I l Initial / Date l b. Divide the value in the " SUM" space by 4(3) AND Record the result in the space rnarked " AVG". Initial / Date

c. Determine the Tilt Ratio for each of the lower detectors by dividing each value in the " Current (Cor.)" column by the value of " AVG" AND Record the results in the " Tilt Ratio" column. l I i Initial / Date l

5. If uncertainty exists with the calculated tilt values, Request the Tilt Review Map from the IPC AND Compare the map with the results of this OST.

I ! Initial / Date C. Test Completion

1. Consult the Acceptance Criteria for acceptable performance.

I initial I Date . 2. Inform the NSS or ANSS of the completion of this test.

                                               .                                                                         I

• I Initial I Date

3. Complete the front cover sheet. /

I Initial I Date p\.. O 1 Oi M i! % lI k):O?~ C Iqt

                                                         !" T r", A :' a . In .

C I v'h jL s/ I

l Beaver Valley Power Station Unit 1 10ST-2.4 A Opera <ing Surveillance Test issue 4 Revision 1 Page 7 of 10 quadrant Power Tilt Ratio Manual Calculation l Vill. DATA SHEETS, TABLES, FIGURES AND ATTACHMENTS A. Data Sheets ' i ! 1. Manual QPTR Calculation B. Tables NONE C. I Iiaures l l N..O N E D. Attachments

                       .1.        Use of DVM to 'Obtain Current Readings l

i I l l I v: g g(. .., l E-;

                                                                                     . e h. ;#
                                                                                                  #4
                                                                                                        > " % .~
                                                                         I" Mil i d [)g')                     [

( , l!* 4

1 i

l .. . . - .

i .i Beaver Valley Power Station Unit 1 10ST-2.4 A l Issue.4 Revision 1 j Operating Surveillance Test Page 8 of 10 Quadrant Power Tilt Ratio Manual Calculation ( l ! DATA SHEET 1 l MANUAL QPTR CALCULATION UPPER DETECTORS l i.

         ' current (Uncor.)          Norm Factor     l      Current (Cor.)     l         Tilt Ratio l               '

l lN41A , l l l l lN42A l l l l l lN43A l l l l LOWER DETECTORS ( Current (Uncor.) Norm Factor Current (Cor.) l Tilt Ratio l l l l l

 ,   lN41B                    l                        l                        l                              l

! lN428 l l l l lN438 l l l l l ! Performed By / / (Init/ Time /Date) Verified By / (Init/Date)

t 3

n , ,, .

                                                                                        .s r On r.Hi A,iN,iiv,n . ..s,--a u a t ts,w:L

I Beaver Valley Power Station Unit 1 10ST-2,4A ! Issue 4 Revision 1 Operating Surveillance Test Page 9 of 10 Quadrant Power Tilt Ratio Manual Calculation ATTACHMENT A USE OF DVM TO OBTAIN CURRENT READINGS A. S!gn-out the following M&TE equipment:

                                                                        ~  .

1. Digital Voltmeter (DVM), Fluke Model 45 or equivalent.

            -)-     l'nstrument Number Cal. Due Date       /      /
                                                                                              /

Initial / Date B. Set the following controls on the DVM:

1. Set Function to VDC.

l /- !, Initial / Date l- 2. Set Range to AUTO. f

                                                                                               /

Initial 1 Date CAUTION: DO NOT SHORT TEST JACKS TO GROUND - CHANNEL TRIP MAY OCCUR. C. Insert the DVM leads into the Detector A(B) Test Jacks located at the bottom of the Power Range B Drawer.

                                                                                               /

Initial / Date D. Multiply the DVM reading by 1000 to obtain the detector current, (Example: 0.269 VDC x 1000 pA/VDC = 269 pA).

                                                                                                /

initial / Date

E. Record the detector current values to at least the nearest pA in the " Current (Uncor.)"

column of Data Sheet 1. .

                                 ~

i f Initial / Date FoR TRAiWING USE ONLY

Beaver Valley Power Station Unit 1 10ST-2.4A lssue 4 Revision 1 4 Operating Surveillance Test _ Page 10 of 10 Quadrant Power Tilt Ratio Manual Calculation ( IX. REFERENCES A. TECHNICAL SPECIFICATIONS

1. 3.2.4

2. 3.10.2 B. l[PDATED FINAL SAFETY ANALYSIS REPORT '

TONE C.- CdMMITMENTS h0NE D. ADMINISTRATIVE NONE E. VENDOR INFORMATION NONE F. DRAWINGS NONE ( G. OPERATING MANUAL

1. 10M-49.4.G, " Quadrant Power Tilt Ratio"

2. 10M-49.3, " Checklist G.1" H. PLANT MODIFICATION NONE I. OTHER

1. PR 2-95-247, LER 2-95-005; OMCR 1-95-0693 (Rev. 0)

2. OMCR 1-96-0939 (Rev.1) ,

FOR TRA';t;;taa USE Ot.Y

1 l I 1RST-2.9 l ((~ l l

    .X. DATA SHEET 3 i

Nuclear Power Range Calibration Data Dates f *h"h) Initials: Wb NSS Initials. . 49 " Cycle: l Reviewed by: Quadrant Power Tilt Ratio Delta Flux Conversion Factors . Normalization Factors Top Bottom Computer Point Factor Detectors Detectors N-41 K0554 21.885 N-41 0.0557 0.0462 N-42 K0552 18.881 N-42 0.0511 0.0465 N-43 K0551 20.495 N-43 0.0545 0.0533 N-44 K0553 19.904 N-44 0.0422 0.0460

  \

n Calibration Map Identifications: d'jlfil A p}qIC o s i /~) 1 i * /1 I Date: Ud'@ EFPD: S T. "D l l Surveillance Check Performance (Technical Specification 4.3.1.1.1) l l l Surveillance Check Performance Acceptable l l EFPD l- (Above Data Effective Until EFPD Next Check Due) l l Next l----- l Check l ----------------------------------------l-----

                                .Date of          l           Map I.D.                   -------l------------ll l Due           l Most Recent Check        l      Most Recent Check     l      EFPD      l       Initials     l l73378 1             //s3                 i                            l m.56 i /42+3/

l........l........./n...........l.......................l............l............l FAP /hC I i:v.s. e i I I I I i I i i l I I ! I l_ l I I I I I I I L I I I I I I I I I i I I I i l i I I I I I I i I- 1 l... .

                    . .I     ,.   .

l .. i l i. ,O I I I I I I

l RTL #AS.640E DUQUESNE LIGHT COMPANY I Nuclear Power Division  !

 ,                     Training Administrative Manual i

OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Verify Clearance JPM NO.: 1AD-003 COMPUTER CODE: N/A Revision No. Date Revision No. Date PREPARED BY: DATE: l APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, or Designee l i Revision 9

i ! RTL #AS.640E DUQUESNE LIGHT COMPANY l Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET l l l DOCUMENT TITLE: 1AD-003. Verify Clearance 1 l Revision Acoroval No. Brief Description Revised by: Signature Date 1 f l^ l l l-l i l Revision 9

1 4 BEAVER VALLEY JOB PERFORMANCE MEASURE

EVALUATOR COVER SHEET

!       I JPM Number: 1AD-003                                        Rev: 0 - System #: 194                                         Faulted: O

JPM

Title:

Verify Clearance K/A

Reference:

194 001 K1.02 3.7/4.1 Task ID #: 341 BBB 0302 JPM Designation: [] NO [] RO x SRO JPM Application: X NRC X Initial Exam Training {; i. I Evaluation Method LOCATION TYPE i EU Perform Plant Site Training ! Simulate X Simulator [] Annual Requal. Exam f Classroom [] OJT l X Initial Operator Exam Administered By: [] Other:

]

BV-T C NRC l. Other: I

Evaluation Results Performer

Name: Employee No:

Results SAT Time (minutes) i UNSAT* Allotted: 10 Actual: Time Critical: Yes X No

 !

• Comments (Required for UNSAT Evaluation) :

i 4 Evaluation Results Check here if same as above i Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results

 ;                                              Question ID                                                 Allotted              Actual      SAT      UNSAT*

i Question #1 NA Employee No: Question #2 NA [] j Employee No:

• Comments (Required for UNSAT Evaluation):

I l Evaluator (Print): Organization: i Evaluator Signature Date: Revision 9

   ._    ,_    m.     - _ _ .      . _ _ , _ - . _ _ _ _ _ _ _ . . . . _ _ _ _ _ . _ . . - _ . _ . _ _ _ . .        . _ - . . . .

I l RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l , . CANDIDATE DIRECTION SHEET i i THIS SHEET TO BE GIVEN TO CANDIDATE

• l' Read:

l Task: lVerifyClearance l l INITIAL A leak has developed on the Chilled Water ONDITIONS. connection to the Office A/C Unit, [VS-AC-4]. l Chilled Water must be isolated from.the unit l while the leak is repaired. An electrical clearance on the unit is'not required. I i TASK STAN.: Clearance points verified in accordance with NDAP [ 3.4, Clearance Procedure. i l l l t INIT. CUE: Your supervisor directs you to check the Valving / Switching Procedure Form for the i I maintenance on (VS-AC-4].  ! I l l At this time, ask the evaluator any questions you have on this JPM.

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

Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. I l l After completing the task, reread the Task Standard. l' After determining the' Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. i Revision 9 1'

     ~   . . -         - . . . -..       -   - . - .     . . .. . . . . - . ...- - . . - -. .. - - . . .. ~. .. - ..-

l I RIL #A5.635.J ' BEAVER VALLEY JOB PERFORMANCE MEASURE j EVALUATOR DIRECTION SHEET l t JPM NUMBER: 1AD-003 JPM TITLE: Verify Clearance ! RECOMMENDED STARTING LOCATION: CONTROL ROOM l DIRECTIONS: You are to perform the task verify Clearance.  ! i INIT. CONDITIONS: A leak has developed on the Chilled Water l connection to the Office A/C Unit, [VS-AC-4] . Chilled Water must be isolated from the-unit.while the leak is repaired. An , electrical clearance on the unit is not i required. l l TASK STAN.: Clearance points verified in accordance  !

with NDAP 3.4, Clearance Procedure.

L - INIT. CUE: Your supervisor directs you to check the Valving / Switching Procedure Form for the maintenance on (VS-AC-4). *

REFERENCES:

NPDAP 3.4, Revision 6 j l L TOOLS: NONE HANDOUT: NPDAP 3.4, Attachment 1, Equipment Clearance Permit NPDAP 3.4, Valving / Switching Procedure Form 4-f 9 Revision 9

I RTL #AS.635.J NUMBER TITLE 1AD-003 Verify Clearance l STEi? STANDARD (Indicate "S" for Sat. or "U" ("C denotes critical step) for Unsat.) START TIME:

1. Review Equipment Clearance 1. Candidate reviews Permit. Equipment Clearance Permit.

EVALUATOR CUE: Provide candidate with Equipment Clearance Permit and with Valving / Switching Procedure Form. COMMENTS:

2. Review Valving / Switching 21 Candidate reviews Procedure Form. Valving / Switching Procedure Form.

l COMMENTS: 1 4 Page 1 of 4 Revision: 0 l

l l l l i l RTL #A5.635.J NUMBER TITLE { 1AD-003 Verify Clearance l l I i i STEP STANDARD i (Indicate "S" for Sat. or "U"  ! ("C" denotes critical step) for Unsat.) I l l 3. Locate and reference 3.1 Candidate locates DWG. control room print. No. 8700-RM-429-1. ) l COMMENTS:  ; 4 l i 4.C Verify isolation valves 4.1.C. Candidate verifies which should be shut. [1VS-53] should be shut. 4.2.C Candidate verifies [1VS-4 8] should be shut. 4.3.C Candidate verifies (1VS-4 9] should be shut. l l COMMENTS: l l i l l Page 2 of 4 Revision: 0 l l

l l RTL #A5.635.J NUMBER TITLE l l 1AD-003 Verify Clearance ' l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 5C Verify vent and drain 5.1.C Candidate verifies valves which should be (1VS-161] should be open. open. 5.2.C Candidate verifies (1VS-55] should be i open. COMMENTS: 6.C Verify all clearance 6.C Candidate identifies points have been that [1VS-51] should identified. be shut 'o properly isolate [VS-AC-4] EVALUATOR NOTE: The candidate could also move clearance to [1VS-46] a.1d [1VS-53). l COMMENTS: h Page 3 of 4 Revision: 0

        . -  . ..    - . , . . .. . - . - . . . . - . . -            - . .     - _ = . . _ , . . , . - . . - . - - . - - - . . . . .

l RTL'#A5.635.J l l l NUMBER TITLE i j 1AD-003 Verify Clearance l l I STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l 7 EVALUATOR NOTE: This completes l the JPM. I l' i STOP TIME: 1 l: i 4 Page 4 of 4 Revision: 0 l t. t v ir - r i +

4 B l$ RECORD TYPE A9 330W BEAVER VALLEY POWER STATION UNIT ~ SYSTEM NUMBER 1 L9 EQUIPMENT CLEARANCE PERMIT l GROUP FOR M MARK NUMBER '/ b ' M.b_ _- N COMP CODE H ~l' E XC _H EQUIPMENT DESCRIPTION O F E ICE A/c. _Do> < T . _ _ . _ _ _ _ ._ _._ .-- CLEARANCE WPE X RED DANGER MASTER AREA PERMIT g SHIFT SUPERVISOR OPERATING S PROCEDURE NO. WORK PKG NO TASK TYPE IMldRTASK NUMBER 9999Y I 5

     ~

SCOPE OF WORK I?E PAi 12. LEA i<. . o A> INLET C otJ AJ 6 p,7jofd e o _. . _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ . . . _. . _ . . . .

                                                                                                                                                                            ~

SPECIAL CLEARING INSTRUCTIONS 6_l. ECYN I C A_L CLEAll A MId_ $1__ l._2(TCLV i l2t D. WORK TO START DATE_.. TIME OUTAGE NO.__ TIME REQUIRED PERMIT ORIGINATED BY: EMP NUMBER NAME DATE l EQUIPMENT SAFETY RELATED NON. SAFETY RELATED l EMP NSS/ANSS DATE EMP NSS/ANSS DATE

a NUMBER l

I, , NUMBER i  : I d l

     <      ESF CLEARANCE REQUIRED                 YES        NO                    STA (IF YES)

CLEARED AND BLOCKED BY DATE GRP EMP NAME DATE GRP EMP NAME DATE FOR NUMBER WORK PARTY LEADER FOR NUMBER WORK PARTY LEADER 1 oO ' ut S0 6t! l RETURN TO SERVICE #dFORMATION___ . y EQUIPMENT READY /R) OR NOT READY (NR) FOR SERVICE 9 GRP EMP NAME R/ DATE GRP EMP NAME R/ DATE

         @ FOR NUMBER WORK PARTY LEADER NR                                               FOR NUMBER WORK PARTY LEADER NR u

g _. 4 5, ._. . . _ . _ _ . . . l b . . . . . _ _ i i j EMP NO NSS/ DESIGNEE R NR DATE EMP NO NSS/ANSS .R NR, DATE

                                                                                                                                                              ^
                                                                                                                                         ~

Nucletr Power Division Administrativa Manual NPDAP 3.4 Revision 6 CLEARANCE PROCEDURE Page 56 of 98 L ATTACHMENT 2 (Example) Unit 1 (Black on white) Unit 2 (Black on blue) , I a l E

                                              }        l 555 aaa              sa 2                 ii E

o ra x , - O m W n i ti

                                                 . ma E                       I i!            R                                                                                                      !

o  ; il -

                                                        =.

Ae Wz - : E ai c sE <s I

I

- 111 i O5 i H M

s 1

} N >5E  : 95 cn > - ~ 'd 0  ! d C= 2 1 > Z - X - s ag d d d O O g , M W D

3. Nef - N 7 EE

> . IE "f EE E< ;

• t e s h.34 rsa

 ! l 1 la . g 13 i i i l ,  : e y ins wg Mc ez _ c- L 1/3 i l y a e' z h 2 2 m 2 0 I ! > wg >ch8 ,A j dia $!!!) 88 E t-

! rd E D' l l

= s E ri > to , ) l _ _- . . _ . - - . .. ._._m _ -._ _ . _ . . _ . _ . . - . . . .__._. _.... _ __ .__ t No. 8700-RM-429-1 l'T'~''llIld 1 1 4 2 3 3 ' 4 4 5 D' 't 't w;1 w a:tr "Ng I -,- .m. ., ;;, ) .c. .. t , -e a nt y,x,o: a n wn - =, -e w - P . @ ,o i. ' k @m.,s t. 's b @ ', ' b= w eDs "- E'". N m.$.n ,, kc , ) ls ..,s-a . '< @ *, 4GD '* @- .-W Ac,.') WGDs 'c"@. 1Psa; # G,,D, 3 i 4' s e p 9,g = ~ M,e '- 9, D " g D'r g - .'k h s,M. GDd M 'r' i l; ,= i e s- ,, w . g o _ , a tt" -. I maa us ==. 7 r '. == = ' q , ,, l c.y , ,m.u ~, go - - < =.. m W: - '" i , I c 4 '- .  %,. C D, ,, x .Lu_;... > b .m ".:' A5D mAED a c ,-- c  ? [" <GD r  % CE> l ~ .cDx r, --CDi c- ,, i - l l l ,  : 'Q_. c-

.g ,.k rCiD CF '\

j l . l q 'rG E=Y. W ier b l t:.#W'. . . . . . .... L.. . }.v . x.w<.,2,, M ,

r. v.:n TV 3,e9 EXEW 1

. m .. ,.. ') 4. . -- . ,.. m W D ... e c i ;cos' Aco7 a red T.g- e e GEh.e .e N, ,,, . p 3 3 g . .. p g - C-l" <a.-  ;.pco ,g , pe ,.F s7 j~an gw-< t....,m, a: .......t....jv - v,2,,w - - e'F sg.,~ t.._ e .... ..w j. "",,, * [~$*,e Iw ' 4;. "' g ~ . 4; . . e r@g. -- Pco i *' 'I:!  % 4, h

:t -( p;  %.,. .,2.. ,

,eD p . 4,,m, i ,c!D - ===~~~'~ 5.M qv3; ----@.m ;.g.  ; ak ;jg ,,, y,ap gyv1 eif

y. a Q",, gg,,,, k G a

.J-e.y%n m& gbgg.g@am c- po ,g ,,tw.a.. .. . .. .,.,.,.g 1  : j . . *. .s y i. eve t-  ! r m 'I . "E 5,-S' - e . "o'E' r- .7 9 Th2'.-e a 52 - 4 A pA.- GD- e:9. . v .. , j c %'" p= m am ,e l * ,e &g ** ^ :.m ,gg ^ *" na i

3. 4,,av yk, .. 4 r+, * .. - ,

Go< w-4 ,) c = , -@p = 'ar.An'3 sr .A, ><-=>.- A - eo*4- ' 's:::,,5'

c &# w. * # 4 g eid @g. ....

.. e# p a# p .. Ana T,- , - -e , = '+' **x w < _ $ a<G vna/D - are.c.n. :'

3.'*c,.'%.". ,a c il'! . ". *'# I"==' M

. 5" t!! k'i{$j+g!;{}dM  ! i!!i q , ljh_!, 9 3 ._ 2 n n =' 5 F l RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE l PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT' CHECKLIST /JPM TITLE: Enter the Radiological Controlled Area JPM NO.: 1AD-004 ' COMPUTER CODE: N/A Revision No. Date  ! Revision No. Date 1 l PREPARED BY: DATE: APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, or Designee f l Revision 9 _. ._ .m . . _ _ . _ . . _ . . . . . . _ _ _ _ . _ _ _ _ . _ . . _ . . . . _ . _ _ . . . _ . _ . _ . . . . . - . . . . _ . . . _ _ _ . t RTL #A5.640E DUQUESNE LIGHT COMPANY-Nuclear Power Division j , Training Administrative Manual r .- , t I i- LESSON PLAN AND OJT REVISION APPROVAL SHEET t DOCUMENT TITLE: 1AD-004 Enter the Radioloaical Controlled Area ^ i Revision Acoroval  ! No. Brief Description Revised by: Signature Date , l 1 l I r l i i I l I f s I-t i i l l l l l I i i L

i 5

1 I Revision 9 -.-.-..-...-.--.-.~..-..--..---.-...--~--.--.-n. - ! BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET I JPM Number: 1AD-004 Rev: 0 System #: 194 Faulted: O j' JPM

Title:

Enter the Radiological Controlled Area I K/A

Reference:

194 001 K1.03 2.8/3.4 Task ID #: 119 GGG 0304 JPM Designation: O NO O RO x SRO l ! JPM Application: X NRC x Initial Exam O Training 1 ) Evaluation Method LOCATION TYPE l l x Perform E Plant Site O Training j O Simulate O Simulator O Annual Requal. Exam l 0 Classroom O OJT E Initial Operator Exam k Administered By: O Other: ! O sv-T O nRC O Other: Evaluation Rest._1_t;_sq Performer: Name: Employee No: Results O SAT Time (minutes) O UNSAT* Allotted: s Actual: Time Critical: 0 Yes X No

• Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above i Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 NA O O Employee No: Question #2 NA O O Employee No:

• Comments (Required for UNSAT Evaluation):

Evaluator (Print) : Organization: Evaluator Signature Date: Revision 9

 .-_ .  . _ . _ _ _ . _ .      .-__m-       _   ._         _ . . _ - . _ _ . . . _ . _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ . . _ _     _ . . . - _ _ .

RTL.#AS.'635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE' DIRECTION SHEET-

   . ,4 THIS SHEET TO BE GIVEN TO CANDIDATE

• l Read: 1 l

Task: lEntertheRadiologicalControlledArea [ i L ! INITIAL You have been directed to enter the RCA in order l to' perform JPM # , CONDITIONS: . i TASK STAN.: lRCAentryperformedinaccordancewithHealth ' l Physics Manual. INIT. CUE: Your supervisor directs you to enter the RCA in I order to perform JPM # . i i r ! At this time, ask the evaluator any questions you have on this ! JPM. When satisfied that you understand the assigned task, announce i- "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. l 1 i After completing the task, reread the Task Standard. After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. i t t I I Revision 9

RIL #A5.635.J- BEAVER VALLEY JOB PERFORMANCE MEASURE

  ;                            EVALUATOR DIRECTION SHEET I

JPM NUMBER: 1AD-004 l- JPM TITLE: Enter the Radiological Controlled Area l' l l RECOMMENDED 1 i STARTING LOCATION: Control Access I l l l DIRECTIONS: You are to perform the task enter the l- Radiological Controlled Area. j INIT. CONDITIONS: You have been directed to enter the RCA in order to perform JPM # . . l l TASK STAN.: RCA entry performed in accordance with Health Physics Manual. INIT. CUE: Your supervisor directs you to enter the RCA in order to perform JPM # .

REFERENCES:

Health Physics Manual l- LP-RC-02, Revision 17 l l 4 ! TOOLS: NONE l l HANDOUT: NONE i l l l Revision 9

l I l RTL #A5.635.J  ! 1 1 l l NUMBER TITLE I i l 1AD-004 Enter the Radiological Controlled Area 1 4 1 STEP STANDARD (Indicate "S" for Sat. or "U" l I ("C" denotes critical step) for Unsat.) 1 l ? l l START TIME: 1.C Locate and review 1.1 Candidate locates Radiation Work Permit Radiation Work Permit (RWP). (RWP). l 1.2.C Candidate reviews Radiation Work' Permit (RWP). COMMENTS: 1 , 2.C Insert Rados ARD into ARD 2.1 Candidate locates 1 1000 reader. Rados ARD. 2.2.C Candidate inserts Rados into ARD 1000 reader. l l I l COMMENTS: 1 1 i Page 1 of 4 Revision: 0 l l

i l RTL #A5.635.J i NUMBER TITLE 1 1AD-004 Enter the Radiological Controlled Area l 1 STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) I i 3.C I Enter data into ARD 1000 3.1.C Candidate enters ID  ! reader. number into ARD 1000 l reader. l 3.2. Candidate verifies name on ARD 1000 l reader. 1 3.3.C Candidate enters RWP number into ARD 1000 reader. COMMENTS: Page 2 of 4 Revision: 0 l l

  . .    .  .,     .   .. . .    - . . .      - . . ~ . . - . - - . - . .
                                                .                                   .. . . . ~ .      . . . - -. . . . . .

RTL #AS.635.J , i NUMBER TITLE ,- 1AD-004 Enter the Radiological Controlled Area l-l

• 1 STEP STANDARD (Indicate "S" for' Sat, or "U"

("C" denotes critical step) for Unsat.) I l 4. Observe and note ARD 4.1. Candidate observes ARD dose and dose rate 1000 reader display setpoint. and notes ARD dose setpoint. ( 4.2 Candidate observes ARD 1000 reader display and notes ARD dose rate setpoint, i COMMENTS: i l l l. r Page 3 of 4 Revision: 0

i l RTL #A5.635.J NUMBER TITLE l t 1AD-004 Enter the Radiological Controlled Area STEP STANDARD l (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 1 1 1 5.C Remove Rados ARD from 5.1.C Candidate removes reader. Rados ARD from ARD 1000 reader.

         .                            5.2.C   Candidate places Rados ARD on upper body near   l TLD.

COMMENTS: 6.C Enter the RCA. 6.C Candidate enters the RCA. COMMENTS: l l l STOP TIME: l f I Page 4 of 4 Revision: 0

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division

Training Administrative Manual I

OJT CHECKLIST /JPM COVER PAGE 1 PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training l OJT CHECKLIST /JPM TITLE: Classify Emergency Plan Event JPM NO : 1AD-005 COMPUTER CODE: N/A Revision No. Date Revision No. Date l i l l l PREPARED BY: DATE: APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, or Designee l Revision 9

                                    . . _ . _ . _ . . . _ . . _ _ . . _ _ - . _ . . . _ _ . - _ _ . _ . . . . _ . . _ _ _ _ _ _ _ _ . . _ _ . . . . . . ~ . . . _ _ . ..

J 4 .. \- RTL #A5.'640E DUQUESNE LIGHT COMPANY-Nuclear Power Division  ! Training Administrative Manual

• l l' i LESSON PLAN AND OJT REVISION APPROVAL SHEET i i

      ^

i l DOCUMENT TITLE: 1AD-005.-Classifv Emercency Plan Event  ; l Revision . . . Acoroval i No. Brief Description Revised by: Signature Date ( r

                                                                                                                                                                            ?

i 5 l i l,  ! r l l l Revision 9

    .- .- _ - _ .. ...~ - - .                    .._ _... - . .. - .              .   . _ - . . _ . - .           - . . _       _ - . . . .    . . _- ..

i t i ~ BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET i I JPM Number: 1AD-005 Rev: 0 System #: 194 Faulted: O JPM

Title:

Classify Emergency Plan Event i K/A

Reference:

194 001 A1.16 3.1/4.4 Task IL #: 344 019 0302 4 j JPM Designation: O NO RO X SRO - i JPM Application: X NRC x Initial Exam O Training 1 y i 4 Evaluation Method LOCATION TYPE X Perform Plant Site O Training j Simulate @ Simulator Annual Requal. Exam j 1 Classroom O OJT X Initial Operator Exam l Administered By: Other: A BV-T O NRC ! Other: i

Evaluation Results i

1 Performer: Name: Employee No: l Results SAT Time (minutes) ) ! UNSAT* Allotted: 15 Actual: l ] Time Critical: X Yes No

• Comments'(Required for UNSAT Evaluation)- l Evaluation Results Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 NA Employee No: Question #2 NA 1 Employee No:

• Comments (Required for UNSAT Evaluation):

j I Evaluator (Print): Organization: Evaluator Signature Date: Revision 9

                        . ~ - . -          - ~ - - - . - ~ .~ . .. -    .~ .. - -      ....- - .-.-..... -

ll r h RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l-4 CANDIDATE DIRECTION SHEET THIS SHEET TO BE GIVEN TO CANDIDATE

• i

                      ~ Read:

i l l Task: Classify Emergency Plan Event i INITIAL You have just completed Simulator Scenario No: CONDITIONS: 9- . e s mu a r s now in Freeze. i i l L TASK STAN.: Emergency Conditions classified in accordance with EPP/I-la. i l i i  ! INIT. CUE: You are to. classify the event that just occurred on the simulator. The simulator is now in Freeze. 'i You may review plant and system status as , necessary prior to performing the Emergency Plan Classification. At this time, ask the-evaluator any questions you have on this 'i JPM. ' When satisfied that you understand the assigned task, announce "I am now beginning the.JPM". Simulate performance or perform as directed the required task. Point to any indicator or. component you verify or check and announce your observations. After completing the task, reread the Task Standard, i After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. i Revision 9

    .         - - . . . - - - - .      ~ . - . . . _ . . . - . . . ~ , - - . - ~ . _ . . . - . . . . - . . . . . - _ ..

RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1AD-005 l JPM TITLE: Classify-Emergency. Plan Event 1 I 1

          -RECOMMENDED l-          STARTING LOCATION:            Simulator 1

l DIRECTIONS: You are to perform the task classify Emergency Plan Event i 1 INIT. CONDITIONS: You have just completed Simulator Scenario No: 97-1. The simulator is now in Freeze. I TASK STAN.: TASK STAN.: Emergency Conditions classified in accordance with EPP/I-la.

           'INIT. CUE:                   You are to classify the event that just occurred on the simulator. The simulator is-now in Freeze..You may review plant and system status as necessary prior to performing the Emergency Plan Classification.

REFERENCES:

EPP/I-1.a, Revision 6 TOOLS': NONE HANDOUT: NONE l l l I Revision 9

RTL #A5.635.J l NUMBER TITLE 1AD-005 Classify Emergency Plan Event STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR NOTE: This JPM is to be performed immediately following the completion of Simulator Scenario No: 97-1. The simulator should be left in Freeze following the completion of this scenario and while the JPM is being performed. l START TIME: Candidate locates and reviews EPP/I-1.a.

1. Determine plant 1. Candidate reviews l conditions. plant conditions.

EVALUATOR NOTE: The Candidate may choose to walk down the . control boards to review / determine plant conditions. COMMENTS: i I l Page 1 of 2 Revision: 0 l

                                                                              +e

I RTL #RS.635.J NUMBER TITLE 1AD-005 Classify Emergency Plan Event i I I STEP STANDARD { (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) I 2.C ) Classify the Event. 2.C Candidate classifies l the event as an  ! UNUSUAL EVENT. l l EVALUATOR NOTE: Tab 2.10 COMMENTS:  ! l t STOP TIME: i Page 2 of 2 Revision: 0 l i

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Classify Emergency Plan Event JPM NO.: 1AD-006 COMPUTER CODE: N/A Revision No. Date Revision No. Date l l l PREPARED BY: DATE: APPROVED FOR IMPLEMENTATION: PATE: Director, Operations Training, or Designee 1 l l l Revision 9

1 . ( RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division l Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: 1AD-006, Classifv Emercency Plan Event Revision Acoroval No. Brief Description Revised by: Signature Date Revision 9

     . . .--..- - - - -. ..               .-.    . - _ . - . . .            . . . -    - . ~ - . - - . ~ . - . . - . . . - . - . - . - - - . - . - . . -

l BEAVER VALLEY JOB PERFORMANCE MEASURE e EVALUATOR COVER SHEET }4 JPM Number: 1AD-006 Rev: O System #: 194 Faulted: O JPM

Title:

Classify Emergency Plan Event i K/A

Reference:

194 001 A1.16 3.1/4.4 Task ID #: 344 019 0302 l I JPM Designation: O NO O RO x SRO ) X X JPM Application: NRC Initial Exam O Training i

Evaluation Method LOCATION TYPE l X Perform O Plant Site O Training O Simulate x Simulator O Annual Requal. Exam

O Classroom O OJT X

f Initial Operator Exam l Administered By: O Other: ! O av-T O NRC 0 Other: 4

Evaluation Results j Performer

Name: Employee No:

Results O SAT Time (minutes) O UNSAT* Allotted: is Actual: Time Critical: X Yes O No

• Comments (Required for UNSAT Evaluation) :

Evaluation Results O check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 __ NA O O Employee No: Question #2 NA O O Employee No:

• Comments (Required for UNSAT Evaluation):

4 Evaluator (Print) : Organization: Evaluator Signature Date: Revision 9

  .     .   ---      - - ..,.-.- ,        ~.. - .- - .~ ...- _.-.. - . _-.-...-...~.   - . . - . - - . -

RTL #AS.635.J- BEAVER VALLEY JOB PERFORMANCE MEASURE l

      ,                                       CANDIDATE DIRECTION SHEET t.

THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

i Task: lClassifyEmergencyPlanEvent l l l 1 INITIAL You have.just completed Simulator Scenario No: 1 CONDITIONS: 9 - . e s mu a r s now-in Freeze. l l l< r I I TASK STAN.: Emergency Conditions classified in accordance .

with EPP/I-la. i INIT. CUE: You are to classify the event that just' occurred on the1 simulator. The simulator is now in Freeze.

                                                                                 ~

l You may review plant and system status.as l necessary prior to performing the Emergency Plan ' classification. At this time,-ask the evaluator any questions you have on this ! JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. i After completing the task, reread the Task Standard. After determining the Task Standard has been met, announce "I l have completed the JPM". Then hand back this sheet to the l- evaluator. l l L I l l' ! -Revision 9 i

  ._     -_...-.-._.____-m .

RIL #A5.635.J . BEAVER VALLEY JOB PERFORMANCE MEASURE l EVALUATOR DIRECTION SHEET 7 JPM NUMBER: 1AD-006 p JPM TITLE: Classify Emergency Plan Event RECOMMENDED l

           . STARTING LOCATION:              Simulator l;

i DIRECTIONS: You.are to perform the task classify Emergency Plan Event. INIT. CONDITIONS: You have just completed Simulator Scenario No: 97-2. The simulator is now in Freeze. TASK STAN.: TASK STAN.: Emergency Conditions classified in accordance with EPP/I-la. - . i L INIT. CUE: You are to classify the event that-just- ' 1 occurred on the simulator. The simulator is l now in Freeze. You may review plant and i system status as necessary prior to 3 performing the Emergency Plan classification.

REFERENCES:

EPP/I-1.a, Revision 6 TOOLS: NONE 4 HANDOUT: NONE i Revision 9

RTL #A5.635.J l l NUMBER TITLE l 1AD-006 Classify Emergency Plan Event f STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR NOTE: This JPM is to be performed immediately following the completion of Simulator Scenario No: 97-2. The simulator should be left in Freeze following the l completion of this scenario I and while the JPM is being performed. START TIME: Candidate locates and l 7eviews EPP/I-1.a.

1. Determine plant 1. Candidate reviews i conditions. plant conditions. l EVALUATOR NOTJ1 The Candidate may choose to walk down the control boards to review /

determine plant conditions. l COMMENTS: I I Page 1 of 2 Revision: 0

. _ . . . - . _ _ . . .. .. _ . . _ _ m. . - -. . _ . . . . . _ - . . . . _ . . - . _ _ - . _ . _ . _ _ _ _ . _ _ . . _ . . _ . . . i RTL~#A5.635.J-( _ NUMBER TITLE 1AD-006 Classify Emergency Plan Event STEP STANDARD (Indicate "S" 'for Sat. or."U" (."C" denotes critical step) for-Unsat.) 2.C Classify the Event. 2.C Candidate classifies the event as an ALERT. , 1 l EVALUATOR NOTE: Tab-1.2.1 1 COMMENTS: STOP TIME: l l l l 4 t Page 2 of 2 Revision: 0

       . .      . .     .   . _ .        .. . _ _ . _ . _ _ _ . . _ ._        .m _ . _ . . . . _ . _ _ . - . . _ _ _ . _ .    .~

1 RTL #A5;640E DUQUESNE LIGHT COMPANY Nuclear Power Division I

Training Administrative Manual i -

OJT CHECKLIST /JPM COVER PAGE-PROGRAM TITLE: Licensed Operatur Training , SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Classify Emergency Plan Event

           'JPM NO.:                               1AD-007
           . COMPUTER CODE:                       N/A I

Revision No. Date Revision No. Date I PREPARED BY: DATE: 1-l l l APPROVED FOR L IMPLEMENTATION: DAIE: Director, Operations Training, or Designee i i f - l l Revision 9

1 RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division i Training Administrative Manual ( { I J LESSON PLAN AND OJT REVISION APPROVAL SHEET I 1 DOCUMENT TITLE: 1AD-007, Classifv Etreroency Plan Event l i Revision Acoroval No. Brief Description Revised by: Signature Date i i l r 4

                                                                                                                                        )

I l L Revision 9

   . - - -. . . - - . - - - . -          . . . - . - - -      - . .    . . _ - - -             . ~ ~ ~ - . ~ . - - - - .                - . . - . . . -

4 t BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET ! I JPM Number: 1AD-007 Rev: O System #: 194 Faulted: O { JPM

Title:

Classify Emergency Plan Event j K/A

Reference:

194 001 A1.16 3.1/4.4 Task ID #: 344 019 0302 i JPM Designation: O NO O RO x SRO , I JPM Application: X NRC E Initial Exam O Training ! l i ! Evaluation Method LOCATION TYPE l X Perform O Plant Site O Training l 0 Simulate E Simulator O Annual Requal. Exam ' O Classroom 0 oJT E Initial Operator Exam Administered By: O Other: O av-T O NRC O Other: Evaluation Results Performer: Name: Employee No: Results O SAT Time (minutes) O uNSAT* Allotted: Is Actual: Time Critical: X Yes O No

• Comments (Required for UNSAT Evaluation) :

Evaluation Results O Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 NA O O Employee No: Question #2 NA ' O O Employee No:

• Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization: Evaluator Signature Date: Revision 9

,__._ -. - . _ - . - - - - - _ _ _ . - . . _ . - . . . . - . . - - - . . . . . ~ . . - . . - - - _ . - - l , l RTL #A5.635.J BEAVER VALLEY JOB' PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET l1 - , THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

i Task: Classify Emergency Plan Event t INITIAL You have just completed Simulator Scenario No: CONDITIONS: 9- . e simulator is now in Freeze. TASK STAN.: Emergency Conditions classified in accordance with EPP/I-la. INIT. CUE: You are to classify the event that just occurred on the simulator. The simulator is now in Freeze. You may review plant and system status as necessary prior to performing the Emergency Plan  ; Classification. At this time, ask the evaluator any questions you have on this JPM. When satisfied'that you understand the assigned task, announce-

                        "I am now beginning the JPM".

i Simulate performance or perform as directed the required task.  ! Point to any indicator or component you verify or check and i announce your-observations. t After completing the task, reread the Task Standard. < After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the  ! evaluator. , i l Revision 9 r . . ,

! RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l i

                                                                                                                                )

EVALUATOR DIRECTION SHEET i JPM NUMBER: 1AD-007 JPM TITLE: Classify Emergency Plan Event  ! j RECOMMENDED STARTING LOCATION: Simulator l

             . DIRECTIONS:                                   You are to perform the task classify Emergency Plan Event.

INIT. CONDITIONS: You have just completed Simulator Scenario No: 97-3. The simulator is now in Freeze. TASK STAN.: TASK STAN.: Emergency Conditions classified in accordance with EPP/I-la. INIT. CUE: You are to classify the event that.just occurred on the simulator. The simulator is now in Freeze. You may review plant and system status as necessary prior to performing the Emergency Plan Classification.

REFERENCES:

EPP/I-1.a, Revision 6  ! TOOLS: NONE HANDOUT: NONE i l Revision 9

RTL #AS.635.J t l L i - NUMBER TITLE 1AD-007 Classify Emergency Plan Event l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR NOTE: This JPM is to be performed immediately following the completion of Simulator Scenario No: 97-3. The simulator should be left in Freeze following the completion of this scenario and while the JPM is being performed. START TIME: Candidate locates and reviews EPP/I-1.a.

1. Determine plant 1. Candidate reviews conditions, plant conditions.

EVALUATOR NOTE: The Candidate may choose to walk down the control boards to review / determine plant conditions. COMMENTS: l 1. Page 1 of 2 Revision: 0

l 1 l RTL #A5.635.J l k l NUMBER TITLE ) 1AD-007 Classify Emergency Plan Event I STEP STANDARD l (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.)  ! 1 1 I 2.C Classify the Event. 2.C Candidate classifies  ; the event as an ALERT. l l EVALUATOR NOTE: Tab 1.2.4 l COMMENTS: l l l 1 1 STOP TIME: l l l Page 2 of 2 Revision: 0

                   . _ -    .     .       . - = . ~ . _ _ __ -    .  . . _ .

l

                                                                             )

l RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual i l l OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training I SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Classify Emergency Plan Event l JPM NO,: 1AD-008 1 COMPUTER CODE: N/A I Revision No. Date Revision No. Date PREPARED BY: DATE: APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, or Designee Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY < Nuclear Power Division I Training Administrative Manual l I LESSON PLAN AND OJT REVISION APPROVAL SHEET ) l I DOCUMENT TITLE: 1AD-008. Classify Emercency Plan Event 1 Revision Acoroval No. Brief Description Revised by: Signature Date Revision 9

   . - - . .  - . . . - -         . . . ~ - .      . - .     . . - .        . . .    - . - -        . ~ . . _ . - . . _ -      . . . _ . - - . - . -

l 1 BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET

JPM Number: 1AD-008 Rev: 0 System #: 194 Faulted: O l JPM

Title:

Classify Emergency Plan Event i K/A

Reference:

194 001 A1.16 3.1/4.4 Task ID #: 344 019 0302 JPM Designation: O NO O RO x sRO JPM Application: X NRC X Initial Exam O Training i I Evaluation Method LOCATION TYPE l X Perform O Plant site O Training O simulate x simulator O Annual Requal. Exam O Classroom O OJT X Initial Operator Exam Administered By: O Other: O Bv-T O NRC O Other: l 1 Evaluation Results Performer: Name: Employee No: Results O SAT Time (minutes) O UNSAT* Allotted: 15 Actual: Time Critical: x Yes O No

• Comments (Required for UNSAT Evaluation) :

Evaluation Results O Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 NA O O Employee No: Question #2 NA O O Employee No:

• Comments (Required for UNSAT Evaluation) :

i i i Evaluator (Print): Organization: Evaluator Signature Date: Revision 9

l

                    'RTL #A5.635.J                BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET.

{. - THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Task: lClassifyEmergencyPlanEvent ' i INITIAL You have just completed Simulator Scenario No: CONDITIONS: 97-4. The_ simulator is now in Freeze. . TASK ~STAN.: lEmergencyConditionsclassifiedinaccordance

with EPP/I-la.

1

      ,                INIT. CUE:              You are to classify the event that just' occurred on the simulator. The simulator is now in Freeze.                                                           j You may review plant and system status as                                                                    .

necessary prior to performing the Emergency Plan ' Classification. At this-time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". l Simulate performance or perform as directed the required task.  ; Point to any indicator or component you verify or check and j announce your observations. l

                           -After completing the task, reread the Task Standard.                                                                            l After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator, l-l l

r Revision 9

        . _ - - . -         -  .   ..       - ~ ~ - _ . . - _ . - - . - - -  - - .. . . -    --

L i RIL M5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE I

 ;                               EVALUATOR DIRECTION SHEET JPM NUMBER:                1AD-008 JPM TITLE:                 Classify Emergency Plan Event
     . RECOMMENDED STARTING LOCATION:        Simulator l
     ' DIRECTIONS:               You are to perform the task classify                           l Emergency Plan Event.                                          ,

INIT. CONDITIONS: You have just completed Simulator Scenario No: 97-4. The simulator is now in Freeze. TASK STAN.: TASK STAN.: Emergency Conditions classified in accordance with EPP/I-la. INIT. CUE: You are to classify the event that just occurred on the simulator. The simulator is ' now in Freeze. You may review plant and system status as necessary prior to performing the Emergency Plan Classification.

REFERENCES:

EPP/I-1.a, Revision 6 TOOLS: NONE HANDOUT: NONE 4 l Revision 9

l RTL #A5.635.J l 4 NUMBER TITLE 1AD-008 Classify Emergency Plan Event STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR NOTE: This JPM is to be performed immediately following the completion of Simulator Scenario No: 97-4. The simulator should be left in Freeze following the completion of this scenario and while the JPM is being performed. START TIME: Candidate locates and reviews EPP/I-1.a.

1. Determine plant 1. Candidate reviews conditions. plant conditions.

EVALUATOR NOTE: The Candidate may choose to walk down.the control boards to review / determine plant conditions. COMMENTS: Page 1 of 2 Revision: 0

_m _ _ _ . . ._ _ _ _ . . . . . . . _ . _ _ . _ _ _ . _ _ . . _ _ . . . . . _ . _ . _ _ . . . _ _ _ . _ _ _ . ~ RTL #AS.635.J e i NUMBER TITLE l i i i-1AD-008 Classify Emergency Plan Event i i i l

l. STEP STANDARD I (Indicate "S" for Sat. or "U"

("C" denotes' critical step) for Unsat.) t 2.C Classify the Event. 2.C Candidate classifies the event as an SITE AREA EMERGENCY. l EVALUATOR NOTE: Tab.2.3 COMMENTS: I l l STOP TIME: l i l l i I L: l' e Page 2 of 2 Revision: 0

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual l 1 OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Classify Emergency Plan Event JPM NO.: 1AD-009 COMPUTER CODE: N/A Revision No. Date Revision No. Date PREPARED BY: DATE: APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, or Designee i Revision 9

    . _ - . - . .  . - . .   . . - .. .        .. ~ .. - - ...-..      . - - - - - - - - - -               .-- - ~ ~ - -

\. l l l RTL #AS.640E DUQUESNE LIGHT' COMPANY, j (- Nuclear Power. Division , ! Training Administrative Manual l 1 l l 1 LESSON PLAN AND OJT REVISION APPROVAL SHEET i i i l DOCUMENT TITLE: 1AD-009. Classifv Emeroency Plan Event l I Revision Acoroval l No. Brief Description ' Revised by: Signature Date-1 i o 1 s I l

                                                                  -Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE l EVALUATOR COVER SHEET \

                                                                                                                                                                                           \

! JPM Number: 1AD-009 Rev: 0 System #: 194 Faulted: O l JPM

Title:

Classify Emergency Plan Event l K/A

Reference:

194 001 A1.16 3.1/4.4 Task ID #: 344 019 0302 JPM Designation: O NO O RO E SRO l JPM Application: x NRC X Initial Exam O Training l l Evaluation Method LOCATION TYPE l X Perform Plant Site O Training O Simulate x Simulator O Annual Requal. Exam I O Classroom O OJT l E Initial Operator Exam Administered By: O Other: O av-T O NRC O Other: Evaluation Results Performer: Name: Employee No: Results O SAT Time (minutes) O UNSAT* Allotted: 15 Actual: Time Critical: X Yes O No

• Comments (Required for UNSAT Evaluation) :

Evaluation Results O Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 NA O O Employee No: Question #2 NA O O Employee No:

• Comments (Required for UNSAT Evaluation) :

( . . Evaluator (Print) : Organization: Evaluator Signature _ Date: l Revision 9

. ~     _ - . -        - . - -       - - . . - . - . . . . . ~       . . - - - _ . - . - . - . . - . . . . _ - - - . . -

I RTL #RS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l

CANDIDATE DIRECTION SHEET

.! I

• i THIS SHEET TO BE GIVEN TO CANDIDATE
• l 1 Read: i i

l

• Task: Classify Emergency Plan Event l

l INITIAL You have just completed Simulator Scenario No: CONDITIONS: 9- . e s mu a r s now in Freeze. l 4 TASK STAN.: Emergency Conditions classified in accordance

- with EPP/I-la. i i 1 INIT. CUE

You are to classify the event that just occurred on the simulator. The simulator is now in Freeze.

You may review plant and system status as _ _ necessary prior to performing the Emergency Plan l ' Classification. I At this time, ask the evaluator any questions you have on this 1 g . JPM. j ' i ' l When satisfied that you understand the assigned task, announce I "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and

                  -~

announce your observations. j E After completing the task, reread the Task Standard. i 7 After determining the Task Standard has been met, announce "I

~~"

                          -have completed the JPM". Then hand back this sheet to the j                            evaluator.

i:~ d -. a Revision 9.

l i RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE i I EVALUATOR DIRECTION SHEET I l JPM NUMBER: 1AD-009 I JPM TITLE: Classify Emergency Plan Event 1 l RECOMMENDED STARTING LOCATION: Simulator i I l DIRECTIONS: You are to perform the task classify Emergency Plan' Event. INIT. CONDITIONS: You have just completed Simulator Scenario No: 97-5. The simulator is now in Freeze. TASK STAN.: TASK STAN.: Emergency Condit, ns classified in accordance with EPP/I-1c INIT. CUE: You are to classify the event that just occurred on the simulator. The simulator is now in Freeze. You may review plant and system status as necessary prior to performing the Emergency Plan Classification.

REFERENCES:

EPP/I-1.a, Revision 6 TOOLS: NONE HANDOUT: NONE l Revision 9

I i RTL #A5.635.J l l , NUMBER TITLE i 1AD-009 Classify Emergency Plan Event i i i i STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR NOTE: This JPM is to be performed immediately following the completion of Simulator Scenario No: 97-5. The simulator should be left in Freeze following the , completion of this scenario and while the JPM is being performed. START TIME: Candidate locates and l reviews EPP/I-1.a. l

1. Determine plant 1. Candidate reviews conditions. plant conditions.

EVALUATOR NOTE: The Candidate may choose to walk down the control boards to review / determine plant conditions. I l COMMENTS: Page 1 of 2 Revision: 0

          -RTL #A5.635.J

NUMBER TITLE 1AD-009 Classify Emergency Plan Event 1

4 STEP - STANDARD (Indicate "S" for Sat. or "U" 4 i ("C" denotes critical step) for Unsat.) f. t j 2.C Classify the Event. 2.C Candidate classifies the event as an UNUSUAL EVENT. l EVALUATOR NOTE: Tab 2.10 COMMENTS: STOP TIME: Page 2 of 2 Revision: 0

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual 4 OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Classify Emergency Plan Event JPM NO.: 1AD-010 COMPUTER CODE: N/A Revision No. Date Revision No. Date PREPARED BY: DATE: I l APPROVED FOR I IMPLEMENTATION: DATE: 1 Director, Operations Training, or Designee j i

                                                                )

Revision 9

l RTL #A5.640E DUQUESNE LIGHT COMPANY l ' Nuclear Power Division I Training Administrative Manual  ! k j LESSON PLAN AND OJT REVISION APPROVAL SHEET l DOCUMENT TITLE: 1AD b10, Classifv Emeroency Plan Event Revision ADoroval No. Brief Description Revised by: Signature Date l l Revision 9 l

l I BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: 1AD-010 Rev: O System #: 194 Faulted: O j JPM

Title:

Classify Emergency Plan Event K/A

Reference:

194 001 A1.16 3.1/4.4 Task ID #: 344 019 0302 JPM Designation: O NO O RO x SRO JPM Application: X NRC E Initial Exam O Training j'. Evaluation Method LOCATION TYPE X Perform O Plant Site O Training O Simulate x Simulator O Annual Requal. Exam O Classroom O OJT x Initial Operator Exam Administered By: O Other: I O Bv-T O NRC 0 Other: ' Evaluation Results Performer: Name: Employee No: Results O SAT Time (minutes) 1 O UNSAT* Allotted: 15 Actual: ) I Time Critical: X Yes O No

• Comments (Required for UNSAT Evaluation) :

Evaluation Results O Check here if same as above Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 NA O O Employee No: Question #2 NA O O I Employee No: l

• Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization: Ev;1uator Signature Date: Revision 9

t t RTL #A5.635.'J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET I i' THIS SHEET TO BE GIVEN TO CANDIDATE *

                                                                                                                                              )

I I Read: ' Task: Classify Emergency Plan Event l l INITIAL You have.just completed Simulator Scenario No: CONDITIONS: 97-6. The simulator is now in Freeze. , l TASK STAN.: Emergency Conditions classified in accordance with EPP/I-la. INIT. CUE: You are to classify the event that just occurred on the simulator. The simulator is now in Freeze. You may review plant and system status as necessary prior to performing the Emergency Plan . Classification. , At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. j Point to any indicator or component you verify or check and j announce your observations. { l After completing the task, reread the Task Standard. After determining the Task Standard has been met, announce "I  ; have completed the JPM". Then hand back this sheet to the L evaluator. l l Revision 9

 -         - ~,- - -.- -              . . - . . . . .              - - - - ~ - - - . -    . -    . ----.

l RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE j EVALUATOR DIRECTION SHEET i i l JPM NUMBER: 1AD-010 i l JPM TITLE: Classify Emergency Plan-Event l 1 1 RECOMMENDED  ! STARTING LOCATION: Simulator ) l DIRECTIONS: You are to perform the task classify L Emergency Plan Event. i ' l l INIT. CONDITIONS: You have just completed Simulator Scenario No: 97-6. The simulator is now in Freeze. TASK STAN.: TASK STAN.: Emergency Conditions classified

~

in accordance with EPP/I-la. INIT. CUE: You are to classify the event that just occurred on the simulator. The simulator is now in Freeze. You may review plant and system status as necessary prior to l performing the Emergency Plan classification.

REFERENCES:

EPP/I-1.a, Revision 6 TOOLS: NONE HANDOUT: NONE l l-l- l i - 5 4 l i Revision 9

l RTL #AS.635.J l t l NUMBER TITLE 1AD-010 Classify Emergency Plan Event l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR NOTE: This JPM is to be performed immediately following the completion of Simulator Scenario No: 97-6. The simulator should be left in Freeze following the completion of this scenario and while the JPM is being-performed. START TIME: Candidate locates and reviews EPP/I-1.a.

1. Determine plant 1. Candidate-reviews conditions. plant conditions.

EVALUATOR NOTE: The Candidate may choose to walk down the control boards to review / determine plant conditions. COMMENTS: l l Page 1 of 2 Revision: 0

  ..   . . . . . -..    .          -.         . - _ ~ . . _ . . . , _ . .         . . - . . .--. -        ... . .. . . _ - .

RTL #AS.635.J i

                                                                                                                             )

NUMBER TITLE 1AD-010 Classify Emergency Plan Event l l-STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 2.C Classify the Event. 2.C Candidate classifies the event as a SITE AREA EMERGENCY. EVALUATOR NOTE: Tab 1.2.4 AND 1.3.4 COMMENTS: L STOP TIME: l l Page 2 of 2 Revision: 0

          - _ - . . - . - . . - ~ .  - - - . _ ~ .- -.-                . - . . . - - . - - - .       - ..- - ... - . - - - .

RTL.#AS.64OE DUQUESNE LIGHT COMPANY I Nuclear Power Division-Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE i PROGRAM TITLE: Licensed Operator Training ' SUBDIVISION: On-the-Job Training l OJT CHECKLIST /JPM TITLE: Fill Out An Operating Manual Change Notice (OMCN) { JPM'NO.: 1AD-011 COMPUTER CODE: N/A 1 1 Revision No. Date Revision No. Date l 1 l-PREPARED BY: DATE: i APPROVED FOR

j. IMPLEMENTATION: DATE:

l. Director, Operations Training, or Designee d

4 Revision 9

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual l1 LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: 1AD-011. Fill Out An Ooeratina Manual Chance Notice (OMCN) Revision Accroval No. Brief Description Revised by: Signature Date l l i Revision 9 l

_BEAIER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET I JPM Number: 1AD-011 Rev: 0 System #: 194 Faulted: O JPM

Title:

Fill Out An Operating Manual Change Notice (OMCN) K/A

Reference:

194 001 A1.01 3.3/3.4 Task ID #: 343 020 0302 l JPM Designation: O NO RO E SRO . l JPM Application: X NRC X Initial Exam Training Evaluation Method LOCATION TYPE ( Perform Plant Site Training i Simulate O Simulator Annual Requal. Exam

Classroom OJT O Initial Operator Exam

] Administered By: Other: i J BV-T NRC Other: ? k Eval'uation Results f Performer: Name: Employee No: ! Results SAT Time (minutes) I UNSAT* Allotted: 20 Actual: Time Critical: Yes X No I

• Comments ' (Required for UNSAT Evaluation) :

i 1 Evaluation Results O Check here if same as above

Observer 1

Name: Employee No:

Observer 2: Name Employee No:

l Observer 3: Name Employee No: i Observer 4: Name Employee No: i Time (minutes) Results l Question ID Allotted Actual SAT UNSAT* l Question #1 0

Employee No

. Question #2

} Employee No: }

• Comments (Required for UNSAT Evaluation):

}

, Evaluator (Print) : Organization: Evaluator Signature Date: i Revision 9

I RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE (' EVALUATOR DIRECTION SHEET s JPM NUMBER: 1AD-011 JPM TITLE: Fill Out An Operating Manual Change Notice (OMCN) RECOMMENDED STARTING. LOCATION: CONTROL ROOM I DIRECTIONS. You are to simulate (perform) the task fill out an OMCN. INIT. CONDITIONS: You have been directed to fill out an OMCN for a change to 10M-24.4.D, Placing the Second Steam Generator Feed Pump in Service, The vendor for the Main Feed Pumps [1FW-P-1A(1B) recommends that the Aux Oil pump be run in MANUAL for 5 minutes prior to starting a second main feed pump. The change is NOT being tracked as a commitment and does NOT affect NSA or UFSAR figures. TASK STAN.: OMCN properly filled out and ready for distribution (OMCN does'not need to be distributed). INIT. WE : Your supervisor directs you to add the following underlined words to step IV.A.3.b of 10M-24.4.D.

                         . . .is in MANUAL AND pump is running "fgr five minutes with a discharge. . .

REFERENCES:

1/20M-48.2.B Issue 4, Revision 8 10M-24.4.D Issue 4 Revision 0 TOOLS: NONE IUSDOUT: OMCN form and procedures

                                                                    - -9

! RTL #A5.635.J i NUMBER TITLE 1AD-011 Fill Out An Operating Manual Change Notice (OMCN) STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) START TIME:

1. Locates OMCN form and 1.1 Candidate locates OMCN instructions, form 1/2OM-48.2.B-2 1.1 Candidate locates procedure 10M-24.4.D step IV.3.b

                                                                           ]

1 1 EVALUATOR NOTE: Provide , candidate a copy of OMCN form and-procedure, j i COMMENTS: l l l Page 1 of 8 Revision: 0 l

RTL #A5.635.J NUMBER TITLE 1AD-011 Fill Out An Operating Manual Change Notice (OMCN) STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

2. Fills out administrative 2. Candidate performs the information. following:

Circles Unit 1 Enters ' ' 1. 2 4 . 4 ' ' Enters D Enters Issue 4 Revision 0 Enters ' ' h /A ' ' as Annunciator Window No. Enters X in NO Box for Intent Change. Enters X in NO box for UFSAR or NSA change. Enters X in NO box for Commitment. COMMENTS: Page 2 of 8 Revision: 0

RTL #AS.635.J l t I NUMBER TITLE 1AD-011 Fill _Out An Operating Manual Change Notice (OMCN) STEP STANCARD (Indicate "S" for Sat. or "U"

     -("C" denotes critical step)                   for Unsat.)

EVALUATOR NOTE: The procedure original is double. sided, the JPM copy is single sided, if needed cue the candidate.

   - .3 . C Record the OMCN purpose                    3.1.               Candidate records the and originator data.                                          attached page number as Page D1,D2 of 5.

3.2. Indicates that there are 3 pages total. 3.3.C Indicates the reason for change is Vendor Recommendation . 3.4.C Writes in his Employee number, Signs and Dates the Originator line. COMMENTS: i l l .i L I Page 3 of 8 Revision: 0

 -    . . .        .-       .-    _ .        ~.    .  -.            - - . -         _   . .
                                                                                            'l 1

l RTL #AS.535.J ' l

   ~J                                                                                         :

NUMBER TITLE I 1AD-011 Fill Out An Operating Manual Change Notice l (OMCN) i l l STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) l l i 1 EVALUATOR CUE: Inform j candidate that you are a i qualified Plant Staff Member, i review OMCN and then si'gn and date the initial approval line as applicable. Also inform ) him for JPM purposes that he is qualified to sign the SRO line. I 4.C Signs the Unit.1 and 2 SRO 4.1.C Candidate records his ) review line. signature,* employee number and date on the Unit'l SRO line. j 4.2. Candidate records

                                                           ' ' N/A' ' on the Unit 2           :

SRO line. COMMENTS: l l l I I l Page 4 of 8 Revision: 0

i RTL #AS.635.J l f l NUMBER TITLE 1AD-011 Fill Out An Operating Manu'al Change Notice (OMCN) l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

5. Leave blank the INTENT 5.1. Candidate bypasses the change data blocks. data blocks for:  ;

BV-OSC Number Unreviewed Safety Question

                                                 ' Approval Recommended OSC Comments General Manager Nuclear Operations approval.

COMMENTS: l i i ! Page 5 of 8 Revision: 0 l

                                 -    ~_   ..       ~.      .    .  -

RTL #AS.635.J i i i NUMBER TITLE 1AD-011 Fill Out An Operating Manual Change Notice I ( (OMCN) , L k STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) , 1 1 6.C Determine if the OMCN 6.1. Candidate refers to affects an Operator Aid or the OMCN log, ensures station log. that 10M-24.4.D is not an Operator Aid. 6.2.C Candidate places an-

                                                        X in the NO box for Operator' Aid.

EVALUATOR CUE: This change does NOT affect any Station Log. 6.3. Candidate places an

                                                        X in the NO box for Station Log.            I COMMENTS:

l l I Page 6 of 8 Revision: 0 l r .

RTL #AS.635.J k NUMBER TITLE 1 1AD-011 Fill Out An Operating Manual Change Notice  ! (OMCN)

                                                                                ]

I  ! STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR NOTE: The candidate may reference another controlled procedure copy for this verification.

7. Determine if the revision 7.1. Candidate refers to used for the OMCN is the Control Room or current. NSS copy of 10M-24.4.D.

7.2. Compares the OMCN copy to the controlled copy, ensures the revision is the same,  ! that no other OMCNs l exist, and places an

                                                   X in the review box.

COMMENTS: I Page 7 of 8 Revision: 0

     . _ . _ . . . . . _ _ _ . _       _ - . _      ,_ .  .   . _ _ . - _ . _            . _ . _ . . . _ . . . . . _ . . . ~ . _ . . _ . _ . . . . _ _ _ _ _ .      - .

l l RTL #A5.635.J I ! NUMBER TITLE-l - 1AD-011. Fill Out An Operating Manual Change. Notice

                                                  -(OMCN)                                                                                                                 I t

r STEP STANDARD (Indicate "S for Sat, or "U" ("C" denotes critical step) for Unsat.) 8.C Determine the next. 8.1. Candidate refers to , available OMCN number, the OMCN log for the-next avai3able number. 8.2.C Records the effective date, time and OMCN i number in the box  ; shown.

                                                                                                                                                                 ?

l l i f EVALUATOR CUE: It is not'  ! necessary to distribute the OMCN at ' this time. The JPM is now complete. t

1. .

COMMENTS: l STOP TIME: li Page 8 of 8 Revision: 0 l l l I , _ . - - - . - . . - -. - - . . - - - . .

l I I fr)ct { VO 1~ ( . OMCN INSTRUCTIONS (Refer to 1/2 OM-IS 2.B IV C.1 for complete details)

1. Circle the applicable Unit

2. Enter the alTected Chapter and Sechnn (Esample 16 3,1/2 SSA 4, TOP, etc.)

3. Enter the affected Procedure or Documen' munber (Example IRC Valve List, B 1. C, AAA, IOST 46.4, ITOP-944)7, ete )

4. Enter the procedure / document issue number and revision level

5. Enter the annunciator window number, N/A if not applicable.

6 Respond if change is Intent by placing an "X" in either the Yes or NO box.

7. Respond if a UFSAR tipure or a NSA change is involved by placing an "X" in either the Yes or No box.^ 5

8. Respond if tlus change is in response to or changes a Conumtment by placing an "X" in either the Yes or NO box. If Yes, identify the comnutment and the basis (refer to NPDAP 2.3)

9. Make the reouired changes as follows:

Both sides of a double-sided page must be reproduced as single pages for OMCN incorporation purposes. (Example if page 7 is beutg changed then page 8 is to be hicluded, and vice versa). Insert changes in the exact sequence that they are to be performed. Place a single line through all deleted information. DO NOT use correction tape or fluid. If cuttmg, pasting or taping is necessary, copy the atTected page to produce a c!can original. Veritly a page number is on each procedure page. The page number should be the same as the original procedure and any inserted pages shall be numbered using a letter sutlix (i.e. A,B,C, etc.).

• Record all of the attached atYected page numbers 10 Enter the total number of OMCN pages

11. Enter the reason for the change, hsting any reference documents.

12. Enter the Employee Ntunber Signature and Date.

13. Obtain Plant StatTMember review and Signature, Emplovee Number and Date.

14. Obtain applicable Unit SRO review and Signature, Employee Number and Date. N/A Unit SRO signature that is not'

         , applicable Both signatures are required for Dual Unit OMCNs IF THE OMCN IS AN INTENT CHANGE blocks 15 through 19 are required pn9tto assigmnent of the OMCN number.

For NON-INTENT changes blocks 15 through 19 may be completed later and a number may be assigned (proceed to step 21). Blocks 15 through 19 are required to be completed within 14 days atler the OMCN number is assigned. i 1

15. Enter the OSC Meeting Number or OSC Poll Number.

{

16. Respond if an Unreview ed Safety Question is involved by placmg an "X" m either the Yes or No box. (Refer to ~

NPDAP 8.10).

17. Respond if the OSC recosmnends Approval by placing an *X" in either the Yes or No box.

I8. Record any OSC conunents and enter the date of the OSC review. I9. Obtain GMNO review and Signature, Employee Number and Date. Assigning the OMCN Number

20. Using the Operator Aids Index located in front of the applicable OMCN log (Dual Unit OMCNs use both Unit's log) respond to does this OMCN change an Operator Aid by placing an *X" in either the Yes or No box.

21. Respond to does this OMCN change a Station Log by placing an *X" in eithei the Yes or No box.

22. Respond to is the revision used for tlus OMCN current bv:

• Comparmg the OMCN to the Control Room or NSS controlled copy of the atrected doctunent.

Ensuring that the revision used for the OMCN is the same as the controlled copy.

• All previously issued OMCNs are mcluded on any pages attached to the OMCN.
• Any disparity is corrected prior to assigning the OMCN number.
• Place an *X" in the Yes box.

23. Obtain the next OMCN ntunber froin the OMCN log, record the date, time and number.

24. Distribute the OMCN in accordance with 1/20M-48.2.B IV.C, place the Employee Number, printed name and

( signature of the person completed this section of the OMCN. Revision 8 i 50R TRMENG OdlN

i Recewd Tme

                              ' G Aba ATO R cop 7   DUQUESNE UGHT COMPANY 1/2OM-48.2.B-2 Circle A           le Unit Asssoc                                     Beaver Valley Power Station nit 1 (White) i                                   OPERATING MANUAL CHANGE                                                      Unit 2 (Blue)

NOTICE Unit 1/2 (Pink) Affected Chapters & Sections ,_ l . 2. % .i Procedure / Document - D issue 4 Rev. () _ Annunciator Window No. N/A Intent Change l :Yes IXl No Does this change affect an UFSAR Figure or change an NSA?A.s l ;Yes l ><l No (if Yes, then a Safety Evaluation (10CFR50.59) and a VCN !s required.) Is this change in response to or changes a Regulatory or DLC Commitment? i  ! Yes !)<l No (If Yes identify the Commitment document and basis) RECORD ALL OF THE ATTACHED PAGE NUMBERS: Pay b (0,o e K This is Page 1 of $ Pages REASON FOR CHANGE: y c. A_.9 c #,_% _ ao h w ORIGINATOR: x>oor. _ dg x x /xy 19 7 Employee Number SIGNATURE DATE initial Approval Signatures: ev.wh 6 c.h*

• o= bg') gg Plant Staff Member - Employee Number Date J C A rks xuv v ulu/n N/h N/A N/A Unit 1 SRO Employee No Date Unit 2 SRO Empiovee No. Date OSC Review: Unreviewed Safety Question [ Yes No

    /     Meeting Number         BV-OSC-                 _.

Approval Recommended

                                                                                                               .] Yes [ No N
    *[                                                                                                            OSC Comments / Date W

L:)p" [ Approved [ Disapproved General Manager, Nuclear Operations Employee Number Date NOTE: INTENT changes REQUlRE GMNO approval PRIOR to implementation. NON-tNTENT changes REQUJEE GMNO approvalwithin 14 days of Effective Date. Does this OMCN Change an Operator Aid? l] Yes l[ No The revision used for this OMCN is current. X Yes Does the OMCN Change a Station Log? [ Yes 3 No Prior to assignment of the OMCN, number. thrs form has been administratively reviewed for applicable form completeness in accordance with the instructions on the back. { xw/xx lo m xy Number: OMCN- 1 - O - m Effective Date Time This section completed by: Employee No Pnnted Name Signature "e*'"* 50R TRMNING QeiLY

l 1 l Beaver Valley Power Station Unit 1 10M-24.4.D Steam Generator Feedwater System issue 4 Revision 0 l, l Operating Procedures Page D 1 of 5 j Placing the Second Steam Generator Feed Pump in Service l

1. PURPOSE This procedure provides steps necessary to place a second main feed pump in service.

Equipment numbers for 1 A main feed pump are in parenthesis. II. PRECAUTIONS AND LIMITATIONS A. Second main feed pump should be ed between main feedwater flow of 14,000 - 15,000 GPM. B. Do not exceed one main feedw er pump operation above 16.000 GP ll1. INITIAL CONDITIO A. Feedwate flow is between 14,000 - 15,000 GPMp An. A7-39, "ST ENERATOR FEED M SCH FLOW HI START 2ND PU P",is O B. V-1FW 150B(A)],1B(A) Mz;n FW Pum isch Viv is Closed. ( -C). Two condensate pumps are in operation to p ve a low suction pressure trip. IV. INST UCTIONS A. Second Feed Pump Start

1. Verify [1SD-P-1 A OR 1 ], Heater rain 1 A O 1B Pump, is in operation, (BB-C).

2. Place the following pu an otor bearing temperatures on trend:

f1 FW-P-181 (f1 FW-P-1 All l T2386A 326A) FW PUMP 181(1 A1) MOTOR STATOR TEMP T2387A (T2327A) FW PUMP 182(1 A2) MOTOR STATOR TEMP , 2380 (T2320A) FW PUMP 181(1 A1) MOTOR INBD BRG TEMP ' T2381A (T2321 A) FW PUMP 181(1 A1) MOTOR OUTBD BRG TEMP l 7 T2382A (T2322A) FW PUMP 182(1 A2) MOTOR INBD BRG TEMP M T2383A (T2323A) FW PUMP 182(1 A2) MOTOR OUTBD BRG TEMP T T2385A (T2324A) FW PUMP 1B(1 A) OUTBD END BRG TEMP ' O T2384A (T2325A) FW PUMP 1B(1 A) INBD END BRG TEMP O 3. Perform the following at [1FW-P-18(1 A)], Main FW 1B(1 A) Pump, to be started, (Turb Bldg. 693'): 2"

a. Check that [1FW-P-1B(1 A)], Main FW 18(1 A) Pump, oil sump has normal oil level (21/2" in sight glass).

b. Ensure control switch for [1LO-P-3B(3A)], Aux Oil gmgo3 team S Gen Feed j >*" Pump, is in MANUAL AND pump is runningMI) a dis 3harge pressure 210 psig on [PI-LO-205B(A)],1B(1 A) SGFP Bearing Oil Supply, (Turb Bldg. 693').

Q c. Open [1FW-215(214)], Bypass for [MOV-1FW-150B(A)], three turns, to allow LJ pump casing warm up. (Turb Bldg. 693').

d. Verify pump does not rotate in reverse direction.

l

i i RTL #A5.635.J . BEAVER VALLEY' JOB PERFORMANCE MEASURE i CANDIDATE DIRECTION SHEET

l. -

THIS SHEET TO-BE'GIVEN TO CANDIDATE *

                ' Read:

1 1 Task: Fill Out An Operating Manual Change Notice (OMCN) - l l l INITIAL You have been directed to fill out an OMCN for a CONDITIONS: change to 10M-24.4.D, Placing the Second Steam - Generator Feed Pump in Service. The vendor for the Main Feed Pumps (1FW-P-1A(1B) recommends that , the Aux Oil pump be run in MANUAL for 5 minutes prior to starting a second main feed pump. :The i change is NOT being tracked as a commitment and  : does NOT affect NSA or UFSAR figures. , i' TASK STAN.: OMCN properly filled out and ready for distribution (OMCN does not need to be 1 distributed). INIT.1 CUE: lYoursupervisordirectsyoutoaddthefollowing  ! underlined words to step.IV.A.3.b of 10M-24.4.D.

                            . . .is in MANUAL AND pump is running " for - five minutes with a discharge...                             .,

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

              ' Point to any indicator or component you verify or check and             )

i announce your observations. l After comp 1'eting the task, reread the Task Standard.

After determining the Task Standard has been met, announce "I

have completed the JPM". Then hand back this sheet to the

, evaluator- .

l t [ Revision.9

                                                                               ,-wv-

j { OMCN INSTRUCTIOhS (Reter to 1/2 OM48.2.8.IV.C.I for complete details)

1. Circle the applicable Uma 2 Enter the alTected Chapter and Section (Esample 16.3,1/2 55A 4, TOP, etc.)

3. Enter the atiected Procedure or Dosument number (Example IRC Valve List B 1, C, AAA, IOST46 4, ITOP-94-07, etc.)

4. Enter the procedure /doemnent Issue number and revision level.

5 Enter the annunciator uindow number, N/A if not applicable

6. Respond if change is bitent by placing an "X" in either the Yes or NO box 1 Respond if a UFSAR tipure or a NSA change is involved by placing an "X" in either the Yes or No box.^3 8

Respond if this change is in response to or changes a Conumtment by placing an X" in either the Yes or NO box. If Yes, identify the comsrutment and the basis (refer to NPDAP 2.3).

9. Make the required changes as follows.

Both sides of a double sided page irmst be reproduced as single pages for OMCN incorporation purposes (Example if page 7 is being changed then page 8 is to be included, and vice versa). Insert changes in the exact sequence that they are to be performed. e Place a single itne through all deleted information. DO NOT use correction tape or fluid. If cuttmg, pasimg or tapuig is necessary, copy the atYected page to produce a clean origmal. Verify a page amnber is on each procedure page. The page number should be the same as the original procedure and any inserted pages shall be munbered using a letter sutlix (i.e. A,B,C, etc.)

                 . Record all of the attached atreeted page numbers.

10. Enter the total number of OMCN pages.

I1. Enter the reason for the change listmg any reference documents.

12. Enter the Employee Nwnber, Signature und Date.

13. Obtain Plant StatiMember review and Signature, Employee Number and Date.

14. Obtain applicable Umt SRO resiew and Signature, Employee Number and Date. N/A Unit SRO signature that is not' applicable. Both signatures are required tbr Dual Unit OMCNs.

IF ME OMCN IS AN INTENT CHANUE blocks 15 through 19 are required pnotto assignment of the OMCN number. For NON-INTENT clumges blocks 15 tivough 19 may be completed later and a number may be assigned (proceed to step

21) Blocks 15 through 19 are required to be completed within 14 days atler the OMCN nwnber is assigned.

15. Enter the OSC Meeting Ntunber or OSC Poll Ntunber.

16. Respond if an Unreviewed Saferv Question is involved by placing an *X" in either the Yes or No box. (Refer to NPDAP 810).

17. Respond if the OSC reconunends Approval by placing an *X* in either the Yes or No box. i 18 Record any OSC comments and emer the date of the OSC review. I

19. Obtain GMNO review and Signature, Employee Number and Date. I i

Assignmg the OMCN Number i 20 Usmg the Operator Aids Index located in front of the applicable OMCN log (Dual Unit OMCNs use both Unit's log) respond to does this OMCN change an Operator Aid by placing an "X" in either the Yes or No bot

21. Respond to does this OMCN change a Station Log by placing an "X" in either the Yes or No box.

22. Respond to is the revision used t'or this OMCN cwrent by:

Compartng the OMCN to the Control Room or NSS controlled copy of the atYected doewnent. Ensunng that the revision used for the OMCN is the same as the controlled copy.

• i All previous l3 ssued OMCNs are included on any pages attached to the OMCN.
• Any dispanty is corrected prior to assigning the OMCN number.
• Place an "X" m the Yes bos.

l 23. Obtain the next OMCN number from the OMCN log, record the date, time and number.

24. Distnbute the OMCN in accordance with 1/20M-48.2.B.IV.C, place the Employee Number, prmted name and signature of the person completed this section of the OMCN.

• Revision 8 50RIRAM #

1/20M-48.2.B 2 Record Type DUQUESNE UGHT COMPANY Circle Applicable Unit es 330c Beaver Valley Power Station Unit.1 (White) QP_ERATING MANUAL CHANGE unit 2 (Blue) NOTICE Unit 1/2 (Pink) Affected Chapters & Sections Procedure / Document 1 Issue Rev. ,_ Annunciator Window No. Intent Change i .Yes i I No Does this change affect an UFSAR Figure or change an NSA?A.s l Yes I i No (if Yes, then a Safety Evaluation (10CFR50.59) and a VCN is required.) is this change in response to or changes a Regulatory or DLC Commitment? i Yes l i No I (If Yes identify the Commitment document and basis)  ; RECORD ALL OF THE ATTACHED PAGE NUMBERS: This is Page 1 of Pages REASON FOR CHANGE: _ j ORIGINATOR: Employee Number SIGNATURE D AT E Initial Approval Signatures: Plant Staff Member Employee Number Date Unit 1 SRO Employee No Date Unit 2 SRO Employee No. Date l OSC Review: Unreviewed Safety Question ] Yes C No l Meeting Number BV-OSC- Approval Recommended ] Yes [ No l OSC Comments / Date General Manager, Nuclear Operations Employee Number Date NOTE: INTENT changes REQUEE GMNO approval PRIOR to implementation. NON-INTENT changes REQUEE GMNO approval within 14 days of Effective Date. Does this OMCN Change an Operator Aid? U Yes U No The revision used for this OMCN is current. Yes Does this OMCN Change a Station Log? [ Yes No Prior to assignment of the OMCN, number, this form has been administratively reviewed for appheable form completeness in accordance with the instructions on the back. ( Number: OMCN- - - Effective Date Time This section completed by: Employee No Pnnted Name Sianature 50R TRAINING ONLY

Beaver Valley Power Station Unit 1/2 1/20M-48.2.B Conduct of Operations k Operating Procedures issue 4 Revision 8 Page B 10 of 67 Control of Operating Procedures C. Procedure Channes Note: Refer to Figure 48.2.B-3 for Procedure Change Process guidance.

1. On the Spot Changes Note: OMCN changes to EOPs/AOPs cannot be made if the change would require revalidation of the EOP/AOP. Contact the General Manger, Nuclear Operations for a determination of validation requirements on any proposed EOP/AOP changes.

a. On the spot changes to operating procedures may be made providing:

1) The intent of the original procedure is not altered. An OMCN involving an intent change (refer to NPDAP 2.3) may be made provided that it receives the same level of review as the original procedure (i.e., OSC review and GMNO approval in accordance with Tech Spec 6.8) prior to implementation. If unclear on intent determination, then the Operations OSC member / alternate or an Operations Unit Non-Intent Reviewer shall be consulted to assist in the determination prior to its implementation.

2) The change is Reauired in less than 30 calendar days or the change will prevent a Plant Trip, Reduction of Power or other Productivity or Safety concern.

3) The change is approved by two members of the plant management staff, at least one of whom holds an SRO license on the affected BVPS unit. l Dual unit changes require an SRO from each unit. l

4) The change is documented, reviewed by the OSC and approved by the General Manager, Nuclear Operations within 14 days of implementation.

b. If an or the spot change is required, an OMCN shall be filled out and submitted by the originator in accordance with the guidelines below, refer to Figure 48.2.B-2. A separate OMCN is required for each chapter section, procedure or annunciator window.

1) Circle the applicable unit.

2) Enter the affected chapter, including unit number, and section.

(Example: 1.6.3, 2.7.4,1/2.17.4 A. TOP)

3) Enter the affected procedure or document number. (Example: 1RC Valve List, B.1, B, AA, ABC, OST-1.11.14, 2OST-36.1,1 TOP-94-07)

4) Enter the procedure / document issue number and revision level.

5) Enter the annunciator window number, N/A if not applicable.

6) Respond to intent change by placing an "X" in either the Yes or No Box.

l COR TRAINING ON13

Beaver Valley Power Station Unit 1/2 1/2OM-48.2.B Conduct of Operations issue 4 Revision 8 4- Operating Procedures Page B 11 of 67 Control of Operating Procedures

7) Respond to the question "Does this change affect an UFSAR Figure or change an NSA?" by placing an "X" in either the Yes or No box. If Yes, then prepare a safety evaluation in accordance with NPDAP 8.18, "10CFR50.59 Safety Evaluation", a VOND Deficiency Report (VDR) in accordance with instruction IV.D of this procedure and a UFSAR change request in accordance with NPDAP 7.3," Annual Final Safety Analysis Report Update."

8) Respond to the question "Is this change in response to or changes a Regulatory or DLC Commitment?" by placing an "X" in either the Yes or No box. If Yes, then identify the commitment document and basis in accordance with NPDAP 2.3, " Procedure Preparation and Control".

9) The originator shall make the required changes as follows:

a) The entire affected portion of the procedure shall be copied to single sided paper including pages that will be affer.ted due to I double sided pages (example, if page 7 is being changed, then page 8 is to be included and vice versa). b) Insert changes in the exact sequence that they are to be performed. c) The changed pages shall retain all of the current revision approved information including all previously approved and issued OMCNs. If  ; any of this information is changed, then it shell be lined out and the l new information entered on the page. DO NOT use correction tape j or fluid to delete information. d) If cutting, pasting or taping is necessary, copy the affected page to ,

    ;ll>                            produce a clean original,                                              I J

g e) Verify a page number is on each procedure page. The page g number should be the same as the original procedure and any inserted or expanded page shall be numbered using a letter suffix g (ie. A, B, C etc.) (Example Page 10A,108,15A etc.). [ f) Record all of the attached page numbers. l 2

10) Place the total number of OMCN pages in the "This is Page 1 of j Pages" space.

E 11) Reason For Change: Describe in detail the reason for the procedure

    >='s                      change, include any reference documents used.

M 12) The originator shall print their employee number, sign and date the Q OMCN Form. b8

c. The OMCN shall be reviewed by two (2) members of the plant management staff at least one holding an SRO License on the affected BVPS unit (s). If the OMCN affects a dual Unit Procedure, then a review is required from two (2)

SROs, one of which holds a Unit 1 SRO license and the other holding a Unit 2 SRO License. These reviews shall be documented by the individuals signing their name, filling in their employee number, and date in the " Initial Approval Signatures:" area of the OMCN form.

I Beaver Valley Power Station Unit 1/2 1/20M-48.2.B i Conduct of Operations l issue 4 Revision 8 I l 3 Operating Procedures Page B 12 of-67  ; l Control of Operating Procedures A

d. If the OMCN is an Intent change, then give/ mail the original OMCN to the Operations OSC Member / Alternate. DO NOT assign a number to this OMCN.

e. If the change is not an intent change, the Unit Operations Clerk if available, or any Operations Staff Member shall process the OMCN and assign a number as follows:

1) Using the Operator Aids Index located in front of the applicable Unit's OMCN log (Dual Unit OMCNs use both Unit's log) respond to the question "Does this OMCN Change an Operator Aid?" b) placing an "X" in either the Yes or the No box.

2) If the change is for Operating Manual Chapter 54 Station Logs, then place an "X" in the Yes box otherwise place an "X" in the No box.

3) Compare the OMCN to the Control Room or NSS Controlled copy of the affected procedure / document.

a) Ensure that the revision used for the OMCN is the same as the controlled copy. b) All previously issued OMCNs are included on any page(s) attached to the OMCN being processed. c) Any disparity identified shall be corrected prior to assigning the ( OMCN number. d) Place an "X" in the Yes box to indicate that the above steps have been completed.

4) Enter the change into the applicable Unit's OMCN Log (Figure 48.2.B-1).

If the OMCN affects a dual unit procedure, make the entry in the dual unit OMCN Log located in the Unit 2 OMCN Log Book.

                                                                                          ~

a) Obtain the next sequential OMCN number. Format for the OMCN number is OMCN, dash, Unit, dash, Year, dash, Sequential number. (Example: OMCN-1/2-94-23, OMCN-1-94-153). b) Enter the chapter and section, affected procedure, date effective and the initials of the person entering this information into the OMCN Log.

5) Place the effective date, time and OMCN number onto the OMCN form.

l COR TRAINING ONLY

l Beaver Valley Power Station Unit 1/2 1/2OM-48.2.B

   , Conduct of Operations                                                              issue 4 Revision 8 l

I I Operating Procedures Page B 13 of 67 Control of Operating Procedures {

6) If the OMCN has a sequential number assigned to it, this signifies that the OMCN is ready for implementation and distribution. as follows:

Note:

                   . There are two different transmittal forms, one to be used if the OMCN being             ;

distributed does not have a GMNO signature, the other form is to be used if i the OMCN being distributed does have a GMNO signature. l a A separate transmittal form shall be used for Unit 1. Unit 2 or Dual Unit OMCNs. I a) Obtain the appropriate " Operating Manual Change Notice (OMCN)  ; Transmittal form, Figure 48.2.B-20A or 48.2.B-208, from the front of l the OMCN Logbook and place the current date on the "Date Transmitted:" Line and identify all OMCN's in the OMCN's area. l b) If the OMCN has been identified as being an Operator Aid, then ' place the @ symbol and the number of copies next to the OMON l number on the transmittal form (ex. @i) if not an Operator Aid then l place a N/A on the Operator Aid " Received by/Date" line. c) Figure 48.2.B-25 Operator Aids Traveler SHALL be used to track l l 4 the placement and filing of each Oper'ator Aid Document in the l plant. The individual performing the distribution SHALL place the l OMCN number, Operator Aid Document ID and location on the form. A separate form is required for each OMCN Operator Aid Document and for each location if the documen' is in multiple locations. The individual that will be receivino the Operator Aid for filing shall be l written onto the form under the recipient column. k d) The individual performing the distribution shall determine if any of l the OMCNs are for Station Logs and place the "#" symbol next to g the OMCN number on the transmittal form otherwise place a "N/A" N on the Station Logs " Received by/Date" lines. l e) Obtain the next transmittal no. from the unit OPS transmittal log located in the Operations Office and enter it on the " Transmittal l 4 No." line. Format for transmittal number is unit, OPS, dash, sequential number (ex.10PS-17, 2 OPS-86,1/20PS-2, etc.). f) Provide the information requested on the transmittal log. (Refer to Figure 48.2.B-16 for a typical transmittal log). Note: Copies shall be made using the appropriate colored paper for the unit (white, blue or pink). g) The individual performing the distribution shall perform the following:

1. Place the OMCN number on each attached page of the OMCN.

Beaver Valley Power Station Unit 1/2 1/2OM-48.2.8

 , Conduct of Operations                                                           issue 4 Revision 8 Operating Procedures                                                               Page B 14 of 67 Control of Operating Procedures i

2. Make the required number of copies identified on the transmittal form.

3. Stamp the OMCN first page of each copy with the appropriate Unit's Controlled copy starup or with the Uncontrolled stamp.

4. Forward the original transmittal form and the operations office copy to the Unit Operations Clerk.

5. Forward the Operator Aids Copy to the appropriate Unit's ANSS for placement with tne Operator Aid.

6. Forward the copies as indicated on the transmittal.

7. Place the employee number printed name and signature of the person completing this section of the OMCN.

f. The controlled OMCN copies shall be filed as follows:

1) The copy of the OMCN cover page shall be place directly behind the document approval page and Table of Contents (if applicable).

2) Each attached revised page(s) of the OMCN shall be placed into the document and the old revised page(s) removed. The removed pages shall be destroyed and discarded.

g. The individual receiving the transmitted OMCN and performing the filing shall sign and date the transmittal form on the " received by" line and return the l transmittal form to the Unit Operations Clerk within 14 calendar days.

h. The Operations OSC member / designee shall process the OMCN as follows:

Note: The OMCN once assigned a sequential number is considered available for implementation and is required by T.S. 6.8.3.c to be reviewed by the OSC and approved by the GMNO within 14 days from the date of implementation.M A 1) The OMCN is prepared and presented to the OSC in accordance with NPDAP 8.10, "On-Site Safety Committee." Q 2) After review by the OSC the OMCN is presented to the General l Manager, Nuclear Operations for review and approval. j D i. The GMNO approved OMCN should be distributed by the Unit Operations i g Clerk, if available, or any Operations Staff Member as follows: l i

      .D ,                 1) If the OMCN was not previously assigned a number then, follow the            l instructions in Step C.1.e for the assigning an OMCN number and             {

distributing the OMCN. 1 I

    )==.

2) Enter the OSC meeting No. GMNO approval date and the initials of the i Qg person entering this information into the OMCN Log. Any other j Q additional information deemed pertinent or informative may be placed in IJ the remarks column of the OMCN Log.

l

l l I Beaver Valley Power Station Unit 1/2 1/20M-48.2.8 ( Conduct of Operations issue 4 Revision 8 Operating Procedures Page B 15 of 67 Control of Operating Procedures

3) If the OMCN number had been previously assigned, then distribute the OMCN as instructed in Step C.1.e.6.

j The Supervisor, Operations Procedures / designee shall coordinate with the Manager, Management Services / designee the incorporation, typing and l distribution of the GMNO approved OMCN into an Operating Manual revision  ; within 30 days of the GMNO approval date. Revisions that only incorporate OMCNs can be issued without General Manager, Nuclear Operations

                                                                                                        )

approval. The OMCN number (s) shall be placed in the OSC Meeting No. area j of the Approval Sheet and the Supervisor Operations Procedures shall sign ) in the " Approved by:' area of the Approval Sheet. If problems arise that will prevent incorporation of the approved OMCN in a type written, revised format within the 30 day timeframe, the original OMCN may be distributed, in accordance with NPDAP 6.1 by the SOP / designee, to all O.M. copyholders in i the hand-written form. The OMCN will then be incorporated as a revision as soon as practical. l I

k. If the OMCN has NOT been approved by the General Manager, Nuclear Operations within 14 days of the effective date, then the Operations OSC Member / designee shall be responsible for the following:

1) Removal of the OMCN from all Controlled Operating Manuals. 1

2) Preparing a problem report in accordance with NPDAP 5.2," Preparation of Problem Reports, Conduct of Critiques and Followup Action."

1. If the OMCN was for a ONE TIME ONLY CHANGE, then the Operations OSC i Member / designee is responsible for coordinating the removal of the OMCN from the Operating Manual controlled copies when the conditions / requirements for removal identified on the OMCN have been met.

An Operating Manual Change Notice (OMCN) Transmittal Form, Figure 48.2.B-20B shall be used to instruct the removal of the OMCN. y m. If conditions / requirements for removal were not stated on the original OMCN J or it is desirable to remove an OMCN under different T conditions / requirements, then a new OMCN shall be written or a procedure Q revision issued to remove the original OMCN. g n. The Supervisor, Operations Procedures shall be responsible for forwarding g the original General Manager, Nuclear Operations signed OMCNs to the

            ,              Records Vault and should provide a copy of any disapproved OMCNs to the 3                  originator with a reason for the disapproval.

! ==== l o. The Unit Operations Clerk shall maintain a file of Transmittal Forms, l Transmittal Tracking Forms (Figure 48.2.B-17) and verify recipient receipt 1 )=== acknowledgement. l l g p. The Unit Operations Clerk shall notify a recipient when transmittal receipt Q acknowledgement has not been obtained within the 14 day period by Ls completion of Figure 48.2.B-18 and entering the Notice Date on the Transmittal Tracking Form, Figure 48.2.B-17. This should be performed weekly until receipt acknowledgement is received.

                                                 ,             (        hk"                                    - :Q :.

34%pl.7.;w;lG

   .,f.__,;_,        -                   .        ;e.                   w . .vv.v.-      ,

t M@4 WBeaver Valley Power Station #- ' ' " " : Unit 1/2 - ~ 1/2OM2482.81  !

               ;; o . Conduct of Operations
     .]                                                                                                issue 4 Rdvision?8$ f%.            ]
                                                                                                                           ~
                    . Operating Procedures of 67'j Ni Page9.'" B':29 g(                      Control of Operating Procedures                         '       '

9 '+1 M.;j '

\.        i ... .

[ FIGURE' 48.2.B-1 (Example) DUQUESNE LIGHT COMPANY Beaver Valley Power Station

                                                                ', ,     OMCN LOG                 BVPS Unit No.

CHAPTER OSC GMNO ' ' AND AFFECTED ~ DATE MEETING APPROVAL OMCN- SECTION PROCEDURE EFF. INT. N O. DATE INT. REMARKS l

     ~

l>

4

       *E C

0 2- , l 6 -

      'J
     . k8                                                                                                                                     ,

Unit 1 - White / Unit 2 - Blue / Unit 1/2 - Pink

                                                                                                                              . -, - ..~ ,         l

• 4 .

     "                                                                                                                                       mt , ayg.,,

Beaver Valley Power Station Unit 1/2 I Conduct of Operations r" NSW1/20M48'.'2'.84 '

• 4 .: Issue ^f4fR6viil6nIBI Operating Procedures -

5.- "Pagh.8250io"672 Control of Operating Procedures ' IL ~itM"/W[.[k%( ,. \

                                                                                                                                          ...a.      .~

g FIGURE 48.2.B-2 (Example) Front

                                                                                                                                $b n re T,e.                           DUQUESNE LMNT COMPANY                            @ Circle Applicable Unit aamac                                Beewer vesey Po=w stemon Unit 1 (White)

OPERATING MANUAL CHANGE unct 2 (sive) NOTICE Unit 1/2 (Pink) 2 Affected Chapters & Sectons ,

                                                                             @ Procedure / Document :

4 lasuo Rev. 5 AnnunciatorWindow No.:

             @ Intent Change                                                                                 Yes             No
            @ Does this change affect an UFSAR Figura of change an NSA?                                    Yes C No ;

(If Yes, then a Safety Evaluaton (10CFR50.59) and a VCN is required.) . 6 la this change irt response to or changes a Regulatory or DLC Commitment? [ Yas [ No, _,_ _ , (if Yes identdy the Comtntment document and basis)

             @ RECORD ALL OF THE ATTACHED PAGE NUMBERS

• 10 This is Page 1 of Pages 11 REASON FOR CHANGE: --

12 ORIGINATOR: Ernp6oyee Number SIGNATURE DATE instal Approval Signatures: 13 Phrt Statt Norrter snee, su.e., Date 14 Und 1 SAO EqWapw Na Date Unit 2 SRO tmee r we. Date OSC Review: 16 Urreviewed Safetycueston O vee O No 15 Meeting Number BV-OSC- 17 ApprovalRecommended O Yes No 50 w OSC Comments / Date EE.e 19 / O Aparo ed O o)==anraved O General Managw. Nuc6 ear Operatorts seemy eure r Date NOTE: INTENT changes KOutAE GMNO approval PRIOR to implementation. @ NON-lNTENT changes REQUIRE GMNO approval wtthin 14 days of Effecthre Date. g m.mo

              @ ca em oucN chang.enopereier Aasi 21 0 een oMCN Ctene.e Sh Lag' V.e O a.

Ves No 22 ise r v r ie oocN i. e .,< 0 vos 2

                                                                                                                                             ""ee Prbr 6) assignment of ew OMCN nurnber, eds term has been Asturustratvely rewtowed for applicatae form completeness in accordance with the instructions on the back.

Number-. OMCN- - - H 23 Effectwo Date Tome 24 This section completed by; i G wa Primed Narne Sipature { l $8 \ l Figure 482.8-2(front) Rev.6 l (EXAMPLE)

i l 11

                                                                                                                                        ~d.2dllRIB%g                  a Beaver Valley Power Station                             ' . " > Unit 1/2               - '              A-                             2 Conduct of Operations                                                                   ~            '              N4.'A1/209I$51.'B                      i{        '

Issue [4R6fidi 8' y Operating Procedures Page18 617 _d (' 7 Control of Operatin'g Procedures W k"In M@p

                                                                                                                                               .s .;             . %. Q. j

_A. .l..h

         . . .                                                                                                                                     -'            , s., J    '
                                                                                                                                                .                          .J      j FIGURE 48.2.B 2 (Example) Back A                                        I OMCN INSTRUCnONS (Refer to I/2 OM-4g.2.B .IV.C.I for complete details)

I, 2. Cirtle the applicable Unit. Enter the stected Chapter and Section1 Example 1.6J,1/2.55A.4. TOP, etc.)

                                                                                                                                                                             )]    i

3. Enter the afected Procedure or D ocument'manber (Example IRC Valve List, B.1, C, AAA, IOST-46.4, ITOP-9447, etc.) ,

4. Enter the procedure / document issue number ano revision level 1

5. Enter the annunciator wsadow nwnber. N/A if not app 1hable. . m......

6. Respood if change is latent by placing an 'X* in either the Yes or NO box. *

7. Respond if a UFSAR figure or a NSA change is involved by placing an T in either the Yes or No box.A.5 , , ,

8. Respond if this change is in response to or changes a Commitment by placing an *X* in either the Yes or NO bor. IT Yes, identify the commitment and the basis (refer to NPDAP 23). .

                                                                                                                                                                           )e ,    ,

9. Make the required changes as follows: . V

• Both sides of a double-sided page unust be ,v t- ' as single pages for OMCN incorporation purposes.  ; Jh 1 (Example if page 7 is being changed then page g is to be included, and vice veru). _ 2.
• Insert changes in the exact sequence that they are to be performed
• Place a single line through all deleted information. DO NOT use ccricction tape or fluid.
• If cutting. pastmg or taping is r-ry, copy the afected page to produce a clean origir.al.
• Verify a page number is on each procedure page. The page number should be tlx sarne as the original proced.us and any inserted pages shall be nurnbered using a letter suffix (i.e. A.E.C, etc.).
• Record all of the attached afected page numbers

/                           10. Enter the total number of OMCN pages.

( ll. Enter the reason for the change, listing any refercoce documents,

12. Enter the Employee Number, Signature and Date.

13. Obtain Plant Staff Member review and Signature, Employee Number and Date.

14. Obtain applicable Unit SRO review and Signatwe, Employee Number and Date. N/A Unit SRO signature that is not applicable Both signatures are required for Dual Unit OMCNrm ,

I IF THE OMCN IS AN INTT.NT CHANGE blocks 15 through 19 are requiredI n2r to assipment of the OMCN inumber. I For NON-INTENT changes blocks 15 through 19 may be completedlater and a snanber may be assigned (proceed to step j 21). Blocks 15 through 19 are rupiired to be completed within 14 days after the OMCN number is assigned.

                                                                                                                                                                                   )

l

15. Enter the OSC Meeting Nanber or OSC PoU Number.

16. Respond if an Unreviewed Safety Question is involved by placizg an T in either the Yes or No box. (Refer to l NPDAP.8.10).

17. Respond if the OSC reconunends Approval by placing an T in either the Yes or No box.

18. Record any OSC comments and enter the date of tlw OSC eview.

l 19. Obtain OMNO review and Sipature Employee Number and Date. Assagmng the OMCN Number

20. Using the Operator Aids lodex locatec in fmnt of the applicable OMCN tcg (Dum! Unit OMCNs use both Unirs log) respond to does this OMCN change an Operator Aid by placing an T in either the Yes or No box.

21. Respond to does this OMCN change a Station 1.og by placing an T in either the Yes or No box.

22. Respond to is the revision used for this OMCN current by-

• Comparing the OMCN to the Control Room or NSS controlled copy of the asceted document.
• Ensuring that the revision used for the OMCN is the same as the controlled copy.
• All previously issued OMCNs are included on any pages attached to the OMCN.
• Any disparity is coTected prior to assigmng the OMCH number.
• Place an 'X* in the Yes box.

23. Obtain the oext OMCN oumber from the OMCN log. record the date, time and number.

24. Distribute the OMCN in 5-n: w with 1/20M-48.2.B.IV.C. place the Employee Number, printed name and signature of the person completed this section of the OMCN.

Figure 48.2.B.2(Back) Rev.6 (EXAMPLE) . ,

                                                                                                         ~

c0R TRAENG 0W ' Q,,3

                ~                                                                                                                                  .
                                                                                                                                                                                                                                                                                           . -       . . i.

J U O o o tn Ot Oo

3 (D 3 03

~

PROCEDURE CHANGE PROCESS eh o gan< . O3., l IS THE CHANGE BEQUIRED IN LESS THAN 30 DAYST , oo l YES NO ,(Dk 'O

• lI 'm' OkT 1r ~- a 03 O WOULD THE REVtSCN PREVENT A PLANT TRIP, 3 C .I Ifv!TIATE AN OPERATING MANUAL 2 REDUCTION OF POWER OR OTHER PRODUCTMTV O g O G

                                                                                                                            ' YES     OR SAFETY CONCERN 7                                                                                                              ,

g CHANGE NOTICE {OMCNI. NO O y 1P o ~ g O INITIATE AN OPERATING MANUAL OMCN REVtEWED BY UNIT (33 SRO l CHANGE REQUEST (OttCR). C l m I AND PtANT STAFF MEMBER. I CD

                                                                                                                                                                                                                                                                          &3 1F 3y OMOR REV*EWED BY SUPERVISOR l         IS THE CHANGE WTENTT                                                    l                                                 OPERATIONS PROCEDURES AND APPROVED.

INO 1YES YES g NO T y lI ~ OPER ATONS CLERg REVfEW REOtMRED BY SEND COPY TO REVISCN PREPARED OR OSC. AND APPROVED 8V GWNO. ORIOtNATOR WITH BY PROCEDURE ENGMEER. C OPERATONS STAFP MEveER " R F TE '  % C U ASSIGN OMCN NUWBER. ORIDINAL RETA!NED 1P m . DISTRIOUTE AND FLE OmCN. CHANOEIS AVAILABLE FOR USE. f SY OPERATIONS M PROCEDURES. a OPERATtONS CLERK ESCHANGE CO  % k C*ER AWS STAN MEmeER OR MW y N OPERATIOsts OSC MER/ ALTERNATE WmRN 14 DAYS MAvE OMCN ASSION OMCN NUMBER he REVIEWED BY OSC AND APPftOVED BY OSINO. IS CHANCl! REVISON 4w if sAFErv  % NO 3ppnoygo gy gggg, RELATEDT JL*gRATIONS CLERK YE3 OR

• OPERATIONS STAFF MEMBER II Off TRIBUTE AND FILE CNNO APPROVED OwCN. PROCEDURE ENGINEER g 08 TAMS OSC REVIEW.

OPERATIONS PROCEDURES SECTION II PREPARE REVISON WITHfN 3S DAYS. _ I REVISCN APPROVED BY SUPERVISOR,OPER ATIOht PROCEDURES (SOP). APPROVED BY CUNO. g mC g G l l ,, v REVISCN OfSTRIBUTED. l .$ g

                                              ,    P.--.,-, EO.                                                          ,

Q'dOQ"CR g ,oq_ SENT a.o m < 3: t0R TRAINING OriLY dn

           \                                                                                                                                          .

i )

                                                                                                                                                                                                                                                                                           =

• i

Record Type #A9.3308 ( DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit 1 10M-24.4.D Placing the Second Steam Generator Feed Pump in Service Issue 4 Revision 0 Prepared by Date Pages issued Effective Date R. J. Wolfe 10/22/92 D1 thru D5 AVG 0 71995 Reviewed by Date piged by gte g C.R.Kuhn 11/19/92 G. P. Smith 06/24/95 Unit 1 Manager Date OSC Meeting No. Dato [ggf p Jf py BV-OSC-28-95 07/13/95 1 nit 2 Manager Date y Date n'^ Apprho edr xh=Q % sc ( 20R TRAINING ONLY co m oula BVPS MT 1

l l l Beaver Valley Power Station Unit 1 10M-24.4.D l , Steam Generator Feedwater System issue 4 Revision 0 ((- Operating Procedures Placing the Second Steam Generator Page D 1 of 5 Feed Pump in Service ___.

l. PURPOSE This procedure provides steps necessary to place a second main feed pump in service.

Equipment numbers for 1 A main feed pump are in parenthesis.

11. PRECAUTIONS AND LIMITATIONS A. Second main feed pump should be started between main feedwater flow of 14.000 -

15,000 GPM. B. Do not exceed one main feedwater pump operation above 16.000 GPM. Ill. INITIAL CONDITIONS A. Feedwater flow is between 14.000 - 15,000 GPM OR Ann. A7-39. "STM GENERATOR FEED PUMP DISCH FLOW HI START 2ND PUMP", is ON. B. [MOV-1FW-150B(A)],1B(A) Main FW Pump Disch Viv, is Closed. (BB-C). C. Two condensate pumps are in operation to prevent - low suction pressure trip. IV. INSTRUCTIONS A. Second Feed Pump Start

1. Verify [1SD-P-1 A OR 1B], Heater Drain 1 A OR 1B Pump, is in operation, (BB-C).

2. Place the following pump and motor bearing temperatures on trend:

f1 FW-P-181 {f1 FW-P-1 All T2386A (T2326A) FW PUMP 181(1 A1) MOTOR STATOR TEMP T2387A (T2327A) FW PUMP 182(1 A2) MOTOR STATOR TEMP T2380A (T2320A) FW PUMP 181(1 A1) MOTOR INBD BRG TEMP T2381 A (T2321 A) FW PUMP 181(1 A1) MOTOR OUTBD BRG TEMP l P T2382A (T2322A) FW PUMP 182(1 A2) MOTOR INBD BRG TEMP M T2383A (T2323A) FW PUMP 182(1 A2) MOTOR OUTBD BRG TEMP T T2385A (T2324A) FW PUMP 1B(1 A) OUTBD END BRG TEMP O T2384A (T2325A) FW PUMP 1B(1 A) INBD END BRG TEMP O 3. Perform the following at [1FW-P-1B(1 A)], Main FW 1B(1 A) Pump, to be started, (Turb Bldg,693'): 2

a. Cneck that [1FW-P-1B(1 A)], Main FW 1B(1 A) Pump, "il sump has normal oil level (21/2" in sight glass).

b. Ensure control switch for [1LO-P-3B(3A)], Aux Oil Pump For Steam Gen Feed

g W Pump, is in MANUAL AND pump is running with a discharge pressure 210 l

psig on [PI-LO-205B(A)],1B(1 A) SGFP Bearir.g Oil Supply, (Turb Bldg,693'). O c. Open [1FW-215(214)], Bypass for [MOV-1CW-150B(A)], three turns, to allow W. pump casing warm up (Turb Bldg. 693').

d. Verify pump does'not rotate in reverse direction.

Beaver Valley Power Station Unit 1 10M-24.4.D Steam Generator Feedwater System issue 4 Revision 0 k Operating Procedures - Page D 2 of 5 Placing the Second Steam Generator . Feed Pump in Service (

e. Vent inboard AND outboard pump seals by opening all four seal package vent valves on lines to and from seal coolers, (Turb Bldg. 603').

l

1) Close vent valves when a solid stream of water is seen.

f. Check cooling water flow through:

1) [FE 1CC-101B(A)],1B(1 A) SGFP Coolers Combined CCT Return, (Turb Bldg, 693').

2) [FE-1CC-205B1(A1)],1B(1 A) SGFP Stuffing Box Jacket CCT Return. (Turb Bldg, 693').

3) [FE-1CC-205B2(A2)],1B(1 A) SGFP Stuffing Box Jacket CCT Return, (Turb Bldg, 693').

g. Check the following for < 120 F temperature:

1) [TI 1CC-205B1(A1)], Main Feedwater Pump 1B(A) Outboard Seal Wtr Inlet Temp to Seal Clr, (Turb Bldg,693').

2) [TI-1CC-205B2(A2)], Main Feedwater Pump 1B(A) Inboard Seal Wtr Inlet Temp to Seal Ctr, (lurb Bldg,693').

h. Check [TI-1LO-205B(A)], Main Feedwater PP 1B(A) Oil Cooler Outlet Temp,7 for temperature < 155"F, (Turb Bldg. 693'). (

Note: Normal seal leakage is none. Mechanical seals often leak slightly at startup and require varying amounts of "run in" time. A large leak would indicate a seal failure.

i. Check seal for excess leakage.

M 4. If main feed pump 4KV Busses 1C and 1D (1A and 1B) are being supplied by unit station service transformers, Perform a Hot bus transfer to the system station I service transformers in accordance with 10M-36.4.B. ~4KV Station Service System O Shutdown", Part A. D Note: If 4KV bus voltage cannot be raised to provide adequate bus potential, then g

• starting the main feed pump will cause a bus voltage drop, resulting in an i E

expected emergency diesel generator auto-start. Diesel auto-start for this j condition is not considered an ESF actuation. \ ! H 5. If 4KV Bus 1 A OR 1B (1C OR 1D) voltage is < 127 VAC, (VB-C), Perform the following: Q a. Adjust voltage on 4KV Bus 1 A AND 1B (1C AND 10) using Load Tap Le Changers, Bus 1 A (18) (1C) (1D) 4160V Lower Raise & Auto Sws, (VB-C), ur voltage indicates 2: 127 VAC.

b. Ensure Load Tap Changer, Bus 1 A AND 18 (1C AND 1D) 4160V Lower Raise

                                  & Auto SWs, are in MAN (Control Switch pushed in toward Vertical Board).

l Beaver Valley Power Station Unit 1 10M-24.4.D j Steam Generator Feedwater System Issue 4 Revision 0 ( Operating Procedures Page D 3 of 5 Placing the Second Steam Generator Feed Pump in Service

6. Place control switch for [1FW-P-1B(1 A)], Main FW 1B(1 A) Pump, in START AND Hold until both motor breakers are closed (BB-C).

a. Verify first motor breaker c!oses (red light and ammeter indication) (BB-C).

l b. 1.5 seconds later, Verify second motor breaker closes (red light and ammeter indication), (BB-C).

c. Verify [MOV-1FW-150B(A)],1B(1 A) Main FW Pump Disch Viv, starts to Open, (B B-C).

7. Release [1FW-P-1B(1 A)], Main FW 1B(1 A) Pump, control switch to spring return to NOR M AL, (B B-C).

8. Verify Main FW Pump Amps return to normal running current (approximately 400 amps), (BB-C).

I 9. Ensure [MOV-1FW-150B(A)],1B(1 A) Main FW Pump Disch Viv, Opens, (BB-C).

10. After pump starts, Perform a hot bus transfer to unit station service transformer in accordance with 10M-36.4.A, "4KV Station Service System Startup", Part B.

11. Place control switch for [1LO-P-3B(A)], Aux Oil Pump for Steam Gen Feed Pump, to AUTO, (Turb Bldg. 693').

l

a. Verify aux oil pump stops.

12. Close [1FW-215(214)], Bypass for [MOV-1FW-150B(A)], (Turb Bldg. 693').

13. Check the following at [1FW-P-1B(1 A)] Main FW 1B(1 A) Pump, (Turb Bldg. 693'):

a. Cooling water flow through:

1) [FE 1CC-101B(A)],1B(1 A) SGFP Coolers Combined CCT Return, (Turb Bldg. 693').

2) [FE-1CC-20581(A1)],1B(1 A) SGFP Stuffing Box Jacket CCT Return (Turb Bldg. 693').

3) [FE-1CC-20582(A2)],1B(1 A) SGFP Stuffing Box Jacket CCT Return, (Turb Bldg. 693').

b. [TI-1CC-205B1(A1)], Main Feedwater Pump 1B(A) Outboard Seal Wtr Inlet I Temp to Seal Cir, for < 120'F temperature, (Turb Bldg. 693').

c. [TI-1CC-205B2(A2)], Main Feedwater Pump 1B(A) Inboard Seal Wtr Inlet Temp to Seal Clr, for < 120*F temperature, (Turb Bldg,693').

d. [TI-1LO-205B(A)], Main Feedwater PP 18(A) Oil Cooler Outlet Temp, for temperature < 155'F, (Turb Bldg 693'),

e. [PI-LO-205B(A)],1B(1 A) SGFP Bearing Oil Supply for pressure 210 psig, (Turb Bldg,693').

t . l '0R TRAINING OnlLY

                                                                                                      ^-

> } l l l il

i i 7

Beaver Valley Power Station Unit 1 10M-24.4.D y Steam Generator Feedwater System Il issue 4 Revision 0 *. 1 Operating Procedures Page D 4 of 5 Placing the Second Steam Generator . { Feed Pump in Service l f ' l Note: Normal sean leakage is none. Mechanical seals often leak slightly at startup and j require varying amounts of "run in" time. A large leak would indicate a seal , f ailur e. l

f. Check seal for execss leakage.

14. Monitor pump and motors for excess vibration.

l l I (.

i I Beaver Valley Power Station Unit 1 10M-24.4.D i Steam Generator Feedwater System issue 4 Revision 0 ( Operating Procedures Placing the Second Steam Generator Page D 5 of 5 Feed Pump in Service V. REFERENCES A. TECHNICAL SPECIFICATIONS I NONE B. UPDATED FINAL SAFETY ANALYSIS REPORT

1. UFS AR-1 Section 10.3.5

2. UFSAR-1 Figure 10.3.5 C. COMMITMENTS j NONE D. ADMINISTRATIVE  !

NONE E. VENDOR INFORMATION I NONE F. DRAWINGS

1. 8700-RM-424-3, VO JD Feedwater System G. OPERATING MANUAL

1. 10M-24.1, Steam Generator Feedwater System - Description .

2. 10M-24.31FW Valve List

3. 10M-28.31CCT Valve List 1

4. 10M-36.4.A,4KV Service Station Shutdown

5. 10M-36.4.B. 4KV Service Station Startup i

6. 10M-54.3.L4, Station Logs (Turbine Plant)

H. PLANT MODIFICATION NONE I. OTHER

1. Computer input / Output List

2. OMCN 1-92-191; OMDR 1-88-0436, 0768,1-91-1047,1-92-0677,0850,1203,1-95-0330 l (Issue 4, Revision 0) l c0R TRAINING ONLY

INDEX l SIMULATOR DRILLS i DRILL 97-1 DRILL 97-2 l- DRILL 97-3 l DRILL 97-4 l DRILL 97-5

DRILL 97-6 i

JPMs l ICR-132, Perform RHR Pump Performance Test , ICR-133, Respond to RHR Pump Trip l ICR-134, Energize Stub Busses l l ICR-135, Start Containment Instrument Air Compressor ICR-136, Operate Feedwater Following SG Hi-Hi Level ICR-137, Respond to Radiation Monitor Alarm - 1 1CR-638, Depressurize RCS during SGTR (alternate path) ICR-639, Verify Shutdown Margin (alternate path) ICR-640, Respond to Radiation Monitor Alarm - 2 (alternate path)

  ,.         1CR-641, Verify SI Flow is Not Required (alternate path)    ,

ES-301 Scenario Events Form ES-301-3 i Simulation Facility: Scenario No.: 97-1 Beaver Valley Power Station - Unit 1 Examiners: Applicants: Initial Conditions: 1 12% power, BOL,1437 ppm boron, XE free, plant startup in progress. Turnover:

1. FW-P-3A, MDAFW pump is on clearance for motor replacement. Due to be returned next shift.

2. SA-C-1B, station air compressor on clearance for compressor failure. Not due to be retumed for 2 days.

3. Rod control is in manual, CBD is at 140 steps.

4. FW-P-4, the dedicated AFW pump, is on clearance for motor bearing replacement. Not due to be returned for 2 days. Fire Watch for AFW room is required, once per hour.

5. Main generator is warmed up and rolling at 1800 rpm, ready to be loaded.

6. SGWLC is in AUTO on main feed on bypass valves.

7. OM 52.4.A, Increasing power from 5%, is completed through step 69. Crew starts at Step 70 and continues unit startup.

8. FW-150A&B are failed open and CN 101 is in Manual and closed.

9. Boron is 1437 ppm.

Event Malf. Event Event No. No. Typc* Description 1 MALF I N36 IR instrument power fuse blows. Remove instrument from service NIS7B IAW AOP 1.2.lB. Take action IAW TS 3.3.1.1 act. 3. 2 R Raise power from 12% to sync. Main generator. 3 N Sync Main Generator. 4 MALF I l-PT-MS-464, main steam header press transmitter, fails high causing

MSSI1 steam dumps to fail open.

5 MALF C 1 steam dump valve fails / sticks open with a steamline break outside of MSS 8 containment. 6 MALF C Failure of CH-P 1B to start . SIS 5A 7 INII51 1 Failure of Auto Main Steamline Isolation. M Low steamline pressure SI. Scenario termmation criteria - SI terminated / BIT isolated and letdown is in service. E-0... ES-1.1

   *       (N)ormal,        (R)eactivity,         (I)nstmment,          (C)omponent,            (M)ajor Exammer:

ChiefExaminer: 1 Examiner Standards 23 of 26 Rev. 7, January 1993 i l BVPS Rev.0

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-1-1 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l r Initialize the simulator at IC-48 Reactor plant at 12% power, BOL, plant startup is in progress. IOM-52.4.A is complete through step 69. Insert FILE SIMIC Insert FILE PWRSETUP Places equipment out of service per the initial conditions setup page. L ACTIVATE PLINH51=T Inhibits MSLI IPC RODUP Assign shift positions: NSS Simulator Frozen until after shift ANSS turnover unless it needs to be on RO momentarily for an alignment change. , PO STA , Conduct shift turnover with oncoming Oncoming operators should complete the operators. required checklists and cany out a formal shift turnover. i

DUQUESNE LIGH1 COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-1-2 Rev. 0 l INSTRUCTIONAL GUIDELINES -l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l AQceen.......................... When the shift turnover is complete, pl::ce the simulator to RUN and Simulator running. Crew assumes control of the unit. commence the drill.

                   .a..............................                                                                                                                                                                                                                                                                                               l Three minutes after crew assumes the                                                                                                                                                              ANSS directs crew to continue plant shift:                                                                                                                                                                                           startup.

, EVENT #1 Intermediate Range NI, N36 power supply failure. Instrument power fuse blows on N-36 drawer NI36 fails low RO acknowledges alarms, reviews ACTIVATE MALF NIS7B,1 NI 36 trip and rod block alarms indications, diagnoses NI36 failure, and actuated. Loss of Detector / informs ANSS. aaaaaaaaaaaaaaaaaaaa******aaa*** compensating voltage - AN 04- 95,96. ANSS refers to AOP 1.2.lB, Intermediate l Range Channel Malfunction. Verifies Unit is in Mode I and goes to Step 4. Crew verifies power still greater than 10% and intermediate range trip is still blocked.

DUQUESNE LIGH1 COMPANY Nuclear Power Division Training Administrative Manual-DRILL 97-1-3 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l [ Crew places Caution Tag on Source - Range which states " Manually unblock Source Range on Shutdown" ANSS references Technical Specification 3.3.1.1, Action 3.C. , i Crew continues power operation EVENT #2  ; Raise power to 15 - 18% in preparation  ! for synching main generator to the grid  ; ANSS directs the crew to continue with  ! unit startup IAW OM 52 procedure "A" step 70, startup of the main generator. RO withdraws rods to raise reactor power > to 15 -18%  ! RO/PO maintain reactor power, Tavg, and  ! SGWL in preparation for unit  ; synchronization. j s When contacted as System Operator, Unit ready to synchronize. Crew informs system they are prepared to request the unit to be brought to full synchronize. power operations.

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual. , DRILL 97-1-4 Rev. 0 l- INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l EVENT #3 Generator prepared forloading. , t Sync main generator to the grid. Voltage regulator in OFF. PO checks voltage regulator in OFF.  ; Base adjuster is at minimum position. PO verifies electrical status. Voltage adjuster is at minimum position. PCB-331 and 341 in AFTER PO prepares for electrical output. TRIPPED position. Synch switch in Manual position. As Turbine Building Operator, when Transformer cooling initiated. PO directs local operator to initiate main request report transformer cooling is in transformer cooling. [ service and the 125v DC control power breakers are closed , Test switch in test. PO places Main Field Ground Test Switch Annunciator is off. to TEST. ACB-41 closed. PO applies excitation. Voltmeter indicates 107.5 volts. l Turbine at 1800 RPM. PMG circuit breaker closed. [ Test switch in test. PO places Main Field Ground Test Switch - Annunciator is off. to TEST. Synch switch in Bus 3/4 position. PO places synch switch in Bus 3/4  ! position. , i l

(N . DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-1-5 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Synch switch slow in fast direction. PO adjust turbine speed. Voltage 0.5 volts higher than mnning PO adjust generator voltage. voltage. Generator output breakers closed. PO parallels to grid. Generator picks up 5% load. PO monitors EHC. EHC in load control. NOTE: Aftet the unit has been synchronized, inform the crew that the required soak time has i been satisfied, and that they are to continue with the power increase to full load. Following generator sync and stable conditions established proceed with Event 4. Event # 4 & # 5 PT-MS-464 fails opening steam dumps which initiates a steam break outside of containment. aaaaaa****aa**aaa*******a******* CH-P-1B will not start. Crew identifies the excessive high steam Main Steamline Isolation will not Auto flow i Insert FILE DRL971B. Initiate.

 ********************************                           l-PT-MS-464, main steam header                                                                                                                                 i i

press transmitter, fails high causing steam dumps to fail open. One steam dump valve fails / sticks open.

n .. . DUQUESNE LIGH1 COMPANY Nuclear Power Division . Training Administrative Manual DRILL 97-1-6 Rev. 0 'l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l- OB.IECTIVE l EXPECTED STUDENT RESPONSE -l "A" SteamliW-eaks outside of PO identifies steam dump problem, , Containment. Uteam dumps open then informs ANSS. reclose, except for stuck open valve. ANSS directs PO to close steam dumps ~f via manual operation or defeat switches.  ; Stuck open valve will not close with PO places steam dumps to manual,. switch in Off. observes dumps remain open, places'  : interlock defeat switches to off, observes - i stuck open valve, and reports status to ANSS. Reactor trips on SI on Low Steamline Pressure. RO and PO commence immediate actions of E-0, ANSS references E-0 to verify - immediate actions. Reactor trip and bypass breakers open, RO verifies reactor trip and informs neutron flux decreasing. Rod bottom ANSS. lights lit. RO/PO sounds standby alarm, announces Unit I reactor trip. Throttle and governor valves closed, PO verifies turbine tripped. reheat stop and intercept valves closed. __-.m _ m __ m___ _ _ . . - _ _ _ _ _ _ _ _ _ _ __.____

DUQUESNE LIGHz COMPANY i Nuclear Power Division ' Training Administrative Manual

,     DRILL 97-1-7 Rev. 0 l         INSTRUCTIONAL GUIDELINES                                                                     l PLANT STATUS OR RESPONSE l                                                                                    OBJECTIVE   -l                 EXPECTED STUDENT RESPONSE                                                l             !

Reheat flow control valves and MOVs PO ensures reheat steam isolation by closed. depressing reheat controller reset push- l ' button and checks MOV 100A & B shut. r Main generator output breakers open. PO verifies generator trip. Exciter circuit breaker open. j AE and DF busses energized. PO verifies Emergency Busses energized. l Immediate operator actions complete. Any SI annunciator. RO checks if SI has actuated, reports SI  : SI actuation status lights. actuated. 1 SI actuated by Low Steam Line  ; Pressure. Both EDGs running. PO verifies EDGs running at normal RPM. - EVENT #6  : i CH-P-1B does not start and cannot be started.  ! All red marked SIS valve indicating RO/PO verify SI pumps m service.  ! lights lit. Reports CH-P-1B did not start and  ; CH-P-1 A. mnning. unsuccessfully attempts to start. FI-SI-943 indicates flow. f I

FW-P-3B mnning. PO verifies AFW status. i FW-P-2 running. MOV-FW-151 A  ;

through F open. j i P _ __. . _ - - _ . - . .- - - _ = - _ _ _ _ . . . _ . - - _ - _ _ _ - - - . - _ . _ - _ _ . _ - -'

DUQUESNE LIGFfl COMPANY ' Nuclear Power Division Training Administrative Manual DRILL 97-1-8 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l-RPRW pumps running. RO verifies River Water System in service. CCR Ht Ex RW pressure > 20 psig. All indicating lights with orange marks RO/PO verify CIA. lit. All indicating lights witi. green FWI RO/PO verify FWI. marks lit. t Event # 7 All indicating lights with yellow marks RO/PO recognizes the need for MSLI and lit following MANUAL actions. performs manual closure of YELLOW , MSLI does not occur automatically. MARKED valves.. CNMT spray not actuated, not 'O/PO verify CIB/ SPRAY not actuated, required. report status to ANSS CCR pumps running. RO checks CCR status. SR detector high voltage selector RO verifies SR detector high voltage I switches - normal. selector switches in normal. AFW flow > 325 gpm. PO verifies total AFW flow greater than 325 gpm. Station Instrument Air Header . PO verifies station instrument air header  ; Pressure > 100 psig. pressure > 100 psig. i i i r

n. -

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-1-9 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE ' l OBJECTIVE l EXPECTED STUDENT RESPONSE - l Tavg trending to 547 F. RO checks RCS Tavg stable at or trending to 547 F. ANSS directs personnel to perform emergency safety function checklist when atailable. PORVs closed. RO checks PZR PORVs, safeties and Safeties closed. spray valves. Spray valves at zero demand.

                                                                                                              . Power available to PORV MOVs.

PORV MOVs open with associated PORVsin Auto. RCPs running. _ RO checks ifRCPs should be stopped. RCS/SG D/P > 150 psid. CCR flows to RCPs normal. MSLI actuated.- PO checks if any SGs are faulted. No SGs are faulted. 1 All SG levels - none rising in an PO checks if SG tubes are intact. uncontrolled manner. Secondary radiation monitors - consistent with pre-event levels. RCS intact, CNMT radiation, pressure RO checks ifRCS is intact. and sump levels consistent with pre-event.

               ,%YTp*

DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual . DRILL 97-1-10 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l . EXPECI'ED STUDENT RESPONSE l RCS subcooling > 23 F. Crew checks if SI flow should be Secondary heat sink sat, AFW flow terminated. controlled as necessary to maintain SG levels. RCS pressure stable or rising. PZR level > 5%. i ANSS transitions to ES-1.1 upon PZR level increasing greater than 5%. CNMT vent and drains systems RO verifies CNMT vent and drain systems isolated. isolated. DG-P-1 A & 1B - PTL DA-P-4A & 4B - stopped CV-P-1 A & IB - PTL TV-DG-109A & B - shut SI reset. (both trains) . RO resets SI. CIA reset. (both trains) RO resets CIA and CIB. CIB reset. (both trains) One HHSI Pump is running. ANSS directs RO to ensure one HHSI

                                                                                                                             .                                                                                                                                                                                                                              pump is running..

4KV stub busses energized. PO to verifies stub busses energized. 480V stub busses energized. ___ _____ ~___.. ._ ________ ____._______ __m _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ . . _ _ _

n - P DUQUESNE LIGH'1 COMPANY l Nuclear Power Division Training Administrative Manual' y l DRILL 97-1-11 Rev. O .l c INSTRUCTIONAL GUIDELINES ~ l PLANT STATUS OR RESPONSE l ' OBJECTIVE . l EXPEC1ED STUDENT RESPONSE l Auto cold leg recirc change over reset. RO resets auto cold leg recirc change over  ; (both trains). Containment air compressors one PO to verifies CNMTinstrument air running, one in standby. available.

• Containment air receiver greater than 85 psig, A6-110 act lit.

RCS pressure is stable or rising. RO checks RCS pressure. l 1 MOV-CH-289 and 310 open. RO establishes normal charging flow. FCV-CH-122 in throttled to maintain i pressurizer level.  ; i b MOV-SI-867A through D shut. RO isolates the BIT. i 4 Pressurizer level between Sand 50%. RO attempts to maintain Pressurizer level (Could be higher due to SI flow.) between Sand 50%. l LHSI pumps stopped and in auto. RO stops LHSI pumps and places then in auto.  ! I CNMT Spray Pumps not running. RO checksif CNMT spray pumps should be stopped i RCS subcooling - satisfactory. RO verifies SI flow not required. ' PZR level greater than 5%. t Pressurizer level > 18%. RO verifies Pressurizer level > 18%. _ . _ . . _ . . . _ . _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ . _ . . _ . - - . . _ . . . - , ~ , ~ - . . . . . . . . ~ = , - _ _ _ _ . . . _ . - . . . . _ . . . _ _ _

                      'Y %e                                                                                                                                                                                                                     "

m DUQUESNE LIGh, COMPANY Nuclear Power Division , Training A.dministrative Manual

    . DRILL 97-1-12 Rev. 0

l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l t

                                                                                                                                                                                                                                                                                      ?

Normal charging flow established. RO establishes letdown. FI-CH-122 flow indicated MOV-CH-289 and 310 open PCV-CH-145 in manual and 75% OPen. TV-CH-204 open. . LCV-CH-460 A and B open. TV-CH-200A, B/C open.  ; PCV-CH-145 set to 300 psig and in -> auto. i Terminate drill afterletdown is in . service. Collect and review logs after allowing Operator logs should be clear, accurate operators to complete them. and concise. , t Erase any vond markings associated j with this drill.

                                                                                                                                                                                                                                                                                     .k i

I t

                                                                                                                                                                                                                                                                                      ?

1 ES-301 Scenario Events Form ES-301-3 . i l Simultaion Facility: Scenario No.: 97-2 Beaver Valley Power Station Unit 1 l l Examiners: Applicants: I 1 l Initial Conditions: I l 75% power. MOL,722 ppm Boron. Power reduction in progress due to high vibes on FW-P-1B, Main feedwater  ; pump. Xe concentration is building in @ 250 pcm/hr. Le shutdown from 100% was perfonned at 1%/ min. and

   ~25 minutes to perform.                                                                                              l j

l Tumover: l

1. FW-P-3 A, MDAFW pump is on clearance for motor replacement. Due to be retumed next shift.

1

2. SA-C-1B, station air compressor on clearance for compressor failure. Not due to be returned for 2 days.  !

3. Rod control is in automatic, CBD is at 175 steps.

4. FW-P-4, the dedicated AFW pump, is on clearance for motor bearing replacement. Not due to be retumed l

for 2 days. Fire Watch required in AFW room once an hour.  ;

5. Management directs power to be reduced at 1%/ min and remove FW-P-1B from service as soon as possible, '

using 1OM-52.B Load Follow. Event Malf. Event Event No. No. Type

• Description 1 R Perform power reduction of greater than 5% IAW AOP 51.1, Emergency Shutdown.

2 N Remove FW-P-1B, main feed pump, from service at approximately 60% power. 3 MALF 1 PT-RC-444, RCS pressure transmitter, fails high causing PCV-RC-PRS 8D 455C, PZR PORV, to open. Crews responds to failure IAW IFM 6.4.IF. Possible entry into TS 3.2.5 - DNB Parameters due to low RCS pressure. 4 MALF C Upon closure, PCV-RC-455C, PZR PORV, dew is a leak. Block PRS 3A valw is to be manually closed within I hour I S 3.4.11 act. a.

                 =5%                                                                                                   I 5        MALF               C       2"dmain feed pump trip /Rx trip on low SGWL.                               I FWM1A,             C       FW-P-2, terry turbine AFP, fails to start due to mechanical failure of the FWM11C                     trip valve.

6 MALF C Re DF 4KV Emergency bus trips when the turbine generator output  ! EPS4F breakers open. ' EPSI1B ne #2 emergency DO starts and loads 60 seconds after the DF bus is M lost, then trips and won't restan. His causes a loss of the DF 4KV emergency bus and FW-P-3B, motor driven AFW pump, resulting in a Loss of Heat Sink condition. Scenario termination criteria - Fced flow established from the condensate system. E-0... ES-0.1... FR-H. l. l (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner: ChiefExaminer: Examiner Standards 23 of 26 Rev. 7l January 1993 HVPS Rev0

DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual Drill 97-2-1 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Initialize the simulator atIC-60 Reactor plant at 75% power, at MOL with Xe concentration buildingin. Insert FILE SIMIC On IPCInsert: Rodup and SIM Insert FILE PWRSETUP Places equipment out of service per the initial conditions setup page. Assign shift positions: , SRO Simulator Frozen until after shift ANSS tumover unless it needs to be on RO momentarily for an alignment change. PO STA Conduct shift tumover with oncoming Oncoming operators should complete the oper:lors. required checklists and carry out a formal ' shift tumover. AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA When the shift turnover is complete, place the simulator to RUN and Simulator mnning. Crew assumes control of the unit. commence the drill. AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA Three minutes after crew assumes the shift:

                                                                                                                           =

kM-  % DUQUESNE LIGH1 COMPANY Nuclear Power Division ' Training Administrative Manual Drill 97-2-2 INSTRUCTIONAL GUIDELINES l PLANT STATUS GR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l EVENT #1 Perform power reduction ofgreater than 5% IAW AOP 51.1, Emergency Shutdown. Three minutes after crew assumes the witch,as the NSS Tell crew to ammence an Emergency Shutdown IAW AOP 1.51.1 to mmove FW-P-1B from (peration, as vibrations are incmasing at .5 mils /hr from 6 mils. Power reduction commences. ANSS references AOP 1.51.1 Emergency Shutdown, and orders an emergency plant shutdown. , 4 Operators sound standby alarm and announce trouble on the page-party system. SRO evaluate if EPP should be initiated. EPP should not be initiated. ANSS evaluates if EPP should be initiated. PORVs in auto with block valves open RO ensures one PORV in auto with its associated block valve open. Turbine load reducing. PO sets desired load on Load setter. Sets l rate to 5% / min and presses GO. i r

DUQUESNE LIGH'i COMPANY Nuclear Power Division Training Administrative Manual Drill 97-2-3 l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Tavg within 5 F ofTref. RO maintains Tavg within +/-5 F ofTref. Delta flux in target band. RO borates as necessary to maintain delta flux with'n the target band Rods above rod insertion limits. RO maintains rods above the Rod Insertion Limits. System Operator notified. ANSS notifies System Operator ofload reduction. EVENT # 2  ; Remove FW-P-1B, main feed pump, 1 from service at approximately 60% power. ' Usa LOA FWM 29 =T,when requested A7-31 is received. When FW flow is less than 14,000 gpm, ts st rt the Aux Oil Pump LO-P-3B. Crew removes FW-P-1B from service IAW with OM 1.24.4.F. Crew stabilizes turbine load and reactor power. EVENT #3 6 PT-RC-444 failure. . f Aft:r plant stabilizes continue with PT-RC-444 failure.

DUQUESNE LIGFn COMPANY Nuclear Power Division  : Training Administrative Manual . Drill 97-2-4

 -l     INSTRUCTIONAL GUIDELINES             l PLANT STATUS OR RESPONSE l                        UBJECTIVE'     -l    EXPECTED STUDENT RESPONSE                         l FILE LOT 2A.                                  PT-RC-444 fails high. M-10 High                                  RO notes alarm, informs SRO that PT-Press Dev alarm. PZR heaters turn                                RC-444 failed high.                                    3
    ...............................               ofr, . Spray valves open. A4-5 PCV-FILE :                                        RC-455C opens. A4-11 RCS pressure

( MALFS PRS 8D decreases rapidly. A4-12 RCS Low PRS 3A =5% Press Dev alarm. A4-54 OT delta T runback and rod stops possible. ' RCS pressure dropping. Crew refers to ARP A4-11, and Instrument Failure Procedure 1.6.4.IF ' Attachment 2. , t Event # 4 RCS pressure dropping. RO takes manual control ofmaster pressure controller and ensures PORVs  ; PCV-RC-455C leaks. shut, spray valves closed, heaters j energized. Informs ANSS of PORV 455C Acoustic panel alarm reset: failure to close. LOA PRS 9 =T. RCS pressure begins to increase. RO closes MOV-RC-535. Shut Down Panelindications SAT SRO refers to Tech Specs 3.4.11,3.3.5 j If requested to de-energize block valve at E-5 use Overrides: and 3.3.8. P07061 A=2 RED Light P07061B=2 Green Light i t f

DUQUESNE LIGIri COMPANY Nuclear Power Division Training Administrative Manual Drill 97-2-5 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPEC1ED STUDENT RESPONSE l Continue with scenario and initiate the SRO directs I&C to investigate and repair next event when: pressure channel..

1. RCS pressure returned to normal.

2. Tech Spec has been identified and crew shows intent to comply.

Event # 5 and # 6 Loss of Feedwater- Reactor Trip and failure ofTurbine Driven AFP to start. ENTER FILE LOT 2B

                     ******************************** Loss of"A" MFP. FW-P-2 does not                                                                                                                                                                         Crew recognizes trip of MFP FW-P-Malf:                                      start. Plant could trip on LoLo S/G                                                                                                                                                            1 A.and Manually trips reactor prior to Lo FWM1A                          Level. FW-P-1B will not restart.                                                                                                                                                               Lo reactor trip.

FWM IB  : FWM i1C BE READY TO ENTER LOT 2C Reactor trip and bypass breakers open, RO manually trips reactor and verifies WHEN GENERATOR OUTPUT neutron flux decreasing. Rod bottom reactor tripped. t BREAKERS TRIP!!! lights lit. Rod position indication at O. Crew Performs the immediate operator ANSS refers to E-0 to verify immediate actions ofE-0. actions, operators commence E-0 immediate actions. l

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual Drill 97-2-6 , l INSTRUCTIONALGUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l , RO sounds standby alarm and announces Unit I reactor trip. Throttle Governor, Reheat Stop, and PO verifies turbine tripped. Interceptor Valves closed. r Reheat Block Valves closed. PO ensures reheat steam isolation. Event # 6 s Loss of Bus DF and 3B AFP .

 .....o..........................

When generator trips: Main generator output breakers open. PO verifies generator trip. Exciter circuit breaker open. Ent:r File: LOT 2C eeeeee.......................... MALFS EPS4F EPSI1B with 60 see TD AE bus energized, DF bus is PO verifies DF buss energized following deenergized, No. 2 EDG starts , loads diesel sequencing . Recognizes diesel trip , and fails 60 sec after start. attempts to manually start the No. 2 EDG , and informs ANSS that it will not start. t L

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual Drill 97-2-7 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Crew dispatches an operator to investigate problem with the No. 2 EDG. No SI annunciator. RO checks if SI has actuated. SI actuation status light not lit. l SIis not required. Crew transitions to ES-0.1. ANSS transitions to ES-0.1 and informs > the control room. STA monitors status trees. Approximately 3 minutes after request, Loss of all feed to steam generators. PO informs ANSS ofFW-P-3B motor Report to control room that the No. 2 TDAFWP [FW-P-2] and MDAFWP driven Aux. feed pump loss. EDG local panelis deenergized and [FW-P-3B] trip. All steam generator request Electrical Maintenance aid in levels less than 5% narrow range. Crew continues with actions of ES-0.1 the investigation. until red path on FR-H.1 is identified. Crew continues with actions of ES-0.1 until red path on FR-H.1 is identified. STA or operators determine that FR-H.1 is applicable. i Crew transitions to FR-H.l. ANSS transitions to FR-H.1 when notified of the red path and informs crew.

w. DUQUESNE LIGH'1 COMPANY Nucicar Power Division Training Administrative Manual

Drill 97-2-8 i-l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l RCS pressure > SG pressure. PO checks ifsecondary heat sink is RCS hot leg temp > 325 F. required.

i WR level in all SGs > 10%. ANSS checks if RCS feed and bleed not PZR pressure < 2300 psig. required. PDWST level > 27.5 feet. PO checks PDWST level greater than 27.5 feet. Terry turbine tripped. Crew tries to establish AFW flow to at FW-P-3 A on clearance. least one SG FW-P-3B DF de-energized AFW pump suction pressure ~ 10psig Dedicated AFP pump not available.

When sequested to check the TDAFW, FW-P-2 trip throttle valve trip collar Crew dispatches an operator to investigate i as the PAB Operator, report that the broken. AFW pumps.

TDAFWP trip collaris broken and will i not reset. NOTE: Stopping RCPs will result in SI not in service. Crew minimizes RCS heat input. RCS pressure increase. This may RCPs stopped. prompt crew to initiate bleed and feed. Pressurizer heaters in Pull-to-Lock. While this action is not expected, it is t conservative. Blowdown valves closed. Crew checks blowdown status. Sample valves closed.

DUQUESNE I?iHi COMPANY Nuclear Power Division Training ' Administrative Manual .!

     - Drill 97-2-9 l     INSTRUCTIONAL GUIDELINES                                                           l PLANT STATUS OR RESPONSE l                                                                                      OBJECTIVE          l      EXPECTED STUDENT RESPONSE                                                                      l  l l*

CN-P-1 A,B running. PO checks condensate system in service. Hotwell level > 27 in. Valves with green FWI marks closed. [ FW-P-1 A and FW-P-1B cannot be Crew determines that no MFW pump is  !

                                                                                                                                                                                                                                                                                                                                          ?

i started. available for SG feed. RCS pressure approximately 1950 RO depressurizes RCS to 1950 psig using psig. aux spray flow or a PORV ifnecessary,  ; Low pressure SI blocked. and blocks low pressure SIS. 4 Steamline SI blocked. Selected steam generator pressure PO begins depressurizing a steam decreasing to less than 490 psig. generator to less than 490 psig. i ANSS has operators line up to feed from the condensate system in accordance with  ! Attachment 2-J. t Crew establishes feedwater flow into at AFW pumps in PTL. Operators perform step 1 of Attachment least one steam generator. MFW pumps in PTL. 2-J. MFRVs shut. BFRVs shut. i MFRV isolation valves shut. l BFRV isolation valves open.

f

                                                                                                                                                                                                                                                                                                                                          +

DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual , Drill 97-2-10 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECIED STUDENT RESPONSE l l osooeseeeeeeeeeeeeeeeeeeeeeeeees When directed open main feed pump discharge valve by: MOV-FW-150A or 150B. Crew directs plant operator to open MFP , SET RFWH150B = 1 discharge isolation valve. j Report valve open.

      .....eeeeeeeeeeeeeeeeeeeeeeeeees                                                                                                                                                  ,

If desired to deenergize FWP discharge valve open MOV-FW-150A, wait until , operator states valve full open then insert FILE LOT 2D. File c:ntains OVRD P09066B =2,P09066A=2 turns red and grn lights off, LOA FWhGl=1 l Ifrequested to de-energize open 150B, CN-P-1 A or B nmning. Operator verifies at least one condensate  ; insert File LOT 2E. pump n.aning. Fila contains P09%7b=2, p09067A=2, and LOA 7 FWM 32=1. FCV-FW-479/489/499 open to feed Operators open feedwater bypass valve to selected S/G. feed selected S/G. r Feedwater flow > 325 gpm to selected Crew establishes feedwater flow > 325 S/G. gpm to selected S/G. L

a t h

                                                                   . DUQUESNE LIGbi COMPANY Nuclear Power Division -

Training Administrative Manual Drill 97-2-11 l PLANT STATUS OR RESPONSE- l OBJECTIVE l EXPECitD STUDENT RESPONSE. l' l INSTRUCTIONAL GUIDELINES Terminate' drill after feedwater flow established. Operator logs should be clear, accurate Collect and review logs after allowing and concise. operators to complete them. -. Erase any vond markings associated ' with this drill. s

                                                                                        .m. --  . .- ..__-

L g ES-301 Scenario Events Form ES-301-3 I

• Simulation Facility:

Scenario No.: 97 3 Beaver Valley Power Station - Unit 1 Examinersi . Applicants: Initial Conditions: 100% power, BOL,938 ppm boron, equilibrium conditions, i Turnover: i

1. FW-P-3A, MDAFW pump is on clearance for motor replacement,8 hours ago. Due to be retumed next shifL-TS 3.7.1.2.

2. SA-C lD, station air compressor on clearance for compressor failure. Not due to be retumed for 2 days.

3. Rod control is in automatic, Control Bank D is at 227 steps.

4. FW-P-4, the dedicated AFW pump, is on clearance for motor bearing replacement. Not due to be retumed for 2 days. Fire Watch for AFW room is required, once per hour.

1 Maintain 100% power.' Event Malf. Event Event No. No. Type

• Description MALF . I 1 N44 power range detector fails high. Auto Rod control drives rods in.

NIS3D Crew removes channel from service IAW AOP 1.2.1C. l l 2 MALF C During rod insertion, rod F-6 (control bank rod) drops due to blown fuse j CRF4 on stationary gripper. No Rx trip occurs. 3 N/R Power reduction initiated in response to dropped rod IAW AOP 1.1.5.- 4 MALF C After N44 is removed from service, Loss of 120 vac vital bus III causing EPS6C a Rx trip on high PR flux. 5- MALF M Rx trip causes a 350 gpm SGTR on IB S/O. Scenario temunation criteria ( RC53B - SI termmated and second charging pump stopped in E 3. E-0... E 3. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor l l Examiner: ChiefExaminer; l. i ll I i 1-Examiner Standards . 23 of 26 Rev. 7, January 1993 rw w as

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-3-1 Rev. 0 -l l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l' i Initialize the simulator at IC 50 Reactor plant at 100% power, , ENSURE RODS IN AUTO equilibrium conditions, BOL. Insert FILE SIMIC Insert FILE PWRSETUP Places equipment out of service per the IPC RODUP initial conditions setup page. - Assign shift positions: NSS Simulator Frozen until after shift ANSS turnover unless it needs to be on , RO momentarily for an alignment change. , PO STA Conduct shin turnover with oncoming Oncoming operators should complete the operators. required checklists and carry out a formal t shift turnover.  ; l AAAGAAAAAAAAAAAAAAAAAAAAAAAAAAAA I When the shift turnoveris complete, place the simulator to RUN and Simulator running. Crew assumes control of the unit. commence the drill. AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA Three minutes after crew assumes the shift: i _---__----__--------.-,-__--._---_---__.---_-__---___-----a-a-__--------------_.-_---:

r DUQUESNE LIGH1 COMPANY Nuclear Power Division Training Adminis.trative Manual DRILL 97-3-2 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l , EVENT # 1& # 2 Power Range NI N-44 upper detector fails HIGH. Rods drive in and rod F-6 drops.

                 ********************************                                                                PR Channel N44 upper detector fails                                                                                                                                                                                                '

high. Five minutes after turnover, insert the N44 powerindicationsjump to 200 following: AFD out of target band alarm. NIS PR Upper Section Flux Deviation FILE DRL973A Or Auto Defeat alarm. NIS PR Comparator Deviation alarm. aaaaaaaaaaa**aaaa**aa**aa******a NIS PR Flux Rate High alarm. Malfs A4-52,-67,-68,-69. NIS3D,200,0 ROD F-6 rod bottom light is lit and . CRF4,2,F6,3 IRPI is zero. Pzr level and pressure, RCS Tavg drop RO acknowledges alarms, reviews , with related alarms. indications, diagnoses N44 failure and dropped rod and informs ANSS. t Crew prioritizes use of AOP 1.1.5 and AOP 1.2.lc. and responds to drop rod first Only rod F-6 indicates O steps, only RO verifies only one rod dropped. rod bottom light lit.

DUQUESNE LIGH'1 COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-3-3 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Rod controlin manual. RO places / verifies rod control selector switch in manual. When asked to investigate dropped rod, Rod F-6 stationary gripper fuse blown. Crew directs I&C to investigate the cause - inform control room after appropriate of dropped rod. dday that the stationary gripper fuse is blown for F-6. Event # 3 Turbine load reducing. Crew continues actions of AOP Lt.5, reduces turbine load to < 70%, using OM-Power Reduction 52.4.B. Inform control room (as I&C) that cause for failure appears to be faulty fuse, and that it can be replaced and the rod recovered. Conditions established and maintained ANSS refers to T.S. 3.1.3.1, informs plant , for rod recovery. management of status and ability to recover rod, contacts reactor engineering for assistance. Crew references to AOP 1.2.1.C POWER RANGE CHANNEL MALFUNCTION" Bistable tripped. Crew removes N44 control power fuses

                                                                                                                                                          # rom Drawer A.

t

                                                             .-___-.__a         _____a.m ___._ __i. _ _ _ _ _ . . -    ____m-.._m..-____.__      _m___-       ______.___m           ___-_ .m _.                  -.-m.__.,_.-           .__m._

DUQUESNE LIGHi COMPANY - Nuclear Power Division 1 Training Administrative Manual DRILL 97-3-4 Rev. 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Rod control in manual Crew verifies rod control systems in manual. Rod Stop Bypass Switch -N44. Operator defeats N44 at NIS racic Upper Section Comparator Defeat Switch - N44. Lower Section Comparator Defeat Switch - N44. Comparator Channel Defeat , Switch - N44 RO selects or ensures NR-45 is selected to an operable channel. NSS refers to Tech. Spec. 3.3.1.1 and 4.2.1.1.b. After NI-44 has been removed from service and power has been reduced to 85% continue with next event.

           ...........*e...................

Ins 2rt FILE DRL973B to initiate EvInts S&6. o............................... EVENT # 4 Loss of Vital Bus 3 Mal EPS6C Reactor trips on loss ofsecond power Crew recognizes trip and enters E-0 . range-N43. Steam Dumps are inoperable in Steam Pressure Mode. Source Ranges will not auto energize.

DUQUESNE LIGtri. COMPANY Nuclear Power Disision Training Administrative Manual  !

                                                                                                                                                                                                                                                                                                                                   -i
       - DRILL 97-3-5 Rev. 0

[ INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPEcitD STUDENT RESPONSE l t

      -EVENT #5                                                                                                                                                                                                                                                                                                                    .}
         "B" SG 350 gpm Tube Rupture Mal RCS3B=350 gpm Immediately after the reactor trip,              350 gpm SGTR on "B" SG.

insert: MAL RCS3B= 350 gpm  ; ee.............................. .; Crew performsimmediate operator Reactor trip and bypass breakers open, RO verifies reactor tripped. + actions of E-0. neutron flux decreasing Rod bottom lights lit. Rod position indication at O. . RO sounds standby alarm and announces Unit I reactor trip. I Throttle and governor valves closed, PO verifies turbine tripped. reheat stop and intercept valves closed. Reheat flow control valves and MOVs PO ensures reheat steam isolation by closed. depressing reheat controller reset push-button and checks MOV 100A & B shut. Main generator output breakers open. PO verifies generator trip. Exciter circuit breaker open.

                                   ~

n DUQUESNE LIGH'1 COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-3-6 Rev. O l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l- OBJECTIVE l EXPECTED STUDENT RESPONSE l AE and DF busses energized. . PO verifies Emergency Busses energized. . t SI may not have actuated yet, crew may RO checks if SI is actuated or required. opt to manuallyinitiate SI(due to i degrading conditions) prior to exceeding actuation cdteria. Immediate Operator Actions Completed.

                                                                     .                                                                                                                                                          ANSS makes transition to ES-0.1 if SI is not manually initiated and informs crew.

STA begins monitoring status trees (if transition is made). , SI actuated Crew manually actuates SI when or before I actuation criteria are met. ANSS returns to E-0 Step 1 upon SI actuation and informs the crew. Reverifies i Immediate action steps of E-0. j Crew performsimmediate operator Reactor trip and bypass breakers open, RO verifies reactor tripped. l actions of E-0. neutron flux decreasing. Rod bottom lights lit. Rod positim indication at O. i

   . ~ _ _ _ _ . . . _ _ . _ . . _ _                                            .         ..                                                                                                     _ - . - -     --.

1

                               .~                                                                        -.
                                                                                  'DUQUESNE LIGIfl COMPANY Nuclear Power Division .                                                                                                     ,

Training Administrative Manual'  ;

,    DRILL 97-3-7 Rev.~ 0
'l       INSTRUCTIONAL GUIDELINES                    l PLANT STATUS OR RESPONSE l                                               OBJECTIVE l     EXPECTED STUDENT RESPONSE                                l RO sounds standby alarm and annources :                                ;

Unit I safetyinjection. ) i e Throttle and governor valves closed, PO verifies turbine tripped.' reheat stop and intercept valves closed. Reheat flow control valves and MOVs PO ensures reheat steam isolation by closed. depressing reheat controller reset push- f button and checks MOV 100A & B shut. , I I Main generator output breakers open. ' PO verifies generator trip. , Exciter circuit breaker open. AE and DF busses energized. PO verifies Emergency Busses energized. j i i Immediate operator actions complete. Any SI annunciator. RO checks if SI has actuated, reports SI j SI actuation status lights. actuated. Both EDGs running. PO verifies EDGs running at normal RPM. HHSI pumps mnning. RO/PO verify SI system status. FI-SI-943 indicates flow. .j LHSI pumps running. All red marked SIS valve indicating lights lit.

                                                                                                                                                                                                                   -r

                                                                                                                                                                                                                                      .n DUQUESNE LIGH'1 COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-3-8 Rev. 0 l      INSTRUCTIONAL GUIDELINES                                   l PLANT STATUS OR RESPONSE l                                               OBJECTIVE              l          EXPECTED STUDENT RESPONSE                               l FW-P-3A & 3B running.                                                                      PO verifies AFW status.

FW-P-2 running. MOV-FW-151 A through F open. RPRW pumps running. RO verifies River Water System in senice. CCR Ht Ex RW pressure > 20 psig. All indicating lights with orange CIA RO/PO verifies CIA. marks lit. Allindicating lights with green FWI RO/PO verifies FWI. marks lit. CNMT pressure < 3 psig. RO/PO check if main steamline isolation is Steamline pressure > 500 psig. required. No steamline pressure high rate  ; bistables lit. Annunciator Al-72 not lit. RO checks CIB and CNMT spray status. . CNMT pressure < 8 psig. - Two CCR pumps running. RO/PO verify CCR in sen' ice. SR channels in proper alignment. RO verifies source range detector high voltage switches in noimal. PO verifies total AFT flow > 325 gpm. Total AFW flow > 325 gpm. Zero AFW flow indicated to "C" SG due to loss of Vital bus III

2 DUQUESNE LIGHi COMPANY Nuclear Power Division i Training Administrative Manual DRILL 97-3-9 Rev. 0 , l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE- l OBJECTIVE l EXPECTED STUDENT RESPONSE l -l i StationInstrument AirHeader PO verifies station instrument air header -  ! Pressure > 100 psig.. pressure > 100 psig. Tavg dropping under the influence of RO checks RCS Tavg stable at or trending AFW flow. to 547 F. Tavg < 547 ANSS directs PO to stop dumping steam and reduce AFW flow, but maintain flow . greater than 325 gpm. ANSS directs performance ofESF checklists. i Recirc spray pumps not running. RO checks recirc spray pump status. , PORVs closed. RO checks PRZR isolated.- + Safeties closed. Spray valves at zero demand. . Power available to PORV MOVs. PORV MOVs open with associated PORVsin Auto. RCP's running. RO checks ifRCPs should be stopped. CCR flows indicated. No SGs are faulted. PO checks if any SGs are faulted. < B SG level rising. RO/PO check if SG tubes are intact. Secondary radiation high.

                                                                                                      . - - _ _ _ _ _ _ _ _ _ _ - = . .                    _ _ _ . _ - _ - _ . . _ - _ _ - - . _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ - _ _ _ - - _ - _ - _ _ _ _ _ - - _ - _ - _ _                      -

DUQUESNE LIGH1 COMPANY , Nuclear Power Division Training Administrative Manual

     . DRILL 97-3-10 Rev. 0 l        INSTRUCTIONAL GUIDELINES                                                                     l PLANT STATUS OR RESPONSE l                                 OBJECTIVE                   l    EXPECTED STUDENT RESPONSE                                    l l

ANSS determines, via operator reports, ANSS transitions to E-3 and informs crew. that a ruptured S/G exists and transitions to E-3. .; STA begins monitoring Status Trees (if j

not started previously). l Control room RM not in high alarm. PO checks control room habitability, l' CIB has not occurred.. determines CREBAPS actuation is not required. [

RCP's running. RO checks ifRCP should be stopped and RCS/SG D/P > 150 psid. reports pump conditions are sat.. . CCR available. As shift chemist, when requested, ANSS requests Chemistry tom " itiate acknowledge request to perform secondary side sampling.  ! isotopic analysis for dose equivalent  ; iodine - 131 in the RCS and all SGs. , t Outside operator is dispatched to realign  ! Blowdown Sample sink to North Sump. l DA-P-4A&B in stop. RO resets SI/ CIA.  ! DG-P-1 A&B in PTL. P.0/PO isolate containment vents and  : CV-P-1 A&B in PTL. drains [ TV-DG109Al & A2 closed.  ! SI reset.  ; CIA reset. I i t t

5 M. I DUQUESNE LIGN COMPANY

                                                                                        - Nuclear Power Division Training Administrative Manual DRILL 97-3-11 Rev. 0 l-       INSTRUCTIONAL GUIDELINES                     l PLANT STATUS OR RESPONSE l                       OBJECTIVE l      EXPECTED STUDENT RESPONSE                 l CCR pumps running.                                            PO checks CCR pump running.                          !

I TV-ICC-134-1 open. RO/PO aligns CCR to sample coolers. TV-1CC-134-3 open. i TV-1CC-134-2 open. I TV-1CC-133-2 open. r i Crew dispatches Operator to realign ' Blowdown Sample Sink drain from RPRW-to PAB North Sump.  ; i As PAB Operator, when requested to Crew dispatches Operator to Open SOV-open SOV-SS-117 insert: SS-117 SG Sample Line CNMT ISO Viv -  ! Interlock. [ LOA Aux 199 = T then report actions to the Control ' r Room. TV-ISS-117A,B,C open Crew Opens TV-SS-117A, B, & C, SG  ! Sample Outside CNMT Iso Valves. l

               *e..............................                                                                                                                                    ,

t i' As shift rad tech inform ANSS of "B" SG level is rising unexpectedly. ANSS makes positive identification of the elevated radiation levels ofB S/G ruptured S/G, based on PO report of"B"  ; blowdown sample, ion exchange SG level rise, or Rad Techs report. column, and steamline. t {

                                                                                                                                                                                  ?
                                                                                               . . . _          - , . -          .    .-                -i _     , - _

DUQUESNE LIGH COMPANY Nuclear Power Division - Training Administrative Manual DRILL 97-3-12 Rev 0 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE j Use LOAs PCV-MS-101B closed in manual. Crew isolates flow from the "B" S/G FWM35 =0 to close MS-16 and- HCV-MS-104 closed. FWM36=1 to open MS-17. MS-16 closed. l MS-17 opened.  ; Report valves status to control room TV-MS-11IB closed.

                                        "B" MSIV, bypass and NRV closed.
                                        "B" S/G > 5% NR.                                                                               PO checks ruptured SG NR level > 5%.

MOV-FW-151C and D closed. Crew isolates feed flow to "B" SG. BFRV-MOV-FW-155B closed.  ! MFRV-MOV-FW-154B closed.  ; MOV-RC-537 energized. RO checks PORVs and block valves. l RCS pressure < 2325 psig. PORVs cicsed. MOVs open. PORVs in auto. No S/Gs are faulted. PO checks if any S/Gs are faulted. , Pressure in all S/Gs stable. , Intact levels rising to 5-50% NR. PO checks intact S/G levels, maintain 5-50%, or maintain > 325 gpm feed flow. Air pressure > 100 psig PO checks Instrument Air > 100 psig.

                           ~                                                                                                                                               -                                                                                                      _

DUQUESNE LIGI-fi COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-3-13 Rev. 0 l IN'STRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l DG-P-1 A&B in PTL. RO verifies CNMT vents and drains DA-P-4A&B in stop. isolated. CV-P-1 A&lB in PTL. TV-DA-109Al&A2 closed. , SI previously reset. RO reset both trains of SI. CIA /CIB previously reset. RO resets both trains of CIA and CIB. - t 4KV stub busses energized. PO verifies 4KV stub busses energized. 480V AE and DF stub bus energized. PO verifies 480V stub busses energized. CNMTinstrument air compressor PO verifies CNMT instrument air  ! running. CNMT air pressure greater available. e than 85 psig. AN A6-110 not lit. t PO reports AE and DF bus energized by i AE and DF energized by offsite power. offsite. RCS > 250 psig. RO checks ifLHSI pumps should be i LHSI pumps stopped stopped, stops LHSI pumps places in auto. 1 t

DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-3-14 Rev. 0 l ' INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE- l "B" SG > ECA-3.1 transition pressure- PO checks ruptured S/G pressure >

                                                                     - 330 psig.                                                                                            ECA-3.1 transition pressure.

Target temperature based on mptured ANSS determines target cooldown S/G pressure.(515) temperature, based on mptured SG . pressure. STA trends cooldown rate ~ Condenser steam dumps unavailable Crew initiates RCS cooldown at the due to vital bus failure. maximum rate to the target temperature using atmospheric dump valves on A&C generators. RCS pressure < 1950 psig. Steamline RO blocks steamline SI when RCS low pressure SI blocked. pressure is below 1950 psig. Average of the 5 highest TCs at target Crew stops RCS cooldown at target temperature. temperature.

                                                                       "B" S/G pressure stable.                                                                             PO checks ruptured S/G pressure stable or rising.

Subcooling > 23*F. RO checks RCS subcooling on ICCM greater than 23 F.

DUQUESNE LIGH r COMPANY I Nuclear Power Division Training Administrative Manual DRILL 97-3-15 Rev. O < l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l. , Spray available. Crew uses spray valves to depressurize RCS. RCS pressure < "B" S/G pressure and Crew stops depressurization by closing PZR level > 5%, or PZR level > 76%, spray valve. or RCS subcooling < Attachment 6-A. RCS subcooling > 23 . Crew checks if SI flow should be Total feed flow to SG > 350 gpm terminated. and/orintact NR levels > 5%. RCS pressure stable or rising. PZR level > 5%. One HHSI pump - running. Crew stops one HHSI pump. Terminate drill after stopping one HHSI pump in E-3. Collect and review logs after allowing Operator logs should be clear, accurate , operators to complete them. and concise. Erase any vond markings associated i with this drill.

1 l l ES-301 Scenario Events Form ES-301-3 i I g Simulation Facility: Scenario No.: 97-4 j Beaver Valley Power Station - Unit 1 , 1 1 Examiners: Applicants:

                                                                                                                     )

1 1 Initial Conditions: l l l 75% power, EOL,161 ppm boron, Xenon increasing @ 200pcm/hr due to power decrease from 100% over the past 2 hours. i Tumover; i

1. FW-P-3A, MDAFW pump is on clearance for motor replacement. Due to be returned next shift. ,

2. SA-C-1B, station air compressor on clearance for compresor failure. Not due to be returned for 2 days.

3. Rod control is in automatic, CBD @ 206 steps, boron = 161 ppm, burnup = 12,000 MWT)/MTU. I

4. FW-P-4, the dedicated AFW pump, is on clearance for motor bearing replacement. Not due to be returned for 2 days. Fire Watch required in AFW room once an hour.

5. N42 Power Range channel inoperable and removed from service IAW AOP 1.2.1C.

j

6. Crew is to maintain current power level pending request of System Operator. <

Event Malf. No. Event Event i No. Type

• Description j 1 MALF i PT-RC-455, RCS pressure protection channel i fails high. With N42 NIS3B, rdready inoperable TS 3.0.3 should be entered due to 2/3 OT/DT channels PRSSA. being inoperable. )

2 N Power reduction due to TS 3.0.3. 3 R Power reduction of at least 5%. 4 MALF C Excessive #1 seal leak off of 20 gpm on 1RC-P-1B, B loop RCP, requiring RCS5B a Rx trip 1AW ARP 7.4.ABE.

                                                                                                                     ]

i 5 MALF M ATWS that causes a PZR PORV to open. Local Rx trip to occur at t = 2 CRF12 minutes aRer requested from crew. ll A&B 6 MALF C PCV-RC-455C, PZR PORV, leaks. PRS 3A = 50 % 7 OVRD C MOV-RC-535, PZR PORV block valve, fails to close resulting in a PZR M vapor space leak /SBLOCA. Scenario termination criteria: Transition to ES-1.2. E-0... FRS-1. . E-0... E-1. . ES-1.2. I ! * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner: ChiefExammer. i l l Examiner Standards 23 of 26 Rev. 7, January 1993 DVPs Rev0

DUQUESNE LIGHT COMPANY

                                                                        . Nuclear Power Division Training Administrative Manual DRILL 97-4-1 l      INSTRUCTIONAL GUIDELINES              l PLANT STATUS OR RESPONSE l                                                        OBJECTIVE                                                                                                                      l EXPECTED STUDENT RESPONSE l Initialize the simulator at IC-46.           Reactor plant at 75% power, Xenon increasing, EOL.

Insert FILE SIMIC Insert FILE PWRSETUP Places equipment out of service per the initial conditions setup page. , REMOVE CONTROL POWER FUSES FROM N-42, PLACE TAGS and ' CHECK SWITCH POSITIONS. IPC RODUP Insert MALF NIS3B NI42 removed from service on prior. shiR and bistables BS-422 C-1 and BS-422 C-2 are tripped.. Insed MALF CRF12A & B Auto and manual ATWS. Insen Overrides P07061C=1 and PORV, PCV-RC-455C, block valve, P07061D = 2 MOV-RC-535, will not close. Assign shin positions: NSS Simulator Frozen until aner shin ANSS turnover unless it needs to be on RO momentarily for an alignment change. PO STA'  ! I

DUQUESNE LIGI-fI COMPANY Nuclear Power Division Training Administrative Manual

             - DRILL 97-4-2 l      INSTRUCTIONAL GUIDELINES               l PLANT STATUS OR RESPONSE                                                l- OBJECTIVE l   EXPECTED STUDENT RESPONSE                l ,

Conduct shift turnover with oncoming Oncoming operators should complete the operators. required checklists and carry out a formal shift tumover. t COAAAAAAAAAA.AA.***AAA***A.***** When the shift turnoveris complete, place the simulator to RUN and Simulator running. Crew assumes control of the unit. t commence the drill.

              $2AAAAA..AA.AAAAAAAAAAAA.AAAAA.*

Three minutes after crew assumes the shift. EVENT #1  ; PT-RC-455, RCS pressure protection channel I fails high.

              ............A...............****                                                                                                                                                ,

ACTIVATE MALF PRS 8A,2500 PT-RC-455 fails high. RO acknowledges alarm, verifies alarm and informs ANSS.

              ........**.........A.**.          *******                                                                                                                                       l Crew refers to ARPs as necessary.

RO informs ANSS that PT-455 fails high.

                                                                                                                                                                                                                                                              .4 %.

DUQUESNELIGHT COMPANY Nuclear Power Division i Training Administrative Manual DRILL 97-4-3 , l . INSTRUCTIONAL GUII?FLINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l ANSS ensures plant is stable. i Crew refers to T.S. 3.3.1.1 Crew recognizes that compliance with action statement will result in reactor trip. ANSS enters Technical Specification 3.0.3 Crew refers to OM 1, Table 1 - 6 to obtain bistable number.  ; i If requested as I&C to trip bistables.

 ********************************                                                                                                                                                                                      ANSS directs I&C to trip the bistables, r

SET OVR P072029W = 1 Channel I prot. rack 3 door open. IAW OM-1, Table 1 - 6, or OM 1.6.4.IF. EXCEPT BS-412C-1 and BS-412C-2  ; RCS-39 = 1 BS 455A tripped RCS-40 = 1 BS 455C tripped. ANSS directs I&C to investigate the repair RCS-41 = 1 BS 455D tripped. PT-RC-455 in accordance with MWR. RCS-42 = 1 BS 455B tripped. . RO monitors bistable tripping. SET OVR P07029W = 0 Channel I prot. rack 3 door closed. . t essese************************** f

aMy DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-4-4

-l                  INSTRUCTIONAL GUIDELINES             l PLANT STATUS OR RESPONSE l                                                                                  OBJECTIVE         l                     EXPEUIED STUDENT RESPONSE                                                    l Event # 2                                                                                                                                                                          ANSS directs operators to commence a normal plant shutdown in accordance with Decision to reduce power due Technical                                                                                                                                              OM 1.52.4.B plant shutdown in order to Specification 3.0.3                                                                                                                                                               comply with Technical Specification 3.0.3 Event # 3 Power reduction e.e ..eee.eeeeeee.**************                                                                                                                                                  RO and PO coordinate load reduction.

As Turbine Plant Operator when Crew continues normal shutdown. requested to start "B" MFP aux lube oil Pump INSERT LOA FWM29 = T oeoeseeseeeeeeeeeeeeeeeeeeeeeees Allow power reduction to at ~65% Crewinforms System Operator of before proceeding to Event 4 shutdown. EVENT #4 , RCP Seal Failure

d,N DUQUESNE LIGifI COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-4-5 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l

 ******************************'                                                           _cssive #1 Seal Leak off at 20 gpm                                                                                                              RO acknowledges and verifies and alarm on IRC-P-1B, Annunciator A3-87                                                                                                                                      andinforms ANSS.

- ACTIVATE MALF RCS5B,20,0,0 actuates encones......................... i Crew refers to ARP IOM-7.4.ABE. Crew determines #1 seal leak off flow. Crew verifies seal injection flow and valve lineup. Crew determines that reactor trip and RCP trip are required EVENT #5 ATWS Reactor Trip Breakers do not open. RO manually trips the reactor ATWS situation develops when reactor fails to trip.

 ********************************                                                                                                                                                                                                         RO notes that a reactor trip has not ACTIVATE MAL PRS 3A,50%                                                                                                                                                                                                                  occurred, attempts to manually trip the WHEN TURBINE IS MANUALLY                                                                                                                                                                                                                 reactor, notes manual attempts fail, reports TRIPPED.                                                                                                                                                                                                                                 ATWS condition to the ANSS.

eesseeeeeeeeeeeeeeeeeeeeeeeeeees

DUQUESNE LIGin COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-4-6 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPEUIED STUDENT RESPONSE l Crew transitions to FR-S.I. Steps 1 Operators commence immediate manual , through 5 are immediate manual actions ofE-0 and FR-S.1 and ANSS actions.- refers to E-0 and transitions to FR-S.1 STA monitors status trees for information only during performance of FR-S.I. Reactor trip and bypass breakers shut. RO verifies no reactor trip, attempts to Neutron flux steady. trip reactor. j Rod bottom lights not lit. Rod position indication not at zero. Rods move in while in auto. RO verifies Rods move in and continues [ Rods will respond in manual. rod motion in manual when rod motion slows to < 48SPM. aaaaaaaa***aaaaaa*******aaaa**** Reactor trip breakers open two Crew dispatches operator to locally open Two minutes after crew calls operator, minutes after operator directed to reactor trip breakers.  : locally open breakers. , USE MAL CRF14A and CRF 14B  ; TO LOCALLY TRIP REACTOR.  !

         ......aaaaa****a*********a******

RO sounds standby alarm and announces  : Unit I reactor trip /ATWS. t i t h _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ . _ _ _ _ . _ _ = _ , ,_ _ . _ _ _ . _ _ . _ _ . _ _ _ _ _ _ _ . _ _ . _ _ ___ ________ _ _ .

                                                                                                                                                                                                                                                                        ~                   ,

DUQUiiSNE LIGH COMPANY Nuclear Power Division Trairimg Administrative Manual - DRILL 97-4-7 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE - l OBJECTIVE l EXPECTED STUDENT RESPONSE l Turbine trips. PO manually trips turbine using both Erst.re PRS 3A,50% is active turbine trip push buttons. EVENT #6 & # 7 PORV stuck open with failure ofblock valve to close. Steam Dump control switches in OFF. PO isolates the condenser steam dump valves. Reheat flow control valves and MOVs PO ensures reheat steam isolation by closed. depressing reheat controller reset push-button and checks MOV 100A & B shut. Immediate manual actions complete. FW-P-3A on clearance, FW-P-3B and PO verifies AFW system status. FW-P-2 running, MOV 151 A - F full open. NOTE: SI may be actuated by this time. CH-P-1 A mnning. RO initiates emergency boration. i MOV-CH-350 open. Boric acid pump in fast speed. FCV-CH-122 open 75 - 150 gpm. . Pzr pressure < 2335 PSIG. Crew verify RCS pressure < PORV setpoint. i i

                                  ~ . . _ .              . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _                                        = _ _ _     ___ _

DUQUESNE LIGH1 COMPANY Nuclear Power Division , Training Administrative Manual. DRILL 97-4-8

 .l  INSTRUCTIONAL GUIDELINES                                                              l PLANT STATUS OR RESPONSE l                                OBJECTIVE       l       EXPECitD STUDENT RESPONSE                                                                        l SI actuation possible.                                                          Crew checks SI actuation status and if                                                                              ;

actuated, PO performs first 15 steps of E-0, (if time permits and directed by ANSS) l RO/ANSS continue with FR-S.I. AFW flow supplied to all SGs, levels PO controls AFW flow to SGs to maintain - rising, actual level time dependent. NR levels between 5 - 50% Station Instrument Air pressure > 100 PO verifies St ' ion Instrument Air psig. pressure > 10'e psig. , SR detector high voltage switches - Crew verifies SR high voltage switches in i f normal. normal. Reactor trip breakers open, all control RO infonns crew that reactor has been rods fully inserted. (2 minutes after tripped (when actual trip occurs.) person dispatched to locally open i breakers). i 4 FCV-CH-113B closed. RO verifies dilution paths isolated. FCV-CH-114A closed. FCV-CH-114B closed. Uncontrolled cooldown not in RO monitors for uncontrolled cooldown. , progress. , i

DUQUESNELIGHT COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-4-9

 .l                      INSTRUCTIONAL GUIDELINES  l PLANT STATUS OR RESPONSE l                                                                                     OBJECTIVE l    EXPECTED STUDENT RESPONSE                l PR NIs < 5%                                                                                                                 RO verifies reactor sub critical.

IR NIs indicate negative SUR. Durixg E-O RCP IB should be tripped and MOV-CH-303B closed. Crew transitions to E-0 step 1 ANSS transitions from FR-S.1 back to E-0 step 1 and informs operators to commence immediate manual actions of E-0. 9 Steps 1 - 7 are immediate manual RO/PO commence IMAs ofE-0, ANSS actions. references E-0 to verify immediate actions. Reactor trip and bypass breakers open, RO verifies reactor trip. t neutron flux dropping, rod bottom lights lit, all rod position indication at zero steps. Crew sounds standby alarm and announces UNIT 1 REACTOR TRIP. Throttle, governor, reheat stops and PO verifies turbme inp. intercept valves all closed. Reheat flow control valves and MOVs PO ensures reheat steam isolation by closed. depressing reheat controller reset push-button and checks MOVs MS - 100A&B , shut. , i

52, DUQUESNE LIGH'1 COMPANY

                                                                                                                    -Nuclear Power Division
                                                                                                                ~ Training Administrative Manual l        DRILL 97-4-10                                                                                                                                                                                     >
  -- l     INSTRUCTIONAL GUIDELINES                                                     l PLANT STATUS OR RESPONSE -l                         OBJECTIVE-   l        EXPECitD STUDENT RESPONSE -l Main generator output breakers open.                              PO verifies generator trip ~               !

Exciter circuit breaker open. AE and DF Emergency 4KV busses - PO verifies AE and DF busses energized. l energized from offsite. . SI actuation status light lit Crew checks SI actuation status, informs [ ANSS SIis actuated.  ; EDGs running. PO verifies EDGs running at normal RPM. HHSI pumps running. Crew verifies SI system status .  ; FI-SI-943 indicates flow. l LHSI pumps running. j All red marked SIS valveindicating  ! lights lit. [ l

                                                                      ,                      FW-P-3 A on clearance, FW-P-3B and                                PO verifies AFW system status.            ]

FW-P-2 running. j MOV- FW-151 A-F full open. Crew may trip RCPs on Left Hand page RPRW pumps running. RO verifies river water system in service criteria, if d/p less < 150 psid with high CCR HT EX RW pressure > 20 PSIG. . head flowindicated. All indicating lights with orange marks . Crew verifies CIA j lit. All green marked FWI valve indicating Crew verifies FWI. lights lit. } i l

DUQUESNE LIGhi COMPANY Nuclear Power Division Training Administrative Manual

          - DRILL 97-4-11 l . INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l'                                               OBJECTIVE                                   l   EXPEC160 STUDENT RESPONSE                                l CNMT pressure < 3 PSIG.                                                                                                 Crew checks if MSLI required, detennines Steamline pressure > 500 PSIG, no                                                                                       MSLI not required, steam line high rate bistables lit.

CIB not required. ANSS checks control room habitability, Control room rad monitors normal. determines CIB not required, habitability system activation not required. CCR pumps running Crew verifies CCR system status. SR detector high voltage selector RO verifies SR detector high voltage switches - normal. selector switches in normal. AFW flow > 325 gpm. PO verifies AFW flow > 325 gpm. Station Instrument Air pressure > 100 PO verifies Station Instrument Air psig. pressure > 100 psig. Tavg responds correctly to steam RO checks Tavg stable at- or trending to dumps and AFW flow. 547 F. ANSS directs operators to perform safety function checklists as personnel become available. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- __ _ . _ _ _ _ -. . ~ . . _________ ______._ _ ___._____ ____ _ ._. _ _ _ _ _ _ . _ _ _ . - _ _ _

DUQUESNE LIGHi COMPANY [ Nuclear Power Division Training Administrative Manual DRILL 97-4-12 - l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l PORV 455C stuck open. RO reports stuck open PORV and failure MOV-RC-535 (PORV 455C block of block vdve to close to ANSS. valve) will not close. [ Acoustic monitor for PORV 455C indicates flow.  ! High tailpipe temperature on PORV , exists. l Crew transitions to E-1 ANSS directs crew to transition to E-1 based on operator report ofopen PORV l and associated block valve. Control Room Habitability system is Crew verifies Control Room Habitability not required. system is not required. RCPs stopped. Crew checks if RCPs should be stopped, and stops RCPs., if not already stopped. When requested to start WR Hydrogen i analyzers:

  ****************************                                                           Wide range hydrogen analyzers placed                                                                            ANSS direct additional operator to place in service.                                                                                                     wide' range hydrogen analyzers in service.

ANNUN AN02097 = 1 ANNUN AN02105 = 1 Then report actions to control room. _ _ . -- ..m.m -___ _ ____ _ ___ ____.___ . __ _ _________ _ _ __ _ ___ _ __ __

                .                                                                                                                                                        w DUQUESNE LIGhi COMPANY                                                                                                                            !

Nuclear Power Division  ! Training Administrative Manual I DRILL 97-4-13 ' l . INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE - l OBJECTIVE l EXPECTED STUDENT RESPONSE ' l j SGs not faulted. - PO checks if any SGs are faulted, reports SG pressures stable. no faulted SGs. AFW flow > 325 gpm. PO checks intact SG levels and maintains SG levels increasing at controlled rate. flow to control levels 5 - 50% NR level. I 1 Station Instrument Air pressure > 100 PO verifies Startion Instrument Air  ; psig. pressure > 100 psig. l

PORV 455C stuck open.

RO reports status ofPORV 455C and its i l MOV-RC-535 stuck open associated block valve to ANSS. i Subcooling < 23F ANSS checks if SI can be terminated, I Heat sink sat. continues E-1 actions based on operator reports oflowering RCS pressure. RCS pressure and Subcooling lowering due to leaking PORV/ block  ; valve. i No SG level tising in uncontrolled PO checks if SG tubes intact. manner. Secondary radiation consistent with pre event values.- t i No quench spray pumps mnriing. ANSS checks if CNMT spray should be j stopped. l 1 i

                                                                                                                                                                                                  )

i i f

DUQUESNE LIGH1 COMPANY Nuclear Power Division Training Administrative Manual l DRILL 97-4-14 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Containment vents and drains isolated. RO isolates containment vents and drains. DG-P-1 A, IB PTL. . DA-P-4A,4B stop. CV-P-1 A,1B PTL.  ; TV-DG-109Al, A2 closed. Both Trains of SI reset. RO resets SI. , Both Trains of CIA reset. RO resets CIA. i RCS pressure > 250 PSIG and RO checks if LHSI pumps should be j lowering. stopped, and does not stop LHSI pumps. ' i SG pressures stable. PO checks SG pressures.  ; i RCS pressure dropping. RO checks RCS pressure, stable or f reducing. AE and DF 4KV emergency busses PO checks ifEDGs should be stopped, i energized by offsite power. stops unloaded EDGs.  ; Power available to LHSI pumps, ANSS verifies cold leg recirc capability by power available to valves in verifying power to at least one train of j l attachment 1-F equipment listed in attachment 1-F. t et,--m

  - _ _ - _ _ ~ . _ _ - . . . _ _ _ _ _ _ _ _ - _ - _ _ _ . - - _ - - _ - _ _ - _                     _ _ _ - _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ - - - - - - - - - _ _ - - _ _ _ _ - _ - - - - _ _ - _ - _ _ - - _ _ _ _ _ - - _ - _ - _ - _ - _ _ _ _ _ _
                                                   ~

n DUQUESNE LIGFir COMPANY Nuclear Power Division  !

                                                                                                   - Training Administrative Manual DRILL 97-4                                                                                                                                                                                                                                                                                                         -i l          INSTRUCTIONAL GUIDELINES                                       l PLANT STATUS OR RESPONSE l                                                                                                                OBJECTIVE                                   l    EXPECTED STUDENT RESPONSE                          l No unexpected rad level increase.                                                                                                                                                       Crew checks Aux building and safeguards                  :

radiation.  ; ANSS directs chemistry to commence i sampling. Crew starts additional equipment as necessary to assist in plant recovery l RCS pressure > 250 PSIG. ANSS determines method ofcooldown for long term plant recovery. Crew transitions to ES-1.2. ANSS transitions to ES-1.2 for post I LOCA cooldown and depressurization and informs crew. - E i Terminate drill when crew transitions to l ES-1.2 step 1. l I Collect and review logs after allowing Operator logs should be clear, accurate i . operators to complete them. and concise. i i Erase any vond markings associated  ! with this drill. t R: turn N42 to service!  ! ! I

I L

                    - ES-301                                               Scenario Events                                   Form ES-301-3

{' Simulation Facility: Scenario No.: 97-5 Beaver Valley Power Station - Unit 1 Examiners: Applicants: , l Initial Conditions: Rx S/U in progress, Rx power is at IE-8 amps, Xenon free, EOL conditions I' . Turnover: i ! 1. SA-C-1B, station air compressor on cicarance for compressor failure. Not due to be returned for 2 l days. l l 2. Rod control is in manual. i l 3.- FW-P-4, the dedicated AFW pump, is on clearance for motor bearing replacement. Not due to be returned for 2 days. Fire Watch required once per hour in AFW room.

4. OM 50.4.D, Plant startup, at step C.I. Crew is to continue Unit startup.  ;

! 5. FCV-FW-150A&B are failed open and CN 101 is in Manual and shut. i Event Malf.~ Event Event

                        ' No.                No.        Type

• Description 1- MALF I FT RC-414, I A loop flow transmitter, fails low. Remove RCS19A' l

instrument from service IAW IFM 6.4.lF and TS 3.3.1.1 act. 7. l l 2- N Conduct plant startup.  ! 3 R Raise Rx power to the POAH.

           .                 4         MALF                C       Uncontrolled Rod withdrawal requiring a manual Rx trip.

L CRF5B > L 5 MALF M On Rx trip the C S/G becomes faulted inside containment and is not l MSSIC isolable from the S/G. , t 6 INH 49 C Failure of auto actuation of both trains of CIA, requiring manual . actuation of CIA. Scenario termination criteria - Si terminated / BIT isolated. E-0... E-2... E-1... ES-1.1. { _ (N)ormal, (R)eactivity, (I)nstmment, (C)omponent, (M)ajor l l lj~ Examiner; i ' ChiefExaminer: 1 Examiner Standards 23 of 26 Rev. 7, January 1993

                   ' - BVPS -Rev 0         _                 ,          ,                                                                   ,                    ,, ,

DUQUESNE LIGIf1 CONFANY Nuclear Power Division Training Administrative Manual - Drill 97-5-1 . l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l

         , Initialize the simulator at IC-47                                                                      Reactor at 104 amps, EOL, control bank D is at 100 steps. Boron is 634                                                                                                                                                                                                               .

ppm. Insert FILE SIMIC IPC RODUP GGGGQCAAAAAAAAAAAAAAAAAAAAAAAA ACT MAL AUX 2B "B" Station Air Compressor tripped . hsert INH 49=T Failure ofCIA to actuate aaaaaaaaaa****aa**********aa*** automatically. Assign shift positions: NSS Simulator Frozen until after shin ANSS turnover unless it needs to be on i RO. momentarily for an alignment change. PO j STA Conduct shift turnover with oncoming Oncoming operators should complete the operators. required checklists and carry out a formal shin turnover.

                                                                                                                                                                                                                                                                                                                                                                                            ~

F i t _ . - . _ _.... .__.m.w -._-_._____a_m _ . . _ _ _ . _ _ _ _ - . _ -r . -~- w m. - r m--2-- _ _ _ _ . _ ____ _-______-________ _ _ _ - _ _ _ _ _ _ _ _ .a._ _ _ _ _ _ - - . _ . _ -

N EM.- DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual Drill 97-5-2 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l t

    - When the shift turnover is complete, place the simulator to RUN and          Simulator running.                                           Crew assumes control of the unit.

commence the drill. , Three minutes after crew assumes the ' shift: , EVENT #I , i RCS Loop "A" Flow Transmitter FT-RC-414 fails low. eoeeeeeeeeeeeee+ seeeeeeeeeeeee. , t ACTIVATE MALF RCS19A,0,1 RCS Loop 1 A flow FT-RC-414 fails RO acknowledges alarm, reviews low. Reactor cool pump 1 A flow low indications, informs ANSS that FT-RC- ,

     ******************************** annunciator alarms. Channel I low                                  414 has failed low.                              ;

flow status light energizes. Crew references ARP A3-104 and instrument failure procedure IOM-6.4.IF , Attachment 3. Actual A Loop RCS flow normal. RO determines that problem is a single channel failure. i i P

DUQUESNE LIGHi COMPANY ' Nuclear Power Division Training Administrative Manual Drill 97-5-3 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l The NSS initiates MWR to investigate ANSS notifies I&C ofproblem. and repair. t e............................... When requested simulate tripping B/S ANSS identifies Tech. Spec. 3.3.1.1 as per MSP-6.03-1 by opening rack door BS-414 tripped upon failure of applicable and directs crew to place  ! (B/S already tripped). instn2 ment. channel in tripped condition within six  ; hours. OVR P07029W - 1 Prot rack #2 open (CH-1) LOA RCSI = 1 BS-414 RCS low flow. OVR P07029W = 0 Rack #2 door closed. EVENT # 2 Continue reactor startup to 2 to 5% Reactor at 10 amps. RO verifies NI overlap. power. Reactor power between 2% and 5%. RO pulls rods to raise reactor power to 2 to 5%. , Reactor power between 2% and 5%. RO verifies steam dump maintains Tavg between 545 and 549 . i EVENT # 3 Uncontrolled Rod Withdrawal requiring manual reactor trip ,

DUQUESNE LIGH COMPANY Nuclear Power Division Training Administrative Manual Drill 97-5-4 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l ACTIVATE MALF CRF5B Uncontrolled rod withdrawal in RO observes continuous rod withdrawal. Manual. Positive SUR and Power aseen.........................n. jnCreasing. ANSS may references AOP 1.1.3. RO manually trips the reactor. i EVENT #4

               *C" Main Steamline mpture inside CNMT.

Immediately upon reactor : rip: SG low-low level reactor trip first out RO informs ANSS of reactor trip and first AS-11,19,27. out annunciators. ACTIVATE MALFUNCTION Main Steam line break inside MSSIC=2.2E6 LBM/HR. centainment, temperature and pressure , rising. Reactor trip, turbine trip, RCS RO and PO commence immediate actions pressure drops. of E-0, ANSS references E-0 to verify immediate actions.

am DUQUESNE LIGH1 COMPANY Nuclear Power Division - i Training Administrative Manual .t

                 - Drill 97-5-5 Ll                   INSTRUCTIONAL GUIDELINES                                        l PLANT STATUS OR RESPONSE l                                                          OBJECTIVE                                       l            EXPECTED STUDENT RESPONSE                                                    l l                  Crew performs immediate operator                                    Reactor trip and bypass breakers open,                                                                                                   PO verifies reactor tripped.

actiens ofE-0. neutron flux decreasing. Rod bottom j lights lit. Rod position indication at O.  ! RO sounds standby alarm and announces Unit I reactor trip. Throttle and governor valves closed, PO verifies turbine tripped. 4 reheat stop and intercept valves closed. Reheat flow control valves and MOVs PO ensures reheat steam isolation by j closed. depressing reheat controller reset push-button and checks MOV 100A & B shut. l Main generator output breakers open. PO verifies generator trip. Exciter circuit breaker open. l AE and DF busses energized. PO verifies Emergency Busses energized. Immediate operator actions complete. Any SI annunciator. SI actuation RO checks if SI has actuated, reports SI  ; status lights. SI actuated by Low actuated. Steam Line Pressure. Both EDGs running. PO verifies EDGs running at normal RPM.  ! i

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual Drill 97-5-6 l INSTRUCTIONAL GUIDELINES l P!. ANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l HHSI pumps running. RO/PO verify SI system status. FI-SI-943 indicates flow.  ; LHSI pumps running. . All red marked SIS valve indicating lights lit. i FW-P-3B running. PO verifies AFW status. FW-P-2 running. MOV-FW-151 A through F open. l RPRW pumps running. RO verifies River Water System in service. i CCR Ht Ex RW pressure > 20 psig.  ; Event # 5  ; l Failure of automatic CIA.  ; All indicating lights with orange CIA RO/PO verify CIA, determine that it has marks not lit. CIA failed to actuate.- not actuated and report CIA status to the i ANSS.  ! CIA actuated. RO manually actuates CIA at BB-A. All indicating lights with orange CIA RO/PO verify CIA alignment. marks lit.  ! i I

DUQUESNE LIGHi COMPANY Nuclear Power Division Training AdmirJstrative Manual Drill 97-5-7 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Allindicating lights with green FWI RO/PO verify FWI. marks lit. Containment pressure increasing, RO/PO determine MSLI is reasired.

                                                - steam line pressure dropping.

All indicating lights with yellow marks RO/PO verify MSLI. lit. NOTE: CIB may not have actuated at CNMT spray actuates when required. RO/PO check CIB/ SPRAY status, RO this time, however, it will actuate during All indicating lights with blue marks lit. stops RCPs after CIB. the drill. Observe crew verification of RCPs stopped. automatic actions when actuated. (Continuous Action Step.) CCR pumps trip when CIB actuates. RO reports CCR status to ANSS. SR detector high voltage selector RO verifies SR detector high voltage switches - normal. selector switches in normal. AFW flow > 325 gpm. PO verifies total AFW flow greater than 325 gpm. StationInstrument AirHeader PO verifies station instrument air header Pressure > 100 psig. pressure > 100 psig. r Tavg < 547 F and dropping rapidly. RO determines RCS Temperature is (SLI already verified.) dropping.

                                                                                                                                                                                                                     ~

f.* DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual-

          . Drill 97-5-8                                                                                                                                                                                                                                                                                                                          ;

l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l ANSS directs personnel to perform emergency safety function checklists when available.  ; PORVs closed. RO checks PZR PORVs and Spray valves. Safeties closed. Spray valves at zero demand. Power available to PORV MOVs.  ! PORV MOVs open with associated PORVs in Auto. RCPs stopped after CIB. RO stopped RCPs after CIB actuation, reports status to ANSS. f "C" SG pressure is decreasing due to PO checks SG pressures and reports "C" , steam line rupture in containment. SG as faulted to the ANSS.  ; I Crew transitions to E-2. ANSS exits E-0 and enters E-2, and informs the control room. ANSS directs STA to monitor status trees. T b 4

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual Drill 97-5-9

l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l CREBAPS actuated on CIB. PO verifies CREBAPS actuated.

All five Control Room bottled air RED , lights are lit. Both emergency ventilation timers are mnning. Control Room intake and Exhaust dampers are closed. PO request Unit 2 Control Room to check dampers closed. Yellow marks lit. RO/PO verifies steamline isolation.

                                                                       "A" and "B" SG pressures are stable.                       PO checks for.non-faulted SG "C" SG pressure is dropping                                Crew identifies "C" SG as faulted.

uncontrollably. FW-P-2 aligned to A&B. FCV-lFW-498 closed. PO closes / verifies "C" MFRV and BFRV closed. FCV-lFW-499 closed. MOV-FW-151 A and 151B closed. PO closes MOV-FW-151 A and 151B. t i FW-P-2 aligned to A&B. PO verifies Turbine Driven ARV pump , steam supply.

3e'in DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual Drill 97-5-10 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l PCV-MS-101C closed. Crew verifies "C" SG atmospheric di mp valve closed. f HCV-MS-104 closed. Crew verifies RHR control valve closed.  ; No SG level rising in an uncontrolled Crew checks ifSG tubes are intact.  ; manner. Crew transitions :o E-1. ANSS exits E-2 at step 7 and enters E-1 and informs control room. Previously verified. ANSS/PO verifies CREBAPS actuated. RCPs stopped ANSS/RO verify RCPs stopped. ANSS directs operator to start H2 When directed as Extra Operator, analyzers per OM 1.46.4.G, Placing WR j startup WR H2analyzers, insert: H2Monitoring System In Operation. ANNUN AN02097 = 1 AN02105 = 1 Then report actions to the control room. t i

                                                                                                                                                                                                                                   ~
                                     "C" SG identified as faulted and                                                                        ANSS/PO detennine"C" SG is faulted.

isolated previously.

t DUQUESNE LIGH1 COMPANY Nuclear Power Division. Training Administrative Manual

     - Drill 97-5-11 l   INSTRUCTIONAL GUIDELINES                 l PLANT STATUS OR RESPONSE l                                                 OBJECTIVE       l    EXPECTED STUDENT RESPONSE                          l             -
                                                   "A" and "B" SG AFW flow > 325 gpm                                                             PO maintains flow to "A" and "B" S/G or level > 5% NR.                                                                             greater than 325 gpm until greater than                            y 5% level, then controls between 5% and                              ;

50%. Station Instrument Air Header PO verifies station instrument air header u Pressure > 100 psig. pressure > 100 psig. PORVs may be cycling at this time if PO verifies PORV and block valves I PZR pressure is high due to SI flow energized and PORVs closed unless  ; filling up PZR. pressure is greater than 2325 psig. j Subcooling' satisfactory. Crew checks if SI flow should be  ! Heat sink satisfactory. terminated.  : PZR pressure stable or increasing. PZRlevel increasing. j i ANSS transitions to ES-1.1 upon PZR  ! Crew transitions to ES-1.1. i level increasing greater than 5%. Primary Drains Transfer Pumps in ' RO isolates CNMT vent and drain  ! Pull-to-Lock. systems. CNMT Sump pumps in Pull-to ' c k. CNMT Vac Pumps in Pull-to-Loo; i PRT Vent Valves closed. , i SI reset. (both trains) RO resets SI. l l CIA reset. (both trains) RO resets CIA and CIB. CIB reset. (both trains) l

ir*- DUQUESNE LIGH1 COMPANY Nuclear Power Division Training Administrative Manual Drill 97-5-12 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l One HHSI pump running. RO secures one HHSI pump. Use LOA'S as required to close CCR pumps in Pull-to-Lock. PO re-energizes stub busses. breakers: Aux RW Pumps in Pull-to-Lock. EPS 138 =T 8N16 4KV stub busses energized. EPS 140 =T 9P16 CNMT Air Recirc Fans in Pull-to-Report 8N22 and 9P21 closed. Lock. CRDM shroud fans in Pull-to-Lock. PRZR Heaters 2A and 2B in Pull-to-Lock. CNMT Instrument Air Cornpressors in Pull-to-Lock. 480V stub busses energized. Auto cold leg recirc change over reset. RO resets auto cold leg recirc change over (both trains). Chiller verified in service. PO starts CNMT Instrument Air TV-1CC-110D and F2 open. Compressors. TV-ICC-110E2 and E3 open. CNMT Instrument Air Compressor Running. CNMT air header pressure > 85 psig. RCS pressure is stable or rising. RO checks RCS pressure. MOV-CH-289 and 310 open. RO establishes normal charging flow. FCV-CH-122 in throttled to maintain pressurizer level.

sP& DUQUESNE LIGh r COMPANY Nuclear Power Division Training Administrative Manual Drill 97-5-13

            .l          INSTRUCTIONAL GUIDELINES                    l PLAM STATUS OR RESPONSE l                           OBJECTIVE -                                                                   l   EXPECTED STUDENT RESPONSE' !.

MOV-SI-867A through D shut. RO isolates the BIT. i Terminate drillin ES-1.1 after BIT isolated. Collect and review logs after allowing Operator logs should be clear, accurate operators to complete them. and concise. Erase any vond markings associated ,- with this drill. I t r f I , I l l

ES-301 Scenario Events Form ES-301-3 i Simulation Facility: Scenario No.: 97-6 Beaver Valley Power Station - Unit 1 Examiners: Applicants: Initial Conditions: 74% power, MOL Xenon increasing @ 200 pcm/hr. Tumover:

1. FW-P 3 A, MDAFW pump is on clearance for motor replacement. Due to be returned next shift.

2. SA C-1B, station air compressor on clearance for compressor failure. Not due to be retumed for 2 days.

3. Rod controlis in automatic.

4. FW-P-4, the dedicated AFW pump, is on clearance for motor bearing replacement. Not due to be retumed for 2 days. Fire Watch required once per hour in AFW room.

5. Load reduction to 75% power has just been completed, using Load Follow procedure, lOM-52.B from 100%

at 12% per hour.

6. 7he boron concentration is 722 ppm. Control Bank D is at 175 steps. 'Ihe core age is 8000 MWD /MTU

7. Maintain current power level per System Operators request.

Event Malf. No. Event Event No. Type

• Description l

1 MALF C S/G tube leak of 30 GPD on the B S/G, requiring a plant shutdown. RCS3B N/R Power reduction to comply with prhnary to secondary leakage AOP 1.6.4. 2 Power reduction of at least 5%. 3 MALF 1 PT-446, Turbine first stage pressure transmitter fails high disabling the TUR18A steam dumps in the Tave load reject mode, and auto rod control. Crew

                   =600                        responds IAW IFM procedure to remove channel from sersice.

4 OVRD C Train B Rx trip breaker fails closed causing steam dumps to main in PO711a=1 the Tave load reject mode. PO711b=2 MALF MSS 7 i 5 MALF M B S/G tube leak. that tums into a 500 gpm SGTR during the power j RCS3B set reduction. ) to 500 gpm l 6 OVRD C S/G safety vahe on B S/G opens on Rx trip due to the loss of the steam CBSTSP dumps and fails open; this results in a ruptured / faulted S/G. Scenario 183=0 termination criteria - RCS cool down initiated IAW ECA-3.1. E 0.. . E-2... E-3. . . ECA-3.1. . I

      *       (N)ormal,        (R)eactivity, (I)nstrument,           (C)omponent,         (M)ajor Examiner:

ChiefExaminer l l Examiner Standards 23 of 26 Rev. 7, January 1993 BvPS -Rev 0

DUQUESNELIGHz COMPANY ' Nuclear Power Division Training Administrative Manual DRILL 97-6-1 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Initialize the simulator at IC-60 Reactor plant at 75% power, MOL. e Insert FILE SIMIC Insert FILE PWRSETUP Places equipment out of service per the initial conditions setup page.

   . Assign shift positions:

1 NSS Simulator Frozen until after shift ANSS turnover unless it needs to be on , RO momentarily for an alignment change. PO > STA Conduct shift turnover with oncoming Oncoming operators should complete the operators. required checklists and carry out a formal shift turnover. AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA When the shift turnoveris complete, place the simulator to RUN and Simulator running. Crew assumes control of the unit. commencc the drill. l 1 4AAAAAAAAAAAAAAAAAAAAtAAAAAAAAAA Allow crew to maintain power for 5 minutes, then proceed to Event 1. ,

DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual . DRILL 97-6-2 INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l EVENT #1 "B" SG 30 gpd leak (.02 gpm). Activate the following: Crew may note symptoms ofexcessive RCS leakage. l MAL RCS3B at .02 gpm l

           ...........................**. .                                                                                                                                                    l 1

A4-88 N-16 Rad Monitor Alarm. Crew references ARP A4-88 when N-16 monitor alarms. Crew references AOP-1.6.4 SG Tube Leakage for guidance. i i Crew dispatches operator or rad con to the As operator sent to N-16 rad monitor N-16 rad monitor to report status ofsteam l delay 3 minutes, then report that "B" SG has TRENDED to 30 gpd (.02 line rad levels. gpm)in thelast 20 minutes and has 4 stabilized.. EVENT #2 Crew determines that a plant shutdown within 5 hours is required. Unit shutdown i

                        ~                                                                                       .                                                   _

DUQUESNE LIGH'i COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-6-3 ,'l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPEUIED STUDENT RESPONSE l Plant shutdown commences at a rate ANSS directs crew to commence a normal specified by NSS/ANSS. shutdown in accordance with Procedure 1.52.4.B. ' ANSS notifies plant supervision and System Operator. NSS/ANSS informs Chemistry / Rad Con If crew requests FW-P-2 to be isolated from the B S/G, use LOA FWM 35 = 0 and directs thm to sample / survey to to shut MS-16 and LOA FWM 36 =l to determine tube leak location and size. open MS-17. Delta-I , Tave controlled within limits RO and PO coordinate power reduction. ! Normal power reduction to 65% When reactor power reaches ~ 65%, commence Event 3. EVENT # 3 Turbine First Stage Pressure transmitter fails high

DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-6-4 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l PT-MSS-446 FAILS HIGH

 ......**************************                                                                                                                 Crew notes alarms and informs ANSS that INSERT FILE DRL976A'                        PT-MS-446 indicates high. Tref                                                                       PT-MS-446 failed high by performing a indicates high in reference to Tave.                                                                 comparison with PT-MS-447.

MALFUNCTION TUR18A, SET = Possible Tave/fref alarm. No S/G 600. level alarms should be received if levcis on program. < PT-447 selected. ANSS directs operators to select PT-MS-447. ANSS references 1.24.4.IF Attachment 5 Instrument Failure Procedure to remove PT-446 from service. If requested, place the PT-446 bistables in test by inserting the Protection CH III , Rack 16 door ANSS direct I&C to place PT-446 following per MSP-26.01-I open. bistables in test and investigate PT-MS-BS-446B SPARE 446 failure. OVR P07029BS=1 LOA RCS 124=1 BS-446A-1 in test (P-13 ANSS references Tech. Spec. 3.3.1.1, for OVR P07029BS=0 Protection CHIII, Rack 16 door P-13 input from PT-446. closed.

p .n DUQUESNE LIGH'1 COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-6-5

;l INSTRUCTIONAL GUIDELINES           l PLANT STATUS OR RESPONSE l                  ' OBJECTIVE            l                             EXPECTED STUDENT RESPONSE                    l.

Ifrequested to start aux Oil Pump for Crew recommences load reduction if FW-P-1B use FWM 29=T. halted to respond to transmitter failure. EVENT #4 Insert FILE DRL97B as crew is red ci;gload. , i aaaaaaaaaaaaaaaaaaaaaaaaaaaa**** Train B reactor trip breaker remains File DRL976B contains: closed. Steam dumps remain in Load Use OVRD's Reject mode. SET P07111A =1 and P07111B=2 to fcil Train B Rx Trip breaker closed. Insert MALF MSS 7 to ensure Steam Ensures Steam dumps will not open., Dumps do not operate during the when the reactor trips.

  . followi2g transient..

R$ACGGAAAAAAAAAAAAAAAAAAAAAAAAAA I I I a t

Ms DUQUESNELIGH3 COMPANY l Nuclear Power Division Training Administrative Manual DRILL 97-6-6 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l [ 1 EVENT #5 "B" SG tube mpture (500 gpm) 4 Enter FILE DRL976C to increase the SG tubeleak to 500 gpm: ( RAMP SMLRCS3(2),.5,300,0 -  ; Report from the N16 Monitor that the Crew identifies the "B" S/G as mptured B S/G leak has increased to greater than and informs ANSS. 1000 gpd. S/G tube rupture of 500 gpm. RO reports increase in tube leak size based Pzr level and pressure decrease. on PRZR level and RCS pressure drop.  ; Charging flow increases l A4-71,72 rad alarms due to Air , Ejector RM-SV-100. , t EVENT #6 S/G Safety opens on B S/G following RX trip

DUQUESNE LIGIfl COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-6-7 'I l INSTRUCTIONAL GUIDELINES - l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l.

        .Upon reactor trip ACTIVATE FILE DRL976D                              "B" SG safety failed open.                                                                    ANSS directs RO to trip the reactor.

(set CBSTSP(183)=0) . Reactor trip, turbine trip, safety RO trips the reactor. i injection. RCS pressure drops, containment  ; pressure and temperature increase. RO and PO commenceimmediate actions ofE-0, ANSS references E-0 to verify  ! immediate actions. Reactor trip and bypass breakers RO verifies reactor trip. opens, neutron flux decreasing. Rod ~ bottomlightslit. Rod position [ indication at 0. i RO sounds standby alarm. ,

                                                                                                                                                                 ~

Depress reheat controller, reset push- PO ensures reheat steam isolation.  ! l button. Reheat flow control and block l t valves closed. I s

DUQUESNELIGITA COMPANY Nuclear Power Division l Training Administrative Manual DRILL 97-6-8 j l: INSTRUCTIONAL GUIDELINES 'l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECIED STUDENT RESPONSE l Main generator output breakers open. PO verifies generator trip. i Exciter circuit breaker open.

                                                                                                                                                                                                    ~

AE and DF busses energized. PO verifies AE and DF busses energized. l i Any SI annunciator. SI actuation RO checksif SIis actuated. '! status lights. Immediate operator actions complete. EDGs running. PO verifies EDGs running. [ t All red marked SIS valveindicating RO/PO verify SI system status. l lights lit. l Two HHSI pumps running.  ; FI-SI-943 indicates flow. [ ! LHSI pumps running. [ FW-P-3B running. PO verifies AFW status.  ! FW-P-2 running. MOV-FW-15) A through F open.  : RPRW pumps running. RO verifies river water system in service. CCR HX pressure > 20 psig.  ; - All indicating lights with orange marks RO/PO verify CIA.  !

lit.

All indicating lights with green marks RO/PO verify FWL [ t lit.

                                                                                                                                                                                                                                                                                                         +

i

                                   . ~ - . . _ - - - . _ _ . . . _ _ _ _ _ _ _ _ _ _ _ - - _ -

_ _ _ . - . _ _ _ .-___._____-_-_-_-__-_?

l DUQUESNE LIGIf1 COMPANY Nuclear Power Division Training Administrative Manual

  - DRILL 97-6-9.

l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l l All indicating lights with yellow marks RO/PO verify MSLI. i lit. , CIB and containment sprav not RO verifies CIB and containment spray required. not required.

   ~ An Outside Area Operator, notify the   CCR pumps mnning.                                              RO verifies CCR status.

Control Room that a safety valve on "B" Main Steam Line is open and +

blowing steam. SR detector selector switches - RO verifies SR detector HV selector normal. switches in normal. AFW flow > 325 gpm. PO <;ddes AFW flow greater than 325 gpm. StationInstrument AirHeader PO verifies station instrument rur header i I Pressure > 100 psig. pressure > 100 psig. EVENT #6 Tavg trending down below 547 F, RO verifies RCS Tavg stable at or f steam dump shut, AFW flow reduced. trending to 547 F, reduce AFW flow to  :

   "B" S/G safety failed open (DRL8C).      Steam flow indicated on "B" S/G.                               325 gpm.

t All yellow marked SLI valve indicators Crew performs a SLI due to RCS C/D. lit.  ; i i 1

     . . .       - , - . .             .                         . ~,             .                .   .     . - _ .        ~ --    . , _ _ _

                        -                                                                                                  .                                                                                                               2                                                      ;

DUQUESNE LIGHi COMPANY i: Nuclear Power Division , Training Administrative Manual

DRILL 97-6 ,

-l             INSTRUCTIONAL GUIDELINES                        l PLANT STATUS OR RESPONSE l                                          OBJECTIVE           l      EXPECTED STUDENT RESPONSE' -l ANSS direcs personnel to perform                                                                                                    ;

emergency safety function checklist when - E available. r PORVs closed. RO checks PZR PORVs, safeties and Safeties closed. spray valves. i Spray valves at zero demand. , Power available to PORV MOVs.

• PORV MOVs open with associated i PORVs in Auto.

RCPs running. RO checks if RCPs should be stopped. . RCS/SG D/P > 150 psid. . CCR flow normal.

                                                                 "B" SG is faulted as indicated by                                                           PO checks if SGs are faulted.

pressure difference between "B" SG coinpared to "A" and "C" SGs. . Crew transitions to E-2. ANSS exits E-0 at Step 22 and enters E-2, , and informs control room. j ANSS directs STA to monitor status trees. 8 Control room dampers shut. Timers "O initiates CREBAPS, and verifies mnning, control room pressurizing. system activated. s _ _ . _ . _.._m..--.;._ m._m_____._..mm._.__.=.m.____ _ _ _ _ _ __- 2..___. - - . ~ _ _ _-- u -_--.n - - - - - _ . - _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ . _ _ _ _ _ . _ _ . _ .

DUQUESNE LIGH'1 COMPANY Nuclear Power Division Training AdministrativeManual

  ~ DRILL 97-6-11                                                                                                                                                                                                                                                                                                                           ,

l INSTRUCTIONAL GUIDELINES l PLANT STA1US OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l t When requested as U-2 operator, report 2HVC* MOD 201 A-D closed. PO verifies CREBAPS actuated in U-2 by  : 2HVC* MOD 201 A-D closed and 2HVC* MOD 204A,B closed. requesting U-2 CREBAPS status.- 2HVC* MOD 204A,B closed. Valve indicators with yellow marks lit. Crew verifies steam line isolation.

                                                                          "A" and "C" SG pressures are stable.
                                                                         "A" and "C" SG pressure stable.                                                                                                                                                                PO checks for any non-faulted SG.

t "B" SG pressure dropping PO identifies "B" SG as faulted. [ uncontrollably. . FCV-FW-488 closed. PO closes / verifies "B" MFRV closed. i FCV-FW-489 closed. PO closes / verifies "B" BPFRV closed. MOV-FW-151C and D closed. PO closes MOV-FW-151C and D. Use LOAs PO directs operator to close MS-16 and to FWM35 =0 to close MS-16 and open MS-17 [ FWM36=1 to open MS-17. Report valves status to control room l WRlevelincreasing slowly without "B" SG level rising in an uncontrolled Crew checks if SG tubes are intact. feedwater flow. manner. 4

                                                                                                                                                                                                                                                                                                                                                                 ...w   P DUQUESNE LIGift COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-6-12

l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l Crew transitions to E-3. ANSS exits E-2, enters E-3 and informs ,

control room. CREBAPS actuated. ANSS directs operators to verify CREBAPS actuated. , All RCPs running. RO checks if RCPs should be stopped, CCR flow, RCS/SG D/P > 150 psig. does not stop RCPs. IDA-P-4A and B stopped. RO resets SI, CIA, and ANSS initiates IDG-P-I A and IB PTL. secondary side sampling. ICV-P-1 A and IB PTL. l TV-IDG-109Al and A2 shut.  ; Reset SI(both trains).  ! Reset CIA (both trains).  : Open TV-ISS-117A,B, and C. Open TV-ICC-134-1,134-2, _ 134-3,133-2. Align AUX Steam from U-2 using LOA Crew dispatches Operator to realign AUX 42=1. Blowdown Sample Sink drain from RPRW to PAB North Sump. t t

-                          " ' ' ' "         - - - -                                                                                       -.__..____.._.._t___m_             _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ , _ _ _ _ _      _ _ , _ _ _ _ _ _                          _,     _   ___                           _ _ _ _ _ _

DUQUESNE LIGIli COMPANY Nuclear Power Division Training Administrative Manual-DRILL 97-6-13 [ l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l ooeseos..........e..eet......... As PAB Operator, when requested to Crew dispatches Operator to open SOV-open SOV-SS-117 insert: SS-117 SG Sample Line Cnmt Iso Viv " Interlock. LOA AUX 199 = T then report actions to the Control Room. oosee ........................... Crew Opens TV-SS-117A, B, & C, SG Sample Outside Cnmt. Iso. Valves. l ANSS identifies "B" S/G as the mptured S/G, based on operator reports. ,

                                                                                  "B" SG Atmospheric Dump Valve in                                                                                                                                                                                                  ANSS directs operators to isolate flow manual and verified closed.                                                                                                                                                                                                       from the "B" S/G. (Already isolated)

RHR valve closed. , MS-16 NSA shut. TV-MS-111B shut. ,

                                                                                 "B" SG main steam trip, bypass and non-return valves shut.                                                                                                                                                                                                                                                                                                        ,

AFW secured to B SG. PO checks ruptured SGWL verifies AFW flow to "B" SG secured.

                     .__    . _ =                                                                                                                -              - - _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ - - _ - _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - - _ - - _ - _ _ _ _ _ _ - - _ _                                                                            _ _ - _ _ _ - - _ _ _ _ _ _ _ - _ - _

DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-6-14 l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l PORVs available. RO checks PORVs and block valves, power available and closed.

                                                                   "B" SG isolated previously.                                                        PO checks if SGs are not faulted.

Ir tact SGs > 5% NR level. PO checks intact SG level > 5% h%, maintains AFW flow > 325 gpm. Station Instrument Air Header PO verifies station instrument air header Pressure > 100 psig. pressure > 100 psig. CTMT vents and drains isolated. ANSS verifies CTMT vents and drains system isolated. SI reset. ANSS verifies SI reset. CIA reset. ANSS verifies CIA and CIB reset. CIB reset. 4160V stub busses - ENERGIZED. PO verifies stub busses energized. 480V stub busses - ENERGIZED.

DUQUESNE LIGb a COMPANY Nuclear Power Division Training Administrative Manual

  . DRILL 97-6   l    INSTRUCTIONAL GUIDELINES    l PLANT STATUS OR RESPONSE l                                                        OBJECTIVE                 l     EXPECTED STUDENT RESPON.SE                        l CNMT instrument air compressors:                                                                               PO verifies CTMT instrument air-one mnning, one in auto.                                                                                       AVAILABLE CTMT instrument air pressure greater than 85 psig                                                                                                                                                                              ,

A6-110 - NOT LIT. AE and DF busses energized by offsite PO verifies emergency AC busses t power. energized by offsite power, RCS pressure greater than 250 psig. RO checks if LHSI pumps should be RCS pressure - stable or increasing. stopped. Stop LHSI pump SI-P-1 A&lB and place in auto.  ; SG pressure > 190 psig. PO verifies ruptured SG pressure greater than 190 psig. TarBet temperature detennined based ANSS determines target temperature. on ruptured SG pressure. .l STA trends cooldown rate. Condenser steam dumps available. Crew initiates RCS cooldown at maximum rate to the target temperature. RCS pressure < 1950 psig. RO blocks steamline SI when RCS pressure is below 1950 psig. Average of the 5 highest TCs at target Crew stops RCS cooldown at target temperature. temperature.

rW y, DUQUESNE LIGHi COMPANY Nuclear Power Division Training Administrative Manual DRILL 97-6-16 l - INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l EXPECTED STUDENT RESPONSE l "B" SG pressure < 200 psi above Crew checks ruptured SG pressure < 200 intact SGs. psig above intact SGs. Crew transitions to ECA-3.1. ANSS transitions to ECA-3.1 based on above step. RWST > 19 feet. RO checks RWST > 19 feet. Previously performed. RO verifies CNMT vents and Drains Isol., SI, CIA and CIB reset. Previously performed. PO verifies stub busses energized. Previously performed. PO verifies CNMT instrument air available. All busses energized. PO verifies all AC busses - energized by , offsite power. CIB has not actuated. ~ RO checks if any Quench Spray Pumps , mnning. RCS pressure greater than 250 psig. RO checks ifLHSI pumps should be LHSI pumps previously stopped. stopped.

                                                                  "B" SG steam and feed flow isolated                                                  PO checks ruptured SG NR level and previously.                                                                          verifies "B" SG isolated.

V DUQUESNE LIGhi COMPANY Nuclear Power Division  : Training Administrative Manual - [ DRILL 97-6 _l INSTRUCTIONAL GUIDELINES l PLANT STATUS OR RESPONSE l OBJECTIVE l- EXPECTED STUDENT RESPONSE l Aux Building and safeguards radiation ANSS initiate evaluation ofplant status.

                                                                                   - consistent with pre-event values.                                                                                                                                                                                      :

Obtain samples as listed in Step 9.b.

                                                                                   "B" S/G previously identified and                                                                                                                          PO checks ifall SGs are faulted.

isolated. "A" and "C" intact. Narrow range level- greater than 5%. PO checks intact SG levels. , StationInstrument AirHeader PO verifies station instrument air header . Pressure > 100 psig. pressure > 100 psig. Do not exceed 100 F/ hour cooldown PO commences cooldown using "A" and in RCS cold leg. "C" S/Gs atmospheric relief's, at < 100 F per hour. Terminate drill when c' oldown staned in ECA-3.1. , Collect and review logs after allowing Operator logs should be accurate, clear crew time to complete. and concise. , l Erase VOND marks. t [

l \ RTL #A5.640E DUQUESNE LIGHT COMPANY l Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE l PROGRAM TITLE: Licensed Operator Training L SUBDIVISION: On-the-Job Training i i

OJT CHECKLIST /JPM TITLE

Perform RHR Pump Performance Test I- -

JPM NO.: 1CR-132 , COMPUTER CODE: N/A 1 i I l u Revision No. Date Revision Nc Date  ! I 8 4 h l PREPARED BY: DATE: I l l .. i APPROVED FOR , JMPLEMENTATION: DATE:__

                                  -Director, Operations Training, or Designee 1

I , Revision 9

l RTL #A5.640E DUQUESNE LIGHT COMPANY j Nuclear Power Division Training Administrative Manual l. LESSON PLAN AND OJT REVISION APPROVAL SHEET-DOCUMENT TITLE: 1CR-132, Perform RHR Pumo Performance Test Revision Acoroval No, Brief Description Revised by: Signature Date i b L l-2 f b; $ Revision 9

l BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET

      !   JPM Number: 1CR-132                               Rev: 0                System #: 005                                           Faulted: O         i JPM

Title:

Perform RHR Pump Performance Test ' l l K/A

Reference:

005 000 A4.01 3.6/3.4 Task ID #: 301 002 0601 { JPM Designation: NO O RO tl SRO j JPM Application: X NRC 3 Initial Exam Training i i Evaluation Method LOCATION TYPE ) x Perform Plant Site O Training Simulate X Simulator O Annual Requal. Exam . Classroom O OJT X Initial Operator Exam j Administered By: O Other: 5 BV-T ! O NRC Other: i Evaluation Results i Performer: Name: Employee No: Results SAT Time (minutes) ! C UNSAT* Allotted: 15 Actual: Time Critical: Yes X No j

• Comments (Required for UNSAT Evaluation) :

i j Evaluation Results check here if same as above , Observer 1: Name: Employee No: Observer 2: Name ___ Employee No: j Observer 3: Name Employee No: j Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 3 C j Employee No: l Question #2 5 C_ ! Employee No: l

• Comments (Required for UNSAT Evaluation) :

I 4 I l Evaluator (Print): _. Organization: 1 j Evaluator Signature Date: i~ Revision 9

RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASLTE CANDIDATE DIRECTION SHEET 5 THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

l l Task: Perform RHR Pump Performance Test l l l INITIAL CONDITIONS: The plant is operating in Mode 5 with the 1B RHR pump in service to maintain { constant RCS temperature. Preparations for the performance of 10ST-10.1, Residual Heat Removal Pump Performance Test, have been made (Part A is complete). TASK STAN.: Residual Heat Removal Pump Performance Test performed in accordance with 10ST-10.1.

                                                                        )

INIT. CUE: Your supervisor directs you to perform 10ST-10.1, i Residual Heat Removal Pump Performance Test on the ' 1A RHR Pump. 1 At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. l After completing the task, reread the Task Standard. 1 After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. Revision 9

    . . . .  .   . . . _ .       _ _ _ _ _ . . _ _ . . _ _ .       _ _ _ . . . . _ . _ _ _ ~ _ _ . . . _ . _ . _ . _ . _ . _ . . . _ _      . . _

1 l 1 ! RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE

          !.                                                 EVALUATOR DIRECTION SHEET JPM NUMBER:                            1CR-132 JPM TITLE

• Perform RHR Pump Performance Test RECOMMENDED r.

STARTING LOCATION: CONTROL ROOM L j L  : L i ! DIRECTIONS: You are to perform the task perform RHR Pump. Performance Test. I

                    'INIT. CONDITIONS:                       The plant is operating in Mode 5 with the l

1B RHR pump in service to maintain constant l RCS temperature. Preparations for the ' l performance of 10ST-10.1, Residual Heat

i. Removal Pump Performance Test, have been made (Part A.is complete).

l TASK STAN.: Residual Heat Removal Pump Performance Test l performed in accordance with 10ST-10.1. INIT. CUE: Your supervisor directs you to perform i 10ST-10.1, Residual Heat Removal Pump l Performance Test on the 1A RHR Pump,

REFERENCES:

10ST-10.1, Issue 4, Rev. 9 3 i TOOLS: NONE HANDOUT: 10ST-10.1, Residual Heat Removal Pump Performance Test i e E

         },

I' , Revision 9

RTL #A5.635.J t r . NUMBER TITLE 1CR-132 Perform RHR Pump Performance Test. l STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) 1 1 Evaluator Setuo: -Initialize Simulator to IC-32. Remove magnetic ' ' RHR ' ' tags from control board. l START TIME: I l Candidate locates and reviews l 10ST-10.1, Residual Heat Removal Pump Performance Test. EVALUATOR CUE: Provide candidate with prepared copy of  ; i 10ST-10.1 (Section A signoff l { l complete). I l l l l l i e 1 i n Page 1 of 10 Revision: 0

RTL #A5.635.J i NUMBER TITLE 1CR-132 Perform RHR Pump Performance Test. STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

1. Determine if pump 1. Candidate determines venting is required. if pump venting is required.

EVALUATOR CUE: The 1A RHR pump has been run in the last ten hours, the pump has been vented. COMMENTS:

2. Install a current 2. Candidate directs calibrated test gauge. local operator install test gauge by performing Step B.2 of 10ST-10.1 EVALUATOR CUE: The test gauge has been installed on the 1A RHR pump COMMENTS:

l Page 2 of 10 Revision: 0

RTL #A5.635.J l 1 NUMBER TITLE ' l 1CR-132 Perform RHR Pump Performance Test. [ l l l I 1 STEP STANDARD  ! (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) , 1 1 l EVALUATOR CUE: The test gauge has been installed on the 1A RHR pump

3. Record pump suction 3. Candidate directs l pressure. local operator to I record pump suction pressure on Data l

Sheets 1 and 4. EVALUATOR CUE: Local operator i reports suction pressure has been recorded (at 270 psig). l l l COMMENTS: l l I Page 3 of 10 Revision: 0 i

1 RTL #A5.635.J 1 i 1 NUMBER TITLE l 1CR-132 Perform RHR Pump Performance Test. l 1 l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 4.C Start the 1A RHR pump. 4.1.C Candidate places the control switch for [1RH-P-1A] in the start position. 4.2 Candidate verifies that [1RH-P-1A] is running. COMMENTS: 5.C Stop the 1B RHR pump. 5.1.C Candidate places the control switch for [1RH-P-1B] in the stop position. l 5.2 Candidate verifies that (1RH-P-1B] is stopped. 1 ( COMMENTS: Page 4 of 10 Revision: 0

   . , .. .-      - .   . .     .- . . .. ~ . - - . . - ,                 - . . . . . -         _ . _ . - ... - ._.._      ..-_ -   . .

RTL #AS.635.J { ~ NUMBER TITLE 1CR-132 Perform RHR Pump Performance Test. I l J STEP STANDARD (Indicate "S" for Sat. or-"U" ("C" denotes critical step) for Unsat.)

6. Obtain RHR flow of 4000 6.1 Candidates adjusts gpm and stable RCS [MOV-1RH-758] as temperature, required to maintain RCS temperature.

EVALUATOR CUE: Your supervisor

directs you to maintain RCS temperature stable.

i 6.2. Candidates adjusts [MOV-1RH-605) as l. required to maintain flow rate of 3,950 -

                                                                                        -4,050 gptc.

COMMENTS: l i ( 1 i t l l Page 5 of 10 Revision: 0

RTL #AS.635.J l l

   !                                                                          l NUMBER                TITLE 1CR-132               Perform RHR Pump Performan'ce Test.

l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

7. Verify SPDS Computer 7. Candidate verifies I Point for 1A RHR pump. SPDS for (1RH-P-1Al indicates ON.

COMMENTS:

8. Verify SPDS Computer 8. Candidate verifies Point for 1B RHR pump. SPDS for (1RH-P-1B]

indicates OFF. l- ! COMMENTS: l i , 1 ? l l l l a , Page 6 of 10 Revision: 0

l l l RTL #AS.635.J l l l NUMBER TITLE 1CR-132 Perform RHR Pump Performance Test. I l STEP STANDARD l (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) I l

9. Check pump discharge 9. Candidate directs check valve for local operator to chattering. check (1RH-3] for chattering. I EVALUATOR CUE: Local operator reports the (1RH-3] is not chattering.

l COMMENTS: i

10. Record pump and motor 10. Candidate directs amp Vibrations. local operator to record motor and pump i

vibration on Data Sheets 2 and 3. ! EVALUATOR CUE: Local operator ! reports that vibration data j has been recorded. l COMMENTS: Page 7 of 10 Revision: 0

l l I l RTL #AS.635.J NUMBER TITLE 1CR-132 Perform RHR Pump Performance Test. l 1 STEP STANDARD I (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.)  ; i I i

11. Record pump suction, 11 Candidate directs discharge and local operator to differential pressure. record pump suction, discharge and differential pressure ,

on Data sheet 1. I EVALUATOR CUE: Local operator reports that pressure data has l l been recorded. j COMMENTS: l I 1 Page 8 of 10 Revision: 0

i RTL #AS.635.J l NUMBER TITLE 1CR-132 Perform RHR Pump Performance Test. 1 STEP STANDARD l (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 12.C Verify pump 12.C Candidate verifies differential pressure differential pressure in is within acceptable acceptable range for the range. number of RCPs running. i l EVALUATOR CUE: Provide j operator with prepared Data 1 Sheet 1. I 1 COMMENTS: l 13.C Full Stroke [1RH-3). 13.C Candidate adjusts [MOV-1RH-605] to obtain flow rate of 4100 = 4150 gpm. EVALUATOR Note: A flow rate of 4100 - 4200 gpm is acceptable. i COMMENTS: Page 9 of 10 Revision: 0

l

                                                                               )

i RTL #A5.635.J I. - NUMBER TITLE 1CR-132 Perform RHR Pump Performance Test. l 1 l l I STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) { 14.C Obtain RHR flow of 4000 14.C Candidate adjusts [MOV-gym. 1RH-605] to obtain flow rate of 3950 = 4050 gpm. EVALUATOR Note: A flow rate of 3900 - 4100 gpm is acceptable. COMMENTS: 1 1 1

15. Inform supervisor that 15. Candidate informs pump test is complete, supervisor that pump test is complete.

COMMENTS: STOP TIME: Page 10 of 10 Revision: 0 L

BEAVER VALLEY JOB PERFORMANCE MEASURE 5

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 1 The RHR inlet and outlet valve interlocks are normally defeated when the system is in service. List two methods of overpressure protection for the RHR piping when the interlocks for these valves are defeated?

I a 4 l

                                                                                         ]

ICR-132

BEAVER VALLEY JOB PERFORMANCE MEASURE i -

            - JPM QUESTION # 1 4

The RHR inlet and outlet valve interlocks are normally defeated when the system is in

                                                                                              ~

service. List two methods of overpressure protection for the RHR piping when the interlocks for these valves are defeated? J 005 000 K4.07 3.2/3.5 Obj: LP-SQS-10.1 ELO-8

Ref: lOM-10.4.A, Issue 4, Revision 9 ANSWER:

1 Overpressure protection is provided by the Overpressure Protection System that is administratively required to be in service when RHR is in service and by a relief valve on , the RHR discharge piping. Comments: , i 1 4 4 a e i 1 ICR-132

1 BEAVER VALLEY JOB PERFORMANCE MEASURE j

• THIS SHEET TO BE GIVEN TO CANDIDATE
• j

! -JPM QUESTION # 2 What would be the heatup rate of the RCS if RHR system flow were to be lost 120 hours ! following reactor shutdown? (Assume the RCS is intact with normal pressurizer level.)

1 I

l l 1CR-132

BEAVER VALLEY JOB PERFORMANCE MEASURE f JPM QUESTION # 2 What would be the heatup rate of the RCS if RHR system flow were to be lost 120 hours following reactor shutdown? (Assume the RCS is intact with normal pressurizer level.) 005 000 A1.013.5/3.6 Obj: LP-SQS-10.1, ELO - 4 Ref: lOM-53C.4.10.1, Issue 3 A, Revision 5 ANSWER 1.1 - 1.2 degrees / min l Comments: i I i i ICR-132

  . . . _. . _ . . _ _      __._-....._.-.m__             . . . . _ - _ .

__.-.>-..._..m 4 t 3 Record Type #A9.3308 { l( - ! DUQUESNE LIGHT COMPANY l Beaver Valley Power Station Unit 1 I 10ST-10.1 l l ' Residual Heat Removal Pump Performance Test i. Issue 4 Revision 9 l. l Date Pagesissued Eftective Date Prepared by J.~ P. Keegan 10/02/96 1 through 33 NOV 2 01996 Date validated by Date Reviewed by F. Schaffner 10/07/96 J.P.Keegan 10/31/96 l

• Date Approved by Date

! OSC Meeting No. ^' BV-OSC-43-96 10/23/96 ff,

                                                                                /

i

                                                  ~
                                                                                           'OR TRAtygyg 94(,

l L r c_omrROLUED ,

d 4 . j Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System Issue 4 Revision 9 j Operating Surveillance Test - Page li l( Residual Heat Removal Pump Performance Test i Table of Contents

1. PURPOSE . . . . . .... . .. ... .... . .. 3

11. DISCUSSION .. ..... . . .. .............. . . .. 3 Ill. ACCEPTANCE CRITERIA .. . ..... ........ ... . ........ 3 l IV. TEST EQUlPMENT 4 f .. . ...... .. . ... ... . .. .. .. ..

V. PRECAUTIONS AND LIMITATIONS . . . . .. ... 4 i l i VI. INITI AL CONDITIONS . .

                                                                                                     .       .       .                 . .                                         4
                                                                                                                                                                                      )

l a- . Vll. INSTRUCTIONS .. . .. ... .. . ... . .. ..... . 7 . \ l Vill. DATA SHEETS, TABLES, FIGURES and ATTACHMENTS . . 24 l e l DATA SHEET 1 . . . . . . . 25 ) i DATA SHEET 2 .... .. . . ... .. . .. . . 26 '

    .           DATA SHEET 3            .. .              .                      ...... .. . .                               ...              .            .                      27 t

DATA SHEET 4 .. .. .. . ........ ....... . . .. .... . 28 1 DATA SHEET 5 ........ ... .. .... .................29 1 i DATA SHEET 6 ... . . . ............. ...... . . 30 I i Figure 1 .. ........... ...... . . . 31 j . ..... . . 4

IX. REFERENCES ... . . ... . .......... . . . . 32 1

4

                                                                                              '0R TRAINING ogy, i

) d

_ . .- - . . _ _ _ - _ - . _ . .. .. ... .-. . - _ _ _ = - _ _ .l . Beaver Valley Power Station Unit 1 10ST-10.1 I Residual Heat Removal System issue 4 Revision 9 l 1 Operating Surveillance Test - Page 1 of 33 i Residual Heat Removal Pump Performance Test Frequency: Q' Surveillance Requirements: 4.4.1.3.1, 4.9.8.2, 4.0.5, 4.3.3.5 Required for Mode (s): 5,6 Date / Time Completed: / l 4 Performed in Mode (s): 4,5 Total Manhours: 4 TEST RESULTS: (Completed by Performer) PERFORMED BY: Name (Print) Initial or N/N i O Test Completed SATISFACTORY ) ~ O Problems Encountered (See Problem Sheet)  ! O Unscheduled / partial OST (explain)  ! I i i l Reviewer Signature /Date STA Review / NSS Approval /  ; COMMENTS: (include Date and initials) O Comments continued on Problem Sheet "When the Reactor Coolant System is S 350F and $ 430 psig.10ST-10.1 shall be performed within 24 hours following the time the RHR pump (s) is used to satisfy Tech. j Spec. 3.4.1.3, 3.9.8.1 or 3.9.8.2.

                                                                                                      .if               OND CONTROLLED

1 Beaver Valley Power Station Unit i 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 { Operating Surveillance Test Page 2 of 33 Residual Heat Removal Pump Performance Test (- OST PROBLEM SHEET See Page and Step No. for problem description. See below for corrective action, eg: MWR 4 No., OMCN No., OMCR or Database change written or other. PAGE NO. STEP NO. DESCRIBE CORRECTIVE ACTION INITIALS DATE l 1 s 3 )

)

i i ( 't

'r COR TRAIN'NG ONLY                         (

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 { Operating Surveillance Test - Page 3 of 33 Residual Heat Removal Pump Performance Test _ _ _

l. PURPOSE This test will verify:

A. That no degradation of the Residual Heat Removal pumps has occurred and that they l I are capable of performing cs designed. B. That [1RH-P-1 A and 1B] can be operated from the SDP. l C. That the SPDS computer points accurately show pump status,

11. DISC SSION A. This test is accomplished by measuring the required parameters while the residual l heat removal system is being operated under normal conditions. l

• l B. Verifying that the pump meets the requirements of ASME Section XI, subsection 1WP-3000, satisfies both the forward and reverse flow exercise requirements for check valves [1RH-3 and 4] as required by ASME XI subsection 1WV-3520.

ll1. ACCEPTANCE CRITERIA

                                ~
       .            A. Each pu'mp, operates within the limits of the ASME IST Program (T.S. 4.0.5) as                   l l

specified in'the Data Sheets for: ' '- 1. Pump and Motor Vibration (Data Sheets 2 & 3. Data Sheets S & 6). l

2. Flow (Q) (Data Sheet 1 Data Sheet 4).

3. Differential Pressure (A P) (Data Sheet 1, Data Sheet 4).

                                                                                                                   !    l I

1 B. Once per year, pumps [1RH-P-1 A] and [1RH-P-1B] start from the Shutdown Panel. ([1RH-P-1 A], Step E; [1RH-P-1B], Step F). C. Dual function check valves [1RH-3 and 4] operate within the requirements of the ASME IST Program (T.S. 4.0.5) as follows:

1. [1RH-3], " A" PP Disch Chk:

a. Forward flow (Step B.14)

b. Reverse flow (if Ill.A.3 above is met; Data Sheet 4)

2. [1RH-4], "B" PP Disch Chk:

a. Forward flow (Step C.14)

b. Reverse flow (If lil.A.3 above is met; Data Sheet 2)

D. SPDS computer points listed in this procedure agree with actual pump status, or an MWR has been initiated.(c.o i* E. Each of the measured RHR outlet temperatures agree'within 20F of each other. (T. S. t 3.3.3.5) (Step D.2)

                                                     ~

c0R TRAINRIG ONI.Y

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 k Operating Surveillance Test - Page 4 of 33 Residual Heat Removal Pump Performance Test (.. IV. TEST EQUIPMENT A. RBC Key. B. Current, calibrate.d pressure gauge (0-600 psig maximum, not to exceed 3 times existing RCS p' essure) OR a current, calibrated A P gauge 0-150 psid or 0 200 psid range. C. An extra ce:ibrated pressure gauge (if available). D. Vent rige comprised of a Health Physics approved bottle equippe'd with two filters for l [1RH-r-1 A and 1B], if required. E. A calibrated, contact pyrometer for the channel check and possibly bearing temperatures. F. A portable vibration meter and magnetic probe, CSI or equivalent. l 2 V. PRECAUTIONS AND LIMITATIONS A. Monitor all pump starts and trip the pump if any unusual vibrations or noises exist. B. Performance of this OST could result in inadvertent mode change due to RCS heatup or cooldown. j C. All Reactor Coolant Pumps and Residual Heat Removal Pumps may be de-energized ( for up to 1 hour in Modes 4 and 5, provided both of the following conditions are met (T.S. 3.4.1.3):

1. No operations are p'ermitted that would cause dilution of the Reactor Coolant System Boron Concentration,

2. Core outlet temperature is maintained at least 10F below s'aturation temperature.

VI. INITIAL CONDITIONS A. Plant Status Chanaes:

1. Made l@PER ABLE (Tech. Spec. Items)

NONE

2. Removed From Service (Non-Tech. Snee.)

NONE

3. Placed in Failed Condition (Tech. Spec. Items)

NONE

4. Alionments Affected 1

a. Residual heat removal system will be limited to one pump in operation while 1

data is being recorded. .g~

5. Special Considerations C0R TRAIN!NG OnlLY

a. A pressure gauge.will be connected to [1RH-200] or a A P gauge will be connected to [1RH-200] and [1RH-213].

        -  .                              .    .-- ~ ~ _ _              - . -       _ _ . -     . - ~       _ . - . - .        .-

o . .4

                                                                                                                                   ~

Beaver Valley Power Station Unit i 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 i- .; Operating Surveillance Test Page 5 oi 33 Residual Heat Removal Pump Performance Test

b. If required, vent rigs will be connected to [1RH-203 and 204].

B. NSSIANSS Sian-on:

                                                                                                                                     ]

Note: If this is the first test performance during a Refueling Outage, then 10ST-10.5

                        " Leak Test [MOV-1RH-700, and 701]" should be done prior to doing this OST.

1. If required,10ST-10.5, " Leak Test [MOV-1RH-700 and 701]" has been comp!sted. l

2. RCS is s 350F and s 430 psig.

3. RCS loop operability requirements are satisfied for the current mode.

4. 10M-10.4.A " Residual Heat Removal System Startup (Plant Cooldown)," is complete.

5. In addition to the operators, the following personnel are available for containment entry to support this test:

a. An MCR for gauge installation.

b. A radiation technician.

6. NSS/ANSS verifies the following:

('

• Section VI.A, Plant Status Changes, has been reviewed.

i

• Requirements of Section VI.B. NSS/ANSS Sign-on have been verified.
• Performance of this procedure is authorized.

I DATE: TIME: CURRENT PLANT MODE: NSS/ANSS COMMENTS: NSS / ANSS Signature C. Reactor Operator Slan-on

1. Reactor Operator perform the following:

• Acknowledge procedure performance.

Reactor Operator Signature D. Procedure Performer Initial Conditions

1. RHR System is operating in accordance with 10M-10.4.A., ' Residual Heat Removal j

System Startup (Plant Cooldown)'.

• I Date

l. i 4

Beaver Valley Power Station Unit 1 10ST-10.1 l Residual Heat Removal System issue 4 Revision 9 i Operating Surveillance Test _ Page 6 of 33 1 Residual Heat Removal Pump Performance Test (

2. The Operator (s) performing this test has reviewed this procedure.

I 1 initial I. Date i / Initial / Date + l / Initial / Date l 1 I 1

,                                                                                                                                   l i

( , 4 1 50R TRAIN!NG ONLY (

1 Beaver Valley Power Station Unit 1 Il 10ST-10.1 l Residual Heat Removal System issue 4 Revision 9 Operating Surveillance Test Page 7 of 33 ( Residual Heat Removal Pump Performance Test Vll. INSTRUCTIONS  : 1

           ; Note: Performance of Steps B, C, D, E and F, can be done in any sequence.                              l A. Test Preparation

1. Previous Performance Information.

a. Record the last date that the RHR pumps were started from the shutdown panel (SDP) as follows:

1) Enter the date in instruction Step E.1 for the last time [1RH-P-1 A] was started from the SDP by this OST.

l l InitialI Date

                           - 2) Enter the date in instruction Step F.1 for the last time [1RH-P-18] was started from the SDP by this OST.

I initial / Date

  -               2. Sign out the following M&TE Equipment:                                                         l

( l

a. Portable vibration meter and magnetic probe (CSI or equivalent). Record ID i Numbers and Cal Due Dates below. l Meter I.D. No.

Meter Cat. Due Date / 1._ Probe I.D. No. Probe Cal. Due Date / l__ I initial / Date

b. Calibrated Contact pyrometer.

I initial / Date

3. Obtain the following for the performance of this test:

a. REO Key.

I C0R TRA!NDG 0&T "'"

b. Current, calibrated pressure gauge (0-600 psig maximum, not to exceed 3 times existing RCS pressure) OR a current, calibrated A P gauge 0-150 psid or 0-200 psid range.

I initial / Date

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System Issue 4 Revision 9 i Operating Surveillance Test - Page 8 of 33 Residual Heat Removal Pump Performance Test (

c. An extra calibrated pressure gauge (if available).

I initial / Date 1

4. Record the position of the following valves:

a. [MOV-1RH-605], Residual Heat Removal Hx Bypass FCV.

Record Position I initial I Date

b. [MOV-1RH-720A], Residual Heat Removal Return isol Viv.

Record Position I initial / Date

c. [MOV-1RH-7208], Residual Heat Removal Return isol Viv.

Record Position I  ! I Initial I Date (

d. [MOV-1RH-758], Residual Heat Removal Hx FCV.

Record Position I initial I Date 4 Record the number of RCPs running on Data Sheet 1 and Data Sheet 4. l l Initial I Date

   '                                                   C0R TR/M!NG ONLY

(

t

                                                                                                                          .i t                                                                                                                           .

i Beaver Valley Power Station Unit i 10ST-10.1 l* Residual Heat Removal System issue 4 Revision 9 7 Operating Surveillance Test Page 9 of 33 i Residual Heat Removal Pump, Performance Test l B. [1RH-P-1 Al. Residual Heat Removal 1 A Pump Performance Test Note: Venting [1RH-P-1 A] is required if any of the following conditions exists:

• This test is being run because unsuccessful results were obtained during the previous performance of this section of the OST.

                     * [1RH-P-1 A] does not show stable amps.
                     * [1RH-P-1 A] has not operated for at least 1/2 hour.

1. If required, vent [1RH-P-1 A] as follows: (Otherwise N/A).

CAUTION: DO NOT VENT THE RHR PUMP IF RHR TEMPERATURE 2: 200F AS INDICATED ON [TRB-1RH-604], (RED PEN - COOLER INLET). (VB-A)

a. Check closed [1RH-203], "A" PP Seal Ctr Vnt. (RH Platform).

I initial / Date

b. Remove the swagelock cap froin [1RH-203], " A" PP seal Clr Vnt. (RH Platform).

I initial / Date

c. Securely connect a vent rig comprised of a Health Physics approved bottle l equipped with two filters to [1RH-203].

I initial / Date

d. Throttle [1RH-203], " A" PP Seal Clr Vent, until a solid stream of water issues.

I initial / Date

e. Close [1RH-203] "A" PP Seal Clr Vent (1) /

Initial I Date (2) I Initial / Date l j f. Disconnect the vent rig and replace the swagelock cap on [1RH-203] unless l further venting is likely to be needed (N/A if vent rig left installed). I ( Initial / Date COR TRAIN!NG ONt.Y

l l Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 l Operating Surveillance Test Page 10 of 33 l l Residual Heat Removal Pump Performance Test (

2. Install, or verify installed, a current calibrated test gauge as follows:

i a. Notify the NSS that a pressure gauge will be installed at [1RH-200] OR between [1RH-200] and [1RH-213], as applicable. I initiali Date

b. Install a pressure gauge (0-600 psig maximum, not to exceed 3 times existing RCS pressure) at [1RH-200], [1RH-P-1 A] Suction Low Point Drn, (under RH Platform, above [11 A-C-1 A,1B]). l OR Connect the low pressure side of the A P gauge (0-150,OR O-200 psid) to

[1RH-200] and the high pressure side to [1RH-213], Pump Disch HPV, (RH l Platform). l (circle method used) (1) I initial / Date (2) I initial / Date

c. Open [1RH-200], [1RH-P-1 A] Suction Low Point Drain. (

I initial I Date

d. If [1RH-213], Pump Disch HPV is being used, Open [1RH-213]. (Otherwise N/A)

I initial / Date

3. Place [1RH-P-1 A] motor bearing temperatures on TREND, (Computer Addresses T0686A, T0687A).

I initial I Date

4. If either of the RHR pumps are not already running, Record the pump suction I

pressure (Pis) prior to pump start on Data Sheet 1 and Data Sheet 4. I I l Initial I Date S. Start, or verify running, [1RH-P-1 A], Residual Heat Removal 1 A Pump. i Initial I Date ..

6. Stop or verify shutdown [1RH-P-1B], Residual Heat Removal 1B Pump.

I C0R TRAIN!NG ONLY

   -         ..                          . -       . .        - -      - . . ~ .   . . .      - .    -    ..  .. .   .-

l l e l Beaver Va'.. y Power Station Unit 1 Residual Heat Removal System 10ST-10.1 s Operating Surveillance Test issue 4 Revision 9 ' l0 Page 11 of 33 ( Residual Heat Removal Pump Performance Test l 7 Obtain RHR Flow, a total RHR (BB-A), flow of 4000 gpm (3950 - 4050 gpm) as read on [Fi-1RH-60 as follows: a. Adjust [MOV-1RH-758], Residua,I Heat Removal Hx FCV, to establish cooldown or maintain RCS/RHR temperatures as desired. I initial / Date b. Adjust [MOV-1RH-605], Residual Heat Removat Hx Bypass FCV, as needed to maintain a flow rate of 4000 gpm. (3950-4050 gpm) I Initial / Date _ 8. Verify SPDS Computer Point for [1RH-P-1 A], RHR PP A Bkr by checking I [1RH-P-1 A] indicates ON (Screen 3RH1).

                                                                                                       /

Initial / Date 9. Verify SPDS Computer Point for [1RH-P-18], RHR PP B Bkr by checking [1RH-P-1B] indicates OFF (Screen 3RH1).

                                                                                                     /

Initial / Date 10. Monitor [1RH-3] "A" PP Disch Chk, for chattering.

                                                                                                    /

Initial / Date 11. Record [1RH-P-1 A] motor and pump Vibrations on Data Sheets 2 and 3. l

                                                                                                    /

Initial / Date

12. '

Record [1RH-P-1 A] flowrate (Q), discharge pressure (Pd) and suction (Pi). or differential pressure (A P,), on Data Sheet 1.

                                                                                                                 ]
                                                                                                    /

Initial / Date Note: If pump AP is in the acceptable range, [1RH-4] is seated properly. j 13. ' Consult the Acceptance Criteria for acceptable performance using the AP criteria for the number of RCPs running. If pump AP is not in the acceptable range, perform the following (N/A if not required):

a. Vent the pump by performing Step B.1

                                                                                                   /-

l COR TRAINmG OnlLY

1 10ST-10.1 Unit 1 -

                                                                                                                        ~

Beaver Valley Power Station Issue 4 Revision 9 ~ l Residual Heat Removal System Page 12 of 33 l 1 l Operating Surveillance Test l (. ! Residual Heat Removal Pump Performance Test

b. Repeat Step B.7 i  ;

Initial I Date l l

c. Repeat Step B.12 I )

Initial / Date

d. If after reventing, the pump does not meet its required a P, contact the ,

Control Room NSS for further instruction before leaving containment. I initial i Date  ; Note: ck. is full stroke

• The following step verifies [1RH-3], "A" PP U:~ :

exercised in the forward direction.

• If all 3 RCPs are in service, sufficient flow to exercise the check-valve is present without throttling open [MOV-1RH-605] because pump re greater with 3 RCPs running.

l

14. Full-stroke exercise [1RH-3] as follows:

a. If 3 RCPs are in service, sufficient flow exists to verify full stroke in the forward direction, N/A Step 14.b. (Otherwise N/A) i

                                                                                                           /

Initiali Date l 1 b. If less than 3 RCPs are running, adjust [MOV-1RH-605], Residual Heat Removal Hx Bypass FCV to obtain a flow rate of 4100 gpm (4100 as read on [FI-1RH-605], RHR Flow, (BB-A) and record below: lr _gpm [FI-1RH-605] _ I initial I Date l l 15. Adjust [MOV-1RH-605], Residual Heat Removal Hx Bypass R FC obtain a flow rate of 4000 gpm'(3950 - 4050 gpm) as read on [FI-1 Flow. I initial I Date C0R TRAIN!NG ONLY

I l l Beaver Valle*y Power Station Unit i 10ST-10.1 ( Residual Heat Removal System issue 4 Revision 9 Operating Surveillance Test Page 13 of 33 Residual Heat Removal Pump Performance Test C. f1RH-P-1Bl. Residual Heat Removal 1B Pump Performance Test

       ! Note: Venting [1RH-P-1B] is required if any of the following conditions exists:

• This test is being run because unsuccessful results were obtained during the previous performance of this section of the OST.

                  * [1RH-P-1B] does not show stable amps.
                  * [1RH-P-1B] has not operated for at least 1/2 hour.

1. If required, vent [1RH-P-18] as follows: (Otherwise N/A).

CAUTION: DO NOT VENT THE RHR PUMP IF RHR TEMPERATURE 2 200F AS INDICATED ON [TRB-RH-604], (RED PEN - COOLER INLET). (VB-A)

a. Check closed, [1RH-204], ~B" PP Seal Clr Vnt (RH Platform).

                                                                                                         /

Initial / Date

b. Remove the swa;elock cap from [1RH-204], "B" PP seal Clr Vnt, (RH Platform).

                                                                                                         '               \

initial / Date l

c. Securely connect a vent rig comprised of a Health Physics approved bottle l equipped with two filters to [1RH-204].

I initial / Date

d. Throttle [1RH-204], "B" PP Seal Clr Vent, until a solid stream of water issues.

                                                                                                           /

Initial / Date

e. Close [1RH-204] "B" PP Seal Ctr Vent.

(1) / Initial / Date (2) / Initial / Date

f. Disconnect the vent rig and replace the swagelock cap on [1RH-204] unless further venting is likely to be needed (N/A if vent rig left installed).

                                                                                                            /

I initial / Date C0R TRAIN!NG ONLY

l Beaver Valley Power Station Unit 1 10ST-10.1 l Residual Heat Removal System ( Issue 4 Revision 9 Operating Surveillance Test Page 14 of 33 Residual Heat Removal Pump Performance Test

2. Install, or verify installed, a current calibrated test gauge as follows: l

a. Notify the NSS that a pressure gauge will be installed at [1RH-200] OR .

between [1RH-200] and [1RH-213], as applicable. l

                                                                                                                                                /

Initial / Date

b. Install a pressure gauge (0-600 psig maximum, not to exceed 3 times existing i RCS pressure) at [1RH-200], [RH-P-1 A] Suction Low Point Drn (under RH Platform, above [11A-C-1 A,1B]). I i

                                                                       ,                  OR Connect the low pressure side of the A P gauge (0 450 UR 0-200 psid) to                                            !

[1RH-200] and the high pressure side to [1RH-2GJ, Pump Disch HPV, (RH Platform). g (circle method used) (1) I

                                                                                                                                    . initial I Date (2)               /

initial I Date

c. Open [1RH-200], [1RH-P-1 A] Suction Low Point Drain. ,

I initial I Date i

d. If [1RH-213], Pump Disch HPV is being used. Open [1RH-213]. (Otherwise l NIA)

I initial I Date , i

3. Place [1RH-P-1B] motor bearing temperatures on TREND, (Computer Addresses )

TO696A, T0697A). I initial I Date 4 If either of the RHR pumps is not already running, record the pump suction pressure (Pis) prior to pump start on Data Sheet 4 and Data Sheet 1. l I initial I Date

5. Start, or verify running, [1RH-P-18], Residual Heat Removal 1B Pump.

\ ! I initial I Date f

                                                                                                                                      ~

C0R TRAIN!NG ONLY

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System - Issue 4 Revision 9 j Operating Surveillance Test Page 15 of 33 ' l Residual Heat Removal Pump Performance Test  !

6. Stop or verify shutdown [1RH-P-1 A] Residual Heat Removal 1 A Pump.

I Initial / Date

7. Obtain a total RHR Flow of 4000 gpm (3950 - 4050 gpm) as read on [F1-1RH-605],

RHR Flow, as follows:

a. Adjust [MOV-1RH-758), Residual Heat Removal Hx FCV, to establish  !

cooldown or maintain RCS/RHR temperatures as desired. I l Initial / Date

b. Adjust [MOV-1RH-605], Residual Heat Removal Hx Bypass FCV, as needed to maintain a flow rate of 4000 gpm. (3950-4050 gpm)

I Initial / Date

8. Verify SPDS Computer Point for [1RH-P-18], RHR PP B Bkr by checking

[1RH-P-1B] indicates ON (Screen 3RH1). I initial / Date

9. Verify SPDS Computer Point for [1RH-P-1 A], RHR PP A Bkr by checking

[1RH-P-1 A] indicates OFF (Screen 3RH1). l 1 Initial / Date l

10. Monitor [1RH-4] ~B" PP Disch Chk, for chattenng.

l l Initial / Date

11. Record [1RH-P-1B] motor and pump Vibrations on Data Sheets 5 and 6.

I initial / Date i

12. Record [1RH-P-1B] flowrate (Q), discharge pressure (Pd) and suction (PI), or differential pressure (AP m) on Data Sheet 4.

I initial / Date

                                                      'OR Ty um,g 9 4,

l Beaver Valley Power Station Unit 1 10ST-10.1 l Residual Heat Removal System issue 4 Revision 9 Operating Surveillance Test Page 16 of 33 Residual Heat Removal Pump Performance Test ( [ l Note: If pump AP is in the acceptable range. [1RH-3] is seated properly,

13. Consult the Acceptance Criteria for acceptable performance using the AP criteria for the number of RCPs running. If pump AP is not in the acceptable range, perform the following: (NIA if not required)

a. Vent the pump by performing Step C.1 I

initial I Date

b. Repeat Step C.7 I l Initial / Date J

c. Repeat Step C.12 I

initial I Date

d. If after reventing, the pump does not meet its required A P, contact the Control Room NSS for further instruction before leaving containment.

I initial I Date l Note: l

• The following step verifies [1RH-4]. "B" PP Disch Check, is full stroke '

exercised in the forward direction.

• If all 3 RCPs are in service, sufficient flow to exercise the check valve is present without throttling open [MOV-1RH-605] because pump recirc flow is greater with 3 RCPs running.

14. Full-stroke exercise [1RH-4] as follows:

a. If 3 RCPs are in service, sufficient flow exists to verify full stroke in the forward direction, NIA Step 14.b. (Otherwise NIA)

I initial I Date

b. If less than 3 RCPs are running, adjust [MOV-1RH-605], Residual Heat Removal Hx Bypass FCV to obtain a flow rate of 4100 gpm (4100 - 4150 gpm)

' as read on [F1-1RH-605], RHR Flow, (BB-A) and record below: [F1-1RH-605] gpm 1' I C0R TRAIN!AG OnlLY .

i I

                                    .                                                                                                          I l       Beaver Valley Power Station                        Unit 1                                                                10ST-10.1 l  3 Residual Heat Removal Systerr.                                                                        Issue 4 Revision 9                I l

Operating Surveillance Test Page 17 of 33 j l Residual Heat Remaval Pump Performance Test ( 15. Adjust [MOV-1RH-605], Residual Heat Removal Hx Bypass FCV as required to ) obtain a flow rate of 4000 gpm (3950 - 4050 gpm) as read on [F1-1RH-605], RHR Flow. I Initial / Date D. RHS Temperature Indicator Comparison Check

1. Verify RHS flow established (one or two RHR Pumps running), for at least 15 minutes prior to taking pyrometer readings. (If cooldown is in progress, the readings should be phoned into the control room for timely comparison).

I initial / Date

2. Compare RHR outlet temperature indicators as follows:

l

a. Take a pyrometer reading on one of the following depending on the flow path:

• If [MOV-1RH-720A] is open, read temperature on the valve body of

[MOV-1RH-720A] (near St Accumulator 1 A, CNMT 692). F.

• If [MOV-1RH-720B] is open, read temperature on the valve body of

[MOV-1RH-7208] (near SI Accumulator 18, CNMT 692). F. l I , initial / Date

b. Record Loop return temperature,in Plant Computer address T0627A.

F. 1 I initial / Date

c. Record [TI-1RH-606], RHR Heat X Outlet Temp, reading at shutdown panel.

F I initial / Date

d. Record [TR-1RH-604], RHR Temperature Green Pen - Loop Return, (VB-A).

F 1 I- initial / Date l 1

                                                                  '0R TRAINING ogy

Beaver Valley Power Station Unit 1 10ST-10.1 ( Residual Heat Removal System issue 4 Revision 9

                                                                                                                  ~

Operating Surveillance Test Page 18 of 33 Residual Heat Removal Pump Performance Test ( Note: The following provides a dynamic channel check to verify the validity of the static' channel check performed per OST 1.45.2 while in Modes 13 (T.S. 3.3.3.5).

e. Verify the above four temperatures agree within 20F of each other.

I initial I Date

3. Compare RHR inlet temperature indicators as follows:

a. Record cooler inlet temperature Ir. Plant Computer address T0630A. F I

initial / Date

b. Record [TR-1RH-604], RHR Temperature Red Pen - Cooler inlet, (VB-A).

F I initial / Date

c. Verify the above two temperatures agree within 20F.

I , initial / Date E. Operatina f1RH-P-1 A1 from the SDP

1. Enter the date the last time [1RH-P-1 A] was started and stopped from the SDP.

Date Note: Starting and stopping [1RH-P-1 A] from the shutdown panel is required annually, if i annual testing of [1RH-P-1 A] pump controlis not due, the rest of this section is NIA.

2. Circle the applicable condition of [1RH-P-1 A], Residual Heat Removal 1 A Pump, control switch at BB-A.

a. Centered after START (Red target visible).

b. Centered after STOP (Green target visible),

c. PULL-TO-LOCK (Green target visible).

initial / Date 1

3. Verify or place [1RH-P-1 A], Residual Heat Pump 1 A, control switch at the SDP in same position circled in the step above.

C0R TRAIN.!hG ONLY 'ani ' ' o*

s Beaver Vallef Power Station Unit i 10ST-10.1 { Residual Heat Removal System _ lssue 4 Revision 9

• Operating Surveillance Test Page 19 of 33 Residual Heat Removal Pump Performance Test

4. Press the CONT TRANSF TO SDP RESIDUAL HEAT REMOVAL [1RH-P-1 A]

pushbutton at the SDP. l Initial I Date 1 5. Verify that the Annunciator A4-73, CONTROL AT SHUTDOWN PANEL, is ON. I initial / Date Note: If [1RH-P-1 A] is stopped, perform the actions / verifications indicated in parentheses.

6. Verify that the Red Running (White Stopped) light is ON for [1RH-P-1 A] at tr.s SDP.

I initial / Date i

7. Verify that the requirements of T.S. 3.4.1.3 are met before stopping all RHR

pumps, refer to Precautions and Limitations, Step C.

I initial I Date

8. Place the control switch for [1RH-P-1 A], Residual Heat Pump 1 A, in the STOP 1 (START) position, spring return to center, at the SDP.

I

Initial / Date  ;

1

9. Verify the White Stopped (Red Running) light is ON for [1RH-P-1 A] at the SDP.

I

initial / Date

10. Place the control switch for [1RH-P-1 A], Residual Heat Pump 1 A, in the START (STOP) position, spring return to center, at the SDP.

I initial / Date

11. Verify that the Red Running (White Stopped) light is ON for [1RH-P-1 A] at the SDP.

i ' I i Initial / Date

12. Verify, or place the BB-A control switch for [1RH- P-1 A], Residual Heat Removal

                           ' 1 A Pump, in the same position as the SDP control switch.

I COR TRAINING ONLY

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System Issue 4 Revision 9 Operating Surveillance Test Page 20 of 33 Residual Heat Removal Pump Performance Test (

13. Transfer control'back to the Control Room by placing [43-VE103X], Control Transfer Switch, in RESET,4160V Emer Bus 1 AE, Breaker [1E3].

                                                                                            /

initial / Date

14. Verify that Annunciator A4-73, CONTROL AT SHUTDOWN PANEL, is OFF.

                                                                                            /

initial / Date

15. Verify that the Red Running (White Stopped) light for [1RH-P ' A] is ON, BB-A.

                                                                                             /

initial / Date F. Operatina f1RH-P-1Bl from the SDP

1. Enter the date the last time [1RH-P-1B] was started and stopped from the SDP.

Date

                                                                                              /

Initial / Date Note: Starting and stopping [1RH-P-18] from the shutdown panel is required annually. If annual testing of [1RH-P-18] pump control is not due, the rest of this section is N/A.

2. Circle the applicable condition of [1RH-P-18], Residual Heat Removal 18 Pump, control switch at (BB-A).

a. Centered after START (Red target visible).

b. Centered after STOP (Green target visible).

c. PULL-TO-LOCK (Green target visible).

I initial / Date

3. Verify or place [1RH-P-1B], Residual Heat Pump 18, control switch at the SDP in the same position circled in the step above.

                                                                                                /

Initial / Date

4. Press the CONT TRANSF TO SDP RESIDUAL HEAT REMOVAL [1RH-P-1B]

pushbutton at the SDP. I initial / Date (

5. Verify that the Annunciator A4-73, CONTROL AT SHUTDOWN PANEL. is ON.

COR TRAINING nanv ._.s,,m._

 .   .            .-             .          . - ,       _  . - - _ - _ _ - - - =_      _. ..                   ~.    -

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 - Operating Surveillance Test Page 21 of 33 Residual Heat Removal Pump Performance Test 1 2 Note: If [1RH-P-18], is stopped, perform the actions / verifications indicated in l parentheses. l

6. Verify that the Red Running (White Stopped) light is ON for [1RH-P-18] at the SDP.

I initial / Date

7. Verify that the requirements of T.S. 3.4.1.3 are met before stopping all RHR pumps, refer to Precautions and Limitations, Step C.

I initial / Date

8. Place the control switch for [1RH-P-18], Residual Heat Pump 18, in the STOP (START) position, spring return to center, at the SDP.

I initial / Date

9. Verify the White Stopped (Red Running) light is ON for [1RH-P-1B] at the SDP.

I

initial / Date

10. Place the control switch for [1RH-P-1B], Residual Heat Pump 1B, in the START (STOP) position, spring return to center, at the SDP.

I initial / Date l

11. Verify that the Red Running (White Stopped) light is ON for [1RH-P-1B] at the SDP.

I initialI Date

12. Verify or place the BB-A control switch for [1RH-P-1B], Residual Heat Removal 1 A Pump, in the same position as the SDP control switch.

I initial i Date

13. Transfer control back to the Control Room by placing [43-VF103X], Control Transfer Switch, in RESET,4160V Emer Bus 1DF, Breaker [1F3].

I initial / Date

14. Verify that Annunciator A4-73, CONTROL AT SHUTDOWN PANEL, is OFF.

I

                                                  ~t0R TRAIN!iVG ONLY

a Beaver Valley Power Station Unit i 10ST-10.1  ; i Residual Heat Removal System issue 4 Revision 9 ' Operating Surveillance Test Page 22 of 33 Residual Heat Removal Pump Performance Test

15. Verify ON the Red Running (White Stopped) light for [1RH-P-1B], BB-A.

I initial I Date G. System Restoration

1. Restore RHR to the pretest positions recorded in the Test Preparation section, OR as directed by the NSS/ANSS.

a. [MOV-1RH-605], Residual Heat Removal Hx Bypass FCV.

I initial / Date

b. [MOV-1RH-758], Residual Heat Removal Hx FCV.

I initial / Date

2. Remove the test gauge installed as follows: (N/A step not used)

a. Notify the NSS that the pressure gauge will be removed from [1RH-200] OR between [1RH-200] and [1RH-213], as applicable.

                                                        -                                                                                         /

Initial / Date

b. Close [1RH-200], [1RH-P-1 A] Suction Low Point Drain.

(1) / initial / Date I ( (2) initiali Date

c. If [1RH-21;3] Pump Disch HPV was opened, Close [1RH-213]. (Otherwise N/A)

(1) / Initial / Date (2) I initial / Date

d. Remove the pressure gauge from [1RH-200], [1RH-P-1 A] Suct Low Point Drain (under RH platform, above [11A-C-1 A,B]. g OR Remove the AP gauge from [1RH-200] and [1RH-213] Pump Disch HPV, RHR platform.

(1) / , Initial '/ Date ( GOR ,c,RAINhTG ONLY (2) Initial / Date

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System - Issue 4 Revision 9 - Operating Surveillance Test Page 23 of 33 Residual Heat Removal Pump Performance Test

3. Continue operation of the RHR system in accordance with 10M-10.4.A. " Residual Heat Removal System Startup (Plant Shutdown)."

I Initial / Date H. Test Completion

1. Consult the Acceptance Criteria for acceptable performance.

I initial / Date

2. Inform the NSS or ANSS of the completion of this test. l I

initial / Date

3. Complete the front cover sheet. j I

initialI Date l l t C0R TRAIN!NG ONty

l l < Beaver Valley Power Station Unit i 10ST-10.1 s Residual Heat Removal System Issue 4 Revision 9 Operating Surveillance Test Page 24 of 33 Residual Heat Removal Pump Performance Test ( Vill. DATA SHEETS, TABLES, FIGURES and ATTACHMENTS A. Data Sheets

1. [1RH-P-1 A] ASME XI Performance Data.

2. [1RH-P-1 A] ASME XI Vibration Data.

3. [1RH-P-1 A] Pump Vibration Data. ,

4. [1RH-P-18] ASME XI Performance Data. l S. [1RH-P-1B] ASME XI Vibration Data.

6. [1RH-P-1B] Pump Vibration Data.

B. Tables NONE , 1 C. Fioures

1. Vibration Reading Locations.

D. Attachments NONE l - 4 i

                                                                  *0R TRAINING ONLY

l Beaver Val!ey Power Station Unit i 10ST-10.1 a Residual Heat Removal System Issue 4 Revision 9 - I k Operating Surveillance Test Page 25 of 33 I l Residual Heat Removal Pump Performance Test j DATA SHEET 1 , l [1 RH-P-1 A] l ASME XI PUMP PERFORMANCE DATA I l Pump Performance Data P. = Pump Dynamic Suction Pressure in PSIG Number of RCPs running P. = Pump Discharge Pressure in PSIG AP, = Calculated Differential Pressure, (Pd - Pi), in PSID AP, = Measured Differential Pressure PSID Q = Flowrate in GPM l l Pu = [ Test Gauge] Prior to pump start (Local) P. = [ Test Gauge] (Local) Test Gauge ID# Cal Due Date i Initials /Date / l P, = [Pl-1RH-600] (Local) Cal. Due Date initials /Date /

                                                                                                                     )

AP, = Pd - Pi + 5.21 psi (1) Initials /Date / AP,= (2) Initials /Date I ' OR AP, = [AP Test Gauge] (Local) AP Test Gauge ID# Cal Due Date initials /Date / Q = [FI-1RH-605] (3950 - 4050 gpm) Cal Due Date  ; initials /Date I Note: If AP is not within the Acceptable Range but is within the Alert Range, continued pump operation is permitted; however, the test frequency shall be doubled until the cause of the deviation is determined and the condition corrected. If the AP is not within either the Acceptable or Alert Ranges, the pump shall be declared inoperable. l l ASME XI Acceptance Criteria: (AP), Q = 4000 gpm No. of Acceptable Alert Range Alert Range Required Required RCPs Range (LOW) (HICH) Action Range Action Range Running (LOW) (HICH) ! AP 0 or 1 90.45AP $99.2 87.55AP <90.4 99.'.< AP $100.1 <87.5 >100.1 AP 2 84.0$AP $92.1 81.35AP <84.0 92.1<AP 593.0 <81.3 >93.0 MO T' h 1 I nf r as n u . . . . AP 3 82.25AP $90.2 79.65AP <82.2 MP $90th lIl MUdJ VN[$1.1

Beaver Valley Power Station (Jnit 1 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 i

Operating Surveillance Test Page 26 of 33 l Residual Heat Removal Pump Performance Test ( DATA SHEET 2 [1RH P-1 A] ASME XI VIBRATION DATA Note: Ensure the vibration meter magnetic probe is placed over the fixed metal lettered location tag (as shown on the (MAGNETIC PROBE) right) when obtaining vibration measurements per Figure

1. If a metal lettered location tag is missing, notify the IST l Coordinator (via a memo) and obtain the vibration measurement at the location on Figure 1.

l (TAG) i Note:

• If vibration readings are not within the Acceptable Range, but are within the Alert Range.

continued pump operation is permitted, however, the test frequency must be doubled until ( the cause of the deviation is determined and the condition corrected, if vibration readings are not within either the Acceptable Range or the Alert Range, the pump must be declared INOPERABLE.

• See Figure i for bearing locations. The vertical points are in the direction of the discharge piping.
• Motor Speed = 1780 RPM I

i Motor Vibration ReadingstCU l l Date / / Time initials Actual Reference Acceptable Alert Metal Location Vibration Vibration Range O Range O Bearing Location (#) Tag (Letter) (in/sec) (in/sec) (inisec) (in/sec) Motor Outboard (1) Axial (A) 0.049 $0.123 $0.343 Motor Outboard (1) Horizontal (H) 0.178 $0.325 $0.70 Motor Outboard (1) Vertical (V) 0.226 $0.325 $0.70 l Motor Inboard (2) Axial (A) CO Q 0.0p 4p, y g J0.jp5 n J0d24 Motor Inboard (2) Horizontal (H) '0.0i$ * * # OSO V NdQE56 Motor Inboard (2) Vertical (V) 0.079 $0.198 $0.474 I

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 - Operating Surveillance Test Page 27 of 33 Residual Heat Removal Pump Performance Test DATA SHEET 3 [1 RH-P-1 A] ASME XI VIBRATION DATA l Note: Ensure the vibration meter magnetic probe is placed over the fixed metal lettered location t.ag (as shown on the (MAGNETIC PROBE) right) when obtaining vibration measurements per Figure

1. If a metal lettered location tag is missing, notify the IST -

Coordinator (via a memo) and obtain the vibration measurement at the location on Figure 1. (TAG) i Note:

• If vibration readings are not within the Acceptable Range, but are within the Alert Range, continued pump operation is permitted, however, the test frequency must be doubled until the cause of the deviation is determined and the condition corrected. _ If vibration readings are not within either the Acceptable Range or the Alert Range, the pump must be declared INOPERA 9LE.

i

                   . See Figure i for bearing locations. The vertical points are in the direction of the discharge piping.

• Pump Speed = 1780 RPM Pump Vibration Readings (c.23 1

! Date / / Time initials Actual Reference Acceptable Alert l Range O l Metal !.ocation Vibration Vibration Range O Bearing Location (#) Tag (Letter) (in/sec) (in/sec) (in/sec) (in/sec) Pump inboard (3) Horizontal (H) 0.023 $0.058 $0.138 Pump inboard (3) Vertical (V) 0.035 $0.088 $0.210

 .                                                             C0R hiAiri.iNG ONLY

l i l Beaver Valley Power Station Unit i 10ST-10.1 i 4 Residual Heat Removal System issue 4 Revision 9

• Operating Surveillance Test Page 28 of 33 Residual Heat Removal Pump Performance Test l DATA SHEET 4 l [1RH P-1'B]

ASME XI PUMP PERFORMANCE DATA I l Pump Performance Data l P. = Pump Dynamic Suction Pressure in PSIG Number of RCPs running l P, = Pump Discharge Pressure in PSIG AP, = Calculated Differential Pressure (Pd - Pi), in PSID AP, = Measured Differential Pressure PSID Q = Flowrate ir. GPM P,i = [ Test Gauge] Prior to pump start (Local) P, = [ Test Gauge] (Local) Test Gauge ID# Cal Due Date initials /Date / i l P, = [PI-1RH-601] (Local) Cal. Due Date l Initials /Date I AP, = Pd - Pi + 5.21 psi (1) Initials /Date I j AP e = (2) Initials /Date I ' OR AP, = [AP Test Gauge] (Local) AP Test Gauge ID# j Cal Due Date 1 Initials /Date / l O = [FI-1RH-605] (3950 - 4050 gpm) Cal Due Date initials /Date / l l Note: If AP is not within the Acceptable Range but is within the Alert Range, continued l pump operation is permitted; however, the test frequency shall be doubled until the cause of the deviation is determined and the condition corrected. If the AP is not within either the Acceptable or Alert Ranges, the pump shall be declared inoperable. ASME XI Acceptance Criteria: (AP), Q = 4000 gpm No. of Acceptable Alert Range Alert Range Re< quired Required RCPs Range (LOW) (HICH) Action Range Action Range Running (LOW) (HIGH) AP O or 1 83,9 sap $92.0 83.8 sap <83.9 <83.8 >92.9 PQ2.9 3 8 I hl11lo A _ n a mi , AP 2 76.1 sap $33.5 76.0aP <76.1 83MdP sl d.fA 8 ' Mtl.1 Q I J N @ .3 l AP 3 73.8 SAP $81.0 N/ Asap N/A 81.0<aP $81.8 <73.8 >81.8 l

l l l Unit 1 Beaver Valley Power Station . 10ST-10.1

 ;    Residual Heat Removal System                                                         issue 4 Revision 9            -

Operating Surveillance Test Page 29 of 33 l Residual Heat Removal Pump Performance Test DATA SHEET 5 [1 RH-P-1 B] ASME XI VIBRATION DATA Note: Ensure the vibration meter magnetic probe is placed over the fixed metal lettered location tag (as shown on the (MAGNETIC PROBE) right) when obtaining vibration measurements per Figure

1. If a metal letterea location tag is missing, notify the IST Coordinator (via a memo) and obtain the vibration I measurement at the location on Figure 1.

(TAG)

                                                                                      .               .;                   l l

l I Note:

• If vibration readings are not within the Acceptable Range, but are within the Alert Range,  ;

continued pump operation is permitted, however, the test frequency must be doubled until th.e cause of the deviation is determined and the condition corrected. If vibration readings rre not within either the Acceptable Range or the Alert Range, the pump must be declared hC f'F D ABLE.

• See Figure i for bearing locations. The vertical points are in the direction of the discharge piping.
• Motor Speed = 1780 RPM Motor Vibration Readings (C2 Date / / Time initials Actual Reference Acceptable Alert Metal Location Vibration Vibration Range O Range O Bearing Location (#) Tag (Letter) (in/sec) (in/sec) (in/sec) (in/sec) l l Motor Outboard (1) Axial (A) 0.033 $0.083 $0.198 l Motor Outboard (1) Horizontal (H) 0.139 $0.325 $0.70

( Motor Outboard (1) Vertical (V) 0.110 $0.275 $0.660 Motor inboard (2) Axial (A) hkj hh.0QQ l $0.210 ~ Motor Inboard (2) Horizontal (H) 0.047 $0.118 ~ '50.282 Motor inboard (2) Vertical (V) 0.048 $0.12 $0.288

'O

 ,     Beaver Valley Power Station                         Unit 1                                       10ST-10.1 i*  Residual Heat Removal System                                                         issue 4 Revision 9 Operating Surveillance Test                                                                Page 30 of 33 Residual Heat Removal Pump Performance Test

( DATA SHEET 6 [1RH P-1B] ASME XI PUMP VIBRATION DATA Note: Ensure the vibration meter magnetic probe is placed over the fixed metal lettered location tag (as shown on the (MAGNETIC PROBE) right) when obtaining vibration measurements per Figure

1. If a metal lettered location tag is missing, notify the IST 1

Coordinator (via a memo) and obtain the vibration measurement at the location on Figure 1. l (TAG) Note: If vibration readings are not within the Acceptable Range, but are within the Alert Range, i continued pump operation is permitted, however, the test frequency must be doubled until  ; the cause of the deviation is determined and the condition corrected. If vibration readings  ! are not within either the Acceptable Range or the Alert Range, the pump must be declared INOPERABLE.

                     . See Figure i for bearing locations. The vertical points are in the direction of the discharge piping.

• Pump Speed = 1780 RPM i

Pump Vibration Readings (ca Date / / Time initials 1 Actual Reference Acceptable Alert l Metal Location Vibration Vibration Range O Range O Bearing Location (#) Tag (Letter) (in/sec) (inisec) (in/sec) (in/sec) Pump inboard (3) Horizonatal (H) 0.033 $0.083 $0.198 Pump inboard (3) Vertical (V) 0.049 $0.123 $0.294 c0c" i .u'u"d.! NG ON LY (

I Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 '

                                                                                                          )

( Operating Surveillance Test Page 31 of 33 i Residual Heat Rr.movat Pump Performance Test Figure 1 l l 1 l

                                                                \(A)
                                                      /

1(H)* +- 1(V) { l i l l I I

                                            ~

2 (H) ,

                                                  -                 ."        2(V) i                           ::2(A) 3(V)                        i I                                                              i i                                         ,

3 (H)L.) l L I

                                                      \

c

                                                                /

1 l l l l l l l l C0R buu.sjplG ONty i

l l l Beaver Valley Power Station Unit 1 10ST-10.1 i Residual Heat Removal System issue 4 Revision 9 Operating Surveillance Test Page 32 of 33 i Residual Heat Removal Pump Performance Test ( l IX. REFERENCES  ; A. TECHNICAL SPECIFICATIONS j

1. BVPS-1 T.S.

2. BVPS-1 T.S. 4.4.1.3.1.

3. BVPS-1 T.S. 4.9.8.2.

4. BVPS-1 T.S. 4.0.5.

5. BVPS-1 T.S. 3.4.1.3.

6. BVPS-1 T.S. 3.3.3.5.

B. UPDATED FINAL SAFETY ANALYSIS REPORT None C. COMMITMENTS

1. Letter ND1NSM:3390 " Response to NRC Request for Plant Specific ln' formation on SPDS (TAC 51221) Safety Analysis Report", OMDR 1-89-1688. (D on page 3)

2. NRC inspection Report 50-334/94-20 D. ADMINISTRATIVE

1. i3VPS Unit 1 IST Pump Test Outline.

2. NGAP 7.4 E. VENDOR INFORM ATION None F. DRAWINGS

1. 8700-RM-410 VOND Residual Heat Removal System.

G. OPERATING MANUAL

1. 10M Residual Heat Removal System.

2. 10M Station Shutdown.

3. 10ST-10.5 - Leak Test [MOV-1RH-700 and 701].

4. 10M-10.4.A - Residual Heat Removal System Startup (Plant Cooldown).

5. OST 1.45.2.

H. PLANT MODIFICATION g ( None NG ONLY

Beaver Valley Power Station ' Unit 1 10ST-10.1

     - Residual Heat Removal System                                           issue 4 Revision 9
   ?  Operating Surveillance Test                                                 Page 33 of 33 Residual Heat Removal Pump Performance Test I, OTHER

1. ASME Section XI, Subsection; IWP-3000, IWV3520.

2. OMDR 1-90-1028,1-91-0228 (Rev. 0).

3. OMDR 1-92-0270, OMCN 1-92-358 (Rev.1).

4. OMCN 1-93-213,632 (Rev 2).

5. OMCN 1-94-164 (one time only); OMDR 1-93-1008 (Rev. 3).

6. OMDR 1-93-0387,1-94-2040 (Rev. 4).

7. OMCN 1-95-177 (Rev. 5).

                 ' 8. OMCN 1-95-257 (Rev. 6).

9. OMCN 1-96-123 (Rev. 7).

10. OMCN 1-96-140 (Rev. 8).

11. OMCR 1-96-0971,1150 (Rev. 9).

a 1 r . 50R TRAINING ONLY

Beaver Valley Power Station Unit 1 10ST-10.1 Residual Heat Removal System issue 4 Revision 9 - Operating Surveillance Test Page 25 of 33 Residual Heat Removal Pump Performance Test DATA SHEET 1 [1 RH-P-1 A] ASME XI PUMP PERFORMANCE DATA Pump Performance Data P. = Pump Dynamic Suction Pressure in PSIG Number of RCPs running P. = Pump Discharge Pressure in PSIG AP, = Calculated Differential Pressure, (Pd - Pi), in PSID AP, = Measured Differential Pressure PSID Q = Flowrate in GPM P, = [ Test Gauge] Prior to pump start (Local) P, = [ Test Gauge] (Local) Test Gauge ID# Cal Due Date Initials /Date / P. = [PI-1RH-600] (Local) Cal. Due Date initials /Date / AP, = Pd - Pi + 5.21 psi (1) Initials /Date / AP,= (2) Initials /Date / OR AP, = [AP Test Gauge] (Local) AP Test Gauge ID# Cal Due Date Initials /Date / Q = [FI 1RH-605] (3950 - 4050 gpm) Cal Due Date initirls/Date / Note: If AP is not within the Acceptable Range but is within the Alert Range, continued pump operation is permitted; however, the test frequency shall be doubled until the cause of the deviation is determined and the condition corrected. If the AP is not within either the Acceptable or Alert Ranges, the pump shall be declared inoperable. gg yggg{gQ gly w pg a s un s 's s e u w w ii n r ASME XI Acceptance Criteria: (AP), Q = 4000 gpm No. of Acceptable Alert Range Alert Range Required Required RCPs Range (LOW) (HIGH) Action Range Action Range Running (LOW) (H'GH) AP 0 or 1 90.45AP $99.2 87.5 SAP <90.4 99.2<AP $100.1 <87.5 >100.1 AP 2 84.0$AP 592.1 81.3 SAP <84.0 92.1<AP $93.0 <81.3 >93.0 AP 3 82.25AP $90.2 79.6 SAP <82.2 ' 90.2<aP $91.1 <79.6 >91.1

       . - , -                  .- . . ~ . . -            . . -  .. . ... .~ -            _ -.-.. . -
                                                                                                      . ..~ . ..

l i RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division ' Training Administrative Manual l s l I i OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training !~ SUBDIVISION: On-the-Job Training l OJT CHECKLIST /JPM TITLE: Respond to RHR Pump Trip l JPM NO.: 1CR-133 l COMPUTER CODE: N/A > 1 I Revision No. Date Revision No. Date i i i l l PREPARED BY: DATE: 4 i APPROVED FOR , IMPLEMENTATION: DATE: ( Director, Operations Training, (_ or Designee r i ? l Revision 9

  . .   . -.        .  - . .    - . . .          . .   ..   ..... -     -.~.-.- ..             . . ~ - . . . . . - .

RTL.#A5.640E~ DUQUESNE LIGHT COMPANY' Nuclear Power Division Training Administrative Manual

                             ' LESSON PLAN AND OJT REVISION APPROVAL SHEET l-            DOCUMENT TITLE: 1CR-133. Resoond to RHR Pumo' Trio 1

l l, Revision Acoroval 4 No. 'Brief Description Revised by: Signature Date i i t I 1 l- r I e-t i ! h i I

                                                                                                                             \

lt i 'l l \ J l l l; t-l i l L. Revision 9

                                                                 ~

l I 1 j i l DEAVER VALLEY JOB PERFORMANCE MEASURE l l EVALUATOR COVER SHEET I ! I. JPM Number: 1CR-133 Rev: 0 System #: 005 Faulted: O l l JPM

Title:

Respond to RHR Pump Trip i ! K/A

Reference:

005 000 A2.03 2.9/3.1 Task ID #: 000 018 0401 l JPM Designation: O NO RO E SRO JPM Application: X NRC X Initial Exam ! Training i i Evaluation Method LOCATION TYPE l X Perform O Plant Site O Training { Simulate X Simulator O Annual Requal. Exam l U Classroom OJT l @ Initial Operator Exam j Administered By: O Other: i BV-T l NRC Other: i j Evaluat.4.on Results { Performer: Name: Employee No: , Results SAT Time (minutes) UNSAT* Allotted: 6 Actual: { Time Critical: 0 Yes x No i

• Comments (Required for UNSAT Evaluation):

I t I ~ Evaluation Results Check here if same as above l l Observer 1: Name: Employee No: i Observer 2: Name Employee No: Observer 3: Name Employee No: , Observer 4: Name Employee No: Time (minutes) Results ? I Question ID Allotted Actual SAT UNSAT* Question #1 3 0

Employee No

Question #2 3 j Employee No: {

• Comments (Required for UNSAT Evaluation) :

i 1 ! j ' l Evaluator (Print): Organization: _ t i Evaluator Signature Date: i Revision 9

RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE. DIRECTION SHEET

• THIS SHEET TO BE GIVEN TO CANDIDATE
• Read:

Task: Respond to RHR Pump Trip l I INITIAL CONDITIONS: The plant is in Mode 5 with decay heat being--removed by the 4,000 gpm of flow from the 1A RHR pump. An RCS boration is in progress to raise the RCS boron concentration by 25 ppm. Annunciator Al-127, Residual Heat Removal Pump Auto Stop, was actuated 1-0 seconds ago. P TASK STAN.: RHR flow restored in accordance~with 10M-10.4.AAC. INIT. CUE: Your supervisor directs you to respond to: Annunciator Al-127, Residual Heat Removal Pump

• Auto Stop.

At this time, ask the evaluator any questions you have on this-JPM. ) When satisfied that you understand the assigned task, announce ,

         "I am now beginning the JPM".                                                         -;

Simulate performance or perform asLdirected the required task. Point to any indicator or component you verify.or check and announce your observations. After completing the task, reread the Task Standard. After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. N l Revision 9

 ._ _  ..   . _ , _ . _ _ . _ . _ _ _ .   . > . . ~ . . _ _ . . . .       . _ _ ..       _ _ _ _ _ _ _ . . . _ . . _ . _ . . _.

RIL ilAS.635;J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: 1CR-133 I TITLE: Respond to RHR Pump Trip RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to perform the task respond to RHR pump trip. INIT. CONDITIONS: The plant is in Mode 5 with decay heat being removed by the 4,000 gpm of flow from the 1A RHR pump. An RCS boration is in progress to raise the RCS boron concentration by 25 ppm. Annunciator Al-127, Residual Heat Removal Pump Auto Stop, was actuated 10 seconds ago. TASK STAN.: RHR flow restored in accordance with 10M- ) 10.4.AAC.  ! IT. CUE: Your supervisor directs you to respond to Annunciator Al-127, Residual Heat Removal Pump Auto Stop.

REFERENCES:

10M-10.4.AAC, Issue 4, Revision 0 i TOOLS: NONE HANDOUT: NONE l l l

                                                                                                                                     )

i I Revision 9

    ._. _ _        .  ._         _.    . _ - - . _ _ _ _ _ _ _ _          .-m.  . .. . .  -. _ . . _ . _..._. _

RTL #AS.635.J i l NUMBER TITLE l l 1CR-133 Respond to RHR Pump Trip , l j .. STEP STANDARD i (Indicate "S" for Sat. or "U" l- ("C" denotes critical step) for Unsat.) Evaluator Setup: -Initialize Simulator to IC-33. Set Boric Acid Integrator to 1,000. l-START TIME: l-Candidate locates and reviews

10M-10.4.AAC.

1. Verify RHR Pump has 1. Candidate verifies RHR stopped. pump stopped.

l COMMENTS: i l l l f L-i 4 Page 1 of 6 Revision: 0

__ . . . . .- . - - . . ~ . _ . - . - - . - . - . . _ . - . . .- , i RTL #AS.635.J NUMBER TITLE 1CR-133 Respond to RHR Pump Trip i , STEP STANDARD (Indicate "S" for Sat. or "U"  ! ("C" denotes critical step) for Unsat.) l

2.C Stop the boration. 2.1.C Candidate places the 1MU switch in the STOP position.  ;

2.2 Candidate verifies boration flow has stopped. 4 EVALUATOR NOTE: The Candidate < may take other actions to secure the boration. It is only 4 critical that the boration be ' stopped. a l l COMMENTS: j 4 5 Page 2 of 6 Revision: 0

l l > RTL-#AS.635.J-1 ! NUMBER TITLE ' l 1CR-133 Respond to RHR Pump Trip  ! I ( t [ STEP STANDARD  ; i (Indicate "S" for Sat. or "U" l l (".C" denotes critical step) for Unsat.)

3. Investigate the cause 3. Candidate calls l of the pump trip. outside the control room to investigate t l

the cause of the pump trip.

     - t.

I EVALUATOR CUE: When called as ' l outside operator or as maintenance inform candidate , that the breaker tripped on instantaneous over current ' (probable electrical fault.) i COMMENTS:

                                                                                                                                                                                        )

l 1 l l I i l l L t Page 3 of 6 Revision: 0 I t

                 -   . _..    ..._._.m_.       . _ _ . . . . . . = _ . . _ _ _ _ _ _ . _ _ .._ _ _. _ _ _ .. _ . _

t l l I RTL #A5.635.J '

't- .

1 NUMBER TITLE I i l 1CR-133 Respond to RHR Pump Trip l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) i 4.C Start the standby pump. 4.1.C Candidate places the control switch for i [1RH-P-1B] in the Start position. 1 1 4.2 Candidate verifies 1B RHR pump has started and monitors pump  ; performance. I i l l COMMENTS: l 5.C Restore RHR flow to 5.C Candidate monitors RER approximately 4,000 flow and adjusts [MOV-

                           . gpm .                                                                        1RH-605) as necessary to restore RHR flow to    l approximately 4,000       1 9Pm.

COMMENTS: l l l [ Page 4 of 6 Revision: 0

_ _ . . _ . . _ _ . . . . _ . - . . . _ . . _ _ . . . . _ . _ - . . . _ . . _ _ _ _ . _ _ . . - _ _ _ . _ . . ~ . . . _ _ _ _ _ _ . _ . _ _ . 1 5 i RTL #A5.635.J I NUMBER TITLE 4 i 1

1CR-133.. Respond to RHR Pump Trip i

+ i + 1 STEP STANDARD l (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) j jr 6. Monitor incore 6. Candidates prints thermocouples. incore' thermocouple map OR monitors at least 2 incore thermocouples. EVALUATOR CUE: It is not necessary to-print an incore thermocouple map. 1 I COMMENTS: i

7. Refer to Technical 7. Candidate refers to Specifications. Technical Specification 3.4.1.3.

COMMENTS: Page 5 of 6. Revision: 0

  . - - . _ . -,     ..    .-.       ..   . -.       . . - ~ - - , . . . =          - - . ~ . . ~ . . _ - . . . . - - . . . ~ _.

i

RTL #AS.635.J i i -

4 NUMBER TITLE i 1CR-133 i i Respond to RHR Pump Trip  ; 1 d l l l l 4 STEP. STANDARD (Indicate "S" for Sat.'or "U" ) ("C" denotes critical step) for Unsat.) l . i

j. 8.C Notify NRC of unplanned 8.C Candidate notifies NRC l loss of RHR flow, of unplanned loss of i RHR flow. '

I EVALUATOR CUE: Your supervisor  ; will-notify the NRC of-loss of j RHR flow. ' l COMMENTS: i

9. Inform supervisor that 9. Candidate-informs actions for annunciator supervisor that actions Al-127 are complete. for annunciator Al-127 are complete.

COMMENTS: j i i

                                                                                                                                 )

j STOP TIME: i j Page 6 of 6 Revision: 0

BEAVER VALLEY JOB PERFORMANCE hEASURE

• THIS SHEET TO BE GIVEN TO CANDIDATE
• l JPM QUESTION # 1 i

~ List two common mode failures for the RHR pumps that would prevent you from starting the standby RHR pump if the running pump tripped. l L l l l- . I i ( r r l ICR-133

1 l BEAVER VALLEY JOB PERFORMANCE MEASURE N 1 JPM QUESTION # 1 i- l 4

          ' List two common mode failures for the RHR pumps that would prevent you from starting i            the ~ standby RHR pump if the mnning pump tripped.

005 000 A2.04 2.9/2.9

Obj: LP-SQS-10.1, ELO 5 Ref: lOM-10.2.A Issue 4, Rev. 3, OM Figure 10-1 d

ANSWER:

1) Vortexing if operating at reduced inventory.

2) Loss oflevel/ inventory.

3) Air entrainment

          . 4)        Loss of CCR 5)-       Closure of RHR inlet or Return isolation valves.                                         1 i-                                                                                                              ,

1 Comments: l t 1 4 l l ICR-133

BEAVER VALLEY JOB PERFORMANCE MEASURE l l t

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 2 1 I

i The RHR system is normally aligned such that part of the of the discharge passes through HCV-142 to the CVCS system. List three functions provided by the RHR to CVCS  ; connection? ' 4 ]., o I-i k 1 s-ICR-133

BEAVER VALLEY JOB PERFORMANCE MEASURE i , f l i JPM QUESTION # 2 The RHR system is normally aligned such that part of the of the discharge passes through HCV-142 to the CVCS system. List three functions provided by the RHR to GVCS connection? 005 000 K1.04 2.9/3.1 Obj: LP-SQS-10.1, ELO - 1 Ref: 10M-10.1.B Issue 4 Rev.0, OM Figure 10-1 4 ANSWER:

     'Any three:

1) RCS purification at low pressure.

2) RCS pressure control when solid.

3) Flow path for RHR boron equalization.

4) Flow path for RHR warm-up.

5) CVCS connection prevents drawing a vacuum in the RHR system when cooling down the system.

6) Inventory Control.

Comments: l 4 1CR 133

l l* I I t DUQUESNE LIGHT COMPANY I Beaver Valley Power Station l Unit 1 l 10M-10.4. AAC Residual Heat Removal PP Auto Stop l l l Issue 4 Revision 0 Prepared by Date Pagesissued Effective Date C. J. Verderber 12/19/90 AACl thru AAC3 /# / Reviewed by Date Validated by Date l W. F. Minerich 1/14/91 G. J. verderber 12/19/90 Unit 1 Mgr. Review Date OSC Meeting No. Date

        /1 ki4&&          -               "!I
                                                      /        Non-Intent                                        3/27/91 Unit 2 Mgr. Review                  Date                Approved by                                           Date N/A                                                                     M                                 #
                                   ~
                              'OR TRAiqI                                                            "" LLE                       PY NG ONvy

l Beaver Valley Power Station Unit 1 10M-10.4. A AC

   ' Residual Heat Removal System                                                    issue 4 Revision 0         ,
 ' Operating Procedures                                                                Page AAC 1 of 3          l V

V Residual Heat Removal PP Auto Stop RESIDUAL HEAT REMOVAL PP AUTO STOP A1-127 SETPOINTS Breaker Trip i DISCONNECT SWITCH: 2-1873 (2-1874), Ann Bay 2 SER POINT NUMBER: 1216 (1217) SER POINT ID: Residual Heat Removal Pump 1 A (1B) INITIATING DEVICE: Breaker 1E3 (1F3); 1 AE (1DF) 4160 VAC Stub Bus PROBABl.E CAUSE NO.1: Motor electrical protection CORRECTIVE ACTIONS:

1. Verify an RHR pump has stopped.

2. If the plant is operating at a reduced inventory /midloop condition. and the RHR pump has stopped, then go to OM 1.53C.4 AOP 1.10.2 " Loss of RHR while at Reduced Inventory /Midloop Condition."<c n

3. If during refueling, suspend all core alterations until conditions have been corrected.

l

4. If boron concentration changes are ongoing and flow is below 3000 gpm. stop the concentration change.

CAUTION: INVESTIGATING THE CAUSE OF THE PUMP TRIP PRIOR TO ATTEMPTING A START OF THE STANDBY PUMP WILL PREVENT LOSS OF TWO PUMPS TO A COMMON CONDITION.(C U

5. If the RHR pump tripped and the standby pump is available for service, and the cause of the trip is determined and it is of no consequence to the standby pump, start the standby pump and restore flow.

6. i) . R pump investigate and the system return the RHR causetoof preIthe RHRof % pump trip lgsty)i g and if plo

7. If the RHR pump cannot be restarted and the standby RHR pump is unavailable for service, then go to OM 1.53C.4 AOP 1.10.1 " Residual Heat Removal system Loss".

l Beaver Valley Power Station Unit 1 10M-10.4. A AC Residual Heat Removal System issue 4 Revision 0 [ Operating Procedures Page AAC 2 of 3 Residual Heat Removal PP Auto Stop (

8. If two RHR pumps were operating before the pump trip, then continue systern operation at reduced flow by adjusting [MOV 1RH-605], Residual Heat Removat Hx Bypass FCV, to maintain flow between 3200 gpm and 4000 gpm.

a. Determine the cause of the pump trip.

b. If possible, restart the pump and return the system to normal flow conditions.

9. Any time a loss or degraded RHR flow occurs:

a. Print a full thermocouple rnap, of

b. Log at least two incore thermocouples per core quadrandt, every 10 minutes.

10. Log RHR pump amps every 10 minutes until RHR flow is restored.

11. Refer to Technical Specification 3.4.1.3 and 3.9.8.1.

12. Notify NRC immediately on unplanned loss of RHR flow.

( l t 1 1

                                                                              'OR TRAINv'~     . i . .a NLy    O                       (

I Beaver Valley Power Station Unit 1 10M 10.4.AAC Residual Heat Removal System issue 4 Revision 0 t Operating Procedures - Page AAC 3 of 3 Residual Heat Removal PP Auto Stop

REFERENCES:

f A. TECHNICAL SPECIFICATIONS

1. BVPS-1 T.S.

! 2. BVPS-1 T.S. 3.4.1.3 l

3. BVPS-1 T.S. 3.9.8.1.

B .- UPDATED FINAL SAFETY ANALYSIS REPORT None C. COMMITMENTS

1. NRC Generic Letter 88 Midloop Operation. (0.2 on page 1) l 2. BVPS Significant Operating Event Report No. 85-4. (Page 1)

D. - ADMINISTRATIVE None l E. VENDOR INFORMATION 1 l None i i F. DRAWINGS j

1. 8700-RM-410 VOND Residual Heat Removal System i

2. 8700-R E-21J U.

G. OPERATING MANUAL

1. OM 1.53C.4 AOP 1.10.2 - Loss of RHR While at Reduced Inventory /Midloop Condition.

2. OM 1.53C.4 AOP 1.10.1 - Residual Heat Removal System Loss.

H. PLANT MODIFICATION None

1. OTHER None i

s

 ~
                                                                    'OR TRkINIlyv-                .

t. .,

                                                                                                         ~

t RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training QJT CHECKLIST /JPM TITLE: Energize Stub Busses JPM NO.: 1CR-134 COMPUTER CODE: N/A Revision No. Date Revision No. Date 1 1 l l l l PREPARED BY: DATE: APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, or Designee I t Revision 9

RTL #A5.6407 DUQUESNE LIGHT COMPANY Nuclear Power Division  ; Training Administrative Manual

                                                          ~

i

  .L                                                                                                                                            i
                                     ' LESSON PLAN-AND OJT REVISION APPROVAL SHEET I

1 I l DOCUMENT TITLE: 1CR-134, Enercize Stub Busses I l 1 l Revision Acoroval No. Brief Description Revised by: Signature Date

                                                                                                                                                )

l l l l l e I i I I {~ i > Revision 9 l -, - _

    ._ . . _ .        _ _ - _ _ _ . . _         . . _ _ . _ _ . . . . . . . _ ~ _ . . _ . _ _ _ _ . _ _ _ _ _ _ . _ . . . . _ _ . _ _ . - . . _ _ _ _ _ _ _ . _ . _ _ . _ _

1 i 1 BEAVER VALLEY JOB PERFORMANCE MEASURE I l EVALUATOR COVER SHEET 1 1 ii JPM Number: 1CR-134 Rev: O System #: 062 Faulted: O l JPM

Title:

Energize Stub Busses I i j K/A

Reference:

062 000 A4.01 3.3/3.1 Task ID #: 301 002 0601 JPM Designation: NO RO X SRO - l JPM Application: x NRC X Initial Exam [3 Training } i 1 Evaluation Method LOCATION TYPE X Perform Plant Site { Training l Simulate X ) Simulator Annual Requal. Exam Classroom OJT x Initial Operator Exam { j Administered By: Other: i ! [] BV-T l NRC  ! I Other: I 1 Evaluation Results ! Performer: Name: Employee No: Results SAT Time (minutes) i 1 Allotted: 10 UNSAT* Actual: f Time Critical: Yes x No l

• Comments' (Required for UNSAT Evaluation) :

1 1 l Evaluation Results Check here if same as above

Observer 1: Name: Employee No:

{ Observer 2: Name Employee No: 1 Observer 3: Name Employee No: ! Observer 4: Name Employee No: I Time (minutes) Results ! Question ID Allotted Actual SAT UNSAT* f Question #1 6 i Employee No: 1 Question #2 3 i Employee No: i

• Comments (Required for UNSAT Evaluation):

) i i i Evaluator (Print) : Organization: 4 j Evaluator Signature __ Date: 1 Revision 9

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

i l Task: Energize Stub Busses l INITIAL CONDITIONS: A Loss of Coolant Accident has occurred resulting in a Reactor Trip, Safety Injection and Containment Phase A and Phase B Isolations. Step four of ES-1.2, Post LOCA Cooldown and Depressurization, is being performed at this time. TASK STAN.: Stub Busses energized in accordance with 10M- i 53A.1.ES-1.2, Post LOCA Cooldown and Depressurization. i

                                                                          )

INIT. CUE: Your supervisor directs you to energize the Stub Buses using 10M-53A.1.ES-1.2, Post LOCA Cooldown and Depressurization. At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

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

After completing the task, reread the Task Standard. After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. l l l Revision 9

RIL #A5.635.J' BEAVER VALLEY JOB PERFORMANCE MEASURE f

    'jl                                    EVALUATOR DIRECTION SHEET JPM NUMBER:               1CR-134.

JPM' TITLE: Energize Stub Busses

               . RECOMMENDED t                  STARTING LOCATION:        CONTROL ROOM l                                                                                                                    i

! l l \ l DIRECTIONS: You are to perform the task energize Stub  ; i Busses. t i ! l INIT. CONDITIONS: A Loss of Coolant Accident has occurred resulting in a Reactor Trip, Safety Injection and Containment Phase A and Phase B Isolations. Step four of ES-1.2, Post l LOCA Cooldown and Depressurization, is being performed at this time. TASK STAN.: Stub Busses energized in accordance with 10M-53A.1.ES-1.2,. Post LOCA Cooldown and Depressurization. - INIT. CUE: Your supervisor directs you to energize the Stub Buses using 10M-53A.1.ES-1.2, Post LOCA Cooldown and Depressurization.

REFERENCES:

10M-53A.1.ES-1.2, Issue 1B, Revision 4 l l TOOLS: NONE l HANDOUT: NONE l l j Revision 9

l l RTL #AS.635.J NUMBER TITLE 1CR-134 Energize Stub Busses STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) Evaluator Setuo: - Initialize Simulator to IC-36. l START TIME: Candidate locates and reviews 10M-53A.1.ES-1.2, Post LOCA Cooldown and Depressurization, step 4.

1. Check 4160V stub busses 1.1 Candidate determines i l

energized. that (ACB-1E5] open. ( 1.2 Candidate determines , that (ACB-1F5] open.  ! ! COMMENTS: l Page 1 of 10 Revision: 0 i l

l l RTL #A5.635.J i NUMBER TITLE 1CR-134 Energize Stub Busses I STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unset.) i 2.C Place CCR Pumps in 2.1.C Candidate places i Pull-To-Lock. control switch for  ! [1CC-P-1A] in the Pull-To-Lock position. 2.2.C Candidate places control switch for (1CC-P-1B] in the Pull-To-Lock position.' 1 2.3.C Candidate checks control switch for [1CC-P-1C] in the Pull-To-Lock position. l COMMENTS: l l l Page 2 of 10 Revision: 0 i

i f RTL #A5.635.J

                          ~

k NUMBER TITLE 1CR-134 Energize Stub Busses l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 3.C Place Auxiliary River 3.1.C Candidate places Water Pumps in Pull-To- control switch for Lock. [1WR-P-9A] in the Pull-To-Lock position. l 3.2.C Candidate places control switch for I [1WR-P-9B) in the ! Pull-To-Lock position. COMMENTS: I i l l l 4 l l l Page 3 of 10 Revision: 0 i i l

1 RTL #A5.635.J r 1 i e, j NUMBER TITLE 1CR-134 Energize Stub Busses STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 4.C Energize the 1AE and 4.1.C Candidate closes 1DF Stub Busses, breaker [ACB-1ES). 4.2. Candidate verifies breaker closed by verifying red light illuminated. 4.3.C Candic' ate close.s l breaker [ACB-1F5] . 4.4. Candidate verifies breaker closed by verifying red light illuminated. COMMENTS: l l l 4 f l Page 4 of 10 Revision: 0 l t

RTL #A5.635.J NUMBER TITLE 1CR-134 Energize Stub Busses l l I i STEP STANDARD l (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

5. Check 480V stub busses 5.1 Candidate determines energized. that CNMT Air Recirc l fans, or CRDM shroud l fans, or PRZR Heater l Banks 2A or 2B are de- '

energized. COMMENTS: i 6.C . Place Containment Air 6.1.C Candidate places l Recirc Fans in Pull-To- control switch for l' Lock, [1VS-F-1A] in the Pull-To-Lock position. 6.2.C Candidate places control switch for [1VS-F-1B] in the Pull-To-Lock position. l l t i i Page 5 of 10 Revision: 0

l l RTL #A5.635.J l l l NUMBER TITLE 1 1CR-134 Energize Stub Busses l l l l l STEP STANDARD l (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) j l 6.3.C Candidate places / l checks control I switches for [1VS-F- i 1C) in the Pull-To-Lock position. i l I l COMMENTS: i 7.C Place CRDM Shroud Fans 7.1.C Candidate places I in Pull-To-Lock, control switch for l [1VS-F-2A] in the Pull-To-Lock position. 7.2.C Candidate places control switch for {1VS-F-2B) in the Pull-To-Lock position. l Page 6 of 10 Revision: O l l

I RTL #AS.635.J , i* - t l NUMBER TITLE i l 1CR-134 Energize Stub Busses l l STEP STANDARD . (Indicate "S" for Sat, or "U" ' l' i ("C" denotes critical step) for Unsat.) i 7.3.C Candidate places / checks control switches for [1VS-F- i 2C] in the Pull-To-  ! Lock position. COMMENTS: l l l j 8 '. C Place Pressurizer 8.1.C Candidate places Heater Banks 2A and 2B control switch for in Pull-To-Lock. Pressurizer Heater Bank 2A in the Pull-To-Lock position. i l ~ 8.2.C Candidate places control switch for Pressurizer Heater Bank 2B in the Pull-To-Lock position. COMMENTS: 2 l- Page 7 of 10 Revision: O l t i l --

   'RTL #AS.635.J

( 4 NUMBER TITLE 1CR-134 Energize Stub Busses STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 9.C Place Containment 9.1.C Candidate places Instrument Air control switch for the Compressors in Pull-To- 1A Containment Lock. Instrument Air Compressor in the' Pull-To-Lock position. 9.C Candidate places control switch for the-1B Containment Instrument Air Compressor in the Pull-To-Lock position. I I COMMENTS: l

                                                                        \

l i l Page 8 of 10 Revision: 0 l

RTL #AS.635.J i , NUMBER TITLE 1CR-134 Energize Stub Busses ) I l , l l r I STEP STANDARD (Indicate "S" for Sat. or "U" s l ("C" denotes critical step) for Unsat.) , 10.C Dispatch operator to 10.C Candidate dispatches locally close substation coerator to locally 1-8 and 1-9 breakers 8N16 close substation 1-8 l and 9P16. and 1-9 breakers 8N16 l and 9P16. Evaluator Cue: When directed to close 8N16 and 9P16, close breakers using EPS138 and i EPS140 and report to candidate I that 8N16 and 9P16 are closed. l j l COMMENTS: l t I  ! l l Page 9 of 10 Revision: 0 1

l ! 'RTL #AS.635.J f. l l NUMBER TITLE 1CR-134. Energize Stub Busses l l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) I I

11. Dispatch operator to 11. Candidate dispatches

locally close substation operator to locally ,

1-8 and'l-9 breakers 8N22 close 480V substation { and 9P21 1-8 and 1-9 breakers i l 8N22 and 9P21- I f l i Evaluator Cue: When directed I to close 8N22 and 9P21, report l that the breakers are closed. l

l. (It is not necessary to )

simulate closing breakers.) ) i ( COMMENTS:

12. Inform supervisor that 12. Candidate informs  !

the Stub Busses have . supervisor that the Stub been energized. Busses have been reenergized. 1 COMMENTS: l' STOP TIME: l 1 l Page 10 of 10 Revision: 0

' i l

i BEAVER VALLEY JOB PERFORMANCE MEASURE 1

• THIS SHEET TO BE GIVEN TO CANDIDATE *  !

o i JPM QUESTION # 1  ! l List two different loads which were re-energized when MCCI-ElI was reenergized. i i ( l l I i i ICR-134

I t

. BEAVER VALLEY JOB PERFORMANCE MEASURE l

l1 - I l JPM QUESTION # 1 List two different loads which were re-energized when MCCl-ElI was reenergized. i l 062 000 K4.07 2.9/3.3 I; Ref: lOM-37.5.B.7 Issue 4, Rev. 9 Obj: LP-SQS-37.1 ELO # 1 ANSWER-l Any Two o Boric Acid Transfer Pump 2A , o Containment Air Compressor I A o Beric Acid Tank Heaters o Heat Trace o Containment Purge Supply and Exhaust Valves o Safeguards Area Sump Pump , o Emergency Lighting r Comments: i' i ICR-134 1' -, - .,

l l i l. l 3 BEAVER VALLEY JOB PERFORMANCE MEASURE p. i

• THIS SHEET TO BE GIVEN TO CANDIDATE
• i JPM QUESTION # 2 Explain why the Stub Busses are de-energized by a containment phase B (CIB) isolation.

l i i i I 1 l 2 1 ,. i lI i l l l J r i ICR-134

BEAVER VALLEY JOB PERFORMANCE MEASURE I JPM QUESTION # 2 Explain why the Stub Busses are de-energized by a containment phase B (CIB) isolation. 062 000 K4.02 2.5/2.7 Ref: lOM-36.1.C Issue 4, Rev.1 Obj: LP-SQS-37.1 ELO # 2 1 ANS%TR: l l The stub busses are de-energized to secure power to loads which are not required during l an DBA on a CIB. Comments: i i l F-ICR-134

I i BVPS - E0P 10M-53A.1.ES-1.2(ISS13) l Number Title l 4 ES-1.2 Post LOCA Cooldown And Depressurization Issue IB Revision 4 l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. Enercize Stub Busses

a. Check 4160V stub busses - a. Energize 4160V stub busses as l ENERGED follows:

                  .                                                                                             l
                    . L,0 ,-1E5] 1AE stub bus -                 1) Place the following equipment              .

3ED control. switches in l PULL-TO-LOCK:

                '.      LACB-1F5] 10F stub bus -                                                                l

[1CC-P-1 A,1B,1C] , CCR Pumps

                                                                                                               ~

- CLOSED .

                                                                      .    [1WR-P-9A,9B] , Aux RW Pumps

2) To energize IAE(IDF) stub bus, close [ACB-1E5(1F5)] .

b. Check 480V stub busses - b. Energize 480V stub busses as ENERGIZED follows:

                     .   [1VS-F-1A(B)(C)], CNMT Air               1) Place the following equipment Recirc Fans - RUNNING                        control switches in PULL-10-LOCK:

.(

                                           -0R-

~

                                                                      .     [1VS-F-1A,B,C] , CNMT Ai r
            ,        .    [1VS-F-2A(B)(C)], CRDM Shroud                    Recirc Fans Fans - RUNNING  ~
                                                                       .    [1VS-F-2A,B,C],     CRDM
                                           -0R-                            Shroud Fans
                     . PRZR Heater Banks 2A or 28 -                 . PRZR Heater Banks 2A and 2B ENERGIZED
                                                                       .    [11A-C-1A,B] , CNMT Instr Air Compressors

2) Locally close 480V stub bus substation 1-8(1-9) breakers

' 8N16 and 9P16 (Service Bldg - 713', Normal and Emergency l - Switchgear).

3) Locally close 480V substation l 1-8 (1-9) Bkrs 8N22 (9P21),

i 480V 1AE (10 ) stub bus feed to MCC1-E11 E12) (Service

                                      ~

Bldg - 713', Emergency , Swi tchgear) .  ! COR TRAINING ,0NLY i lEs12 8/21/96 3 of 26

i RTL #AS.640E- DUQUESNE LIGHT COMPANY I Nuclear-Power Division Training Administrative Manual

     -{ .                                                    _

l l OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training i SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Start CNMT Instrument Air Compressor l l JPM NO.: 1CR-135 i l COMPUTER CODE: N/A i . 1 ! I l 1

. Revision No. Date Revision No. Date l 'i L ,

1 I

                                                                                                                                                   \

l l l t i i l PREPARED BY: DATE: l l l l APPROVED FOR {. IMPLEMENTATION: DATE:

l. Director, Operations Training,

[ or Designee t' l f' Revision 9 i . .

l l l RTL #AS,640E DUQUESNE LIGHT COMPANY [ Nuclear Power Division , Training Administrative Manual l 1 l LESSON PLAN AND OJT REVISION APPROVAL SHEET l l DOCUMENT TITLE: 1CR-135, St3rt CNMT Instrument Air Comoressor i l 1 l Revision Approval I No. Brief Description Revised by: Signature Date I l l l l l 1 l l l l lI O i t I I l l Revision 9

i l , l 3 BEAVER VALLEY JOB PERFORMANCE MEASURE , EVALUATOR COVER SHEET .ii i JPM Number: 1CR-135 Rev: 0 System #: 000 065 Faulted: O l JPM

Title:

Start CNMT Instrument Air Compressor l i K/A

Reference:

000 065 G9 3.1/3.1 Task ID #: 078 00 0101 JPM Designation: NO RO X SRO JPM Application: X NRC X Initial Exam [3 Training l Evaluation Method LOCATION TYPE X Perform [3 Plant Site Training j [] Simulate X Simulator Annual Requal. Exam ! Classroom [3 OJT X Initial Operator Exam ! Administered By: Other: I BV-T l

[] NRC l Other:

4 Evaluation Results ! Performer: Name: Employee No: l Results SAT Time (minutes) l. [3 UNSAT* Allotted: 8 Actual: Time Critical: Yes x No {

• Comments (Required for UNSAT Evaluation) :

i 1 l Evaluation Results Check here if same as above i Observer 1: Name: Employee No: I ] Observer 2: Name Employee No: Observer 3: Name _ Employee No:

Observer 4

Name Employee No:

i Time (minutes) Results ! Question ID Allotted Actual SAT UNSAT* f Question #1 3 . Employee No: ] Question #2 3

!         Employee No:

)

• Comments (Required for UNSAT Evaluation):

Evaluator (Print) : Organization: Evaluator Signature Date: Revision 9

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE i CANDIDATE DIRECTION SHEET { THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Task: Start CNMT Instrument Air Compressor INITIAL A Loss of Coolant Accident has occurred, CONDITIONS

• resulting in a Reactor Trip, Safety Injection and Containment Phase A and Phase B isolation. The stub busses have been re-energized following the CIB. Step 5 of 10M 53A.1.ES-1.2, Post LOCA Cooldown and Depressurization, is in progress at this time. Containment Instrument Air Compressor 1B is on clearance.

TASK STAN.: Containment Instrument Air Compressor started in accordance with 10M 53A.1.ES-1.2. INIT. CUE: lYoursupervisordirectsyoutorestoreContainment Instrument Air in accordance with 10M 53A.1.ES-1.2, Post LOCA Cooldown and Depressurization. At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. I ! After completing the task, reread the Task Standard. After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. l I i Revision 9

RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET { JPM NtP23R': 1CR-135 I' 1 Start CNMT Instrument Air Compressor RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to perform the task start CNMT Instrument Air Compressor. INIT. CONDITIONS: A Loss of Coolant Accident has occurred, resulting in a Reactor Trip, Safety Injection and Containment Phase A and Phase B isolation. The stub busses have been re-energized following the CIB. Step 5 of 10M 53A.1.ES.1.2, Post LOCA Cooldown and Depressurization, is in progress at this time. Containment Instrument Air Compressor 1B is on clearance. TASK STAN.: Containment Instrument Air Compressor started in accordance with 10M 53A.1.ES-1.2.

        .INIT. CUE:            Your supervisor directs you to restore Containment Instrument Air in accordance with 10M 53A.1.ES-1.2, Post LOCA Cooldown and Depressurization.

REFERENCES:

10M 53A.1.ES-1.2, Issue 1B, Revision 4. TOOLS: NONE HANDOUT: NONE I Revision 9

I l-l RTL #AS.635.J NUMBER TITLE 1CR-135 Start CNMT Instrument Air Compressor l . ~ . _ i I STEP STANDARD (Indicate "S for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR SETUP: - Initialize Simulator to IC-37. Danger Tag the 1B Containment Instrument l

                                           , Air Compressor [1A-C-1B].

l 4 l START TIME: Candidate locates and reviews 10M 53A.1.ES-1.2, Post LOCA Cooldown and Depressurization, step 5. t 1 I I Page 1 of 6 Revision: 0

l RTL #AS.635.J

                                                                                      ~

NUMBER. TITLE 1CR-135, Start CNMT Instrument Air' Compressor  ! STEP STANDARD (Indicate "S" for Sat. or "U" t l ("C" denotes critical step) for Unsat.) J

1. Check at least one 1. Candidate verifies instrument air that no containment compressor running, instrument air compressors are running.

l COMMENTS': l

                   -2.            Check at least one               2.               Candidate dispatches l                                  chiller in service.                               operator to verify l

that [1VS-E-3A, 3B, or 3 C] in service. EVALUATOR CUE: Report that j [1VS-E-3A] is in service.  ! EVALUATOR NOTE: Candidate may l also verify status by checking L annunciators. t f l l COMMENTS: I-l Page 2 of 6 Revision: 0 l' I

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

I RTL'#A5.635.J 4 NUMBER TITLE 1CR-135 Start CNMT Instrument Air Compressor l l l i STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 3.C Open containment Recirc 3.1.C. Candidate places Cooling Coils AC/RW control switch for outlet isolation [TV-1CC-110D) in the valves. open position. 3.2 Candidate verifies [TV-1CC-110D] open by verifying the red indicating light is lit and the green indicating light is dark. 3.3.C Candidate places control switch for [TV-1CC-110F2] in the open position. 3.4 Candidate verifies [TV-1CC-110F2] open by verifying the red indicating light is lit and the green indicating light is dark. COMMENTS: i i l Page 3 of 6 Revision: 0

l l RTL #A5.635.J l

NUMBER TITLE I

1CR-135 Start CNMT Instrument Air Compressor STEP STANDARD l (Indicate "S" for Sat. cr "U" l ("C" denotes critical step) for Unsat.) 4.C Open containment Recirc 4.1.C Candidate places Cooling Coils AC system control switches for inlet isolation valves. [TV-1CC-110E2] in the open position. 4.2 Candidate verifies [TV-1CC-110E2] open by l verifying the red indicating light is lit and the green indicating light is dark. 4.3.C Candidate places control switch for (TV-1CC-110E3] in the open position. 4.4 Candidate verifies [TV-1CC-110E3] open by verifying the red indicating light is i lit and the green l indicating light is  ! dark. l COMMENTS: Page 4 of 6 Revision: 0

l l RTL #A5.635.J  ! ! j. _ NUMBER TITLE 1CR-135 Start CNMT Instrument Air Compressor l i STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) I-l 5.C Start an available 5.1.C Candidates places containment instrument control switch for L air compressor. [1IA-C-1A] in the START or AUTO position. L.2 Candidate verifies the (11A-C-1A] containment instrument air compressor.is running by verifying the red ' indicating light is , lit. COMMENTS: I l l l j Page 5 of 6 Revision: 0

RTL #A5.635.J t - NUMBER TITLE i 1CR-135 Start CNMT Instrument Air Compressor l l l

j. STEP STANDARD l (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.)

6. Check that CNMT 6. Candidate checks that instrument air pressure containment instrument is available. air pressure is > 85 psig, or that Annunciator A6-110, CNMT INSTR AIR SYSTEM PRESS LOW is not lit.

COMMENTS: I l 7. Inform supervisor that 7. Candidate informs a containment supervisor that a instrument air containment instrument  ! compressor has been air compressor has'been , started. started.

                                                                                                                                ]

COMMENTS: STOP TIME: l l l l , l Page 6 of 6 Revision: 0

( BEAVER VALLEY JOB PERFORMANCE MEASURE l !i

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 1 l Explain how Containment Instnament Air is maintained if both Containment Instrument l Air Compressors are lost.

I' l l l l l l r-ICR-135

l. BEAVER VALLEY JOB PERFORMANCE MEASURE I, l JPM QUESTION # 1 i

Explain how Containment Instrument Air is maintained if both Containment Instrument

                                                                                    ~

Air Compressors are lost. i 078 000 K3.03 3.0/3.4 L Ref: IOM-53C.4.1.34.2, Issue 3A, Revision 3 Obj: LPS-SQS-34.1 ELO 4 ANSWER: The operator manually cross connects Station Instrument Air with Containment Instniment Air. 1. Comments: 3 h

                  +

ICR-135

    -  ..       ..  . - .    .  .      -. . ~ . _ . . .      .  . . - . . _ .     . . .    - . - - . - - .

i l l BEAVER VALLEY JOB PERFORMANCE MEASURE k

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 2 l

l What affect will a loss of Containment Instmment Air have on the Pressurizer Level and Pressure Control Systems? l ' l l l i l \ 1 l I l I i I l l l^ r l' ICR-135

BEAVER VALLEY JOB PERFORMANCE MEASURE JPM QUESTION # 2 L What affect will a loss of Containment Instrument Air have on the Pressurizer Level and Pressure Control Systems? , 000 065 EA2.08 2.9/3.3

         ' Ref: lOM-53C.4.1.34.2, Issue 3 A, Revision 3 Obj: LP-SQS-53C.1 ELO 3 ANSWER:

The pressurizer spray valves and PORVs will fail closed and letdown will isolate. Comments: l i 1 l l ICR-135

10M-53 A.1. ES-1.2 (ISSIB) 3VPS - E0P Title Issue IB f N cber Post LOCA Cooldown And Depressurization Revision 4 ES-1.2 RESPONSE NOT OBTAINED - STEP ._ ACTION / EXPECTED RESPONSE

     /5 \ Verify CNMT Instrument Air -

AVAILABLE

a. Perform the following:

a. CNMT Instr Air Compressor - AT '

LEAST ONE RUNNING 1) Check at least one chiller

                 -                                                [1.'is-E-3A,B,C] in service.

jf chiller can 80I be placed

                #                                                 in service, IBEN GO TO Step

- 5.b.

2) Oper. [TV-1CCt110D,F2] CNMT Recirc Cig Coils AC/RW Outlet CNMT Isol Viv.

3) Open [TV-1CC-110E2,E3] CNMT Recirc Clg Coils AC Sys Inlet CNMT Isol Vivs.

4) Start an available

[11A-C-1A(B)] CNMT Instr Air Compressor.

5) If available, place the standby CNMT Instr Air Compressor in AUTO.

b. Perform the following:

b. Check the following:

1) Verify at least one station

• CNMT instrument air header air compressor or the diesel pressure on [PI-11A-106A] - air compressor is RUNNING.

GREATER THAN 85 PSIG

                     .                                            2) Dispatch operator with Key .
                                          -0R-                         SR/0.G to open [11A-90] Instr Air Viv To CNMT Instr Air Isol e   Annunciator A6-110. "CNMT                   Viv (West Cable Vault - 735') .

INSTR AIR SYSTEM PRESS LOW" - WHEU [11A-90] has been opened, NOT LIT IEEB place both CNMT Instr Air Compressors in PULL-TO-LOCK.

                                        ~

c0R TRAINING OelLY

                                               .I 4 of 26 1E512 8/21/96

r i I i l i RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual  !

     $                                                                                                                                                   \

1 l OJT CHECKLIST /JPM COVER PAGE PROGRAM' TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Operate Feed following SG HI-HI Level , i l L- JPM NO.': 1CR-136 I COMPUTER CODE: N/A 1 l- ) Revision No. Date Revision No. Date  ; I l t i 1 PREPARED BY: DATE:

                                                                                                                                                      'l l

1 APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, dr Designee W 1 i Revision 9 - 2

I l- ~RTL #AS.640E DUQUESNE LIGHT COMPANY i Nuclear Power Division

                                              . Training Administrative Manual S,

l LESSON PLAN AND OJT REVISION APPROVAL SHEET I l l DOCUMENT TITLE: 1CR-136. Ooerate Feed followina SG HI-HI Level

• l' Revision Acoroval No. Brief Description Revised by: Signature Date h

f i I s f f l. i I . i f l'- I i i k ll t I. Revision 9-

? l 1 BEAVER VALLEY JOB PERFORMANCE MEASURE i EVALUATOR COVER SHEET ! JPM Number: 1CR-136 Rev: 0 System #: 059 Faulted: O l 1 JPM

Title:

Operate Feed following SG HI-HI Level l l l K/A

Reference:

059 000 A2.03 2.7/3.1 Task ID #: 059 006 0101 l , JPM Designation: NO RO Ud SRO - l JPM Application: X NRC X Initial Exam Training } l Eva.luation Method LOCATION TYPE l- X Perform [3 Plant Site [3 Training [] Simulate x Simulator Annual Requal. Exam i

Classroom OJT X Initial Operator Exam

Administered By: [3 Other:

. BV-T ! NRC 5 [3 Other: 1 Evaluation Results Performer: Name: Employee No: l j Results SAT Time (minutes)  ; ' UNSAT* Allotted: 18 Actual: l i Time Critical: Yes x No !

• Comments'(Required for UNSAT Evaluation):

4 .i Evaluation Results Check here if same as above Observer 1: Name: Employee No: Observ.er 2: Name__ Employee No: i Observer 3: Name Employee No: Observer 4: Name Employee No: Time (minutes) Results l l Question ID Allotted Actual SAT UNSAT* ! Question #1 3

Employee No:

i Question #2 3 [3

j. Employee No:

{

• Comments (Required for UNSAT Evaluation):

j { Evaluator (Print): Organization: a 4 i Evaluator Signature Date:

Revision 9

 .            _.           . .    - _ .    -   - . . _ . - ~.          - .

RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET i THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

l Task: Operate Feed following SG HI-HI Level' INITIAL The reactor was operating at 55% power when a CONDITIONS: regulating valve controller failure resulted in high-high level on the 1B SG. This resulted in a turbine and reactor trip, and automatic start of all auxiliary feedwater pumps. 10M-24-4.N, Feedwater System Operation After HI-HI SG Level Trip, is progress and has been completed through' step 15. All conditions have been met to start one main feedwat- r pump and transfer feeding of steam generators from auxiliary feedwater to main feedwater. t TASK STAN.: Main feedwater'and auxiliary feedwater aligned in accordance with 10M-24.4N, Feedwater System Operation After HI-HI SG Level Trip. INIT. CUE: Your supervisor directs you to start the 1A Main Feedwater Pump and to transfer feedwater control from auxiliary feedwater to main feedwater in i accordance with 10M-24.4N, Feedwater System Operation After HI-HI SG Level Trip. At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce "I am now beginning the JPM". Simulate performance or perform as directed the required task. i Point to any indicator or component you verify or check and i announce your observations. i After completing the task, reread the Task Standard. After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. I Revision 9

1 1 i l ! RIL flA5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET l JPM tmMBER: 1CR-136 l JPM TITLE: Operate Feed following SG HI-HI Level RECOMMENDED STARTING LOCATION: CONTROL ROOM 1 l DIRECTIONS: You are to perform the task operate feed l following SG HI-HI level. INIT. CONDITIONS: The reactor was operating at 55% power when a regulating valve controller failure resulted in high-high level on the 1B SG. l This resulted in a turbine and reactor trip, and automatic start of all auxiliary feedwater pumps. 10M-24-4.N, Feedwater System Operation After HI-HI SG' Level Trip, is progress and has been completed through step 15. All conditions have been met to start one main feedwater pump and transfer feeding of steam generators from auxiliary feedwater to main feedwater. I TASK STAN.: Main feedwater and auxiliary feedwater aligned in accordance with 10M-24.4N, Feedwater System Operation After HI-HI SG Level Trip. INIT. CUE: Your supervisor directs you to start the 1A Main Feedwater Pump and to transfer feedwater control from auxiliary feedwater j to main feedwater in accordance with 10M-24.4N, Feedwater System Operation After HI-HI SG Level Trip.

REFERENCES:

10M-24.4N, Issue 3, Revision 1 10M-24.4A Issue 4, Revision 0 TOOLS: NONE RANDOUT: 10M-24.4N, Feedwater System Operation After HI-HI SG Level Trip. l Revision 9

 . _. . ..    .    .  . _ .  - -..~..       .-     - . . .  ... . _ - - .  . . - .   . - _ _ .

1 RTL #A5.635.J i NUMBER TITLE 1CR-136 Operate Feed Following SG Hi-Hi Level. 4 J STEP STANDARD (Indicate "S" for Sat, or "U" ("C" denotes critical step) for Unsat.) Evaluator Setuo: - Initialize Simulator to IC-42. Ensure main feed pumps are in Pull-to-Lock. START TIME: 1 Candidate locates and reviews 10M-24.4N, Feedwater System i Operation After Hi-Hi SG Level Trip. 1 1 Evaluator Cue: Provide candidate with copy of 10M24.4.N. Inform candidate 1 that procedure steps 1 through 15 are complete. l l l Candidate locates and reviews l 10M-24.4.A, Steam Generator l Feedwater System Startup. Page 1 of 6 Revision: 0

1 RTL #A5.635.J l 1 i NUMBER TITLE 1CR-136 Operate Feed Following SG Hi-Hi Level. STEP STANDARD I (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) I 4 i Evaluator Cue: Provide candidate with copy of 10M24.4.A. Inform candidate , that procedure steps A.1 i through A.7 are complete and  ; that an operator is standing by the 1A Main Feedwater Pump. , Remind Candidate the'Feedwater  : Bypass FCV's are approximately  ; 3% open. = 1 4 Start _ main feedwater pump. 1.C 1.1.C Candidate places i control switch [1FW-P- l 1Al in START and ' holds. 1.2 Candidate verifies both motors have started. 1.3 Candidate verifies l [MOV-1FW-150A] starts I to open. l 1.4 Candidate verifles ' [FCV-1FW-150Al starts to open. 1.5.C Candidate releases control switch for [1FW-P-1A). Page 2 of 6 Revision: O d

                                                                  -                                 r . -

 . ._    -   .  ..    . . . - . - . -   . . . . . . ~ . - .~      . . - . .    - ~ . - . - . . - . .      . . . - . . . - . .

d e 4 RTL #A5.635.J i. l NUMBER TITLE 1CR-136 Operate Feed Following SG Hi-Hi Level. 4 STEP STANDARD (Indicate "S" for Sat. or "U" 3 ("C" denotes critical step) for Unsat.) 1.6 Candidate verifies normal pump amps. 1.7 Candidate verifies (MOV-1FW-150A] open. COMMENTS: Evaluator Cue: Another operator will. perform steps 12 through

                                                                                                                              ]

18. Continue with first 1 l

procedure. Evaluator Note: Steam generator level will begin to increase as soon as feedwater pump is started. It is not expected that candidate will be able to maintain level within 5% of program level.  ! Page 3 of 6 Revision: 0

l l l RTL #AS.635.J l l l NUMBER TITLE 1CR-136 Operate Feed Following SG Hi-Hi Level.  ! 1 I l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l 2.C Transfer feeding of 2.1.C Candidate slowly opens steam generators to each feedwater bypass l Bypass Valves. control valves while slowly closing the l auxiliary FW throttle control valves. 2.2.C Candidate places control switche.s for (1FW-P-3A and 3B] in OFF after all auxiliary FW throttle control valves are closed. 2.3.C Candidate maintains SG level using FW bypass control valves. l Evaluator Note: Candidate may l choose to place bypass control i jvalves in AUTO.  ! l COMMENTS: ' i l t Page 4 of 6 Revision: 0

I 1 I I RTL #A5.635.J j i i NUMBER TITLE  ! 1CR-136 Operate Feed Following SG Hi-Hi Level. STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)  !

3. Align Auxiliary 3.1.C Candidate fully opens Feedwater for automatic [FCV-1FW-151A -F] and operation. verifies valves open by observing red indicating lights light and green indicating lights ,

dark. ' 3.2.C Candidate places control switches for [1FW-P-3A and 3B] in the Auto Position. COMMENTS: i Page 5 of 6 Revision: 0

_..._.m.._ .._m__ . _ f , l l [ RTL #AS.635.J t 4 I NUMBER TITLE 1 l  ! 1CR-136 Operate Feed Following SG Hi-Hi Level. i l l l STEP STANDARD L (Indicate "S" for Sat. or "U"  ! ("C" denotes critical step) for Unsat.) l

4. Inform supervisor that 4. Candidate informs' SG levels are being supervisor that SG maintained by FW bypass levels are being  !

flow and that Auxiliary maintained by FW j FW is aligned for bypass flow and that  ; automatic start. Auxiliary FW is l l aligned for automatic  ! I start. I i l COMMENTS- 1 STOP TIME: i l. t r Page 6 of 6 Revision::0

        . . .         .       .        . .         . ~ .  . - _ - . -.~. -. . - . -       . _ . . ,- .

l l l BEAVER VALLEY JOB PERFORMANCE MEASURE l i

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 1 l

l l' The procedure restores the Auxiliary Feedwater Flow Control Valves to the full open position. Why are these valves left in this position? l l I 1CR-136

t 1 i BEAVER VALLEY JOB PERFORMANCE hEASURE ) l l' I i JPM QUESTION # 1 ' ! i l  ! The procedure restores the Auxiliary Feedwater Flow Control Valves to the full open position. Why are these valves left in this position? 059 000 A4.I13.1/3.3

       ' Ref: 10M-24.2.A Issue 4, Revision 2 Obj: LP-SQS-24.1, ELO-7 ANSWER:

This ensures full flow will be available if AC power is lost. Comments: - I l I I 1CR-136

l l i l BEAVER VALLEY JOB PERFORMANCE MEASURE , i

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 2 l i

The feedwater isolation that occurred resulted in a reactor trip. Explain why the reactor  ! tripped (Which trip signal caused the reactor trip?)  !

                                                                                                               .'i I

l l l 1 E l l I-l i 1 ICR-136

       .                _ _ _ .       .. _ .     . . . _ ~ . _ _ . . . .__           . - . . . _ . _ . - . _ - . . _ . . . _

l 1 BEAVER VALLEY JOB PERFORMANCE MEASURE t lt l-I JPM QUESTION # 2 l The feedwater isolation that occurred resulted in a reactor trip. Explain why. the reactor tripped. (Which trip signal caused the reactor trip?) l l 059 000 A3.06 3.2/3.4 i Ref: 1OM-24.2.B, Issue 4, Revision 0 Obj: LP-SQS-24.1, ELO-5 l ANSWER:

Lo-Lo level on the other two steam generators, or turbine trip - reactor trip.

i i l Comments: i i l l i l l l l 5 i r ICR-136

Record Type #A9.3308 f DUQUESNE LIGHT COMPANY Beaver Valley Power Station I i t Unit 1 1 i . I i i 4 i i i ! 10M-24.4.A 4 1 Steam Generator Feedwater I. System Startup l t 4 Issue 4 Revision 0 Prepared by Date Pages issued Effective Date R. J. Wolfe 01/20/93 A1 through A6 (JUL 2 6 %95; Reviewed by Date Validated by Date R. Prit.e 09/20/93 J. E. Burnecke 07/10/95 G. P. Smith 06/24/95 Unit 1 Manager Date OSC Meeting No. Date N/A Non-Intent 07/12/95 Unit 2 Manager Date Appro,ved by Date . N/A / (,, h & ' 7l,9,/95 ( c0R %. . ,; oay CONTR0 RED _. . . _ . . ._lEtMT-3@ 1AlWRT1. -

s Beaver Valley Power Station Unit 1 10M-24.4. A Steam Generator Feedwater System issue 4 Revision 0 { Operating Procedures Page A 1 of 6 Steam Generator Feedwater System Startup

1. PURPOSE This procedure provides steps necessary for starting the first steam generator feed pump.

Equipment numbers for the 1B main feed pump are in sarentheses. II. PRECAUTIONS AND LIMITATIONS A. If a main feedwater pump trips during this procedure, an auxiliary feedwater pump is expected to auto-start and will not be considered as an ESF actuation. B. To comply with T.S. 3.7.1.2, no more than one motor driven auxiliary feedwater pump can be placed in PULL-TO-LOCK at a time during Modes 1,2, or 3. However, if [1FW-P-2], Turb AFW Pump is INOPERABLE, then both motor driven AFW pumps control switches must remain in AUTO. lit. INITIAL CONDITIONS Note: When steam generator pressure exceeds 500 psig. a main feed pump is required l to supply feedwater, since condensate pump flow decreases above this pressure and will be inadequate to feed steam generators. A. High pressure feedwater is required to steam generators. B. Main feedwater system is aligned and capable of supplying feedwater to steam generators. C. Main feedwater pump suction pressure is > 300 psig. D. Ensure the following valves are partially open (BB-C).

1. [FCV-1FW-479],1 A SG FW Bypass FCV

2. [FCV-1FW-489],18 SG FW Bypass FCV

3. [FCV-1FW-499],1C SG FW Bypass FCV Note: It is preferred to have both [1CN-P-1 A and 18], Main Condensate Pumps, in service, to ensure adequate suction pressure when start.ing a main feedwater pump in this procedure.

E. If available for operation, both [1CN-P-1 A and 18] Condensate Pumps are operating. l cog ,i % ...iu ONiy L

Beaver Valley PoNer Station Unit 1 10 M-24.4. A Steam Generator Feedwater System

                                                                                        ~

' issue 4 Revision 0 . k Operating Procedures Page A 2 of G Steam Generator Feedwater System Startup k IV. INSTRUCTIONS A. Pump Startup

1. Place motor and pump bearings on IPC trend for pump startup monitoring.

[1FW-P-1 A] [1 FW-P-18] T2326A (T2386A) FW PMP 1 A1(181) MTR STATOR T T2327A (T2387A) FW PMP 1 A2(182) MTR STATOR T T2320A (T2380A) FW PMP 1 A1(181) MTR INBD BRG T T2321 A ~ (T2381A) FW PMP 1A1(1B1) MTR OUTBD BRG T T2322A (T2382A) FW PMP 1 A2(182) MTR INBD BRG T T2323A (T2383A) FW PMP 1 A2(182) MTR OUTBD BRG T T2324A (T2385A) FW PMP 1 A(1B) OUTBD END BRG T T2325A (T2384A) FW PMP 1 A(18) INBD END BRG T

2. Check Closed the following valves (BB-C).

a. [FCV-1FW-478],1 A SG Main FW Feed Reg Viv

b. [FCV-1FW-488],1B SG Main FW Feed Reg Viv

c. [FCV-1FW-498], CA SG Main FW Feed Reg Viv

3. Check Closed the following valves (BB-C),

{'

a. [MOV-1FW-154A],1 A SG Main FW isol Viv

b. [MOV-1FW-154B],1B SG Main FW lsol Viv

c. [MOV-1FW-154C],1C SG Main FW lsol Viv

4. Place [1FW-P-1 A AND 1B], Main FW 1 A AND B Pump, control switches in PULL-TO-LOCK, (BB-C).

5. Check Closed [MOV-1FW-150A AND B],1 A AND B Main FW Pump Disch Vlv, (BB-C).

6. Perform the following at [1FW-P-1 A(18)], Main FW 1 A(18) Pump, to be started, (Turb Bldg. 693'):

a. . Check oil sump for level of 21/2" in sightglass.

b. Ensure main feed pump auxiliary oil pump control switch is in MANUAL AND pump is running with a discharge pressure 210 psig on [PI-LO-205A(B)],

1 A(1B) SGFP Bearing Oil Supply, (Turb Bldg. 693').

c. Open [1FW-214(215)], Bypass for [MOV-1FW-150A(B)], to allow pump casing warm up, (Turb Bldg. 693').

d. Check Closed [1FW-215(214)], Bypass for [MOV-1FW-150B(A)], (Turb Bldg, S$ ' *" '-

i C0R TRAnmG ONLY

     - - _ . . ~ . . .                    .           .   ..       .       - -           . -       .   . . -      - - _ _ -     . . - _.

Beaver Valley Power Station Unit 1 10M-24.4. A Steam Generator Feedwater System issue 4 Revision 0 k Operating Procedures Page A 3 of 6

 ,                 Steam Generator Feedwater

( System Startup

e. Vent inboard AND outboard pump seals by opening all four seal package vent valves on lines to and from seal coolers, (Turb Bldg 693').

1) Close vent valves when a solid stream of water is seen. l

f. Check cooling water flow through.

1) [FE-1CC-101 A(B)],1 A(1B) SGFP Coolers Combined CCT Return, (Turb l Bldg. 693').

l

2) [FE-1CC-205A1(B1)],1 A(18) SGFP Stuffing Box Jacket CCT Return, (Turb l Bldg 693').

3) [FE-1CC-205A2(B2)],1 A(18) SGFP Stuffing Box Jacket CCT Return, (Turb Bldg, 693').

g. Check the following for < 120F temperature:

1) [TI-1CC-205A1(B1)], Main Feedwater Pump 1 A(B) Outboa.-d Seal Wtr inlet Temp to Seal Cir, (Turb B!dg,693').

2) [TI-1CC-205A2(B2)], Main Feedwater Pump 1 A(B) Inboard Seal Wtr Inlet Temp to Seal Ctr, (Turb Bldg,693').

h. Check [TI-1LO-205A(B)], Main Feedwater PP 1 A(B) Oil Cooler Outlet Temp,

( for temperature < 155F, (Turb Bldg. 693').

Note: Normal seal leakage is none. Mechanical seals often leak slightly at startup and require varying amounts of "run-in" time. A large leak would indicate a seal failure. 1

i. Check seal for excess leakage.

7. If main feed pump 4KV busses 4KV Bus 1 A AND 1B (1C AND 1D) are being supplied by unit station service transformers, Perform a Hot bus transfer to the system station service transformers in accordance with 10M-36.4.B, "4KV Station Service System Shutdown," Part A.

Note: If 4KV bus voltage cannot be raised to provide adequate bus potential, then l starting the main feed pump will cause a bus voltage drop, resulting in an I expected emergency diesel generator auto-start. Diesel auto-start for this condition is not considered an ESF actuation.

a. If 4KV Bus 1 A OR 1B (1C OR 1D) voltage is < 127 VAC, (VB-C), Perform the following:

1) Adjust voltage on 4KV Bus 1 1hfND'1D) using oad T

!, Changers, Bus 1 A(18)(1C)(1D) 4160V LowerMa*ile' &dAdto C),

   \                                               until voltage indicates 2127 VAC and less than 129 VAC.

Beaver Valley Power Station Unit 1 10 M-24.4. A i Steam Generator Feedwater System issue 4 Revision 0 , 4 Operating Procedures Page A 4 of 6 Steam Generator Feedwater , System Startup (,

2) Ensure Load Tap Changer, Bus 1 A AND 1B (1C AND 1D) 4160V Lower Raise & Auto SWs, are in MAN (Control Switch pushed in toward Vertical Board).

8. Place control switch for [1FW-P-1 A(1B)], Main FW 1 A(1B) Pump, in START AND Hold UNTIL the following transpires:

a. When oil pressure is > 10 psig, Verify first motor breaker closes (red light and ammeter indication, (BB-C).

b. 1.5 seconds later, Verify second motor breaker closes (red light and ammeter indication), (BB-C).

c. Verify [MOV-1FW-150A(B)],1 A(1B) Main FW Pump Disch Viv, starts to Open, (BB-C).

d. Verify [FCV-1FW-150A(B)], SG Main FW Pump 1 A(1B) Recirc Viv, starts to Open, (BB-C).

9. Release [1FW-P-1 A(1B)], Main FW 1 A(1B) Pump, control switch to spring return to NORM AL, (BB-C).

10. Verify Main FW Pump Amps return to normal running current approximately (400 amps), (BB-C). ..

11. Ensure [MOV-1FW-150A(B)],1 A(18) Main FW Pump Disch Viv, Opens, (BB-C).

12. After pump starts, Perform the following:

a. Return voltage on 4KV Bus 1 A AND 18 (1C AND 1D) to normal as follows:

1) Adjust voltage on 4KV Bus 1 A 1B (1C AND 1D) using Load Tap Changer, Bus 1 A(1B)(1C)(1D) 4160V Lower Raise & Auto SW, (VB-C), until voltage indicates 125 VAC.

2) Ensure Load Tap Changers, Bus 1 A AND 1B (1C AND 1D) 4160V Lower Raise & Auto SWs, are in AUTO (Control Switch pulled out, away from Vertical Board).

b. Perform a hot bus transfer to unit station service transformer in accordance with 10M-36.4.A, "4KV Station Service System Startup," Part B.

13. Place control switch for [1LO-P-3A(B)], Aux Oil Pump for Steam Gen Feed Pump, to AUTO, (Turb Bldg. 693').

i

a. Verify aux oil pump stops.

14. Close [1FW-214(215)], Bypass for [MOCg15dXg)J, u{b dg 6g'g

15. Check the following at [1FW-P-1 A(18)] Main FW 1 A(1B) Pump, (Turb Bldg 693'):

a. Check cooling water flow through

,,

1) [FE-1CC-101 A(B)],1 A(18) SGFP Coolers Combined CCT Return, (Turb (

Bldg 693').

2) [FE-1CC-205A1(B1)],1 A(18) SGFP Stuffing Box Jacket CCT Return, (Turb Bld;g, 693').

a Beaver Valley Power Station Unit 1 10M-24.4. A Steam Generator Feedwater System j( Operating Procedures Issue 4 Revision 0 Page A 5 of 6 g Steam Generator Feedwater i System Startup 1

3) [FE-1CC-205A2(B2)],1 A(1B) SGFP Stuffing Box Jacket CCT Return, (Turb Bldg, 693').

b. Check the following for < 120F temperature:

1) [TI-1CC-205A1(B1)], Main Feedwater Pump 1 A(18) Outboard Seal Wtr inlet Temp to Seal Cir, (Turb Bldg. 693').

2) [TI-1CC-2.05A2(B2)], Main Feedwater Pump 1 A(18) Inboard Seal Wtr Inlet Temp to Seal Ctr, (Turb Bldg. 693'). I

c. Check [TI-1LO-205A(B)], Main Feedwater PP 1 A(B) Oil Cooler Outlet Temp, for temperature < 155F, (Turb Bldg,693').

Note: Normal seal leakage is none. Mechanical seals often leak slightly at startup and require varying amounts of "run-in" time. A large leak would indicate a seal l failure, l

d. Check seal for excess leakage. I

16. Monitor pump and motors for excess vibration.

17. Verify proper operation of [FCV-1FW-150A(B)], SG Main FW Pump 1 A(B) Recire  !

!( Viv, in accordance with 10M-24.5, " Table 24-1, Main Feed Pump Recirculation l Valve Operation During Power Ascension", i

18. When feedwater flow approaches 3000 gpm, Perform one of the following:

a. Unless already in service, Start the second [1CN-P-1B(A)], Main Condensate 1B(1 A) Pump, (BB-C).

OR

b. Close [FCV-1FW-150A], SG Main FW Pump 1 A Recirc Viv, (BB-C).

i l c0R TRAINING ONLY I

  \

l l l

• l Beaver Valley Power Station Unit 1 10M-24.4.A j Steam Generator Feedwater System issue 4 Revision 0 -

i Operating Procedures Page A 6 of 6 Steam Generator Feedwater System Startup ( V. REFERENCES l A. TECHNICAL SPECIFICATIONS

1. BVPS-1 T.S. 3.7.1.2 l

l B. UPDATED FINAL SAFETY ANALYSIS REPORT

1. UFSAR-1 Section 10.3.5

2. UFSAR-1 Figure 10.3.5 C. COMMITMENTS

1. EM 101585 "NSA Position of [1FW-P-1 A(1B)] Discharge MOV Bypass Line" D. ADMINISTRATIVE NONE E. VENDOR INFORM ATION NONE F. DRAWINGS

1. 8700-RM-424-3. VOND Feedwater System G. OPERATING MANUAL

1. 10M-24.1, Steam Generator Feedwater System - Description

2. 10M-24.3,1FW Valve List

3. 10M-24.5, Table 1 Main Feed Pump Recirculation Valve Operation During Power Ascension

4. 10M-28.31CCT Valve List

5. 10M-36.4.A,4KV Service Station Shutdown

6. 10M-36.4.B. 4KV Service Station Startup H. PLANT MODIFICATION NONE l

1. OTHER hhh g

1. Computer input / Output List

2. OMDR 1-91-1348,1-92-0676,1-95-0181,1-95-0360 (Issue 4/ Revision 0)

J

     .. .~.      . . . . .       .      . _ .       ---   . .             .  -  ...-          -     .    . _ . . .

( Record Type #A9.3308 i I i DUQUESNE LIGHT COMPANY Beaver Valley Power Station j i i Unit 1 t I 1oM-24.4.N(ISS3) j l FEEDWATER SYSTEM OPERATION AFTER Hi-HI SG LEVEL TRIP

\ .

l I Issue 3 Revision 1 l Prepared by Date Pagesissued Effective Date L. R. Montanari 07/22/96 N1 thru N3 JUL 2 91996 l Reviewed by Date Validated by Date J. E. Burnecke 07/22/96 N/A OSC Meeting No. Date Appro y ate OMCN 1-96-171 } g Q[, ! / ( coR 1R!utddG Ot4LY CONTROLLED BVPS UNOT 1

Beaver Valley Power Station Unit i 10M-24.4.N(ISS3) Steam Generator Feedwater System Issue 3 Revision 1 j- ~ Operating Procedures Page N 1 of 3 FEEDWATER SYSTEM OPER ATION AFTER HI-HI SG LEVEL TRIP PURPOSE This procedure outlines the steps required to recover normal feedwater system operation from a Hi-Hi steam generator level trip. PRECAUTIONS N/A INITIAL CONDITIONS

1. A Hi-Hi level in any steam generator has initiated the following:

a. Turbine trip.

b. Reactor trip if initial power was 49% or greater.

c. Feedwater isolation:

1) Main Feedwater Pump (s) trip.

2) Main Feedwater Pump Discharge Valve (s) shut.

3) Main Feedwater Regulating Valves trip.

4) Bypass Feedwater Control Valves trip.

5) Main Feedwater Containment isolation Valves shut.

2. The Motor Driven Auxiliary FW Pumps [1FW-P-3A and 3B] have started due to main FW pumps trip.

3. Steam generator levels have shrunk due to loss of load.

INSTRUCTIONS

1. Throttle 1C,18, and 1 A SG Auxiliary FW Throttle Valves [MOV-1FW-151 A thru F]

until steam generator levels stabilize. Note: If the Turbine Driven Auxiliary FW Pump [1FW-P 2] starts due to Lo-Lo SG level, another adjustment of the auxiliary FW Throttle valves will be necessary.

2. Increase feed flow sufficiently to slowly raise SG levels back to program value, taking care to not reduce Tavg by over feeding.

3. Place Main Feed Pump control switches in the PULL-TO-LOCK position.

4. When plant conditions have stabilized such that steam flow is just that necessary to

                        . remove residual heat, Tavg is steady at no load value and steam generator levels

i. are at program level 5%, secure unnecesg Auxiliary FW Pumps as follows:

a. Determine total auxiliary feedwater flow b Vertical Board - Section C.

m hkB06.Y 1 i

                                               -.      . _ ~       .   -. -

l l [ Beaver Valley Power Station Unit 1 10M-24.4.N(ISS3) Steam Generator Feedwater System 1ssue 3 Revision 1 { Operating Procedures Page N 2 of 3 FEEDWATER SYSTEM OPERATION AFTER HI-HI SG LEVEL TRIP (

b. If total flow is between 350 and 700 GPM:

l 1) Leave both of the motor driven auxiliary FW pumps [1FW-P-3A and 3B] running.

2) Secure the turbine driven pump [1FW-P-2] by placing both steam supply trip valves [TV-1MS-105A and B] in CLOSE, until the close lights come on, Benchboard - Section C.

3) Readjust 1C,18, and 1 A SG Auxiliary FW Throttle Valves [MOV-1FW-151 A thru F] as necessary to maintain SG levels.

4) Relatch the trip throttle valve in accordance with 10M-24.4.V, "[1FW-P-2]

Trip Throttle Valve Resetting".

c. If total auxillary feedwater flow is less than 350 GPM:

1) Leave the 3A (3B) auxiliary FW pump running.

2) Secure the turbine driven pump [1FW-P-2] by placing both steam supply

trip valves [TV-1MS-105A and B] in CLOSE, until the close lights come on, l t

Benchboard - Section C.

3) Readjust 1C,18, and 1 A SG Auxiliary FW Throttle Valves [MOV-1FW-151 A thru F] as necessary to maintain SG levels.

) 4) Relatch the trip throttle valve in accordance with 10M-24.4.V, "[1FW-P-2] Trip Throttle Valve Resetting".

5) Secure the 3B (3A) auxiliary FW pump by placing its control switch in PULL-TO-LOCK, Benchboard - Section C.

6) Readjust 1C,1B and 1 A SG Auxiliary FW Throttle Valves [MOV-1FW-151 A l thru F] as necessary to maintain SG levels.

l

5. Determine the cause of the Hi-Hi SG level trip.

6. Rectify the cause of the trip so the main feedwater system may be restored to normal.

7. If the Main Feed Regulating Valves [FCV-1FW-478,488 and 498], were in service at

! the time of the high SG level excursion, place them in MANUAL and reduce controller outputs to zero. l

8. Wher, all three main feed regulating valve controllers are at zero output, shut the SG Main FW isolation Valves [MOV-1FW-154A, B and C], Benchboard - Section C.

9. Check the SG Bypass FW Control Valves [FCV-1FW-479,489 and 499] hand controls set at zero.

10. Close or check closed the Bypass FW isolation Valves [MOV-1FW-155A, B and C],

Benchboard - Section C. g the FEEDWATER BYPASS ISOLATION RESET TRAINpuh

11. Reset the SG Bypass FW Control Valves [FCV-1FW- 48 '

A AND TRAIN B Benchboard - Section A.

Beaver Valley Power Station Unit 1 10M-24.4.N(ISS3) 1 Steam Generator Feedwater System issue 3 Revision 1 I l j Operating Procedures Page N 3 of 3 l 1 FEEDWATER SYSTEM OPER ATION AFTER HI-HI SG LEVEL TRIP l I l

12. Check the operation of the SG Bypass FW Control Valves [FCV-1FW-479,489, and 499] by stroking each open and then closed again, Benchboard - Section C.

1

13. Check the SG Bypass Control Valves [FCV-1FW-479,489 and 499] are shut (green j light on, hand control set at zero), Benchboard - Section C.

14. Open the Bypass FW lsolation Valves [MOV-1FW-155A, B and C] Benchboard - l Section C.

15. Open the Main FW Containment isolation Valves [MOV-1FW-156A, B and C]

Benchboard - Section A.

16. Start the 1 A (1B) Main Feed Pump per 10M-24.4.A. "Startup".

17. Transfer the feeding of the steam generators from auxiliary feedwater to main feedwater as follows:

a. Slowly open each bypass feedwater control valve while closing the corresponding auxiliary FW Throttle valves, maintaining steam generator levels at program leveli 5%.

b. When all six auxiliary FW Throttle valves are shut, place the control switch for the running auxiliary FW pump (s) in OFF Benchboard - Section C.

c. Using the bypass FW control valves [FCV-1FW-479,489 and 499], maintain SG levels at program value plus or minus 5% (no level alarms).

18. Place the 1C,18 and 1 A SG Auxiliary FW Throttle Valves [MOV-1FW-151 A thru F] in the full OPEN position, Benchboard - Section C.

19. Check or place both motor driven auxiliary FW pump [1FW-P-3A and 3B] control ,

switches in AUTO, Benchboard - Section C. , l

20. Independently Verify that the control switches for motor driven auxiliary FW pumps '

[1FW-P-3A and 3B] are in AUTO (spring return to AUTO switches) AND Document in 10M-54.2 S1-4(5)(6), Nuclear Control Operators Report.  ! i

21. The feeduater system is now in normal operation per 10M-24.4.8," Feeding Steam ,

Generators Using the Bypass Flow Control Valves". I REFERENCES Note: All references used prior to 08/04/87 are located in Section 5.

1. OMDR 86-1975; 1985 INPO Evaluation Finding OP.5-ia, b Appendix I (Issue 2, Revision 27).

2. OMDR 1-88-1682 (Revision 30).

i 3. OMDR 1-93-1072 (Issue 3, Revision 0).

4. OMCN 1-96-171 (Revision 1).

OR 1gAlNLNG OND '

L RTL #A5.640E DUQUESNE LIGHT COMPANY j Nuclear Power Division Training Administrative Manual i

- OJT CHECKLIST /JPM COVER PAGE l

!'I PROGRAM TITLE: Licensed Operator Training , SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Respond to Radiation Monitor Alarm - 1 !: i l-  : E JPM NO.: 1CR-137 COMPUTER CODE: N/A Revision No. Date Revision No. Date l l l l I PREPARED BY: DATE: l APPROVED FOR IMPLEMENTATION: DATE: Director, Operations Training, or Designee l Revision 9

l l l l RTL #AS 640E DUQUESNE LIGHT COMPANY l Nuclear Power Division l l Training Administrative Manual  ; i l LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: ICR-137. Resoond to Radiation Monitor Alarm - 1 l Revision Anoroval ! No. Brief Description Revised by: Signature Date l 1 l l l l t i I l l Revision 9

4 BEAVER VALLEY JOB PERFORMANCE MEASURE

EVALUATOR COVER SHEET 1

l JPM Number: 1CR-137 Rev: O System #: 068 Faulted: O i JPM

Title:

Respond to Radiation Monitor Alarm - 1

K/A

Reference:

068 000 A4.04 3.8/3.7 Task ID #: 000 042 0401 i 4 i JPM Designation: NO RO X SRO JPM Application: X NRC X Initial Exam O Training l f Evaluation Methad LOCATION TYPE x Perform Plant Site O Training ] x O Annual Requal. Exam

                                                                                                                                                  ~

l Simulate Simulator l Classroom OJT i X Initial Operator Exam Administered By: Other: BV-T , NRC ! Other: i - ) Evaluation Results Performer: Name: Employee No: l Results SAT Time (minutes) l UNSAT* Allotted: 8 Actual: l Time Critical: 0 Yes No

• Comments (Required for UNSAT Evaluation) :

i i Evaluation Results Check here if same as above Observer 1: Name: Employee No: + Observer 2: Name Employee No: j Observer 3: Name Employee No: 1 Observer 4: Name Employee No: 1 Time (minutes) Results j Question ID Allotted Actual SAT UNSAT* Question #1 3 0 1 Employee No: Question #2 3 Employee No: l

• Comments (Required for UNSAT Evaluation):

1 Evaluator (Print): Organization: Evaluator Signature Date: Revision 9

l l, RTL'#AS.635.J BEAVER' VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET I j THIS SHEET TO BE GIVEN TO CANDIDATE

• Read: -

Task: -lRespondtoRadiationMonitorAlarm- 1 L - INITIAL The plant is operating at 100% equilibrium power. CONDITIONS: There is a contaminated drains discharge in I progress from [LW-TK-6Alat this time. 10 seconds  ! ago the Radiation Monitor High and Radiation  ; Monitor High-High annunciators were actuated.  ; L TASK STAN.: Action taken in accordance with the appropriate alarm response procedure. , l L INIT. CUE: Your supervisor directs you to respond-to the Radiation Monitor Alarms. i . l L At this time, ask the evaluator any questions you have on this j l JPM. l j When satisfied that you understand the assigned task, announce l "I am now beginning the JPM". l L ~ Simulate performance or-perform as directed the required task. Point to any indicator or component you verify or check and announce your observations. l After completing the task, reread the Task Standard. After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator. l i Revision 9

i RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE i i { EVALUATOR DIRECTION SHEET JPM NUMBER: 1CR-137 JPM TITLE: Respond to Radiation Monitor Alarm - 1 RECOMMENDED STARTING LOCATION: CONTROL ROOM 1 DIRECTIONS: You are to perform the task respond to Radiation Monitor Alarm. INIT. CONDITIOi.3 : The plant is operating at 100% equilibrium power. There is a contaminated drains discharge in progress from [LW-TK-6A]at this time. 10 seconds ago the Radiation Monitor High and Radiation Monitor High-High annunciators were actuated.

     ~ TASK STAN.:             Action taken in accordance with the          1 appropriate alarm response procedure.       ,

l INIT. CUE: Your supervisor directs you to respond to the Radiation Monitor Alarms. , i

REFERENCES:

10M-43.4.ACR Issue 3, Rev. 3 10M-43.4 AAC Issue 4, Rev. 1 ) J l l TOOLS: NONE j HANDOUT: NONE I l l l I l l \- Revision 9

RTL #A5.635.J  ; 1 j i 1, NUMBER TITLE l l ICR-137 Respond to Radiation Monitor Alarm Case 1 1 I i 1 i j

STEP STANDARD l

(Indicate "S" for Sat. or "U" 4 ("C" denotes critical step) for Unsat.) Evaluator Setuo: - Initialize Simulator to IC-41. Hang

                                                  " Discharge ' ' sign. Run file:

JPM137. Mark valve position. START TIME: , Evaluator Cue: The alarm has already been verified by pushing the reset button and verifying that the alarm re-energized. DO NOT allow

candidate to push reset button.

Candidate locates and references 10M-43.4.AAC, Radiation Monitoring High-High. Evaluator Note: The candidate could also reference'10M-43.4.AAB, Radiation Monitoring High, but should the High-High alarm should be given higher priority. Page 1 of 7 Revision: 0

l l RTL #A5.635.J

   ?

NUMBER TITLE ! 1CR-137 Respond to Radiation Monit'or Alarm Case 1 j l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l t 1.C Determine which 1.1 Candidate checks all L radiation monitor is in l red lights on ' alarm Radiation Monitoring

System Racks to 1 i

determine which I radiation monitor (s) l are alarming. I 1.2.C Candidate determines l [RM-1LW-116] liquid l l Waste Contaminated I Drain Monitor is l alarming COMMENTS: i i 1 l

2. Reference appropriate 2. Candidate references individual radiation 10M-43.4.ACR, Local monitor alarm response High-High [RM-1LW-116]

l procedure. Liquid Waste Contaminated Drain l Monitor. l COMMENTS: l i i f l Page 2 of 7 Revision: 0 i i

i l RTL #A5.635.J NUMBER TITLE 1 1CR-137 Respond to Radiation Monitor Alarm Case 1 I STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) Evaluator Cue: The alarm has already been verified by pushing the reset button and verifying that the alarm re-energized. DO NOT allow candidate to push reset button.

3. Verify alarm. 3.1 Candidate verifies alarm. [RIS-1LW-116] .

3.2 Candidate marks time and date on RM-RR-400. COMMENTS: Evaluator Note: It is only critical to verify either [FCV-1LW-103} or [FCV-1LW-116) closed. l l l Page 3 of 7 Revision: 0 l l

,- RTL #A5.635.J l li NUMBER TITLE 1CR-137 Respond to Radiation Monitor Alarm Case 1 l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 4.C Verify (FCV-1LW-103] 4.C Candidate observes closed. [FCV-1LW-103] closed by observing green indicating light lit and red indicating light dark. COMMENTS: 5C Verify [FCV-1LW-116] 5.C Candidate observes closed. [FCV-1LW-116] closed by observing green indicating light lit and red indicating light dark. l COMMENTS: I l i Page 4 of 7 Revision: 0

I L RTL #A5.635.J- [ NUMBER TITLE

1CR-137 Respond to Radiation Monitor Alarm Case 1 l

l l l l l STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for'Unsat.) l l t 6.C Stop the Contaminated 6.1.C Candidate places the l Drain Transfer Pumps. control switch for l (1LW-P-6A] in STOP l position. I 6.2 Candidate verifles [1LW-P-6 A) stopped by verifying the red light is out. l COMMENTS: l l 1 l l l 1 ! 1 l l l i l l l L Page 5 of 7 Revision: 0 l l

1 l l l 1 l RTL #AS.635.J

l

   ' !t NUMBER               TITLE i

1CR-137 Respond to Radiation Monitor Alarm Case 1 l l l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

7. Notify Health Physics. 7. Candidate informs Health Physics of radiation monitor alarms and termination of liquid release.

l EVALUATOR Cue: Acknowledge report to Health Physics. l COMMENTS: l I 4 i Page 6 of 7 Revision: 0

_ _ ~ . . _ . . . . _ . . _ . _ i  ! RTL #A5.635.J I 4

a. t NUMBER TITLE

                                                                                                                                )

i 1CR-137 Respond to Radiation Monitor Alarm Case 1 J i I  ! STEP STANDARD

(Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.) j 1 Y j' 8. Dispatch operator to 8. Candidate dispatches

close contaminated operator to close  ;

drains transfer pump [1LW-83] and (1LW-84]. i discharge valves. a' EVALUATOR Cue: Acknowledge. order and then inform candidate 4 that [1LW-83] and (1LW-84]are closed. , 4 COMMENTS: i 4 Eyaluator Cue: [RM-1LW-116] flushing will be performed.by 4 another operator. (This { completes the JPM) l

                                                                                                                                )

STOP TIME: j l i l 1 Page 7 of 7 Revision: 0

BEAVER VALLEY JOB PERFORMANCE MEASURE i

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 1 The High High Alarm setpoint for the Contaminated Drain radiation monitor is manually set for each discharge. What factors are considered when determining this setpoint?

1 l l i s ICR-137

l BEAVER VALLEY JOB PERFORMANCE MEASURE -

  'l JPM QUESTION # 1 The High High Alarm setpoint for the Contaminated Drain radiation monitor is manually            ,

set for each discharge. What factors are considered when determining this setpoint? l 068 000 K5,04 3.2/3.5 Obj: LP-SQS-17.1 ELO-3 i~ Ref: 1/20M-17.4A.D Issue 4, Revision 0 l

       -ANSWER-Tank activity, discharge rate, and CT blowdown rate.

Comments:  ; ICR-137 s-

 -- ..    . ~ ~ .     -        .      _       ..                  .~ ..             .- - .=,      . . - . . . . _

BEAVER VALLEY JOB PERFORMANCE MEASURE I

• THIS SHEET TO BE GIVEN TO CANDIDATE
• I JPM QUESTION # 2 I

The radioactive release is automatically terminated on high activity. What other condition would require you to manually terminate the discharge? I l I l l l l i i- 1CR-137 i l

BEAVER VALLEY JOB PERFORMANCE MEASURE l Il l l JPM QUESTION # 2 The radioactive release is automatically terminated on high activity. What other condition would require you to manually terminate the discharge? i . 068 00 A4.03 3.9/3.8 - !. Obj: LP-SQS-17.1 ELO-3

      ' Ref: 1/20M-17.4A.D Issue 4, Revision 0 ANSWEA                                                                                           ,

Cooling Tower Blowdown flow falling below the minimum on the RWDA-L, or when

required by EP, as stated on RWDA-L, etc.

I Comments: i I I t i t f l ICR-137 l

i. l Beaver Valley Power Station Unit 1 10M-43.4. AAC Radiation Monitoring Systems issue 4 Revision 1 {_ Operating Procedures Page AAC 1 of 3 Radiation Monitoring High-High A4-72 l l RADIATION l MONITORING i HIGH-HIGH ! A4-72 l i l I l SETPOINTS: Refer to BVPS Health Physics Manual, Chapter 4, ' l Section 2, or Radiation Monitor Setpoint Log j DISCONNECT SWITCH: 2-2300, (Bay 1) l l SER POINT NUMBER: 164 ) i SER POINT iD: RADIATION MONITOR HIGH-HIGH  ! l l lNITIATING DEVICE: RSHH-1 AS-100 RSHH-1BD-100 RSHH-1CCR-100 l RSHH-1CH-101 A RSHH-1CH-1018 RSHH-1DA-100 l l RSHH-1GW-108A RSHH-1GW-1088 RSHH-1LW-104 RSHH-1LW-116 RSHH-1MS-100A RSHH-1MS-1008

RSHH-1MS-100C RSHH-1MS-101 - RSHH-1RM-201 RSHH-1RM-202 RSHH-1R M-203 RSHH-1RM-204 RSHH-1 RM-205 RSHH-1RM-206 RSHH-1RM-207 RSHH-1RM-208 RSHH-1RM-209 RSHH-1RM-210 l

RSHH-1RM-211 RSHH-1RM-212 RSHH-1RM-214 l l RSHH-1RM-215A RSHH-1RM-215B RSHH-1RM-217A RSHH-1RM-2178 RSHH-1RM-218A RSHH-1RM-218B l RSHH-1RM-219A RSHH-1RM-2198 RSHH-1RW-100 ) RSHH-1RW-100A RSHH-1RW-1008 RSHH-1RW-100C l RSHH-1RW-100D RSHH-1RW-101 RSHH-1SS-100 l RSHH-1SV-100 RSHH-1VS-101 A RSHH-1VS-101B RSHH-1VS-102A RSHH-1VS-1028 RSHH-1VS-103A RSHH-1VS-1038 RSHH 1VS-104A RSHH-1VS-104B RSHH-1VS-105 RSHH-1VS-106 RSHH-1VS-107A RSHH-1VS-1078 l e 5 C0R TRAINING ONLY

I i Beaver Valley Power Station Unit i 10M-43.4. AAC Radiation Monitoring Systems issue 4 Revision 1 Operating Procedures l

  .4 Page AAC 3 of 3           l 1 i
    , Radiation Monitoring High-High                                                                                   A4-72 i

REFERENCES i A. TECHNICAL SPECIFICATIONS a

NONE l B. UPDATED FINAL SAFETY ANALYSIS REPORT

1. UFSAR-1 Section 11.3.3

                 '2. UFSAR-1 Table 11.3-2

3. UFS AR-1 Table 11.3-3 C. COMMITMENTS .

NONE D. ADMINISTRATIVE

1. BVPS Health Physics Manual E. VENDOR INFORMATION NONE F. DRAWINGS

1. 8700-RE-21PP, Annunciator A4 Window Arrangement

2. 8700-RE-21PS, Elementary Diagram Annunciator A4 Sh 3 of 4 G. OPERATING MANUAL 1 10M-43.1, Radiation Monitoring Systems Description H. PLANT MODIFICATION NONE

1. OTHER

1. Computer input /O'utput List ~ ,

2. OMCR 1-95-0985; TER 9673 (Rev.1) e 6 ..a e Gg

• 4 .e 9 O e.

Y  ; f } l n$ 1'i '*s6 ONL

Record Type #A9.330B DUQUESNE LIGHT COMPANY Beaver Valley Power Station i Unit 1 l 10M-43.4.ACR(ISS3) LOCAL HIGH-HIGH ([RM-1LW-116] LIQUID WASTE CONTAMINATED DRAIN MONITOR) 1

                          -        lasue 3       Revision 3 Prepared by                       Date        Pagesissued        Effective Date R. Plummer ,                      11/02/95    ACR1 thru ACR3                  3 1995 NOV Reviewed by                       Date        Validated by                 Date J.P.Keegan                        11/02/95    N/A Unit 1 Manager                    Date        OSC Meeting No.              Date N/A                                           Non-intent            //[.7/9 Unit 2 Manager                    Date        Approved by                   Date n'^                                           /&d6A                        u/yer
                                                 '0R TRAliiiNO o n y CONTROLUB

_ _____ ____ _ BVPS UNIT 11

Beaver Valley Power Station Unit 1 10M-43.4.ACR(ISS3) Radiation Monitoring Systems issue 3 Revision 3 Operating Procedures Page ACR 1 of 3 LOCAL HIGH-HIGH ([RM-1LW-116] LIQUID WASTE CONTAMINATED DRAIN MONITOR)

                                                      \      /
                                                     -@\-
                                                      /    j i

SETPOINTS: Refer to Radiation Monitor Setpoint 1.og DISCONNECT SWITCH: N/A SER POINT NUMBER: N/A SER POINT ID: N/A j INITIATING DEVICE: RSHH-1LW-116

1. Verify the alarm by pushing and reie.n,mg the Reset pushbutton on [RIS-1LW-116]

Liquid Waste Contam Dr Effluent Monitor at [RK-RAD-MON #4], Radiation 1 Monitor!ng System Rack 4. '

a. Verify that the alarm is re-energized. l

b. Mark [RM RR-400], Radiation Monitor Recorder No. 4, Chart with time and date of alarm. l '

2. Verify that [FCV-1LW-103] Flow Control Valve is closed by observing its indicating lights, (BB-A),

3. Verify [TV-1LW-116] is closed by observing its indicating light.

4. Stop [1LW-P-6A and 6B] Contaminated Drain Transfer Pumps (BB-A).

{

5. Notify Health Physics.

l

6. Dispatch an operator to perform the following: '

a. Close the contaminated drains transfer pump discharge valves:

1) [1LW-83]

2) [1LW-84]

b. Place the tank that was being discharged back into the recirculation mode.

7. To flush [RM-1LW-116], Perform the following: l

a. Check Closed the following valves: I I

1) [1BR-548], Flush Isolation for RM-1RW-101, (Aux Bldg,735').

    ;                            BR-P-2B 730 )

3) [1BR-552], Pri Water to RM-1CC-100 Isol, (Aux Bldg,722'). l

4) [1BR-546], Aux Steam Rtrn Water Monitor Flush, (Aux Bldg,735' Primary g Sampic Room). '

__ _ - . . . . - _ - _ _ _ = - . - l l l Beaver Valley Power Station Unit 1 10M-43.4.ACR(ISS3) Radiation Monitoring Systems issue 3 Revision 3 Operating Procedures Page ACR 3 of 3 i LOCAL HIGH-HIGH ([RM-1LW-116] LIQUID WASTE CONTAMINATED DRAIN MONITOR) l ! REFERENCES l Note: All references used prior to 01/10/86 are located in 10M-17.5, " Table of References".

1. OMDR 105-86.

2. OMDR 88-0412; 1985 INPO Evaluation Finding OP.5-ia, b Appendix I (Revision 30).

3. OMDR 1-88-1766 (Revision 34).

4. OMCN 1-91-467 (Issue 3/ Revision 2).

5. OMCR 1-95-0814 (Rev. 3).

C0R TRAINING ONLY l

i l l RTL #AS.640E DUQUESNE LIGHT COMPANY i !' Nuclear Power Division l Training Administrative Manual l l 1 l OJT CHECKLIST /JPM COVER PAGE i PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Trai.ning OJT CHECKLIST /JPM TITLE: Depressurize RCS During SGTR JPM NO.: 1CR-638 I i COMPUTER CODE: N/A l Revision No. Date Revision No. Date PREPARED BY: DATE: APPROVED FOR IMPLEMENTATION: DATE: ~~ Director, Operations Training, or Designee l I Revision 9

.. . - . . . . . . . . . - . - . . . . . . - - - . . - . . . - . . . ~ . . . . . . - . - . . . - . - i RTL #A5.640E DUQUESNE LIGHT COMPANY j Nuclear Power Division  : Training Administrative Manual l

  .(

1 I LESSON PLAN AND OJT REVISION APPROVAL SHEET l DOCUMENT TITLE: 1CR-638, Deoressurize RCS Durino SGTR

                                                                                                                                                       'l i

J Revision- . Accroval No. Brief Description Revised'by: ' Signature Date

                                                                                                                                                         )
                                                                                                                                                       -l i

I 1

                        +

I t i j A 4 Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET 1 l JPM Number: 1CR-638 Rev: O System #: 010 Faulted: X l JPM

Title:

Depressurize RCS During SGTR l K/A

Reference:

010 000 A4.03 4.0/3.8 Task ID #: 301 004 0601 ) JPM Designation: NO RO E SRO j j JPM Application: X NRC E Initial Exam Training ) Evaluation Method LOCATION TYPE j X Perform O Plant Site Training Simulate X Simulator Annual Requal. Exam j O Classroom OJT i @ Initial Operator Exam i Administered By: Other: O av-T } NRC O Other: Evaluation Results 4 Performer: Name: Employee No:

Results SAT Time (minutes) f UNSAT* Allotted

15 Actual:

Time Critical

Yes X No

• Comments (Required for UNSAT Evaluation) :

Evaluation Results Check here if same as above ! Observer 1: Name: Employee No: Observer 2: Name Employee No: Observer 3: Name Employee No: j Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 3 Employee No: Question #2 3 0

Employee No:

j

• Comments (Required for UNSAT Evaluation):

t 3 I Evaluator (Print) : Organization: Evaluator Signature Date: Revision 9

   . . - . - - - -              _ -   . .   . . . .    .. . -. . - . . .            . . - .. _ . . - . - - ,.-.. -. -.~

i RTL #AS.635.J.- BEAVER, VALLEY JOB PERFORMANCE MEASURE !-. CANDIDATE DIRECTION SHEET j ~ THIS SHEET TO BE GIVEN TO CANDIDATE

• j Read:

i

. Task: lDepressurizeRCSDuringSGTR i

j INITIAL CONDITIONS: A SGTR has occurred on the 1-C steam I

generator, resulting in a reactor. trip

, and safety injection. Step 22 of 10M-

,                                                      53A.1.E-3, Steam Generator Tube Rupture, is being performed at this time.

l. TASK STAN.: RCS pressure reduced in accordance with 10M- l 53A.1.E-3.  !

i j $ INIT.' CUE: Your supervisor directs you to depressurize the RCS in accordance with 10M-53A.1.E-3, Steam Generator Tube Rupture. a T l ) At this time, ask the evaluator any questions you have on this JPM. When satisfied that you understand the assigned task, announce

                   -       "I am now beginning the JPM".

1 . Simulate performance or. perform as directed the required task. Point,to any indicator or component you verify or check and announce your observations. After completing the task, reread the Task Standard. 4

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

1 i d ? Revision 9

RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE i 4 EVALUATOR DIRECTION SHEET JPM NUMBER: 1CR-638

JPM TITLE

Depressurize RCS During SGTR RECOMMENDED STARTING LOCATION: CONTROL ROOM i

DIRECTIONS: You are to perform the task depressurize RCS during SGTR. A SGTR has occurred on the 1-C steam INIT. CONDITIONS: , generator, resulting in a reactor trip and  ! safety injection. Step 22 of 10M-53A.1.E-3, Steam Generator Tube Rupture, is being

performed at this time.

i TASK STAN.: RCS pressure reduced in accordance with 10M-53A.1.E-3. . i- INIT. CUE: Your supervisor directs you to depressurize the RCS in accordance with 10M-53A.1.E-3, Steam Generator Tube Rupture. 4

REFERENCES:

10M-53A.1.E-3, Issue 1B, Revision 3 I I TOOLS: NONE i ) HANDOUT: NONE i 1 Revision 9

l l l RTL #A5.635.J l l (- NUMBER TITLE 1CR-638 Depressurize RCS During SGTR l l STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) Evaluator Note: This is a FAULTED JPM. The failure of the Pressurizer Spray valves will require the candidate to use an PORV for RCS depressurization. Evaluator Setuo: -Initialize Simulator to IC-35. START TIME: Candidate locates and reviews , 10M-53A.1.E-3, Steam Generator Tube Rupture. 1 l' Page 1 of 5 Revision: 0

RTL #A5.635.J i NUMBER TITLE l l 1CR-638 Depressurize RCS During SGTR STEP STANDARD  ! (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) l l 4

1. Check Pressurizer Spray 1. Candidate verifies l Valves Available. RCPs are running and  !

that spray valves are l available. 1 1 l COMMENTS: 2.C Spray Pressurizer. 2.1.C Candidate attelapts to open Pressurizer Spray Valves and determines that the spray valves will not open. 2.2.C Candidate makes transition to Step 23. COMMENTS: i i Page 2 of 5 Revision: 0 I i l

  -RTL #A5.635.J

(- ' NUMBER TITLE 1CR-638 Depressurize RCS During SGTR STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

3. Check one PRZR PORV 3. Candidate verifies at Isolation valve open least'one of [MOV-1RC-

• 535, 536, 537] open by verifying red indicating light lit and green indicating light dark.

COMMENTS: 4.C Open one PRZR PORV. 4.1.C Candidate places , control switch for one 1 PRZR PORV in the open position 4.2 Candidate verifies one PORV open. COMMENTS: Page 3 of 5 Revision: 0

l' l RTL #AS.635.J I  : NUMBER TITLE j

1CR-638 Depressurize RCS During SGTR l

I STEP STANDARD (Indicate "S" for Sat, or "U" ("C" denotes critical step) for Unsat.)

5. Close PRZR PORV. 5.1.C Candidate closes the open PRZR PORV when any of the following conditions are satisfied:

PRZR level > 76%, or RCS subcooling less amount determined by Attachment 6-A, or Both: RCS pressure < ruptured SG pressure l AND l PRZR Level > 5% 5.2 Candidate verifies the PZR PORV closed. 1 COMMENTS: i Page 4 of 5 Revision: 0

RTL #AS.635.J l I I l NUMBER TITLE ' 1CR-638 Depressurize RCS During SGTR STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

6. Inform supervisor that 6. Candidate informs the RCS supervisor that the RCS Depressurization is depressurization is complete. complete.

COMMENTS: STOP TIME: l Il l l 1 Page 5 of 5 Revision: 0

BEAVER VALLEY JOB PERFORMANCE MEASURE e

• THIS SHEET TO BE GIVEN TO CANDIDATE
• JPM QUESTION # 1 The purpose of the depressurization that was just performed is to reduce the differential pressure between the RCS and the ruptured steam generator and to refill the pressurizer.

Why is it desirable to refill the pressurizer at this time? I 1 1CR-638  !

BEAVER VALLEY JOB PERFORMANCE MEASURE JPM QUESTION # 1 The purpose of the depressurization that was just performed is to reduce the differential pressure between the RCS and the mptured steam generator and to refill the pressurizer. Why is it desirable to refill the pressurizer at this time? 010 000 K1.013.9/4.1 Ref: lOM 53B.4.E-3, Issue IB, Revision 3 Obj: LP-SQS-53.3, ELO 3 ANSWER: Refilling the pressurizer is necessary to meet SI termination criteria. It is necessary to terminate SI in order to stop break flow into the ruptured steam generator or to provides a reliable RCS level indication that avoids solid plant conditions. Comments: ICR-638

l l BEAVER VALLEY JOB PERFORMANCE MEASURE c

• THIS SHEET TO BE GIVEN TO CANDIDATE
• r-l JPM QUESTION # 2 If the RCS is depressurized without RCPs running, it is likely that a void will form in the reactor vessel head. List two indications that could be used to determine that a void has I formed in the reactor vessel head. -l l

l i I I l l i l l-1 1CR-638

I BEAVER VALLEY JOB PERFORMANCE MEASURE -{- JPM QUESTION'# 2 If the RCS is depressurized without RCPs running, it is likely that a void will form in the reactor vessel head. List two indications that could be used to deterraine that a void has formed in the reactor vessel head. 1 000 038 EKl.03 3.9/4.2 l Ref: 10M-53B.4.E-3, Issue IB, Revision 3 Obj: LP-SQS-53.3, ELO 3 1 ANSWER: Any two:

   . (1)     RVLIS                                                                                        i (2)     Sudden increase in pressurizer level when RCS pressure is lowered.

(3) Sudden drop in pressurizer level when RCS pressure is raised. Note: A description of the effect of changes in charging and letdown flow may also be related to/ substituted for the changes in RCS pressure in the above description. 1 l Comments: I 1CR-638

                                                                                                              \
                                        .                                                                     I BVPS - E0P 10M-53A.I.E-3(ISSIB) !

neeer Title g E-3 Steam Generator Tube Rupture Issue IB  ! 4 Revision 3 ) STEP ACTION / EXPECTED' RESPONSE RESPONSE NOT OBTAINED

21. Check On ICCM RCS Subcoolina Check RCS.subcooling base on core Based On Core Exit TCs - GREATER exit TCs - GREATER THAN SUBC00 LING TFAN 23F T36F ADVERSE CNMTl LISTED ON ATTACHMENT 6-A IF subcooling based on core exit TCs less than required subcooling I on Attachment 6-A, THEN GO TO  !

ECA-3.1, "SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired", Step 1. f J 22. leoressurize RCS To Minimize 3reak Flow And Refill PRZR

a. Check [PCV-1RC-455A(B)], PRZR a. GO TO Step 23.

Spray Vivs - AVAILABLE

b. Spray PRZR with maximum available spray until ANY of the following i conditions satisfied: L

              . PRZR level - GREATER THAN 76% [50% ADVERSE CNMT]                                                                       1
                              -0R-
              . RCS subcooling b'ased on core exit TCs - EQUAL TO SUBC00 LING LISTED ON ATTACHMENT 6-A
                              -OR-
              . BOTH of the following:

1) RCS pressure - LESS THAN RUPTURE SGs PRESSURE

2) PRZR level - GREATER THAN 5% [50% ADVERSE CNMT)

c. Close [PCV-1RC-455A(B)], PRZR c. Stop RCPs supplying failed spray Spray Valves. valves.

                                                                    . RCP 1A and 1C for (PCV-1RC-455A]
                                                                    . RCP IC for (PCV-IRC-455B]

d. GO TO Step 25.

c0R TRALNiNG ONLY 10 09/06/95 20 of 40

BVPS - E0P 10M-53A.I.E-3(ISS18) i Number T it le ' l E-3 Steam Generator Tube Rupture Issue IB Revision 3 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED >

       *

• 1
• CAUTION *

                                    . The PRT rupture disc may rupture if a PRZR PORV

• is used to depressurize the RCS. This may
• result in abnormal containment radiation and
• humidity. *
• Cycling of the PRZR PORV should be minimized *
• to reduce potential of PORV failure.
• NOTE The upper head region may void during RCS depressurization if RCPs are not running. This may result in a rapidly rising PRZR level.

 \

23. Depressurize RCS Usina PRZR PORV  ;

To Minimize Break Flow And Refill  : PRZR

a. Chec'k one PRZR PORV Isol Valve -

OPEN a. O$en V 1ve. at least one PRZR PORV Isol

                   .  'M0V-lRC-535'        for 'PCV-lRC-455C]        1E no block valve can be
                   .  'M0V-lRC-536'        for                       opened, THEN GO TO ECA-3.3,           i lN0V-1RC-537:        for 'PCV-IRC-456))

PCV-1RC-4550 "SGTR Without Pressurizer l Pressure Control," Step 1. C0R TRAINING ONLY T (step continued next page) 1E3 09/06/95 21 of 40

l l l

                                  ~

l ,. BVPS - E0P 10M-53 A. l . E-3(ISSIB) I hueer Titie l E-3 Steam Generator Tube Rupture Issue IB ! Revision 3 I STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l 23. (continued from previous page)

b. Open one PRZR PORV until ANY of b. Attempt to open a PRIR PORV the following conditions are using Overpressure Protection satisfied: System.

PRZR level - GREATER THAN 1) Usin appro riate key 76% [50% ADVERSE CNMT] swit hes, p ace OPPS (PCV-1RC-455Cand455D]

                           -OR-                                  in AUTO (BB-B).
             . RCS subcooling based on core                 IF NOT, THEN GO TO                            i exit TCs - LESS THAN SUBC00 LING            EA-3.3, "SGTR Without LISTED IN ATTACHMENT 6-A                    Pressurizer Pressure Control", Step 1.
             . BOTH of the following:

1) RCS pressure - LESS THAN RUPTURED SGs PRESSURE l PRZR level - GREATER THAN

2) 5% [50% ADVERSE CNMT]

c. Close PRZR PORV. c. Close PRZR PORV isol M0V of open PORV:

                                                             . [MOV-1RC-535] for [PCV-1RC-455C)
                                                                             -OR-
                                                             . (M0V-1RC-536] for (PCV-lRC-456]
                                                                              -OR-
                                                              . [MOV   1"' J37] for [PCV-1RC-4550)

COR TRAINING ONLY l in os/os/ss 22 of 40

l 1 i lI 4 RTL #AS.640E DUQUESNE LIGHT COMPANY , Nuclear Power Division Training Administrative Manual ' l k 1 OJT CHECKLIST /JPM COVER PAGE Licensed Operator Training PROGRAM TITLE: SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Verify Shutdown Margin JPM NO.: ICR-639 i COMPUTER CODE: N/A Revision No. Date Revision No. Date l l PREPARED BY: DATE: 1 APPROVED FOR IMPLEMENTATION: RAIE: Director, Operations Training, or Designee Revision 9

  .      ..         _-  , . . . . . . . . . . _ . - - - . _ _ _ _ _ , _ . ~ . . _ . . _ . - - . . - _ _ _ _ . . _ _ - . . . . . _ . . . _ _ . . _ . . _ . . . _ . . . -

RTL #A5.640E DUQUESNE LIGHT COMPANY r Nuclear' Power Division l . Training Administrative Manual l' l, l. i i .; LESSON PLAN AND OJT REVISION APPROVAL SHEET ' l DOCUMENT TITLE: 1CR-639, Verifv Shutdown Marain t Revision Acoroval No. Brief Description Revised by: Signature .Date > N i i T

                                                                                                                                                                                    .I I                                                                                                                                                                                       a i

b 6 i I i l P l Revision 9

1 1

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET 4

j 4 JPM Number: 1CR-639 Rev: O System #: 004 Faulted: X j JPM

Title:

Verify Shutdown Margin ) K/A

Reference:

004 000 A4.01 3.8/3.9 Task ID #: 004 006 0101 1 s { ! JPM Designation: NO [] RO X SRO JPM Application: X NRC X Initial Exam Training i j Evaluation Method LOCATION TYPE j X Perform Plant Site [] Training l [] Simulate X Simulator Annual Requal. Exam l l [] Classroom [] OJT EU Initial Operator Exam l ' Administered By: [] Other: BV-T , NRC j O Other: Evaluction Resul a 4 Performer: Name: Employee No: f Results [] SAT Time (minutes) l UNSAT* Allotted: 35 Actual:

I j Time Critical: Yes x No

• Comments (Required for UNSAT Evaluation):

1 i Evaluation Results Check here if same as above I Observer 1: Name: Employee No: . Observer 2: Name Employee No: ! Observer 3: Name Employee No: 3 Observer 4: Name Employee No: Time (minutes) Results Question ID Allotted Actual SAT UNSAT* Question #1 3 [3 Employee No: i Question #2 3 Employee No:

• Comments (Required for UNSAT Evaluation):

4 A Evaluator (Print): Organization: Evaluator Signature Date: Revision 9

2 i RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET i THIS SHEET TO BE GIVEN TO CANDIDATE * $ Read: Task: Verify Shutdown Margin INITIAL The plant is operating in Mode 3, one hour CONDITIONS. following a reactor trip from 100% power, equilibrium conditions. All rods are inserted, 5, Tavg is 547 F, ' the RCS boron concentration is 452 l PPM, and core burnup is 7,900 MWD /MTU. i I e

TASK STAN.

Actions for Shutdown Margin. Calculation performed

. in accordance with 10ST-49.2, Shutdown Margin f Calculation. i i INIT. CUE: Your supervisor directs you to verify SHUTDOWN MARGIN using 10ST-49.2, Shutdown Margin Calculation. 4 i S t ! At this time, ask the evaluator any questions you have on this JPM. I i When' satisfied that you understand the assigned task, announce - l

                         -        "I am now beginning the JPM".

Simulate performance _or perform as directed the required task. Point to'any' indicator or component you verify or check and announce your observations. i f' After completing the task, reread the Task Standard. t

                                 .After determining the Task Standard has been met, announce "I

have completed the JPM".- Then hand back this sheet to the i evaluator.

b Revision 9

1 RIL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE ' l i EVALUATOR DIRECTION SHEET 4 JPM NUMBER: 1CR-693 JPM TITILE: , Verify Shutdown Margin l RECOMMENDED STARTING LOCATION: CONTROL ROOM j 1 l l DIRECTIONS: You are to perform the task verify Shutdown Margin. INIT. CONDITIONS: The plant is operating in Mode 3, one hour following a reactor trip from 100% power, , equilibrium conditions. All rods are inserted, Tavg is 547*F, the RCS boron concentration is 452 PPM, and core burnup is 7,900 MWD /MTU. l TASK STAN.: Actions for Shutdown Margin Calculation performed in accordance with 10ST-49.2, Shutdown Margin Calculation. INIT. CUE: Your supervisor directs you to verify SHUTDOWN MARGIN using 10ST-49.2, Shutdown Margin Calculation.

REFERENCES:

10ST-49.2, Issue 4, Revision 4 10M-7.4.S, Issue 4, Revision 1 1 TOOLS: NONE 1 HANDOUT: 10ST-49.2, Shutdown Margin Calculation j l 1 Revision 9

RTL #A5.635.J NUMBER TITLE 1CR-639 Verify Shutdown Margin STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) EVALUATOR NOTE: This a Faulted JPM. RCS boron is not high enough to meet SDM requirements. Emergency Boration will be required. Evaluator Setuo: Initialize Simulator to IC-34. Leave Simulator in Freeze. START TIME:

1. Locate and review 1. Candidate locates and l procedure. reviews procedure. j Evaluator Cue: Provide candidate with copy of 10ST-49.2.

l COMMENTS: Page 1 of 10 Revision: 0

RTL #AS.635.J 4 hTMBER TITLE 1CR-639 Verify Shutdown Margin STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.)

2. Record initial data. 2.1 Candidate records date and tima.

2.2 Candidate records Mode: MODE 3. 2.3 Candidate records present RCS boron concentration: 452 PPM. 2.4 Candidate records total core exposure: 7,900 MWD /MTU. 2.5 Candidate records Tavg: 547 F. l 1 COMMENTS: l i I l 1 i Page 2 of 10 Revision: 0

RTL #AS.635.J NUMBER TITLE 1CR-639 Verify Shutdown Margin STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes' critical step) for Unsat.) i

                                                            ~

3.C Determine the Minimum 3.C Canc1date uses Figure Shutdown Boron 1 to determine and Concentration. then records the required boron concentration: 760 PPM i 10 PPM. COMMENTS:  ;

4. Calculate-the Minimum 4. Candidate determines ,

Shutdown Boron the required boron I Concentration corrected concentration for inoperable rods. corrected for rods: 760 PPM, i 10 PPM. COMMENTS:  ; s i Page 3 of 10 Revision: 0 _. . __. ~ . . _ =. _.~. _ _, - , ._.

4 RTL #A5.635.J l i NUMBER TITLE l 1CR-639 Verify Shutdown Margin STEP STANDARD , 'E (Indicate "S" for Sat. or "U" , i ("C" denotes criti~al step) for Unsat.)

5. Record present and 5. Candidate records required boron present and required concentrations. boron concentrations. .

COMMENTS: i 6.C Inform NSS that present 6.C Candidate informs NSS l boron concentration is that present baron , less than the required concentration is less ' boron concentration. than the required boron concentration. . Evaluator Cue: Acknowledge , communication and direct candidate to determine Xenon Correction , COMMENTS: t Page 4 of 10 Revision: 0 i l'

RTL #A5.635.J a ( NUMBER TITLE 1CR-639 Verify Shutdown Margin STEP STANDARD 1 (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.) l 7.C Determine Xenon 7.1 Candidate records time correction. since shutdown: 1 hours. 7.2.C Candidate determines and records reactivity l form Xenon 24 hours i from now: 2544 pcm, i 50 pcm. l 7.3.C Candidate determines and records differential boron I worth: 9.1 pcm/ ppm i I

                                               .1 pcm/ ppm.                          I l

7.4.C Candidate determines and records equivalent  ! boron worth of xenon: 1 279 PPM, i 15 PPM. l 1 l Page 5 of 10 Revision: 0

l RTL #A5.635.J i NUMBER TITLE i 1CR-639 Verify Shutdown Margin ' i STEP STANDARD I (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 1 7.5.C Candidate determines and records minimum required shutdown boron corrected for { xenon: 481 PPM, i 25 PPM. COMMENTS: l i i 1 8.C Initiate Emergency 8.1C Candidate transitions Boration if the present 10M-7.4.S to begin boron concentration is Emergency Boration. less than the required boron concentration. EVALUATOR CUE: Place Simulator in RUN COMMENTS: Page 6 of 10 Revision: 0

1 4

              -RTL #AS.635.J I1  <

NUMBER TITLE 4 1CR-639 Verify Shutdown Margin i 1 1 STEP STANDARD (Indicate "S" for Sat. or "U" j i ("C" denotes critical step) for Unsat.) -

9. Verify at least 9. Candidate verifies at charging Hi Head Safety least charging Hi Head Injection pump is Safety Injection pump 1 running, is running. l COMMENTS:

4 1 i 10.C Place control switch 10.C Candidate places control ' for Emergency Boration switch for [MOV-1CH-350] Isolation Valve to in OPEN position. l OPEN. COMMENTS: I 1 Page 7 of 10 Revision: 0

RTL #AS.635.J NUMBER TITLE 1CR-639 Verify Shutdown Margin STEP STANDARD (Indicate "S" for Sat. or "U" ("C" denotes critical step) for Unsat.) 11.C Place online Boric Acid 11.C Candidate places Transfer Pump control online Boric Acid switch to fast. Transfer Pump control switch to fast. COMMENTS:

12. Verify emergency 12. Candidate observes (FI-boration flow is 1CH-110] and verifies greater than or equal indicated flow is to 30 gpm. greater than or equal to 30 gpm.

COMMENTS: Page 8 of 10 Revision: 0

   , . . _ _   __       _   . . _ _ __ . _ _ _ _ _ . . ~ . . . . . _ .    .           . _.._..... ..  ._.. m._..__-.._,                 . . . _ _ .

j i RTL #A5.635.J: fL

   -(

i NUMBER TITLE '

                                                                                                                                                         .l 1CR-639                  Verify Shutdown Margin                                                                                          l l

1 i- l 1 i - STEP STANDARD (Indicate "S" for Sat, or "U" 3 ("C" denotes critical step) for Unsat.) .j f.

13. Establish 75 - 150 gpm 13.1 Candidate places charging flow, controller for [FCV-1CH-122] to manual.

l 13.2 Candidate adjusts [FCV-1CH-122] as necessary

• until flow as indicated by_[FI-1CH-122] is 4

     .                                                                                    between 75 and 150 gpm.

1 1 4 e COMMENTS: 1-a , 1 i i l i l t 4 e i-ll

' j 1-4

=

k i j~ Page 9 of 10 Revision: 0 I

RTL #AS.635.J NUMBER TITLE 1CR-639 Verify Shutdown Margin STEP STANDARD (Indicate "S" for Sat. or "U" (?'C" denotes critical step) for Unsat.)

14. Verify RCS pressure is 14. Candidate observes [PI-less than 2335 psig. 1RC-455, 456'and 457] to setermine RCS pressure <

is less than 2335 psig. 1 COMMENTS: Evaluator Cue: This completes the'JPM. STOP. TIME: 1 l 1 1 1 l

                           -Page 10 of 10                   Revision: 0 l

BEAVER VALLEY JOB PERFORMANCE MEASURE s I-

• THIS SHEET TO BE GIVEN TO CANDIDATE
• l I

JPM QUESTION # 1 i}}