ML20207H918

Forwards Facility Submitted Outline,Initial Exam Submittal & as Given Operating Exam for Test Administered on 980413-15 at Plant

ML20207H918
Person / Time
Site:	Vogtle
Issue date:	02/05/1999
From:	Michael B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9903160139
Download: ML20207H918 (200)

Text

.. _ _. -..

February 5,1999 NOTE TO:

NRC Document Control Desk Mail Stop 0-5-D-24 WL D: /)

FROM:-

Beverly Mich g Assistant, Operator Licensing and Human Performance Bran, Division of Reactor Safety, Region 11

SUBJECT:

OPERATOR LICENSING EXAMINATIONS ADMINISTERED APRIL 13 - 15,1998, AT VOGTLE ELECTRIC GENERATING PLANT DOCKET NOS. 50-424 AND 50-425 During the period " Operator Licensing Examinations were administered at the referenced facility. Attached, you will find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR:

3 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.

Item #2 -

Examination Report with the as given written examination attached, designated for distribution under RIDS Code IE42.

Attachments: As stated 3

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SCENARIO OUTLINE Form ES D-1 l

3 t

l Simulation Facility :

Vootle Scenario No. :

1 i

Examiners:

Candidates:

Initial Conditions: The plant is at 76% Power (IC9) with # 3 condensate pump out of service and the TDAFW Pump is in LC0 3.75 condition A due to one steam isolation valve shut.

l Turnover: Plant SU is in progress. Rx power is 76%.

Number 3 condensate pump was was tagged out due to severe vibration 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> ago. The TDAFW pump steam supply valve from

1. 1 SG (1HV-3009) is tagged shut for repairs to the motor operator (7 day LCO).

ETR is sometime tomorrow. SG #3 has a 9 GPD leak rate. Raise power to 80 %. stabilize, and place rods in Auto until diracted to perform calometric.

Preinsert: SEE NEXT PAGE Event Malf Event Event No.

No.

Type Description 1

R0-R Increase power to 80%

TUO4d SRO-I.C Control valve 4 closure. Turbine Impulse Pressure Xmtr Fails TU19a R0-I.C high.

(At T-+35 seconds) 100%

BOP-I.C Pressurizer Spray valve PV 455C Fails to close on transient (At 2

examiner discretion insert PR07, but not to go below 2240 psig)

PR07 SRO-C ESF-125VDC SWGR Fault-ICD 1 3

EL11c BOP-C TDAFW loss of control. N43 failure. letdown isolation R0-C SRO-N Place Excess Letdown in service.

4 BOP-N FWO6b FW Line #2 Rupture Inside Containment causing RX Trip. SIS. FWI ALL-MT and Blowdown of #2 SG.

(Loss of TDAFW Pum) due to SG 5

blowdown.) Turbine fails to auto-trip.

MS_ fails to auto j

isolate.

ELO7a Loss of ESF Bus 1AA02 causing loss of 1 train of ESF.

6 ALL-C (Insert t+30 sec)

/

i

/

(N)ormal.

(R)eactivity.

(I)nstrument.

(C)omponent.

(M)ajor NUREG-1021 Interim Rev. 8. January 1997 DISTRIBUTION CODE A070

)

I Page 2 of 9

i l

I PREINSERTS:

l PZRITsysFbhd TpfsssUFEssis5tsdTt6EtF51HE461/457 l

ES10 *ahd ^ES~~11 'Aut6'^~stssm ~1 i nd'^isbl ati'6H~ f5i liife" TU18 Auto Turbine trip failure AF16 Loop 3 AFW Control - Local AF17 17% MDAFW Pump B SG#3 throttle valve (HV-5134) throttled to yield only 300 gpm.

Overrides Annunciators: 04E2 - Off and 37C2 - Off LO U15D132 - Off LO HS5134a r - On LO zl40096 gb - On i

i NUREG-1021 Interim Rev. 8. January 1997 d

l.

i l

1

' Operator Actions Scenario No.:

1 Event No.:

1 Page 3

of 9

1 Event

Description:

Increase Power to 100%

Time Position Applicant's Actions or Behavior Directs Operators to increase power to 100%.

SRO Refers to Op 12004-C, Power Operation and directs operators.

Notifies load dispatcher Commences dilution R0 Maintains rods above insertion limits Maintains Tave within 2 deg Tref Maintains AFD within target band BOP Loads turbine as directed by SRO 1

i NUREG-1021 Interim Rev. 8. January 1997

l 2

Operator Actions Scenario No.:_

1 Event No.:

2 Page 4

of 9

J Event

Description:

CV 4 Fails Closed. Turbine impulse pressure xmtr PT-505 fails high.

PZR spray valve fails to close.

Time Position Applicant's Actions or Behavior Recognizes indidcations of PT 505 failure Tref /AutTave Hi-Lo Dev R0/ BOP Stm Gen Hi/Lo Lvl Dev C7 Status light on Lo Turb impulse pressure rod stop C5 status light on

' Turbine impule pressure indieation mismatch Control rods stepping in AMSAC Trouble Steam Dump demand 100%

Places rods in manual R0 Maintains rods above insertion limits Restores Tave within 2 deg F of Tref Maintains AFD within target band.

Stops load increase BOP Place stm dump controller in steam pressure mode SRO Refers to A0P 18001-C.H and directs crew operations verifies P-13 status light off NUREG-1021 Interim Rev. 8. January 1997

Operator Actions Scenario No.:

1 Event No.:

2 Page 5

of 9

Event

Description:

Turbine impulse pressure xmtr PT-505 fails high.

PZR spray valve fails to close.

1 1

Time Position Applicant's Actions or Behavior R0/ BOP Notes RCS pressure decreasing below programmed band.

j Refers to ARP D02 PZR CONTROL LO PRESS AND HEATERS ON.

Ensures PZR spray valves and PORVs are closed: Manually closes spray l

valves.

Establishes spray control from loop 4 per 17011-C Place loop 1 in manual close spray valve 445 C i

SRO Directs R0 to close spray valve.

Determines Loop 1 spray valve is inoperative and directs RO to establish spray control using alternate loop.

Refer to TS 3.4.1 LCO 1

NUREG-1021-Interim Rev. 8. January 1997 L

Operator Actions Scenario No.:

1 Event No.: _ 3 Page 6

of 9

Event

Description:

.ESF-125VDC SWGR fault-ICD 1 causing ICY 1A to deenergize (N-43 fails low, letdown isolates. TDAFW pump control lost)

Time Position Applicant's Actions or Behavior Pzr level / pressure place controllers in manual RO Identify loss of ICD 1 (C)

Position PZR pressure control to 455/456 or 455/458 Position PZR level control to 459/460 Position Tave defeat switch to defeat 432 i

Position delta T defeat switch to defeat 431 Restore Tave to program value Restore controllers to auto Block NIS Channel 3 rod stop, Reset Heaters Isolate letdown: shut letdown isolation valve LV-460 BOP maintain seal injection 8-13 gpm Take manual control of charging reduce charging 5-10

)

gpm > than total seal injection Place excess letdown in service (13008)

Enter ADP 18034.C Loss of 125V DC Bus 1CD1 SRO (First action) Dispatch operator to restore power to 120vac instrument panel 1CY1A Enter A0P-18032-1E Loss of vital instrument bus 1CY1A:

Direct isolation of letdown and initiate excess letdown.

Investigate cause of loss of 125V DC bus.

Apply TS 3.8.4 action B:

Be in mode 3 in 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.s.

Apply TS 3.7.5 action B: restore in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> / mode 3 in 6 Refer to Attachment E for loads on ICY 1A NUREG-1021 Interim Rev. 8. January 1997

i Operabr Actions i

Scenario No.:

1 Event No.:

4 Page 7

of 9

Event

Description:

FW Line #2 Rupture Inside Containment causing RX Trip. SIS. FWI and l

Blowdown of #2 SG.

Loss of TDAFW Pump due to SG blowdown.

MDAFW Pump B SG #3 throttle valve throttled to yield only 300 gpm.

Time Position Applicant's Actions or Behavior t

Verify Rx Trip RO/BDP Verify turbine trip Verify power to AC emergency busses: Notes one 4160V aC !E Bus is f

deenergized.

Check if SI Actuated Verify feedwater isolation: MFIVs - shut BFIVs - shut MFRVs - shut BFRVs - shut Verify MLB indications for both trains of ECCS eouipment aligning for injection pase:

Verify containment isolation Phase A actuated.

Verify: MDAFW Pumps running:

SG blowdown isolated TDAFW pump running:

reports not running j

Verify ECCS pumps running: CCPs SI. RHR (one train deenergized)

Verify 2 CCW pumps running on each train Verify 2 NSCW pumps running on each train Verify containment ventillation isolation.

Check if MSLIVs should be isolated: (YES)

Check containment spray not required.

Verify DG running:

Verify ECCS flows.

Verify total AFW flow greater than 570 GPM:

Verify ECCS alignment on MLBs Verify RCS temperatures: Temp < 557 deg & 4 l

NUREG-1021 Interim Rev. 8. January 1997 i

t Operator Actions i

Scenario No.:

1 Event No.:

5 Page 8

of 9

Event

Description:

FW Line #2 Rupture Inside Containment causing RX Trip. SIS, FWI and Blowdown of #2 SG.

Loss of TDAFW Pump due to SG blowdown.

MDAFW Pump B SG #3 throttle valve throttled to yield only 300 gpm.

Time Position Applicant's Actions or Behavior Lower total feed flow.

If all SG levels < 32%. maintain total feed >

570 gpm.

R0 Verify Pzr PORVs shut, block valves open and normal pzr spray valves shut.

Check if RCPs should be stopped:

Check ECCS pumps running Check RCP trip parameter-RCS pressure < 1375 PSIG: STOP RCPs Verify at least 1 ACCW pump running Check SG secondary pressure boundaries: Notes SG #2 pressure decreasing in an uncontrolled manner.

Enter 19000 (E-0)

SR0 Transfers to E-2: Faulted SG Isolation R0/B0P Perform the actions of E-2 as directed:

Close MSIV and MSIV bypass valve Isolate feedwater Close blowdown isolation valves NUREG-1021 Interim Rev. 8. January 1997

i' Operator Actions Scenario No.:

1 Event No.:

6 Page 9

of 9

Event

Description:

Loss of Bus AA02 i

Time Position Applicant's Actions or Behavior Recognizes loss of MDAFW pump A.

Notes FW flow < 570 GPM Transfers to FR-H.1 i

R0 Checks WR level in any 3 SGs less than 44% (adverse): Trip RCPs l

i l

BOP Emergency trips DG1A due to loss of NSCW i

i j

NUREG-1021 Interim Rev. 8, January 1997 i

SCENAR10 OUTLINE Form ES D 1 e

Simulation Facility :

Voatle Scenario No. : _2 _

Examiners:

Candidates:

Initial Conditions: The plant is at 76% Power (IC9) with the #3 condensate pump out of service.

Turnover: Plant SU is in progress. Rx Power is 76%.

Number 3 condensate pump was ed out due to severe vibration 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> ago.

tagg#1 SG (1HV 3009) is tagged shut for repairs to the motor operator (7 day LCO).Th the ETR is sometime tomorrow.

SG #3 has a 9 GPD leak rate and all the applicable actions of 18015 C have been performed. Control rods are in manual.

Preload: Control rods do not function in automatic. 8801a and 880lb closed. RD07 i

ES-01.02.03

~

Event Half Event Event j

No.

No.

Type Description 1

PR-03c SRO-I Begin power increase. LT461 PZR LEVEL channel faiis high.

R0-I.N Enter 18001-C CW01a R0-R at about 77 % CIRC WTR P-1 Motor overload. with Rods in Manual 2

R0-C operators follow power decrease down to about 50 %.

Condenser air in leakage is about 50%

C001 NOTE:SIM OPERATOR - monitor condenser vacuum w/ comp point i

UV-2095 3

TM9b S00 I 506 fai t high.

Powcr reache: about 15t.

^? SAC clar

.. cme in to indicate failure. nc action is required.

TUO2 ALL-C Turbine trip below P-9 due to high vibrations (AOP 18011-C) 4 NOTE: SIM OPERATOR - TUO2 to 80 % when turbine trips 8

PR04 MT-ALL RCS pressure reaches trip setpoint.

Reactor does not trip.

OR R0-C pressure and temperature continue to increase.

Enter ATWT 800b 19211-C.

Bit injection valves do not open.

open NOTE: SIM OPERATOR load PR04 at 100% on trigger and delete 880lb when manipulated.

C-ALL RCS pressure reaches the PORV 456 setpoint.

6 NOTE: SIM OPERATOR - Insert trigger as 456 lifts.

PORV 456 lifts and does not close, nor does block valve 456A.

Enter E-1. 19010-C.

Local actions are successful rods drop into core.

NOTE: SIM OPERATOR - remove 456A failure before step 6 in 19010-C - End scenario when the block valve is closed or 19010-C step 7 is reached o

(N)ormal.

(R)eactivity.

(I)nstrument.

(C)omponent.

(M)ajor NUREG-1021 Interim Rev. 8. January 1997 j

l Operator Actions l

Scenario No.:

1 Event No.:

l' Page 1 of l

Event

Description:

l Time Position Applicant's Actions or Behavior SR0 Directs Operators to increase power to 100 %

Refers to OP 12004-C. Power Operation and directs operators.

Notifies Load Dispatcher Directs entry into 18001-C after PRZR Level Failure R0 Commences dilution Maintains control rods above insertion limits Maintains Tavg within 2 degrees of Tref Maintains AFD in Target Band Detects failure of LT-461 PRZR Level Verify RCS pressure Stable or rising Select unaffected channel on PRZR Level Control Selector 459/460 Return PRZR pressure control to auto Select the same channel on the PRZR Level Recorder Selector switch PS-459 BOP Adjust Turbine Load i

NUREG-1021 Interim Rev. 8. January 1997

(;perator. Actions Scenario No.:

2 Event No.:

2 Page 2 of Event

Description:

At about 77 % CIRC WTR P-1 Motor overload, with Rods in Manual operators follow aower decrease down to about 50 %.

Condenser air in leakage is about 50%

NOTE:Sli OPERATOR - monitor condenser vacuum w/ comp point UV-2095 Time Position Applicant's Actions or Behavior Direct operators to reduce power and reduce load If below 50 percent power and turbine trips. INITIATE 18011-C. " Turbine SRO Trip Below P-9".

(t11s should not happen if actions are rapid enough)

If Reactor power is reduced 215% in a one-hour period. NOTIFY Chemistry to determine iodine activity per Technical Specifications SR 3.4.16.2 (Analysis required complete between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.)

Following loss of P-1 Pump R0 ENSURE control rods insert to match Tavg and Tref.

VERIFY Steam Generator Level Control controlling level in Programmed Band.

DISPATCH an operator to locally check Circulating Water Pump 1 for abnormal conditions.

DISPATCH an operator to check Switchgear 1 NAB 05 in the Turbine Building Level 2 Switc1 gear Room and NOTE which relays picked up.

I BOP RaoidlY REDUCE load as necessary to maintain condenser vacuum.

j START additional Mechanical Vacuum Pumps if required.

VERIFY Steam Dumps armed and responding to Tavg/ Tref deviation.

ENSURE Circulating Water Pump 2 is running.

j NUREG-1021 Interim Rev. 8. January 1997 i

4 4'

i 5

Operator Actions Scenario No.:

2-Event No.:

3 Page 3 of i

Event'

Description:

TV19b. 506 fails high causes AMSAC alarm.

Power reaches about 45 %

l Time Position Applicant's Actions or Behavior l

1 SRO Recognize AMSAC alarm is caused by 506 failure.

1 Determine that there are no required actions.

R0 Assist SR0 as required i

i Operator Actions 4

L l

NUREG-1021' Interim Rev. 8. January 1997 I

S5enarioNo.:

2 Event No.:

4 Page 4 of Event Descr13 tion: Turbine trip below P-9 due to high vibrations (AOP 18011-C)

NOTE: SIM OPERATOR - TUO2 to 80 % when turbine trips Time Position Applicant's Actions or Behavior SR0 Determine entry into 18011-C. Turbine trip below p-9. is required Ensure control rods are in manual R0 Adjust control rods to control reactor power and RCS temperature.

Ensure reactor power within capacity of operable stem dumps.

Restori Tavg to program band.

check PkZ? pressure control - greater than 1960.

BOP Verify terbine trip Transfer steam dumps to the steam pressure mode check main generator output breaker match steam flow and feed flow for all SGs i

i l

NUREG-1021 Interim Rev. 8. January 1997

Operator Actions Scenario No.: 2 Event No.:

5 Page 5 of Event

Description:

RCS pressure reaches trip setpoint.

Reactor does not trip, pressure and temperature continue to increase.

Enter ATWT.'9211-C.

Bit injection valves do not open.

NOTE: SIM OPERATOR load PR04 at 100% on trigger and delete 8001a and 8002 - close.

i Time Position Applicant's Actions or Behavior SRO Determines that Reactor should have tripped due to high pressure.

Directs entry into 19211-C. ATWT R0 Determine reactor has not tripped, after other methods fail dispatch operator to locally trip reactor.

i Verify turbine trip Initiate E,mergency Boration determine that 8001a and 800lb have not opened.

open 8001a and 800lb to ensure emergency boration flow path

{

\\

verify AFW flow i

I l

v i

i NUREG-1021 Interim Rev. 8. January 1997 4

Iperator Actions Scenario No.:

2 Event No.:

6 Page 6 of Event

Description:

RCS pressure reaches the PORV 456 setpoint.

- Insert trigger as 456 lifts.

PORV 456 lifts and does not close, nor does block valve 456A.

Enter E-1, 19010 C.

Local actions are successful rods drop into core.

NOTE: SIM OPERATOR - remove 456A failure before step 6 in 19010-C Time Position Applicant's Actions or Behavior SRO Determine that PORV opened and did not close.

Direct entry into 19010-C. E-1 Loss of Reactor or Secondary Coolant R0 Attempt to close 456A block valve.

Check if RCPs should be stopped Check P,i2R PORV and Block Valves (block valve will close)

BOP Verify ACCW pump running Check secondary pressure boundary Check intact SG levels Check Secondary rad levels NUREG-1021 Interim Rev. 8. January 1997

ES-301 todividual Walk-through Test " '1 9e Form ES-301-2 Facility:l (circle):

R0/SR0(D/SbfU)OperatingiestNo.

V0GTLE D

of Examination: 4/13-15/98 Exam Leve 1

/

i System / JPM Title / Type Safety Plann Questions:

K/A/G //ed Follow-up// Description l

Codes

• Functio.1 Importance

1. Transfer ECCS Pumps to a.

006A4.07 4.4 Hot Leg Recirc II 0.S.L.A 8

b.

013K4.10 3.7

2. Perform Control Room a.

068AK3.17 4.0

. Evacuation: Actions Prior.TkS to IV(s)

A j

D.S 4

b.

2.1.8 3.6

3. ~stablish B0ckfill From a.

038EK3.08 4.2 kuoturedS/

III D.S.L.M 21 b.

038EA1.39 3.7 4.Rgedgroupn misaligned rod to a.

014A2.04 3.9 I

13 b.

014A1.03 3.8 5.Manua}RC"'gnDampers&

ly Ali a.

2.1.28 3.3 5'b.

8 b.

061AA1.01 3.6 6.gsgogtoFailureofRCP a.

003K6.02 3.1 M.S 5

b.

003A1.01 3.2

7. Trip PZR Pressure a.

010K4.03 4.1 3rotecyionSystem VII hfh) 6 b.

010K1.03 3.7 8.LocallgericgiefValve Oper S/G a.

035K6.02 3.5 gosp IV 13 b.

041A4.06 3.1 9.Energgternatepower e 120VAC Vital Bus a.

062K2.01 3.4 VI g

16 b.

062A2.06 3.9 10.gperateContainmentH2 i

a.

028K5.02 3.9 DY" j

7 b.

028A1.02 3.7 path b)

!oi okkk)

$ak$

(l. o b

.WlInh(bbA o,.. s u ~ u-

ES-301 inbividualWalk-throughTest

.line Form ES-301-2 Facility:l (circle):

R0/SR0(I)/hUSfExaminatihes:tNo.

V0GTLE n 4/13-15/98 Exam Leve Operating 1U 1

System / JPM Title / Type Safety Planned Follow-up Oue K/A/G // Importance // D.stions:

l Codes

• Function escription 1 Transfer ECCS Pumps to a.

006A4.07 4.4 Hot Leg Recirc II j

l D.S.L.A 8

b.

013K4.10 3.7

2. Perform Control Room a.

068AK3.17 4.0 l

Actions Prior to IV(s)

-vacuation: ATWS 3.5.M.A 4

b.

2.1.8 3.6

3. g PZR Prgystem ssure a.

010K4.03 4.1 n

VII Bu D.

6 b.

010K1.03 3.7 4.gperageContainmentH2 a.

028K5.02 3.9 DN l

7 b.

028A1.02

3. 'i 5.Energge120VACVitalBus a.

062K2.01 3.4 gm ternate power VI 16 b.

062A2.06 3.9 6.

a.

b.

7.

a b.

8.

a.

b.

9.

a.

b.

10.

a.

b.

path.yp(b) Codes-(D)ireEk) fro $ator.(L)owPower.(P)lant.(R)dA.(A)lternate

• -T Dank. (M)odified from bank. (N ew ontrol room.

imu

I ES-301 Administrative Topics Outline Form ES-301-1 i

l-Facility: Vootle Date of Examination: 4/13-15/98 Examination Level (Circle):

R0/SR01S0peratingTestNumber:

1 & 1U i

Administrative Describe method of evaluation.

Topic / Subject 1.

ONE Administrative JPM. OR Description 2.

TWO Administrative Questions A.1 Plant JPM: Calculate Keff For Rx SU K2.17 3.7/4.4 Parameter N

Verification Shift Staffing JPM: Evaluate use of Overtime 2.1.4 2.3/3.4 Requirements N

A.2 Equipment JPM: Re-a Clearance 2.2.13 3.6/3.8 Control N

A.3 01: Review RWP and Survey Map 2.3.7 2.0/3.3 Radiation Control 02: Criteria for ~ Hot Spots" 2.3.1 2.6/3.0 A.4 Classify Event 2.4.41 2.3/4.1 Emergency Plan Implement Offsite PARS 2.4.44 2.1/4.0 N

n, re,

e n.1 -

L U st Ur N s s

ES-401 PWR SRO Examination Outline form ES-401-3 W/1 uM1 94D1 Facility:

Date of Exam:

Exam Level:

K/A Category Points Tier Group Point K

K K

K K

K A

A A

A G

Total 1

2 3

4 5

6 1

2 3

4 3 f fh hh $ f [ 3 /

24 I

2.

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19 2

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S S [

l 5 l

A I

Systems f3 1

j j

4 Tier 40 Totals 3

5 T 5 2

'9 3

4 9

4 3 3

3.

Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 17 Note:

Attempt to distrii 9 topics among all K/A categories; select at least one topic from every K/A category within each tier.

Actual point totals must match those specified in the table.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

Systems / evolutions withir, each group are identified on the associated outline.

The shaded areas are not applicable to the category / tier.

NUREG-1021 23 of 39 Interim Rev. 8, January 1997

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ES-401 PWR SRO Examinetlon Outline Em eroenny and Abnormal Plant Evolutions - Tier 1/ Group 1 Form ES-401-3 E/ APE # / Name / Safety Function K K K A A G K/A Topicts) Imp. Pointe 1 2 3 1 2 000001 Continuous Rod Withdrawn! /I / C O / A l( l. O 7 9 c[o,z y { 000003 Dropped Control Rod / r / CO3 8 R /, O 7 'fJl3,9 2. NE.O 000005 Inoperable / Stuck Control Rod / I / 0 0 <3 7 A 2. C 3 3s/,4 y_ giuYq 000011 Lecce Break LOCA / lit / OfI M 1.O 8 2.1/3/1 Y Mhg W/E04 LOCA 0 telde Containment I til / G09 K7 2 3@4.o I to B geoif 9 W/E02 St Temanation /111 / / 8 2 E82 e / '3J/% ~71L_ dEO 2 000015/17 HCP Malfunctione /IV O/IN h f. 'LO 'f.0/fr.2 T MM BW!E09: CE/A13: W/LO9&E10 Natural Cire. I tv I E O 9 E K '). Q uff.3 T d C * "! 000024 Emeranney Borstion /I I C19 bNb e O\\ %Ift.t T ).)P C. 4 000026 Loss of Component Coottna Water / Vill _l 01G M i, o7 2els.c zn ~TM ' 000029 Anticipeted Trenaient w/o Scram / ( O29 6K?oi i1 (4.t,(s.7 2 j 000040 (BW/E05: CE/E05: WlE12) Steam Line / D ~ Rupture - Evenenive Hant Trenefer / Iv / O *f o // P e. t) R /,/2 4,'2k 7 WEu > CE/A11: W/E08 RCS Overcoottna - PTS / IV I U N 2,1 3.lbo 3 MEAO 000051 Loss of Condenser veeuum liv / O F/ 6 // 2.01 33/W 7 "y a 000055 Si.non oisekout / vt / 0566H1-(>6 4,i/4 s .bg.rm i 000057 Loss of Vite! AC Elec. Inst. Due / V: I Os 7 4 A'3, O / 4./Ai/ E /JLtd 000059 Accidental Lutuid RndWeste Ral. / IX 000062 Loss of Nucient Service Water /IV i-O O6Q A () 7.Cf \\ M/34 J h$~b 000067 Plant Fira On-site /IX 000068 (BW/A06) Control Room Evse. I Viit .) D G R A R 3. i G 4.e /+g I. Nw 000069 (W/E14) Loss of CTMT intearity / V I 0[> 9 E K.'2.. I L'ilt.7 T " g %,; 000074 (W/EOG&E07) Innd. Core Coolinn / IV I OO /L1 6 d 3,)\\

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BW/E03 Inednaunta Subcoolinn Meroin / IV 000076 Hinh Reactor Cootent Activity / IX I O)b kE b/Of sht 2 3;to BW/A02& A03 Loss of NNI-X/Y / VII f K/A Catannry Totnis: Group Point Totst:

• w/co7 m t eleo, e m. i 3.e.g g NUREG-1021 24 of 39 Interim Rev. 8, January 1997

I9 ~. ES-401 PWR SRO Examination Outline PInnt Svs : ems - Tier r/Grou s 1 Form ES-401-3 System # / Name K K K K K K A A A A G K/A Topic (s) Imp. Points 1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive l O O / // 3,06 39/3/; 1 d Ld ( 003 Reactor Cootent Pump / / C) O J # 2,0 2 3.?l35i I. W l 004 Chemical and Volume Control I 0001 X 1, 0 3 3J/3r I 01DDif t /> ec. G r> Alt. ' 013 Eno!neered Safety Features Actuation / 00/3 61.c) f 3N/4 I "tul 014 Rod Position Indication /' 00:4 6,o I a.W3 o n wca W {W 015 Nuctent Instrumentation I- 'l Oi 5 M,o Lg 3al3.2 I vno-' 017 in-core Temperature Monitor I O I 7 K \\.O l 3,2 kt T f 1. 4 022 Conteinment Coolina 025 fee Condeneer ~ f)/d 026 Containment Sprov I s 0,t G b( ta.C) i '. 2 19, 3 , f i-us u) 058 Condenente 059 Mein Feedwater / f Oh h O/ <O 3 M7/1k) Z dd 061 Auxiliary /Emeraency Feedwater / I 06% 93.0% (4.1/t.;;1] T 083 DC Electrical Distribution 9 l-OG 3 K3 01 7,7/4.s T ^>Ec 6 a' i 009 Ucuid Radweste l-C69 O Q,O2 Jal3,l T dd 071 Weste Gne Disposal L. 072 Area Rndistion Monitorina l O '? ~2. K / s O l 3,l[jg I bbNN 6t's 8 0 8 5 K 3. c '2. 3.sc 3 uetJ O* A C O 3 K L. O '2. 27l3I TII-K u; 059 Y 059 A '1,o 2 pabg g putua i OG @ OG 3 K 'A,o i 2RIs.1 1 Synt j i i L K/A Category Point Totnis: Group Point Total: NUREG-1021 27 of 39 Interim Rev. 8, January 1997

I i7 l + l ES-401 PWR SRO Examinetton Outline l Plant Svelems - Tier r/Grou) 2 Form ES-401-3 System # / Name K K K K K K A A A A G K/A Tople(s) Imp. Points 1 2 3 4 5 8 1 2 3 4 002 Reactor Coolant I 014.o A 7.i/L6 t>co ' 006 Emeroency Core coolina / 006 K I.0 2 't.3ltr,t, V $Q, 010 Preneuriter Pressure Control / O I D #4 /. 07 OJ/f.7) g A/coj 011 Preenuriferlevel Control 012 Reactor Protaction /# f Gi24.m scsh4 7 Mt.M 016 Non-nuclear Instrumentation 8 O t is K4.O3 2 E/2/1 "U A)F l 027 Containment todine Removat 02 rogen Recombiner and Purg l O d 66 tik I A') t i 029 Contelnment Purae I O7Cg{3,c) 33g,3 g pd ! 033 Spent Fuel Pool Coolina 034 runt unmmna Eauinment / O03 K 3.O i 2.9/n I 81$$ Oss stenm Generator I 0 3f /13.0 i <r.oha I Tfy 039 Mein and Rehest Stoem 055 Condeneer Air Removnt 062 AC Deetrical Distribution I D6 M 7,D4 31 f3 8, T 084 Emaranney Diasel Generator i OMI A4.IG 2a/2.4 Z NCN 073 Process Rndintion Monitorinct L 075 Circutntina Water 079 Station Air l 096 Rre Protection i OR % o i M.? '.L 'NE.ru[ 103 Contelnment I /03 4 3,O l 59142 I I 002/110' NAf R. ^>cua fl Of'21CA.Dl (53h.i I h)RC an u ! l K/A Catenory Point Totnis: Grnup Point Totnt: NUREG-1021 28 of 39 t Interim Rev. 8, January 1997

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f hMC ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 l Facility: Date of Exam: Exam Level: Category K/A i Topic Imp. Points i %)1 2.1. S Aed'sd u o d s@ L C l Rom 3.5 /J.6 r ti t. Bj' I

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l D,o \\ ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-4J1-5 Facility: Date of Exam: Exam Level: Category K/A # Topic Imp. Points 2.1. 3 5 Md.k 4-o o w 3 cl54 r utu) 2.1. 74 k5<4 U4d I tJ LLO hkNoN 2.1. /f LdG-5 (M/s.o) T NE 4) 2.1.34 C Wou N L mks halt,{ t mc8-l 2.1. 1 1 2.1. l Total

2. 2. 3 S LJedou m Coel m 3,l/33 91.

fJE LQ 2.2. If Muk o.r.1Wdu.2_ S um -eA 2384 I m,o o me. g Equi 2.2. I b b fa M w roedm.Eaemew, 3.7/3.c Z Conthment ago ol 2.2. 22 LC'C) Knou)b cler 34/4,1 2T_ WE.u) l 2.2. 3 dn ef c)t P9ecexe 3,ll33 E MW 2.2. Total l 23.9 GM m wt be, c._ 25/3,9 u r2.c. ?Am 2.3.11 %tLd-u A o eddd Ne,h edt-as 2 7/3. :t I oLW Radiation 2.3. / /oCFftdoc. m tt5 j 4 /2o) g, et.td Control p,3, y 6,n Q ekvn Cem4cer\\ 9 5/31 7 /J Ep) 2.3. 2.3. Total 2.4. x Nc=J. SecM es 20 5,3 _t us_ud 1 l 2. 4. 1/4 0445'T 3.c/40 H NLu) $3 2.4.37 E e%% M % J-a 24/:g . t-6 1 0 and Plan 2,4 g - @,,3n,c,bem3 3p/gg 7, ' o g.vj 2.4. 1 2.4. Total Tier 1 Target Point Total (RO/SRO) 13/17 NUREG-1021 37 of 39 Interim Rev. 8, January 1997

4 SOUTHERN h COMPANY Energy to Serve Your World" PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-37113-001-03B TRANSFER ECCS PUMPS To hot LEG RECIRCULATION WITH FAILURE OF TRAIN B SI AllGNMENT i Revision 0 May 20,1997 Written By

feetjefuer Date:

5/20/97 Approved By : 4 cat Ray Date: 5/20/97 DISTRIBUTION CODE A070 J

l RQ-JP-37113-001-038 l JPM INFORMATION 4 OPERATOR'S NAME: l l EVALUATION DATE: / / l JPM TITLE: Transfer ECCS Pumps to Hot Leg Recirculation with Failure of Train B SI Alignment REVISION: 0 May 20,1997 COMPLETION TIME: 8 minutes Application: RO/SRO Task Number: 37009 K/A Number: 000011EA111 RO: 4.2 SRO: 4.2 10CFR55.45 Ref.: 6,7,12 Evaluation Method [ ] Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room ( ) Unit 1 [ ] Unit 2 Performance Time: minutes OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: Examinefs Signature: 3 J

RQ-JP-371 C-001-03B INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 19014-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "c.. " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQUIRED ITEMS: 1. 19014, Transfer to Hot Leg Recirculation SIMULATOR SETUP: 1. Reset to IC14 i 2. Perform step 20 of 19010 3. Insert malfunction RC05 at 100% severity 4. Trip all RCPs 5. On the 97 terminal enter: SET CSMRWST=2.2E6 FRZ CNM SET CHMWATER=1.25E6 6. Perform 19013-C steps 1 through 7 7. Override HS8802B/CLOSE 8. Ack/ Reset alarms 9. Freeze simulator 10. After completion of this JPM, on the 97 terminal enter: RUNALL Setup time: 10 minutes i DIRECTIONS TO OPERATOR You will be given information describing the initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task. INmAL CONDmONs: A large break LOCA occurred = 11 hours ago. The crew is on step 21 of 19010. AsslGNED TASK: The USS has directed you to " Transfer the ECCS pumps to hot leg recirculation using 19014". TASK STANDARD: ECCS pumps operating in the hot leg recirculation mode. 4 m

-.. _ ~ _ - _ _ RQ-JP-37113-001-03B r JPM STEPS START TIME: STEP 1 CRITICAL (+) l SAT De UNSAT De Align RHR for hot leg recirculation l Note: The operators would have posiooned these k>ckout switches to ON at step 19 of 19010. aC . Lockout switches HS-8809C and HS-8809D in ON a0 + Cold leg injections HV-8809A and HV-8809B CLOSED wO + Crossconnects HV-8716A and HV-8716B OPEN l 50 . Lockout switch HS-8840A in ON su + Hot leg injection HS-8840 OPEN j STEP 2 CRITICAL (+) SEQ 1 A SAT De UNSAT De Stop SIP A i x0 + SIP A Stopped STEP 3 I CRITICAL (+). SEQ 1B SAT D e UNSAT De Align Train A Si for hot leg recirculation I Note: The operators would have positioned this lockout switch to ON st step 19 of 19010. ? I a0 + Crossconnect HV-8821 A CLOSED I hu . Lockout switch HS-8802C in ON su + Hot leg injection HV-8802A OPEN S

i RQ-JP-37113-001-03B JPM STEPS STEP 4 CRITICAL (*) SEQ 1C SAT De UNSAT De Start SIP A hO + SIP A Running wO e Train A Si flow verified > 100 gpm CUES: O Indicate Train A SI flow = 700 gpm." STEPS CRITICAL (+) SEQ 2A SAT Oxr UNSAT De Stop SIP B s0 + SIP B Stopped STEP 6 CRITICAL (+) l SEQ 28 1 SAT Onr UNSAT Omr Align Train B Si for hot leg recirculation Note: The operators would have posidoned this lockout switch to ON at step 19 of 19010. s0 . + Crossconnect HV-88218 CLOSED i su . Lockout switch HS-8802D ON su . Hot Leg injection HV-8802B verified NOT OPEN sO e Ensure Cold Leg injection HV-8835 OPEN su + Crossconnect HV-8821B OPEN l 6 i

RQ-JP-37113-001-03B l JPM STEPS 4 i STEP 7 CRITICAL (+) SEQ 2C SAT De UNSAT De i Start SIP B wO + SIP B Running sO e Train B Si flow verified > 100 gpm CUES: O Indicate Train B Sl flow = 720 gpm. STEP 8 SAT De UNSAT De Report to USS su . Train A ECCS aligned for Hot Leg Recirc s0 . Train B SIS must remain aligned for Cold Leg Recirc STOP TIME: Field Notes: l 7 a. .a

JPM: 11 SYSTEM: ECCS l QUESTION: 1 K/A: 006A4.07 (4.4/4.4) l OUESTION: Follaving a valid Safety Injection Signal and System Initiation. how does the j ECCS respond automatically? ANSWER: 1. CCPs receive start signals 2. CCP suction valves from the RWST(112D and 112E) open. 3. BIT outlet (8801A and 8801B) isolation valves open to complete the flow path from the-RWST to the RCS cold legs. 4. CCP normal suction valves (1128 and 112C) and normal discharge valves (8105 and 8106) and the CCP miniflow isolation valves to the seal water heat exchanger (8810 and 8811) all close to direct the CCP discharge through the BIT to the RCS cold legs. 5. CCP alternate miniflow valves (8508A and 8509 A and B)will open and close based on CCP discharge pressure (white light on) 6. SI pumps and RHR pumps start and pump water through their respective miniflow lines until system pressure decreases below their respective shut off heads (the pressure necessary to unseat the check valves). i 7. The normally open accumulator isolation valves (8808A through 88080) open if any have been inadvertently closed. Ref. Allowed: May Use Control Boards for Reference.

REFERENCE:

A0P-18038. LO-LP-60328-08-C 's_ j

i 9 JPM: Il SYSTEM: ECCS QUESTION: 2 K/A: 013K4.10 (3.3/3.7) OUESTION: List and describe the interlocks associated with the HHSI (CCP) and LHSI (RHR) system valves. ANSWER: 1 CCP Interlocks are : a. 112 B/C are interlocked with 112 D/E 112D(E) must be open before 112B(C) will AUTOMATICALLY close on SI or 10-10 VCT level. l b. Alt miniflows 8508A/B 8804A and 88048 must be shut and 1128 or 112C must be shut to open 8508A or B Alt miniflows 8509A/B 8804A and B must be shut to open 8509A or B. i When in " ENABLE PTL". or while in " Auto" with an SI Signal present. B508. A/B will operate on CCP discharge pressure. ENABLE PTL bypasses all normal interlocks. RHR Interlocks are. RWST SUCTION VALVES: a. HV-8812A (480V MCC 1 ABD) and HV-88128 (480V MCC 1 BBD) b. HS on OMCB-A and respective shutdown panels c. Sump suction valve B811 and HX discharge B804 to CCP (SIP) must be closed to open these valves CONTAINMENT SUMP SUCTION VALVES: a. HV-8811A (480V MCC 1 ABD) and HV-8811B (480V MCC 1880) b. Must be closed to open 8812A and B valves from RWST . Reference Allowed: YES

REFERENCE:

ENGINEERED SAFETY FEATURES EMERGENCY CORE COOLING SYSTEM LESSON PLAN CHAPTER NO. 9a. and LO-LP 13101 to 13401 l l l

t i i '. 1 t l l JPM: 11 QUESTION: 2 l L i List and describe the interlocks associated with the HHSI (CCP) and LHSI (RHR) i system 'alves. i l 1 l l i l l 1 l l

i JPM: 11 QUESTION: 1 p ..#..w Following a valid Safety Injection Signal and System Initiation, how does the ECCS respond automatically? i I l i l l

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task. initial Conditions: A large break LOCA occurred = 11 hours ago. The crew is on step 21 of 19010. Assigned Task: The USS has directed you to " Transfer the ECCS pumps to iot leg recirculation using 19014" Task Standard: ECCS pumps operating in the hot leg recirculation mode. 2

\\ SOUTHERN h COMPANY Energy to Serve Your World" PLANT VOGTLE l CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE l RQ-JP-60328-001-12 PERFORM CONTROL ROOM ACYlONs PRIOR TO EVACUATION Revision 11 April 2,1998 Written By

D, Scu444cc Date:

4/2/98 i Approved By :D, Sca4 ace Date: 4/2/98 i

RQ-JP-60328-001-12 JPM INFORMATION OPERATOR'S NAME: EVALUATION DATE:,___ / __ / _, JPM TITLE: Perform Control Room Actions Prior to Evacuation REVISION: 11 4/2/98 COMPLETION TIME: 4 minutes Application: RO/SRO Task Number 60010 K/A Number: 000068EA121 RO: 3.9 SRO: 4.1 10CFR55.45 Ref.: Evaluation Method [ ] Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room [ ] Unit 1 [ ] Unit 2 Performance Time: minutes OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: Examiner's Signature: 3

RQ-JP-60328-001-12 INSTRUCTIONS TO EXAMINER This JPM is based on 18038-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "@.. " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQUIRED ITEMS: 1. 18038, Operation from Remote Shutdown Panels SIMULATOR SETUP: 1. lC14 2. Ack/ Reset Alarms 3. Insert overide for HS-40007 ( Rx Trip) to the neutral position 3. Freeze simulator Setup time: 1 minutes DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used 10 perform this task. INITIAL CONDITIONS: A control room fire has compelled the SS to order an evacuation. Although the fire is resulting in equipment degradation, there is no immediate threat to personnel safety. AsslGNED TASK: The USS has directed you to " Perform the controi room actions required for an evacuation due to fire". TASK STANDARD: Reactor tripped and primary and secondary systems aligned for control room evacuation. i 4

L 1 RQ-JP40328-001-12 JPM STEPS 1 START TIME: STEP 1 ' ' - ~ CRITICAL ~(+) SAT Ox - UNSAT De Trip the reactor wD . Operator attempts to manually trip reactor using trip handswitch (HS-40007) sO + Operator trips reactor with attemate trip handswitch (HS-40002) sO + Reactortrip and bypass breakers open sO e DRPl rod bottom li0 hts lit STEP 2 CRITICAL (+) SAT De UNSAT De Shift CCP suction to RWST I su + RWST to CCP HV-112D & lor HV 112E open wD + VCT to CCP HV-112B &/or HV-112C closed L.EP 3 CRITICAL (+) SAT De UNSAT De Isolate PORVs wD + PORV Block Valves HV-8000A and HV-8000B closed STEP 4 CRITICAL (+) SAT De UNSAT De Stop RCPs s0 + RCPs 1 and 4 stopped I l l \\ j

[ RQ-JP-60328-001-12 JPM STEPS STEP 5 CRITICAL (+) SAT De UNSAT Os isolate Steam Generators wO Both MFPs tripped e a0 . MFIVs cl esed - aO e BFIVs c' ased SGBD isolations, HV-7603A, B, C, &D closed a0 wO + MSIVs closed hO + MSBVs closed STEP 6 CRITICAL (+) SAT De UNSAT De Throttle AFWflow su + AFW flow controllers adjusted to reduce total AFW flow to not < 570 gpm (1) CUES: l (f) After AFW flow throttled: "The USS has determined that step 3 need not be performed." l STEP 7 SAT De UNSAT De Report to USS sO . Operator actions for evacuation complete . STOP TIME: Field Notes l l l 4 6 i

l JPM: 12 SYSTEM: Remote Shutdown QUESTION: 1 K/A: 068AK3.17 (3 7/4.0) 1 OUESTION: Given the following conditions:\\ l - Local control of ECCS equipment has been established per A0P-18038, " Operation from Remote Shutdown Panel." - Subsequently, an SI signal is initiated. a. What is the expected plant response ? I b. What operator actions are required, if SI initiates ? c. What operator actions are required if the reactor has not tripped in step 1 of ADP-18038 ANSWER: a. SI will not automatically initiate. A0P-18038 takes precedence over the E0Ps for response to SI. b. In the event an SI does actuate, the crew is first directed to start necessary ECCS pumps if pressure.is lowering and try to terminate it if plant conditions will allow. If this is not possible, the crew is then directed to consult the TSC (after it is manned) to determine additional actions to be taken, c. Take any actions necessary to trip the reactor, Emergency borate, if necessary. Do not enter 19211-C. Ref. Allowed: yes

REFERENCE:

A0P-18038. LP-60328-08-C l l l

i 4 JPM: 12 SYSTEM: Remote Shutdown QUESTION: 2 K/A: 2.1.8 (3.8/3.6) OUESTION: There is a fire in the cable spreading room that requires an immediate evacuation of the control room. You implement AOP-18038 and evacuate the control room. Where do the on shift personnel report? ANSWER-SHIFT SUPERVISOR (USS)- Shutdown Panel B REACTOR OPERATOR - Shutdown Panel B B0P OPERATOR - Shutdown Panel A SSuperintendent (SS)- TSC at ERF Terminal i STA/SSS - TSC at ERF Terminal OUTSIDE AREA OPERATOR - Shutdown Panel C AFW pump house EXTRA SHIFT PERSONNEL - Shutdown Panel B i i l ~ Reference Allowed: N0 i

REFERENCE:

A0P-18038 LO-LP-60328-08-C 1 4 i 4 i

^7 c ~ JPM: 12 QUESTION: 2 Tnere is a fire in the cable spreading room that requires an immediate evacuation of the control room. You implement A0P-18038 and evacuate the control room. Where do the on shift personnel report?

...-. _ =. = - I e e JPM: 12 QUESTION: 1 Given the following conditions: - Local control of ECCS equipment has been established per A0P-18038, " Operation from Remote Shutdown Panel. - Subsequently, an SI signal is initiated. a. What is the expected plant response ? b. What operator actions are required, if SI initiates ? c. What operator actions are required if the reactor has not tripped in step 1 of A0P-18038 1 1 + l

This inforrnation describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task. initial Conditions: A control room fire has compelled the SS to order an evacuation. Although the fire is resulting in equipment degradation, there is no immediate threat to personnel safety. Assigned Task: The USS has directed you to " Perform the control room actions required for an evacuat on due to fire" Task Standard: Reactor tripped with primary and secondary systems aligned for control room evacuation. I 2 s

SOUTHERN h COMPANY Energy to Serve Your World" PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASVRE RQ-J P-37312-001-01 ESTABLISH BACKFILL FROM RUPTURED SG 4 Revision 8 April 2,1998 Written By @, Sca444cc Date: 4/2/98 Approved By O. Sca444cc Date: 4/2/98 4 4

_ ~ RQ-J P-37312-001-01 JPM INFORMATION OPERATOR'S NAME: EVALUATION DATE:,__ /._.,,_ /.,_ JPM TITLE Establish Backfill from Ruptured SG REVISION: 8 4/2/98 COMPLETION TIME: 21 minutes (verify new time based on changes to JPM) Application: RO/SRO Task Number: 37013 K/A Number: 000038EA139 RO: 3.6 SRO: 3.7 10CFR55.45 Ref.: Evaluation Method [ ] Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room ( ) Unit 1 [ ] Unit 2 Performance Time: minutes OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: Examiners Signature: 3 i

) RQ-JP-37312-001-01 INSTRUCTIONS TO EXAMINER This JPM is based on 19031-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "@.. " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQUIRED ITEMS: 1. 19031, Post-SGTR Cooldown Using Backfill SIMULATOR SETUP: 1. Reset to IC14 2. Insert malfunction SG01 A (B,C,or D) at 50% 3. Initiate manual SI, use only 1 train of ECCS 4. Throttle AFW flow to stabilize temperature (stop flow to the ruptured SG when >20% NR level) 5. Perform all of 19030 and steps 1 through 4 of 19031 6. Place two 75 gpm orifices in service when LTDN is established 7. Isolate or vent all accumulators 8. Ack/ Reset alarms i 9. Verify PRZR level is ~ 2.5% and Ruptured SG level - 45% ) 9. Freeze simulator Setup time: 30 minutes Due to the cornplexity of this setup, the intital conditiot's should be setup in advance and snapshot to an IC. DIRECTIONS TO OPERATOR You will be given information describing the initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task. INITIAL CONDITIONS: A tube repture has occurred on SG The crew responded using 19000,19030, and has transitioned to 19031. Steps 1 through 4 of 19031 have been performed. In addition, reactor engineering has determined that the RCS boron conenetration is adequate for the cooldown to Xe - Free Cold Shutdown.. AsslGNED TASK: The USS has directed you to " Continue implementation of procedure 19031 beginning with step 5". TASK STANDARD: RCS backfillinitiated from the ruptured SG and plant parameters within limits. 4

~. -. i RQ-JP-37312-001-01 JPM STEPS i START TIME: STEP 1 '~ CRITICAL (+) SAT De UNSAT De l Initiate RCS cooldown ' Note: It a steandne isulebon occurs, the operstor should estab6sh the cooldown using the intact SG's ARVs. wO + Steam dump controller PIC-507 adjusted to establish RCS cooldown sO e Cooldown rate 50 to 100*Fihr (1) CUES: (1) Once achieved, provide the foUowing cue,"The Common RO will maintain the cooldown rate." STEP 2 SAT De UNSAT De Vesify ruptured SG level a0 + When ruptured SG NR level < 38% NR operator initiates AFW to raise SG level (1) i CUES: 1 (1) Once SG level is increasing

• The common.RO will monitor rupture SG feed flow" STEP 3 SAT De UNSAT Os Verify PRZR level adequate for backfill l

wO + When PRZR level <19% operator raises charging flow to restore level ] i i i e i I 5 i

~.. RQ JP-37312-001-01 JPM STEPS STEP 4 CRITICAL (+) SAT O.er.. UNSAT De l t i Establish RCS backfill from ruptured SG Note: The optimum setup for backM is maximum letdowrt, minimum charging, and RCS pressure adjusted to maintain PRZR level (by varying backM). Without this balance, PRZRlevel wd change. When SIMULATED, the examiner should determine the operator's intent andprovide cues accordogty. I wu + Spray controller PIC-455B and/or PIC-455C adjusted to lower RCS pressure 50 . Backup heaters energized (as needed to maintain subcooling) su + RCS pressure < ruptured SG pressure a0 + Ruptured SG level lowering ( unless feed flow established to refill SG to 81%) (1) j a0 . Subcooling > 24*F a0 . PRZR level < 90% (see note above) CUES: 4 (1) Once student has commenced feeding ruptured SG, RCS pressure < SG press, and PRZR level is being raised then " USS will have the Common RO complete the Post -SGTR Cooldown Using Backfill Procedure" STEPS SAT Oe UNSAT De RepodtoUSS su . Backfill from ruptured SG initiated STOP TIME: Fleid Notes I 4 6

l JPM: 13 SYSTEM: Backfill. ES3.1 QUESTION: 1 K/A: 03,8EK3.08 (4.1/4.2) I a OUESTION: i In 19031. "ES3.1. Post SGTR Cooldown Using Backfill" a. What are the advantages of leaving the RCP's running ? f b. What are the disadvantages of stopping the RCP's ? ANSWER: i a. If RCPs remain running i 1) The ruptured SG fluid will be cooled by reverse heat transfer to the cooler reactor coolant flowing through the U-tubes 2) The insulated steam space should be unaffected by the reverse cooling flow 3) It will maintain homogenous temps throughout the RCS. b. If RCPs are stopped: 1) Ruptured loop flow will stagnate 2) Ruptured loop will cool much more slowly than the active loops Reference Allowed: YES

REFERENCE:

ES3.1 Background. LO-LP-37312-09-C i

JPM: 13 SYSTEM: Backfill ES3.1 QUESTION: 2 K/A: 038EA1.39 (3.6/3.7) OUESTION: ) What are the potential adverse affects of AFW flow into an isolated SG ? ANSWER: a. AFW could lift the insulating layer of warm water. compressing the bubble, and overpressurize the SG to the point of lifting the ARV b. Cold AFW could mix with the warm SG water resulting in a rapid SG depressurization by bubble collapse Reference Allowed: YES

REFERENCE:

ES3.1 Background. LO-LP-37312-09-C l j W

~ _. - JPM: I3 OUESTION: 2 What are the potential adverse affects of AFW flow into an isolated SG ? L i I f l i l l t i 4 f l l

l JPM: 13 OUESTION: 1 In 19031. "ES3.1, Post SGTR Cooldown Using Backfill" j i 1 a. What are the advantages of leaving the RCP's running ? b. What are the disadvantages of stopping the RCP's ? i l J i

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task. 1 Initial Conditions: A tube rupture has occurred on SG The crew responded using 19000,19030, and has transitioned to 19031. Steps 1 through 4 of 19031 have been performed. In addition, reactor engineering has determined that the RCS boron concentration is adequate for the cooldown to Xe - Free Cold Shutdown.. Assigned Task: The USS has directed you to " Continue implementation of procedure 19031 beginning with step 5". Task Standard: RCS backfill initiated from the ruptured SG and plant parameters within limits. 9 2

--_._..-___-..-y SOUTHERN h COMPANY Energy to Serve Your World" PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-60303-002-01 REALIGN MISALIGNED rod To AFFECTED GROUP Revision 12 August 12,1997 Written By - fco7jc faar Date: 8/12/97 Approved By : 2 cat Raef Date: 8/12/97

RQ-JP-60303-002-01 JPM INFORMATION 1' i OPERATOR'S NAME: i EVALUATION DATE: __/ _/__ l JPM TITLE: Realign Misaligned Rod to Affected Group 4 REVISION: 12 August 12,1997 COMPLETION TIME: 13 minutes Application: RO/SRO Task Number: 60037 K/A Number: 001000A203 RO: 3.5 SRO: 4.2 10CFR55.45 Ref.: 6,12 Evaluation Method [ ] Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room [ ] Unit 1 [ ] Unit 2 Performance Time: minutes OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: Examiner's Signature: 3

RQ-JP-60303-002-01 INSTRUCTIONS TO EXAMINER This JPM is based on 18003-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "c..." are provided to enhance simulation of this JPM and should only be used when the simulator is unt vailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQUIRED 1TEMs: 1. 18003, Rod Control System Malfunction SIMULATOR SETUP: 1. Reset to IC15 2. Ensure rods in manual and step counters set at 189 on CBD) 3. Insert malfunction RD10H (Stuck Rod - D4) 4. Withdraw CDB to 204 steps 5. Verify Rod Deviation alarm is illuminated 6. Adjust turbine load as necessary to restore Tavg 7. Remove malfunction RD10H 8. Ack/ Reset alarms 9. Freeze simulator Setup time: 10 minutes DIRECTIONS TO OPERATOR You will be given information describing the initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before t'eginning. You will be allowed access to any item normally used to perform this task. INITIAL CONDITIONS: While withdrawing rods during a power increase, the operators observed Control Bank D rod D4 failed to move. The crew completed steps C1 thru C9 of 18003. After 35 minutes of misalignment, l&C has replaced a blown lift coil fuse. The DRPI rod position was recorded at 204 steps on CBD. AsstGNED TASK: The USS has directed you to " Realign rod D4 to 204 steps on DRPI (recorded in step C7) beginning with step C12 of 18003". TASK CTANDARD: Misaligned rod restored to its associated group's rod height. 4

. _ _ _ _. ~ _ _ _ _ _ _ _ _. _., _... RQ JP-60303-002-01 JPM STEPS START TIME: STEP 1 CRITICAL (*) l SAT De UNSAT De i Select affected bank for control 4 L i hD + Rod Control HS-40041 in CBD STEP 2. CRITICAL (+) SEQ 1 SAT De UNEAT De Disconnect lift coils for bank's unaffected rods l su + Rod disconnect switches M12 D12 M4, and H8 in disconnect (up) l STEP 3 CRITICAL (*) SEQ 2 SAT De UNSAT De Realign the misaligned rod ha + Rod D4 manually withdrawn wO e Tavg maintained t 2*F of Tref during realignment (1) wO + D4 DRPl indication at 204 steps su + F.sd D4 stopped 50 . Time of realignment recorded CUES: (1) "The BOP will ensure Tavg and Tref remained matched during the recovery." 1 J' 5

i RQ-JP 60303-002-01 JPM STEPS STEP 4 CRITICAL (e) SEQ 3 SAT De UNSAT De j Determine rod operability s0 + Reconnect lift coils for rods M12, D12, M4, and H8 su- + Reset Rod Control Urgent Failure Alarm (ys - 4003 h su CBD inserted 10 steps sO.

• DRPI indications of inward rod motion verified a0

. CBD withdrawn 10 steps s0 e DRPIindications of outward rod motion verified STEP 5 CRITICAL (+) SAT De UNSAT De i Reset affected group step countets sO + CBD step counters reset to 204 STEP 6 l SAT O ct UNSAT De l Reset rod control cabinet components s0 . Operator directed to reset P/A converter to 204 (f) CUES: (1) "The P/A converter for Bank D is at 204". I STEP 9 SAT De UNSAT De [ Restore rod control to normal operation s0 . Rod Control HS-40041 in MAN CUES: If asked," Place rods in manual". 6

... ~. RQ-JP-60303-002-01 JPM STEPS I t STEP 10 - SAT De UNSAT De "~~ Rei uest plant computer rod position adjustment { l ? hD e Requests Engineering Duty Manager be notified that rod realignment has occurred and pl ant computer may need adjustment (f) i CUES: (1) "The USS will notify the Engineering Duty Manager". STEP 11 i l SAT De UNSAT De i Report to USS t wD e Rod D4 realigned to 204 steps I i STOP TIME: Field Notes i I k i I i i i 1 l l i i 4 7 ]

SYSTEM KNOWLEDGE QUESTIONS JPM: I4 SYSTEM: Rod Position Indication QUESTION: 1 K/A: 014 A2.04 Ability to predict the impacts of a misaligned rod and based on those predictions, use procedures to correct. control or mitigate the consequence. (3.9) OUESTION: Given the following plant conditions: Reactor is in Mode 3 The reactor trip breakers are closed to allow for hot rod drop testing per Procedure 88006. Shutdown bank A is being withdrawn for the test. When Shutdown bank A is withdrawn to 42 steps on the demand counter, rod M-2 DRPI indication becomes erratic. The crew believes one of the DRPI coils is malfunctioning and decides to pull the bank to 56 steps. With Shutdown bank A at 56 steps on DRPI and the demand counters, rod M-2 still indicates 42 steps on DRPI. What are the required actions? ANSWER: Since the difference between rod M-2 and the rest of the bank was greater than 12 steps, open the reactor trip breakers. Reference Allowed: YES

REFERENCE:

IR 50-424.425/97-10. section 01.4 TRM 13.1.9. ' Test Exceptions for Position Indication system-shutdown." Action Statement A.

p A JPM: I4 SYSTEM: Rod Position Indication OUESTION: 2 K/A: 014 A1.03 Ability to 3redict and monitor changes in parameters associated with operating tie RPIS controls including Rod Insertion Limits. (3.8) OUESTION: What gives you a Rod Insertion Limit Alarm? ANSWER: The Integrated Plant Computer (IPC) compares the DRPI bank average position to the calculated RIL position based on auctioneered hi 6T. If the DRPI bank average position is within 10 steps of the calculated RIL the LO ALARM will be generated. If the RIL position is violated the LO-LO ALARM will be generated. Reference Allowed: NO

REFERENCE:

LO-LP-27201-10. Digital Rod Position Indication System,

t 4 l - JPM: -14 ' OUESTION: 2 What gives you a Rod Insertion Limit Alarm? l 1 1 4 i l l l 1 \\

JPM: 14 QUESTION: 1 Given the following plant conditions: Reactor is in Mode 3 The reactor trip breakers are closed to allow for hot rod drop testing per Procedure 88006. Shutdown bank A is being withdrawn for the test. 1 When Shutdown bank A is withdrawn to 42 steps on the demand counter , rod M-2 DRPI indication becomes erratic. The crew believes one of the DRPI coils is malfunctioning and decides to pull the bank to 56 steps. With Shutdown bank A at 4 56 steps on DRPI and the demand counters, rod M-2 still indicates 42 steps on DRPI. What are the required actions? 1 I

This information describes the Initial Conditions, Assigned Task, and the Task Starudard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task. Initial Conditions: While withdrawing rods during a power increase, the operators observed Control Bank D rod D4 failed to move. The crew completed steps C1 thru C9 of 18003. After 35 minutes of misalignment, I&C has replaced a blown lift coil fuse. The DRPI rod position was recorded at 204 steps on CBD. Assigned Task: The USS has directed you to " Realign rod D4 to 204 steps on DRPI (recorded in step C7) beginning with step C12 of 18003". Task Standard: Misaligned rod restored to its associated group's rod height. 4 i 2

=. - 4 SOUTHERN h COMPANY Energy to Serve Your World" PLANT VOGTLE 1 CONTROL ROOM OPERATOR 1 JOB PERFORMANCE MEASURE RQ-JP-23101-003-01 MANUALLY ALIGN DAMPERS AND FANS FOR CRI l Revision 10 l April 1,1998 1 l Written By

9, S eadaece Date:

04/1/98 Approved By :D, Seu4curce Date: 04/1/98 l

rto. fp.23101-003-01 JPM INFORMATION OPERATOR'S NAME: EVALUATION DATE:._,_ / __ _ /._, JPM TITLE: Manually Align Dampers and Fans for CRI REVISION: 10 April 1,1998 COMPLETION TIME: 8 minutes l Application: RO/SRO Task Number: 23005 K/A Number: 013000A401 RO: 4.5 SRO: 4.8 10CFR55.45 Ref.: Evaluation Method [ ] Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room [ ] Unit 1 [ ] Unit 2 Performance Time: minutes OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: Examiner's Signature: 3

RQ JP-23101-003-01 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 13301-C. Verify this JPM is in accord with the latest procedural revision prior to usec Cues preceded by a "@..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQUIRED lTEMs: 1. 13301, CBCR Normal HVAC and Emergency Filtration System SIMULATOR SETUP: 1. Reset to IC14 2. Insert override: ANN : ALB50B02 3. Insert malfunction ESO4B (failure of Train B CRI) 4. Ack/ Reset alarms 5. Freeze simulator Setup time: 3 minutes DIRECTIONS TO OPERATOR You will be given information describing the initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task. INITIAL CONDmONs: A large brush fire is causing smoke to enter the control room through the outside air dampers resulting in a concern for Control Room habitability. AsslGNED TASK: The USS has directed you to " Manually actuate control room isolation". TASK STANDARD: Control Room ventilation equipment operating in the isolation mode. l 4 4

RQ-JP-23101003-01 ~ JPM STEPS START TIME: STEP 1 SAT O # UNSAT Oe Select procedure and section Note: The operatormay reMirnce We ARP besed on the annuncletor. TNs wd drect be implernentebon of 13301, h aO e 13301, section 4.4.1 selected STEP 2 CRITICAL (+) SAT De UNSAT De Manually actuate CRI wD + CRI actuation HS 12195A or HS-12196Ain ACTUATE CUES: . Only HS-12196A's red light is lit". l STEP 3 i SAT Oe UNSAT De i Check the lead Filter Unit fan in service i a0 . Train B Filter Unit Supply fan stopped (1-1531-N7-002) sO e Train A Filter Unit Supply fan running (1-1531-N7-001) i STEP 4 CRITICAL (+) l SAT De UNSAT De 'i Check the Kitchen, Toilet, and Conference rooms isolated 50 + Kit Toi! & Conf Rm damper HV-12162 closed s0 . Kit Toil & Conf Rm damper HV-12163 closed CUES: C... "HS-12162's red light is lit" e 5 j e.

. _. ~... _ _. _. _ _ _ _ _ _ _ _. _. _ _. 1 RQ-JP 2S101-003-01 JPM STEPS STEP 5 CRITICAL (e) SAT De UNSAT De l i Check nonnal air supply and return dampers closed, if not close them su . Verify normal air supply damper HV-1214.6 closed sO e Close normal air supply damper HV-12147 su e Verify normal air return damper HV-12149 closed s0 e Close normal air return damper HV-12148 1 STE'P6. SAT De UNSAT De i i Check Filter Unit dampers su . Filter Unit outlet damper HV-12128 open J sO . Return fan inlet damper HV-12130 open STEP 7 SAT De UNSAT Oe I Check outside air to normal HVAC fans isolated l sO . Nonnal HVAC intake damper HV-12153 closed STEP 8 SAT De UNSAT Ox Check normal HVAC fans shutdown Note: HS-12164 tlocatedin shift clerk's otnce)is not simulated. su . Normal supply fan 001 and 002 stopped sO . Normal retum fan 009 and 010 stopped { s0 . Kit Toil & Conf Rm exhaust fan stopped (HS-12164) (1) CUES: l (1) "HS-12164's green light is lit", j I l l 6 I

RQ-JP-23101-003-01 l JPM STEPS STEP 9 i CRITICAL (e) SAT De UNSAT Os Isolate outside air to the control room wO' + Outside air dampers HV-12114 and HV-12115 closed t CUES: C... "Both HS-12114's and HS-12115's red lights are lit" STEP 10 l SAT De UNSAT De i Report to USS s0 e CRI equipment manually aligned wO e TSC Air Filtration System should be verified (1) i CUES: (1) "The common BOP will verify proper operation of the TSC Air Filtration System". STOP TIME: 4 Field Notes i l l 7 ) l

JPM: 15 SYSTEM: Control Room Isolation QUESTION: 1 K/A: 2.1.28 Knowledge of the purpose and function of major system components and controls [ Control room ventilation] (3.2/3.3) QUESTION: Once the Control Room Isolation has taken place and the control room is on emergency ventilation. how many people, by design, can be supported in the control room and for how long? ANSWER-The control room emergency ventilation and air-conditioning system is capable i of maintaining an environment suitable for sustained occupancy for a five-person minimum crew, with higher occupancy levels for shorter periods of time. i \\ h Reference Allowed: YES

REFERENCE:

VEGP-FSAR-6, page 6.4.1-1 1

JPM: 15 SYSTEM: Control Room Isolation QUESTION: 2 K/A: 061 AA1.01 Ability to operate and monitor automatic actuations as they apply to the Area Radiation Monitoring system alarms. (3.6/3.6) OVESTION:

a. How do the control room filtration units respond to a CRI signal?

b. How is the TSC habitability maintained in an accident?

ANSWER: a. Unit related filtration unit starts. Only one filter unit required therefore. Lead - lag scheme developed. B Train filter unit is Lead and will start immediately A Train is Lag and will start in 30 seconds if B does not start. Note: If A Train running then B Train will not start b. Auto or manual CRI from either unit results in TSC HVAC swapping to emergency mode. Reference Allowed: NO

REFERENCE:

LO-LP-23101-16C. Control Room HVAC

JPM: 15 QUESTION: 2

a. How do the control room filtration units respond to a CRI signal?

b. How is the TSC habitability maintained in an accident?

l l I l l c e-t 4 4 J

l JPM: IS QUESTION: 1 Once the Control Room Isolation has taken place and the control room is on emergency ventilation. how many people, by design, can be supported in the control room and for how long? 1 i

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task. Initial Conditions: A large brush fire is causing smoke to enter the control room through the outside air dampers resulting in a concern for Control Room habitability. Assigned Task: The USS has directed you to " Manually actuate control room isolation" Task Standard: Control Room ventilation equipment operating in the isolation mode. l l l ) 2

e SOUTHERN h COMPANY Energy to Serve Your World" PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-16401-003-01 RESPOND To FAILURE OF RCP SEAL #1 Revision 17 April 2,1998 \\ Written By . 3. 8ulanu Date: 4/2/98 Approved By : 3. Suluou Date: 4/2/98

_ _. _ _ _ _ _ _. _ ~ _. RQ-JP-16401-003-01 JPM INFORMATION OPERATOR'S NAME: EVALUATION DATE: / / JPM TITLE: Respond to Failure of RCP Seal #1 REVISION: 17 4/2/98 COMPLETION TIME: 5 minutes Application: RO/SRO Task Number: 16008 K/A Number: 00300A201 RO: 3.5 SRO: 3.9 10CFR55.45 Ref.: 3,4,6,12 Evaluation Method [ ] Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room [ ] Unit 1 [ ] Unit 2 Performance Time: minutes OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: Examiner's Signature: 3

RQ JP-16401-003-01 INSTRUCTIONS TO EXAMINER This JPM is based on 13003-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "@.. " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQUIRED ITEMS: 1. 13003-1, Reactor Coolant Pump Operation SIMULATOR SETUP: 1. Reset to IC17 2. Ack/ Reset alarms 3. Freeze simulator 4. Insert malfunction RP06A(B,C, or D) with a Final Value of 100% and a ramp time of 8 seconds -jf-5. Fail #2 seal ( Malfunction RP07A/B/C/D @ 100%)if JPM not ) completed in 5 minutes. Setup time: 5 minutes DIRECTIONS TO OPERATOR You will be given information describing the initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task. INITIAL CONDITIONS: The plant is at 12% power. Preparations are underway to synch the generator to the I grid. AsslGNED TASK: You have been directed by the USS to " Assume the duties of the RO". TASK STANDARD: Plant conditions correctly diagnosed and corrective actions completed. 4 l l 4 l

i RQ-JP-16401-003-01 JPM STEPS i STEP 1 [ SAT De UNSAT De l Determine RCP seal abnormality wO e RCP Controlled Lkg Hi/Lo Flow annunciator in alarm l su e Sealleakoff flow indications increasing i STEP 2 SAT De UNSAT Os I I Select procedure and section s0 13003, section 4.2.1 selected STEP 3 CRITICAL (+) l SAT De UNSAT Oe Evaluate RCP status Note: RCP parameters may be monitored on IPC if available, but are not required for satisfactory pedormance. I wO + Determines #1 seat leakoff flow exceeds normallimits (> 5.5 gpm) -CUES: O Indicate the following; Seal injection flow is 9 gpm; Seal injection temperature is 105'F"; Seal leakoff flow is offscale high on the high range recorder. [ .I START TIME: I i f i l 5 )

.__._._____.~_._______m.__ RQ-JP-16401-003-01 JPM STEPS STEP 4 CRITICAL (+) SAT De UNSAT De Stop the RCP sO . Start oillift pump s0 + Stop affected RCP wO . Initiate 18005-C, Partial Loss of Flow (1) wO + Close HV-8141 A(B,C, or D) xO . Stop oillift pump i _ CUES: (1) "The USS will initiate 18005-C." STOP TIME: t I I f 6 i y

r RQ-JP-16401-003-01 JPM STEPS STEP 5 SAT 04f.. UNSAT 045 i Report to USS a0 . The affected RCP has been stopped Fleid Notes i i l I 1 1 3 j 1 7 l 1

4 JPM: 16 SYSTEM: Seal injection QUESTION: 1 K/A: 003 K6.02 Knowledge of the effect of a loss or malfunction of RCP seals and seal water supply will have on the RCPs. (2.7/3.1) OUESTION: Can the RCPs be operated with a total loss of Seal Injection? Followup questions which may be needed to solicit some of the below information: a. H6W is it accoqalished? b. What systems are needed to support this function? c. H6w long can it be operated in this condition?) l ANSWER: Yes. a. With a loss of seal injection, the pump radial bearings and seals are lubricated by reactor coolant flowing up through the pump. b. ACCW continues to provide. flow to the thermal barrier heat exchanger: which cools the reactor coolant before it enters the pump radial bearing and the shaft seal area. c. The loss of seal injection flow may result in a temperature increase in the pump bearing area, a temperature increase in the seal area, and a resultant increase in the #1 seal leak rate: however, pump operation can be continued (for up to 24 hours) provided these parameters remain within the allowable limits. Reference Allowed: YES

REFERENCE:

VEGP-FSAR-5, section 5.4.1.2.3 (Volume 12 page 5.4.1-4) LP-16401

i JPM: 16~ SYSTEM: Seal injection QUESTION: 2 i l K/A: 003 A 1.01 Ability to manually operate and monitor seal injection in the control room. i3.3/3.2) i i OUESTION: I How will the. #2 seal. respond to a total failure of the #1 seal? I ANSWER: (The #2 seal converts from a face rubbing seal to a film riding seal'.) - Relative small leakage rates would be maintained for period of time (LP 16401 says 30 minutes probably more) which is sufficient to secure the pump. Even if the #1 seal fails entirely during normal operation, the #2 seal would + - maintain these small leakage rates if the proper action is taken by the - operator.. i E i Reference Allowed: NO

REFERENCE:

LP-16401: VEGP-FSAR-5. section 5.4.1.3.1 (Volume 12. page 5.4.1-5) l

-r JPM: I6 i QUESTION: 2 How will the #2 seal respond to a total failure of the #1 seal? l b i 4 t i 5 I b 5 i )

JPM: 16 QUESTION: 1 i Can the RCPs be operated with a total loss of Seal Injection? 5 i I i -) I i

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task. Initial Conditions: The plant is at 12% power. Preparations are underway to synch the generator to the grid. Assigned Task: You have been directed by the USS to " Assume the duties of the RO". Task Standard: Plant conditions correctly diagnosed and corrective actions completed. 2

l 1 l i SOUTHERN h COM.PANY I } Energy to Serve Your World" \\ PLANT VOGTLE CONTROL ROOM OPERATOR i JOB PERFORMANCE MEASURE RQ-JP-60301-007-01C N TRIP PROTECTION SYSTEM BISTABLES PRESSURIZER PRESSURE CHANNEL Revision 1 March 9,1998 i Written By fco7pe far Date: 3/9/98 Approved By : 2 cose R aef Date: 3/9/98

RQ-JP-60301-007-01 C JPM INFORMATION OPERATOR'S NAME: EVALUATION DATE: _ / __ / _ JPM T!TLE: Trip Protection System Bistables - Pressurizer Pressure Channel REVISION: 1 March 9,1998 COMPLETION TIME: 6 minutes Application: RO/SRO Task Number-60029 K/A Number: 012000A404 RO: 3.3 SRO: 3.3 10CFR55.45 Ref.: Evaluation Method [ j Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room [ ] Unit 1 l ] Unit 2 Performance Time: minutes i OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: Examiner's Signature: 3

+ RQ-JP-60301-007-01C INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 18001-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQUIRED lTEMs: 1. 18001-C 2. Process System Protection Cabinets Key COMPONENT LOCATION: Main Control Room,7300 Rx Protection Cabinets CARD LOCATION

REFERENCE:

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!. '. '. 'r 2 1 7 7 1 7 1 1 CARD SLOTS 21 bru36 i, _r - CARD SLOTS 41 thru 56 I I [ I I CARD SL OTS 61 thru 76 DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task. REMEMBER: All steps required for this task are to be simulated. Plant equipment is not to be operated. INITIAL CONDITIONS: Unit 1 Pressurizer pressure channel 1_ PT-455 has failed. The control room operators have stabilized the plant in accordance with the AOP. AsslGNED TASK: The USS has directed you to " Trip the Pressurizer pressure channel 3,_- PT-455 bistables listed in Table C1 of 16.11-C and place the associated Master Test Switch in TEST". TASK STANDARD: The failed instrument channel placed in a tripped condition. 9 4

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RQ-JP-60301 007-01 C JPM STEPS START TIME: Permisssion should be obtained from the applicable Control Room staffin order to access the 7300 Protection Cabinet. '~ STEP 1 SAT De UNSAT Omr Locate protection cabinet a0 . Protection Cabinet i located s0 . Card Frarne 8 located STEP 2 CRITICAL (+) SAT De UNSAT De Place Bistables in a Tripped condition su + Card 46, B/S switches 1,3, & 4 placed in TEST su + Card 22. B/S switches 3 & 4 placed in TEST STEP 3 SAT De UNSAT Osr Place Master Test switch in TEST a0 . Card 74 TEST switch 5 placed in TEST sO e Card 72, TEST switch 1 placed in TEST STEP 4 SAT - De UNSAT De Report to USS s0 . Bistables are tripped and the Master test Switch is in TEST. STOP TIME: Field Notes 5

o JPM: 17 SYSTEM: PZR Pressure Control QUESTION: 1 K/A: 010 K 4.03 Knowledge of PZR pressure control design features and interlocks which provide for over pressure control. (3.8/4.1) QUESTION: List all of inputs and their setpoints required for the PORVs to open and close automatically. ANSWER: PORV 455 - Open setpoint 2315 psig and closes at 2315 - Gets input from master controller which gets its input from whichever transmitter is selected as the primary. Controller is a Proportional / Integral controller. - Valve is automatically closed and block valves interlocked to close on i pressurizer low pressure (2185 psig) PORV 456 - (A bistable) opens the valve at 2335' and closes the valve at 2315 - (Not sensitive to magnitude of pressure transient or the rate of the change of the transient like the integral controller on 455.) - Same low pressure close interlock as 455 Ref. Allowed: NO

REFERENCE:

LP 16303, Pressurizer Pressure Control and Protection

~ JPM: 17 SYSTEM: PZR Pressure Control OVESTION: 2 K/A: 010 K 1.03 Knowledge of the physical connections and cause-effect relationships between the PZR pressure control system and the RCS. (3.6/3.7) OUESTION: With reactor power at 15% during start up, what would happen to pressurizer pressure if #1 RCP tripped and the crew failed to shut the spray isolation valve? ANSWER: (This actually happened on Unit 2 but with RCP #4) The lower delta-p causes the spray to be ineffective. pressure is maintained at a constant value high than program but lower than 2335 (~ 2260 psig ) PORV 455A will eventually cycle open due to the integrated function of controller. PORV 456 is not controlled off SPS Relay master controller will only open at 2335 psig. Reference Allowed: YES

REFERENCE:

LP 16303, Pressurizer Pressure Control and Protection, page 7 4

_. - = - _.. i JPM: I7 I QUESTION: 2 With reactor power at 15% during start up, what would ha> pen to pressurizer i pressure if #1 RCP tripped and the crew failed to shut tie spray isolation valve? i i 1 i f i i

J JPM: 17 QUESTION: 1 List all of inputs and their setpoints required for the PCRVs to open and 1 close automatically. I i l l ) l

~ l i i This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task. REMEMBER: All steps required for this task are to be simulated. Plant equipment is not to be operated. Initial Conditions: Uniti_ Pressurizer pressure channe!1 PT-455 has failed. The control room operators have stabilized the plant in accordance with the AOP. Assigned Task: The USS has directed you to " Trip the Pressurizer pressure channel'I_ PT-455 bistables listed in Table C1 of 18001-C and place the associated Master Test Switch in TEST". Task Standard: The failed instrument channel placed in a tripped condition. 2

__. ~. - -..... _ Appray,t Procedtre 23. Vc,Ja El:ctric GIntrating Pl::nt 18001-C J. T. Gasser NUCLEAR OPERATIONS Rsvision rio. Date 17 1/20/97 Unit COMMMON 1 of 29 Abnormal Operating Procedures PRIMARY SYSTEMS INSTRUMENTATION MALFUNCTION EFFECTIVE UPON ITS IMPLEMENTATION PURPOSE PRB REVIEW REOUIRED This procedure provides instructions for mitigation of the following primary plant instrument failures: A. Failure of RCS Loop Flow Instrumentation. 1 B. Failure of RCS Loop Narrow Range Temperature Instrumentation. C. Failure of PRZR Pressure Instrumentation. D. Failure of PRZR Level, Instrumentation. E. Failure of Steam Generator Level Instrumentation. F. Failure of Steam Generator Pressure Instrumentation. G. Failure of Steam Generator Flow Instrumentation. H. Failure of Turbine Impulse Pressure Instrumentation. SYMPTOMS Specific symptoms for each instrumentation failure are located under the appropriate section.

~. ~... - _ ~. ..... - ~ ... ~....... .~. -. - PROCEDURE No. REVISION NO. PAGE NO. VEGP 18001-C 17 2 of 29 i i A. FAILURE OF RCS LOOP FLOW INSTRUMENTATION SYMPTOMS RCP LOOP 1 (2, 3, 4) LOW FLOW ALERT Annunciator. RC LP 1 (2, 3,

4) LO FLOW bistable status light energized.

Any RCS loop flow meter reading less than 90%. Any RCS loop flow meter reading off scale high. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED A1. Verify that RCS flow is - A1. Initiate 18005-C, PARTIAL GREATER THAN 90% IN ALL LOSS OF FLOW. LOOPS. A2. Identify the affected flow instrument-A3. Initiate maintenance for. repairs. A4. If desired, bypass the affected instrument channel per 13509-C, BYPASS TEST INSTRUMENTATION (BTI) PANEL OPERATION. A5. Within 6 hours trip the AS. Place the reactor in hot affected channel bistable standby within 6 hours. per TABLE A1. A6. Place the MASTER TEST switch to TEST per TABLE A1. A7. Return tripped bistables to NORMAL position and the MASTER TEST switch to NORMAL position when repairs and surveillance are completed. FND OF SUB-PROCEDURE TEXT

~. ..~... PROCEDURE No. REVIslON NO. PAGE No. VEGP 18001-C 17 3 of 29 B. FAILURE OF RCS LOOP NARROW RANGE TEMPERATURE INSTRUMENTATION SYMPTOMS RC LOOP DELTA T/AUCT DELTA T HI-LO DEV Annunciator. RC LOOP TAVG/AUCT TAVG HI-LO DEV Annunciator. TAVG/ TREF DEVIATION Annunciator. AUCT TAVG HIGH Annunciator. TAVG LO-LO PLERT Annunciator. l TERR (TAVE-TREF) LO Annunciator. 4 ACTION /EXPEC"'ED RESPONSE RESPONSE NOT OBTAINED IMMEDIATE OPERATOR ACTIONS + 4 j B1. Place the rods in MANUAL. SUBSEOUENT OPERATOR ACTIONS l 1 B2. Restore TAVG to program band. B3, Defeat the affected channel { input to Delta T and TAVG J auctioneers as follows: 1 a. Select the affected loop on TAVG defeat selector switch TS-412T. b. Select the affected loop on Delta T defeat selector switch TS-411F. l B4. Place rods in AUTO if desired. B5. Initiate mainten%ce for repairs. J

... _ _.. _... -. - -.. - -.. _ - _.. - -...... -.... ~.... -. _ - 4 PaocEDURE N0. nEVISION NO. PAGE NO. VEGP 18001-C. 17 4 of 29 i B. FATLURE OF RCS LOOP NARROW RANGE TEMPERATURE i INSTRUMENTATION ACTION / EXPECTED FRAPONSE RESPONSE NOT OBTAINED ' ~ ~ ~ ' B67 If desired, bypass the affected instrument channel per 13509-C, BYPASS TEST I INSTRUMENTATION (BTI) PANEL OPERATION. B7. Within 6 hours, trip the .B7. Place the reactor in hot affected channel bistables standby within 6 hours. per TABLE Bl. i B8. Place the MASTER TEST switch to TEST per TABLE Bl. B9. Return tripped bistables to NORMAL position and the } MASTER TEST switch to NORMAL position when repairs and surveillance are completed. i END OF SUB'-PROCEDURE TEXT a

PROCEDURE No. REVISION NO. PAGE No. VEGP 18001-C 17 5 of 29 C. FAILURE OF PRZR PRESSURE INSTRUMENTATION SYMPTOMS PRZR HI PRESS Annunciator. PRZR HI PRESS CHANNEL ALERT Annunciator. PV-455A (456) OPEN SIGNAL Annunciator. PRZR CONTROL LO PRESS AND HEATERS ON Annunciator. PRZR LO PRESS ALERT Annunciator. PRZR LO PRESS SI ALERT Annunciator. PRZR PRESS LO PORV BLOCK Annunciator. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED IMMEDIATE OPERATOR ACTIONS C1. Verify RCS pressure - C1. STABLE OR RISING. a. Close spray valves. b. Close affected "RZR PORV. c. Operate PRZR heaters as necessary. SUBSEOUENT OPERATOR ACTIONS C2. Select an unaffected channel on PRZR PRESSURE CONTROL SELECTOR switch PS-455F. C3. Return PRZR pressure control to AUTO: PRZR PORVs Spray Valves PRZR heaters C4. Select the same channel on PRZR PRESSURE RECORDER 1 - - SELECTOR switch PS-455G. ]

PROCEDURE NO. REVISION NO. PAGE No. VEGP 18001-C 17 6 of 29 C. FAILURE OF PRZR PRESSURE INSTRUMENTATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ~~ C5. Initiate maintenance for repairs. C6. If desired, bypass the affected instrument channel per 13509-C, EYPASS TEST INSTRUMENTATION (BTI) PANEL OPERATION. C7. Within 6 hours, trip'the C7. Place the reactor in hot affected channel bistables standby within 6 hours. per TABLE C1. C8. Place the MASTER TEST switch to TEST per TABLE C1. C9. Return tripped bistables to NORMAL position and the MASTER TEST switch to NORMAL position when repairs and surveillance are completed. END OF SUB-PROCEDURE TEXT e e av D

PROCEDURE NO. REVISION No. PAGE No. VEGP 18001-C 17 7 o2 29 D. FAILURE OF PRZR LEVEL INSTRUMENTATION SYMPTOMS PRZR CONTROL HI LEVEL DEV AND HEATERS ON Annunciator. PRZR HI LEVEL ALARM. PRZR HI LEVEL CHANNEL ALERT Annunciator. PRZR LO LEVEL DEVIATION Annunciator. PRZR LO LEVEL HTR CNTL OFF LTDN SECURED Annunciator. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED D1. Verify PRZR level - TRENDING D1. Control charging to restore TO PROGRAM LEVEL. PRZR level. D2. Maintain RCP seal injection flow 8 to 13 gpm. D3. Select an unaffected channel on PRZR LEVEL CONTROL SELECTOR switch LS-459D. D4. Select the same channel on PRZR LEVEL RECORDER SELECTOR switch LS-459E. D5. If required, restore letdown D5. Initiate 13008, CHEMICAL AND flow by initiating 13006, VOLUME CONTROL SYSTEM EXCESS CHEMICAL AND VOLUME CONTROL LETDOWN. SYSTEM. D6. Return appropriate charging pump to AUTO. D7. Verify PRZR level is D7. Maintain manual PRZR level maintained by auto control, control. D8. Initiate maintenance for repairs.

PROCEDURE No. REVis!ON NO. PAGE No. VEGP 18001-C 17-8 of 29 D. FAILURE OF PRZR LEVEL INSTRUMENTATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ~ ~ ~ D9 '. If desired, bypass the affected instrument channel per 13509-C, BYPASS TEST OPERATION. INSTRUMENTATION (BTI) PANEL i D10. Within 6 hours, trip the D10. Place the reactor in hot affected channel bistables standby within 6 hours. per TABLE D1. I D11. Place the MASTER TEST switch to TEST per TABLE D1. l 1 D12.-Return tripped bistables to NORMAL position and the MASTER TEST switch to NORMAL position when repairs and surveillance are completed. END OF SUB; PROCEDURE TEXT i l

.... -. _...... _ - -..... ~,, PROCEDURE No. REVISION No. PAGE No. VEGP 18001-C 17 9 of 29 E. FAILURE OF STEAM GENERATOR LEVEL INSTRUMENTATION SYMPTOMS STM GEN 1 (2, 3, 4) HI/LO LVL DEVIATION Annunciator. STM GEN 1 (2, 3, 4) HI-HI LEVEL ALERT Annunciator. STM GEN 1 (2, 3, 4) LO LEVEL Annunciator. STM GEN 1 (2, 3, 4) LO-LO LVL. ALERT Annunciator. AC. ION / EXPECTED RESPONSE RESPONSE NOT OBTAINED IMMEDIATE OPERATOR ACTIONS El. Verify all SGs: El. Control SG NR level between 60% and 70%. Stm/ feed flow - MATCHED. NR level - AT 65%. SUBSEOUENT OPERATOR ACTIONS S E2. Select an unaffected control channel. E3. Return feed flow to AUTO. E4. Verify that SG level control E4. Control SG NR level between maintains NR level - AT 65%. 60% and 70%. E5. Initiate maintenance for repairs. E6. If desired, bypass the affected instrument channel per 13509-C, BYPASS TEST INSTRUMENTATION (BTI) PANEL OPERATION. E7. Within 6 hours, trip the E7. Place the reactor in hot affected channel bistables standby within 6 hourc per TABLE E1.

.. =.. .~. ... _ _ _. - _. = _.. _. _ _ _. _. _ PROCEDURE NO. REVISION NO. PAGE No. I VEGP 18001-C 17 10 of 29 E. FAILURE OF STEAM GENERATOR LEVEL INST,RUMENTATION t ACTION / EXPECTED RESPON.EE RESPONSE NOT OBTAINED '~ E8.' Place the MASTER TEST switch to TEST per TABLE E1. E9. Return tripped bistables to NORMAL position and the l MASTER TEST switch to NORMAL l position when repairs and surveillance are completed. 4 1 END OF SUB-PROCEDURE TEXT i 4 l -o e e .m

.~_-- .. ~. -. PROCEDURE Wo. REVISION WO. PAGE NO. VEGP 18001-C 17 11 of 29 F. FAILURE OF STEAM GENERATOR PRESSURE INSTRUMENTATION SYMPTOMS i

• . STM GEN 1 (2, 3,

4) HI STM PRESS RATE ALERT Annunciator.

HI STM PRESS RATE (ANY LOOP) Annunciator. STM GEN 1 (2, 3,

4) LO STEAMLINE PRESS ALERT Annunciator.

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l IMMEDIATE OPERATOR ACTIONS i F1. Verify steam and feed flows F1. Take manual control of - MATCHED ON ALL SGs. affected SG feed flow and MFP(s) speed to restore NR level between 60% and 70%. 1 SUBSEOUENT OPERATOR ACTIONS F2.' IE steam flow F2. Go to Step F4. i instrumentation is affected, THEN: i a. Select an unaffected channel using TABLE F2. { b. Return feed flow and MFP(s) speed to AUTO. F3. Verify that SG level control F3. Control affected SG feed maintains NR level - AT 65%. flow and MFP(s) speed to restore NR level between 60% and 70%. F4. Initiate maintenance for repairs. F5. If desired, bypass the affected instrument channel per 13509-C, BYPASS TEST INSTRUMENTATION (BTI) PANEL OPERATION.

.._.-...m_._ ....4 .-_m_... PROCEDURE No. REYlSION NO. PAGE No. VEGP 18001-C 17 12 of 29 F. FAILURE OF STEAM GENERATOR PRESSURE INSTRUMENTATION ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -~~ F6'. Within 6 hours, trip the F6. Place the reactor in hot affected channel bistables standby within 6 hours, per TABLE F1. F7. Place the MASTER TEST switch 4 to TEST per TABLE F1. F8. Return tripped bistables to NORMAL position and the MASTER TEST switch to NORMAL position when repairs and surveillance are complete. END OF SUB-PROCEDURE TEXT 1 1 1 i i

PROCEDURE ho. REVISION NO. ? AGE NO. VEGP 18001-C 17 13 of 29 G. FAILURE OF STEAM GENERATOR FLOW INSTRUMENTATION SYMPTOMS STM GEN 1 (2, 3,

4) FLOW MISMATCH Annunciator.

Any unexplained steam / feed flow mismatch indication. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED IMMEDIATE OPERATOR ACTIONS Gl. Verify steam and feed flows G1. Take manual control of - MATCHED ON ALL SGs. affected SG feed flow and MFP(s) speed to restore NR level between 60% and 70%. SUBSEOUENT OPERATOR ACTIONS G2. Select an unaffected control channel. G3.' Return feed flow and MFP(s) ~ speed to AUTO. G4. Verify that SG level control G4. Control SG NR level between maintains NR level - AT 65%. 60% and 70%. G5. Initiate maintenance as required. 1 END OF SUB-PROCEDURE TEXT l

PROCEDURE NO. REVISION NO. PACE NO. VEGP 18001-C 17 14 of 29 H. FAILURE OF TURBINE IMPULSE PRESSURE INSTRUMENTATION SYMPTQMS TAVG/ TREF DEVIATION. RCS LOOP TAVE/AUCT TAVG HI-LO DEV Annunciator. TURB PWR P13 CHI (II) PB-505(6)A status light - OFF. LO TURB IMP PRESS ROD STOP C5 status light - ON. i LOSS OF TURB LOAD INTLK C7 status light ON. Turbine impulse pressure indication mismatch. AMSAC TROUBLE annunciator. AMSAC LO FW FL AFW ACTUATION TURBINE TRIP. i ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED IMMEDIATE OPERATOR ACTIONS Hl.' Verify - NO ROD MOTION. ~ Hl. Place rods in MANUAL. SUBSEOUENT OPERATOR ACTIONS H2. Restore TAVG to program band. H3. Perform the following: a. Verify steam dumps controller at setpoint to maintain no-load Tavg of 557'F during normal operation (approximately 7.28). b. Place the steam dump control mode select switch in steam pressure mode of operation.

~ -... - - -.. - ~ ~ PROCEDURE NO. REVISION NO. PAGE No. VEGP 18001-C 17 15 of 39 l l H. FAILURE OF TURBINE IMPULSE PRESSURE INSTRUMENTATION ACTION / EXPECTED RESPONSE-RESPONSE NOT OBTAINED H4. Verify the P-13 status light H4. Place the reactor in hot on BPLB is as follows: standby within 6 hours. If greater than 10% t turbine power - OFF. -OR-If less than 10% turbine power - ON. H5. Initiate maintenance as required. H6. WHEN repairs and-surveillances are complete AUR IE greater than 40t turbine power, THEN verify the ATWAS Mitigation System Activation Circuitry (AMSAC). auto ' unblocks by observing permissive light AMSAC BYPASSED LO TURBINE LOAD C20 (BPLB 8-4) extinguished. END OF SUB-PROCEDURE TEXT = e up i

PROCEDURE NO. REVIS10N NO. PAGE NO. VEGP 18001-C 17 16 of 29 Sheet 1 of 2 TABLE Al ~ ~ - Bistable switches to be tripped for RCS flow instrument failure and master test switches are in protection set frame 8. CAUTION:

• Only one test switch for a loop should be tripped.
• The bistable input is placed in the tripped state-by positioning the selector switch on the specified test card to TEST.
• The bistable input identified by the switch number should agree with the location specified by CAB, CARD, and B/S before tripping a bistable input.

If a discrepancy exists, CAB-CARD-B/S should be used, not switch number. d

• Technical Specifications LCO 3.3.1 allows testing in bypass for one inoperable channel at a time for up to 6 hours.

The inoperable channel must be placed in the tripped condition within 6 hours of when it was initially placed in the bypassed condition or declared inoperable.

• Bypassing another channel for Surveillance Testing with a channel inoperable is permitted provided the inoperable channel is in the tripped condition and the channel being tested is not bypassed for more than 4 hours.

MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH FT-414 Failure (Channel 1) Loop 1 Low Flow Reactor Trip 1 62 1 FS-414A 75 5 FT-415 Failure (Channel 2) Loop 1 Low Flow Reactor Trip 2 62 1 FS-415A 75 5 FT-416 Failure (Channel 3) Loop 1 Low Flow Reactor Trip 3 45 1 FS-416A 74 5 9

PROCEDURE No. REVISION NO. PAGE NO. VEGP 18001-C 17 17 of 29 Sheet 2 of 2 TABLE A1 (Cont'd) MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH FT-424 Failure (Channel 1) Loop 2 Low Flow Reactor Trip 1 63 1 FS-424A 75 6 i FT-425 Failure (Channel 2) Loop 2 Low Flow Reactor Trip 2 63 1 FS-425A 75 6 i FT-426 Failure (Channel 3) Loop 2 Low Flow Reactor Trip 3 46 1 FS-426A 74 6 i FT-434 Failure (Channel 1) Loop 3 Low Flow Reactor Trip 1 64 1 FS-434A 75 7 FT-435 Failure (Channel 2) i Loop 3 Low Flow Reactor Trip 2 64 1 FS-435A 75 7 FT-436 Failure (Channel 3) Loop 3 Low Flow Reactor Trip 3 47 1 FS-436A 74 7 ) 4 FT-444 Failure (Channel 1) Loop 4 Low Flow Reactor Trip 1 65 1 FS-444A 76 5 FT-445 Failure (Channel 2) Loop 4 Low Flow Reactor Trip 2 65 1 FS-445A 76 5 FT-446 Failure (Channel 3) Loop 4 Low Flow Reactor Trip 3 48 1 FS-446A 74 2

. = - - - - PROCEDURE No. REVISION NO. iPAGE NO. VEGP 18001-C 17 18 of 29 Sheet 1 of 2 TABLE B1 '~~ Bistable switches to be tripped for RTD failure and NASTER TEST switches are in protection set frame 8 or 4 as indicated below preceding card designator. i I CAUTION:

• ALL test switches for the loop with RTD failure should be tripped.

Only one loop should be tripped. The bistable input is'placed in the tripped state by positioning the Selector Switch on the specified test card to TEST. The bistable input identified by the switch number ) should agree with the location specified by CAB, i CARD, and B/S before tripping a bistable input. If a discrepancy exists, CAB-CARD-B/S should be used, not switch number. d Technical Specifications LCO 3.3.1 and LCO 3.3.2 allow testing in bypass for one inoperable channel j at a time for up to 6 hours. The inoperable channel must be placed iu the tripped condition within 6 hours of when it was initially placed in the bypassed condition or declared inoperable. i Bypassing another channel for Surveillance Testing e with a channel inoperable is permitted provided the inoperable channel is in the tripped condition and the channel being tested is not bypassed for more than 4 hours, l MASTER i TEST SWITCH FRAME FRAME SSPS INPUT CAB / CARD B/S SWITCH / CARD SWITCH Loop 1 RTD Failure (Channel 1) Loop 1 Overtemp Delta T Trip 1 8/22 3 TS-411C 8/72 1 Loop 1 Overtemp Delta T Runback 1 8/22 4 TS-411D 8/72 2 Loop 1 Overpower Delta T Trip 1 8/22 1 TS-411G 8/72 3 Loop 1 Overpower Delta T Runback 1 8/22 2 TS-411H 8/72 4 Loop 1 Lo-Lo TAVG Stm Dump Block 1 8/21 1 TS-412D 4/55 1 Loop 1 Low TAVG FW Isolation 1 8/21 2 TS-412G 4/55 2

.~ . ~. -..._.. ~. PROCEDURE No. REVISION NO. PAGE NO. VEGP 18001-C 17 19 of 29 i i Sheet 2 of 2 TABLE B1 (Cont'd) MASTER TEST SWITCH FRAME FPJLME SSPS INPUT CAB / CARD B/S SWITCH / CARD SWITCH Loop 2 RTD Failure (Channel 2) Loop 2 Overtemp Delta T Trip 2 8/22 3 TS-421C 8/72 1 Loop 2 Overtemp Delta T Runback 2 8/22 4 TS-421D 8/72 2 Loop 2 4. /erpower Delta T Trip 2 8/22 1 TS-421G 8/72 3 i Loop 2 Overpower Delta T Runback 2 8/22 2 TS-421H 8/72 4 Loop 2 Lo-Lo TAVG Stm Dump Block 2 8/21 1 TS-422D 4/55 1 i Loop 2 Low TAVG FW Isolation 2 8/21 2 TS-422G 4/55 2 ) Loop 3 RTD Failure (Channel 3) Loop 3 Overtemp Delta T Trip 3 8/22 3 TS-431C 8/72 1 Loop 3 Overtemp Delta T Runback 3 8/22 4 TS-431D 8/72 2 Loop 3 Overpower Delta T Trip 3 8/22 1 TS-431G 8/72 3 Loop 3 Overpower Delta T Runback 3 8/22 2 TS-431H 8/72 4 Loop 3 Lo-Lo TAVG Stm Dump Block 3 8/21 1 TS-432D 8/75 1 Loop 3 Low TAVG FW Isolation 3 8/21 2 TS-432G 8/75 2 Loop 4 RTD Failure (Channel 4) Loop 4 Overtemp Delta T Trip 4 8/22 3 TS-441C 8/72 1 Loop 4 Overtemp Delta T Runback 4 8/22 4 TS-441D 8/72 2 Loop 4 Overpower Delta T Trip 4 8/22 1 TS-441G 8/72 3 Loop 4 Overpower Delta T Runback 4 8/22 2 TS-441H 8/72 4 Loop 4 Lo-Lo TAVG Stm Dump Block 4 8/21 1 TS-442D 8/75 1 Loop 4 Low TAVG FW Isolation 4 8/21 2 TS-442G 8/75 2

PROCEDURE NO. REVISTON NO. 'PAGE NO. VEGP 18001-C 17 20 of 29 Sheet 1 of 2 TABLE C1 ~~ Bistable switches to be tripped for PRZR pressure sensor failure and master test switches are in protection set frame 8. CAUTION:

• ALL test switches for the failed pressure transmitter should be tripped.

Only one channel should be tripped.

• The bistable input is placed in the tripped state by positioning the Selector Switch on the specified test card t TEST.
• The bistable input identified by the switch number should agree with the location specified by CAB, CARD, and B/S before tripping a bistable input.

If a discrepancy exists, CAB-CARD-B/S should be used, not switch number. q

• Technical Specifications LCO 3.3.1 and LCO 3.3.2 allow testing in bypass for one inoperable channel at a time for up to 6 hours. The inoperable channel i

must be placed in the tripped condition within 6 i hours of wh?n it was initially placed in the l bypassed condition ~or declared inoperable.

• Bypassing anccher channel for Surveillance Testing with a channel inoperable is permitted provided the j

inoperable channel is in the tripped condition and the channel being tested is not bypassed for more j than 4 hours. j i MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH PT-455 Failure (Channel .".) High Pressure Reactor Trip 1 46 1 PS-455A 74 5 Overtemp Delta T Runback and Rod Block 1 22 4 TS-411D 72 1 Overtemp Delta T Trip 1 22 3 TS-411C 72 1 Low Pressure Reactor Trip 1 46 4 PS-455C 74 5 Low Pressure SI 1 46 3 PS-455D 74 5

e ' ^ PROCEDURE No. REVISION NO. IPAGE NO. VEGP 18001-C 17 21 of 29 Sheet 2 of 2 TABLE C1 (Cont'd) t MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH PT-456 Failure (Channel 2) High Pressure Reactor Trip 2 46 1 PS-456A 74 5 ( Overtemp Delta T Runback and Rod Block 2 22 4 TS-421D 72 1 Overtemp Delta T Trip 2 22 3 TS-421C 72 1 Low Pressttre Reactor Trip 2 46 4 PS-456C 74 5 Low Pressure SI 2 46 3 PS-456D 74 5 l PT-457 Failure (Channel 3) High Pressure Peactor Trip 3 42 1 PS-457A 73 6 Overtemp Delta T Runback and Rod Block 3 22 4 TS-431D 72 1 Overtemp Delta T Trip 3 22 3 TS-431C 72 1 Low Pressure Reactor Trip 3 42 4 PS-457C 73 6 i Low P,ressure SI 3 42 3 PS-457D 73 6 PT-458 Failure (Channel 4) High Pressure Reactor Trip 4 43 1 PS-458A 74 5 Overtemp Delta T Runback and Rod Block 4 22 4 TS-441D 72 1 Overtemp Delta T Trip 4 22 3 TS-441C 72 1 Low Pressure Reactor Trip 4 43 3 PS-458C 74 5 Low Pressure SI 4 43 2 PS-458D 74 5

PROCEDURE No. REVISION NO. 'PAGE NO. VEGP 18001-C 17 22 of 29 Sheet 1 of 1 TABLE D1 '~~ Bistable switches to be tripped for PRZR level channel failure and master test switches are in protection set frame 8. CAUTION:

• Only one channel should be tripped.
• The bistable input is placed in the. tripped state by positioning the selector switch on the specified.

test card to TEST.

• The bistable input identified by the switch.1 umber should agree with the location specified by CAB, CARD, and B/S before tripping a bistable input.

If a discrepancy exists, CAB-CAR-B/S should be used, not switch number.

• Technical Specifications LCO 3.3.1 allows testing in bypass for one inoperable channel at a time for up to 6 hours.

The inoperable channel must be placed in the tripped condition within 6 hours of when it was initially placed in the bypassed condition or declared inoperable.

• Bypassing another channel for Surveillance Testing with a channel inoperable is permitted provided the inoperable channel is in the tripped condition and the channel being tested in not bypassed for more than 4 hours.

MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH LT-459 Failure (Channel 1) High Level Reactor Trip 1 47 1 LS-459A 73 7 LT-460 Failure (Channel 2) High Level Reactor Trip 2 47 1 LS-460A 73 7 LT-461 Failure (Channel 3) High Level Reactor Trip 3 44 1 LS-461A 73 7

PROCEDURE NO. REVISION NO. 'PAGE NO. VEGP 18001-C 17 23 of 29 Sheet 1 of 3 TABLE El ~~~ Bistable switches to be tripped for SG pressure sensor failure and master test switches are in protection set frame 8. CAUTION:

• ALL test switches for.the failed level transmitter should be tripped.

Only one channel for each steam generator should be tripped.

• The bistable input is placed in the tripped state by positioning the Selector Switch on the specified test card to TEST.
• The bistable input identified by the switch number should agree with the location specified by CAB, CARD, and B/S before tripping a bistable input.

If a discrepancy exists, CAB-CAR-B/S should be used, not switch number. q = Technical Specifications LCO 3.3.1 and LCO 3.3.2 1 allow testing in bypass for one inoperable channel at a time for up to 6 hours. The inoperable channel must be placed in the tripped condition within 6 hours of when it was initially placed in the bypassed condition or declared inoperable.

• Bypassing another channel for Surveillance Testing with a channel inoperab.e is permitted provided the inoperable channel is in the tripped condition and the channel being tested is not bypassed for more than 4 hours.

MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH LT-551 Failure (Channel 1) SG: Hi-Hi Lvl Turb Trip & FWI 1 52 2 LS-551B SG1 LO-Lo Lvl Reactor Trip & AFW 1 52 1 LS-551a 75 3 LT-519 Failure (Channel 2) SG1 Hi-Hi Lvl Turb Trip & FWI 2 31 1 LS-519A SG1 Lo-Lo Lvl Reactor Trip & AFW 2 31 2 LS-519B 73 1 1 L_

PROCEDURE No. REV]SION NO. PAGE t'O. VEGP 18001-C 17 24 of 29 Sheet 2 of 3 TABLE El (Cont'd) MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH LT-518 Failure (Channel 3) SG1 Hi-Hi Lvl Turb Trip & FWI 31 1 LS-518A SG1 Lo-Lo Lvl Reactor Trip & AFW 31 2 LS-518B 73 1 LT-517 Failure (Channel 4) SG1 Hi-Hi Lvl Turb Trip & FWI 4 31 1 LS-517A SG1 Lo-Lo Lvl Reactor Trip & AFW 4 31 2 LS-517B 73 1 LT-529 Failure (Channel 1) SG2 Hi-Hi Lvl Turb Trip & FWI 1 31 1 LS-529A SG2 Lo-Lo Lvl Reactor Trip & AFW 1 31 2 LS-529B 73 1 LT-552 Failure (Channel 2) SG2 Hi-Hi Lvl Turb Trip & FWI. 2 44 2 LS-552B SG2 Lo-Lo Lvl Reactor Trip & AFW 2 44 1 LS-552A 74 3 LT-528 Failure (Channel 3) SG2 Hi-Hi Lvl Turb Trip & FWI 3 32 1 LS-528A SG2 Lo-Lo Lvl Reactor Trip & AFW 3 32 2 LS-528B 73 2 LT-527 Failure (Channel 4) SG2 Hi-Hi Lvl Turb Trip & FWI 4 32 1 LS-527A SG2 Lo-Lo Lvl Reactor Trip & AFW 4 32 2 LS-527B 73 2 LT-539 Failure (Channel 1) SG3 Hi-Hi Lvl Turb Trip & FWI 1 32 1 LS-539A SG3 Lo-Lo Lvl Reactor Trip & AFW 1 32 2 LS-539B 73 2 LT-553 Failure (Channel 2) SG3 Hi-Hi Lvl Turb Trip & FWI 2 45 2 LS-553B SG3 Lo-Lo Lvl Reactor Trip & AFW 2 45 1 LS-553A 74 4

PROCEDURE No. REVISION NO. PAGE No. VEGP 18001-C 17 25 of 29 e Sheet 3 of 3 TABLE El (Cont'd) 1 MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH h LT-538 Failure (Channel 3) i SG3 Hi-Hi Lvl Turb Trip & FWI 3 33 1 LS-538A SG3 Lo-Lo Lvl Reactor Trip & AFW 3 33 2 LS-538B 73 4 LT-537 Failure (Channel 4) 1 SG3 Hi-Hi Lvl Turb Trip & FWI 4 33 1 LS-537A SG3 Lo-Lo Lvl Reactor Trip & AFW 4 33 2 LS-537B 73 3 LT-554 Failure (Channel 1) SG4 Hi-Hi Lvl Turb Trip & FWI 1 53 2 LS-554B i SG4 Lo-Lo Lvl Reactor Trip & AFW 1 53 1 LS-554A 75 4 LT-549 Failure (Channel 2) SG4 Hi-Hi Lvl Turb Trip & FWI, 2 32 1 LS-549A SG4 Lo-Lo Lvl Reactor Trip & AFW 2 32 2 LS-549B 73 2 LT-548 Failure (Channel 3) SG4 Hi-Hi Lvl Turb Trip & FWI 3 34 1 LS-548A SG4 Lo-Lo Lvl Reactor Trip & AFW 3 34 2 LS-548B 73 5 LT-547 Failure (Channel 4) SG4 Hi-Hi Lvl Turb Trip & FWI' 4 34 1 LS-547A SG4 Lo-Lo Lvl Reactor Trip & AFW 4 34 2 LS-547B 73 4 h e e

PROCEDURE No. REVISION NO. PAGE No. VEGP 18001-C 17 26 of 29 Sheet 1 of 3 TABLE F1 Bistable switches to be tripped for SG pressure sensor failure and master test switches are in protection set frame 8. CAUTION:

• ALL test switches for the failed pressure transmitter should be tripped.

Only one channel for each steam generator should be tripped.

• The bistable input is placed in the tripped state by positioning the Selector Switch on the specified test card to TEST.
• The bistable input identified by the switch number should agree with the location specified by CAB, CARD, and B/S before tripping a bistable input.

If a discrepancy exists, CAB-CAR-B/S should be used, not switch number.

• Technical Specifications LCO 3.3.2 allows testing in bypass for one inoperable channel at a time for up to 6 hours.

The inoperable channel must be placed in the tripped condition within 6 hours of when it was initially placed in the bypassed condition or declared inoperable.

• Bypassing another channel for Surveillance Testing with a channel inoperable is permitted provided the inoperable channel is in the tripped condition and the channel being tested is not bypassed for more than 4 hours.

MASTER TEST SWITCH j SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH PT-514 Failure (Channel 1) SG1 Low Pressure SI 1 36 1 PS-514A SG1 Low Pressure Steamline Iso 1 36 2 PS-514B 73 5 PT-515 Failure (Channel 2) SG1 Low Pressure SI 2 36 1 PS-515A SG1 Low Pressure Steamline Iso 2 36 2 PS-515B 73 5 l l l l

PROCEDURE No. REVISION NO. PAGE NO. VEGP 18001-C 17 27 of 29 Sheet 2 of 3 TABLE F1 (Cont'd) MASTER TEST SWITCH SSPS INPUT CAB CARD B/S SWITCH CARD SWITCH PT-516 Failure (Channel 4) SG1 Low Pressure SI 4 35 1 PS-516A SG1 Low Pressure Steamline Iso 4 35 2 PS-516B 73 5 PT-524 Failure (Channel 1) SG2 Low Pressure SI 1 41 1 PS-524A SG2 Low Pressure Steamline Iso 1 41 2 PS-524B 73 6 PT-525 Failure (Channel 2) SG2 Low Pressure SI 2 41 1 PS-525A SG2 Low Pressure Steamline Iso 2 41 2 PS-525B 74 6 PT-526 Failure (Channel 3) SG2 Low Pressure SI 3 35 1 PS-526A SG2 L'ow Pressure Steamline Iso 3 35 2 PS-526B 74 1 PT-534 Failure (Channel 1) SG3 Low Pressure SI 1 48 1 PS-534A SG3 Low Pressure Steamline Iso 1 48 2 PS-534B 74 6 PT-535 Failure (Channel 2) SG3 Low Pressure SI 2 48 1 PS-535A SG3 Low Pressure Steandine Iso 2 48 2 PS-535B 73 6 PT-536 Failure (Channel 3) i SG3 Low Pressure SI 3 36 1 PS-536A SG3 Low Pressure Steamline Iso 3 36 2 PS-536B 74 4 1 PT-544 Failure (Channel 1) I SG4 Low Pressure SI 1 49 1 PS-544A SG4 Low Pressure Steamline Iso 1 49 2 PS-544B 74 7

PROCEDURE No. REVISION NO. 'PAGE No. VEGP 18001-C 17-28 of 29 Sheet 3 of 3 TABLE F1 (Cont'd) MASTER TEST SWITCH SSPS INPUT CA23 CARD B/S SWITCH' CARD SWITCH-l 1 PT-545' Failure (Channel 2) SG4 Low Pressure SI 2 49 1 PS-545A l SG4 Low Pressure Steamline Iso 2 49 2 PS-545B 74 7 l PT-546 Failure (Channel 1) l SG4 Low Pressure SI 4 36 1 PS-546A SG4 Low Pressurc Steamline Iso 4 36 2 PS-546B 73 6 i i e 1 1 i tur

PROCEDURI No. REV18!ON NO. IPAGE No. VEGP 18001-C 17 29 of 29 Sheet 1 of 1 TABLE F2 AFFECTED SC ASSOCIATED PRESSURE SG FLOW SELECTOR INSTRUMENT CHANNEL SWITCH SG PT-514 F512 PT-515 F513 FS-512C 1 PT-524 F522 i PT-525 F523 FS-522C 2 PT-534 F532 PT-535 F533 FS-532C 3 PT-544 F542 PT-545 F543 FS-542C 4 a e

9 s SOUTHERN h COMPANY Energy to Serve Your World" PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-21420-003-01 LOCALLY OPERATE STEAM GENERATOR ARV Revision 17 April 2,1998 Written By S.1/anu Date: 4/2/98 Approved By O.1/auu Date: 4/2/98 y

RQ-JP-21420-003-01 JPM INFORMATION OPERATOR'S NAME: EVALUATION DATE: / / JPM TITLE: Loca!!y Operate Steam Generator ARV REVISION: 17 4/2/98 COMPLETION TIME: 13 minutes Application: RO/SRO Task Number: 21007 K/A Number: 000055EG06 RO: 5.8 SRO: 4.1 10CFR55.45 Ref.: 6,12 Evaluation Method [ ] Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room [ ] Unit 1 [ ] Unit 2 Performance Time: minutes OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: Examiner's Signature: 3

RC-JP-21420-003-01 INSTRUCTIONS TO EXAMINER This JPM is based 19030-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "@. " are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQu! RED ITEMS: 1. 18038, Attachment E. Local Operation of the S'G ARVs Provided locally at the handpump stations COMPONENT LOCATION: SMSVR: PV-3000 PV- 030 NMSVR: PV-3010 PV-302 DIRECTIONS TO G?ERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task. REMEMBER: Allsteps required for this task are to be simulated. Plant equipment is not to be operated. INITIAL CONDITIONS: Complications from an electrical fault have resulted in a reactor trip and main steamline isolation on Unit 2. The crew has subsequently diagnosed a steam generator tube rupture on SG # 2. Due to the electrical fault, the crew has determined that local ARV operation will be required and has dispatched the ABO to open the breakers for the ARV hydraulic pumps. AsslGNED TASK: The USS has directed you to " establish the maximum rate cooldown of 19030-C using SG # 3 ARV". TASK STANDARD: Steam Generator ARV locally opened. 4

i i RQ-JP-21420-003-01 JPM STEPS { i START TIME: STEP 1 SAT De UNSAT De Establish communications with Control Room Note: Communications may be established using the sound powered phone system, plant P/A telephone, or radio. l The breakers forthe ARVs are: 2-PV300_0 9 ARR-25 2-PV3010 2-BBB-25 i Q-PV-3020

• 2-BBB-26) 2-PY3030- 2-ABB 26 t

wO e Verify the hydraulic pump breaker is open (1) 50 . ARV Local Hand Pump station located j wO e Communications established with Control Room (2) i CUES: l (1) If requested,"The ABO reports that 2-BBB-26 is open." (see note above) (2) . Once demonstrated or discussed: " Communications have been established". l STEP 2 SAT De UNSAT De i - Align and verify proper operation of hand pump i hO . Level verified in hydraulic fluid reservoir sightglass aO e Selector Valve 2 in NEUTRAL hO e Hand pump bleed off valve closed l wO . Hand pump stroked freely I -STEP 3 I CRITICAL (+ ) l SAT De UNSAT De j Depressurize ARV accumulator wO + Reservoir inlet valve 11 A closed. 80 + Accumulator Dump Pilot Supply valve 11B open. wO - t .+ Hand pump stroked to maintain fluid pressure 2 2000 psig for 1 minute. xO' . + Reservoir iniet valve 11 A open, sO-Fluid pressure at 0 psig. sO + Accumulator dump pilot supply valve 11B closed. Reservoir inlet valve 11 A closed. wO-5 W eo. -~4-e s-y- y ,-e -w

RQ-JP-21420-003-01 JPM STEPS STEP 4 CRITICAL (+) SAT O s-UNSAT De Open the ARV a0 + Selector Valve 2 in OPEN a0 + Hand pump stroked to OPEN selected ARV (1) wO e Selector Valve 2 in NEUTRAL CUES: (1) If requested: "The Control Room desires that the ARV be fully opened". 6 STOP TIME: STEP 5 SAT Ox UNSAT Or1 Report to USS l s0

• ARV is open.

Fleid Notes I i l 1 l I 4 6 'emw

JPM: 18 SYSTEM: Main Steam QUESTION: 1 K/A: 035 K6.02 Knowledge of the effect of malfunction of the secondary PORV on the S/Gs, (3.1/3.5) OVESTION: How would the plant response to a failed open Main Steam Safety Valve (MSSV) differ from the plant response of a failed open Atmospheric Relief Valve (ARV) at 100% power? ANSWER:_ A failed open MSSV will pass steam equivalent to 6% power (there are 5 MSSVs on each of the 4 headers with a total capability of relieving 117% of rated steam flow). As opposed to a failed o)en ARV which will pass steam equivalent to 4% power (there is one ARV on eac1 S/G). Reference Allowed: YES

REFERENCE:

LP 21102-21C, Main Steam System: TS Basis, p. B3.7-1 L._-

r i JPM: 18 SYSTEM: Main Steam OVESTION: 2 K/A: 041 A4.06 Ability to manually operate and monitor ARV controllers in the control room. (2.9/3.1)' OUESTION: a. At what pressure do the ARVs open and how is this setpoint determined. b. At approximately what pressure are they expected to reseat. ANSWER: a. When the control is in auto, they open at the setpoint determined by the potentiometer. It is nominally at 7.5 which is 75% of a 0-1500 psig scale or 1125 psig. b. The valves reseat at approximately 10 psi below the lift setpoint. Reference Allowed: YES

REFERENCE:

LP 21102-21C. Main Steam System l

JPM: 18 OUESTION: 2 a. At what pressure do the ARVs open and how is this setpoint determined. b. At approximately what pressure are they expected to reseat. f 1 l t l l i j f L. ]

r JPM: 18 QUESTION: 1 How would the plant response to a failed open Main Steam Safety Valve (MSSV) differ from the plant response of a failed open Atmospheric Relief Valve (ARV) at 100% power? f 6 b i i i t I i i r i 6 5

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task. REMEMBER: All steps required for this task are to be simulated. Plant equipment is not to be operated. Initial Conditions: Complications from an electrical fault have resulted in a reactor trip and main steamline isolation on Unit 2. The crew has subsequently diagnosed a steam generator tube rupture on SG # 2. Due to the electrical fault, the crew has determined that local ARV operation will be required and has dispatched the ABO to open the breakers for the ARV hydraulic pumps. Assigned Task: The USS has directed you to " establish the maximum rate cooldown of 19030-C using SG # 3 ARV". Task Standard: Steam Generator ARV locally opened. l 2 i

4 a-wm SOUTHERN L COMPANY 1 Energy to Serve YourWorld' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-JP-60324-001-03 ENERGlZE 120V AC VITAL Bus FROM ALTERNATE POWER SUPPLY l Revision 14 April 2,1998 Written By

9, S cu4 a ce Date:

4/2/98 Approved By :9, Sc#4 deed Date: 4/1/98 l t

RQ JP-60324-001-03 JPM INFORMATION o s J OPERATOR'S NAME: EVALUATION DATE: / / JPM TITLE: Energize 120V AC Vital Bus From Alternate Power Supply ) REVISION: 14 4/2/98 l COMPLETION TIME: 16 minutes Application: RO/SRO Task Number: 01020 K/A Number: 000057EA101 RO: 3.7 SRO: 3.7 10CFR55.45 Ref.: 6,12 Evaluation Method ! ) Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room ( ) Unit 1 ( ) Unit 2 i l 1 Performance Time: minutes 1 1 OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments: l Examiner's Signature: 3 x

RQ JP-60324-001-03 INSTRUCTIONS TO EXAMINER This JPM is based on procedure 13431-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues designa'.ed by (#) are to be provided to the examinee during the performance of this JPM. REQUIRED ITEMS: 1. 13431,120V AC 1E Vital Instrument Distribution System 2. Select ONE of the following 120 VAC Panels: AY2A BY2B COMPONENT LOCATION: As provided in procedure DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task. REMEMBER: All steps required for this task are to be simulated. Plant equipment is not to be operated. I INITIAL CONDITIONS: The crew is responding to a' loss of M ANO using 18032. ASSIGNED TASK: The USS has directed you to " Transfer 3 AX1A to its alternate supply using 13431-1" TASK STANDARD: 120V Vital Bus transferred to its alternate power supply. l 4 s

RQ-JP-60324 001-03 JPM STEPS START TIME: STEP 1 @e

• gye to CFF-PCS (D d CRITICAL (+ )

SAT De UNSAT De Energize Regulated Transformer Note: Use 13431 Table 2 to determ' e the appropriate breaker for the bus chosen. a0

• Alternate supply breaker ated ABB-40 r BBB-40) a0 8PMternate supply breaker ON rui m

STEP 2 CRITICAL (+ )' SAT De UNSAT De Energize Vital Bus Note: Use 13431 Table 2 to determine the appropriate breakers for the bus chosen. aO e Perform steps 1 thru 4 of checklist 1 (1) a0 + Panel breaker 02 OPfhormal supply breaker) See e dM a0 + Panel breaker 01 ON (alternate supply breaker) aO e 120V AC verified on the bus voltmeter a0 Independent verification requested (2) e a0 Shutdown inverter (3) aO e Perform steps 5 & 6 of checklist 1 (1) CUES: l - (1) "The USS has determined that checkiist 1 is N/A since the bus is already de-energized and these actuations have occurred" (2) If requested, "The SSS will perform the IV." j (3) If requested, "The ABO will shutdown the inverter". STEP 3 SAT De UNSAT De i Report to USS 1 a0

• Bus transferred to alternate supply l

STOP TIME: Field Notes i f I 1 5 i i (.

JPM: 19 SYSTEM: AC Distribution OUESTION: 1 K/A: 062 K2.01 Knowledge of bus power supplies to major system loads. (3.3/3.4) i OUEST10N: Are any Class IE loads shared by Unit 1 and Unit 2? (i.e. d not have separate o power supplies fran each Unit) i ANSWER: Certain Fuel Handling Building Loads (Post Accident Unit Heater. Post Accident Exhaust Fan, and Radiation Monitor.) are powered only from Class 1E sources, associated with Unit 1 only and have no provision for connection to Unit 2 power supplies. i ) Reference Allowed: YES

REFERENCE:

VEGP-FSAR-8, page 8.3.1-2.3

9 e JPM: 19 SYSTEM: AC Distribution OUESTION: 2 K/A: 062 A2.06 Ability to ]redict the impacts of keeping the safeguards busses electrically separate on t1e ac distribution system and use procedures to control the operation. (3.4/3.9) OUESTION: Unit 2 is in Mode 1. In order to transfer preferred offsite power cources. it is proposed that both Class 1E 4.16 kV busses be manually connected to the same Reserve Auxiliary Transformer. Is this permissible. ANSWER: Yes, provided the following administrative control is provided. 1. Grid voltage is maintained at or above the minimum expected 100% grid voltage while the busses are interconnected to the one RAT: 2. No additional nonsafety-related 4.16 kV loads. (other than those normally fed from the Class 1E 4.16 kV safety busses.) shall be manually connected to the RAT while the busses are interconnected: and 3. The automatic bus transfer schemes for the nonsafety-related 4.16 kV busses shall be disabled during the connection of both trains to one RAT. Reference Allowed: YES

REFERENCE:

VEGP-FSAR-8. page 8.3.1-5 1

r-JPM: 19 QUESTION: 2 Unit-2 is in Mode 1. In order to transfer preferred offsite power sources, it is proposed that both Class 1E 4.16 kV busses be manually connected to the same Reserve Auxiliary Transformer. Is this permissible? \\ j 1

4 g JPM: 19 QUESTION: 1 'l Are any Class 1E loads shared by Unit 1 and Unit 2? (i.e. do not have separate . power supp1ies from each Unit) i l 2 f a l ) i 4 l 4 4 4

. _. _, -~ Approved By J. D. Williams Wgtle Electn. G:::zratm.g Plant ' Procedure Number Rev c 13431-2 10 om ^,, -.d r sumser i 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 1of15 l 1.0 PURPOSE i This procedure provides the necessary instructions for energizing, operating, and de-energizing the 120V AC 1E Vital l Instrument Distribution System. Instructions include the i following sections: 4.1.2 7.5KVA Inverter Startup ~ 4.1.3 10KVA Inverter Startup l 4.1.4 Energizing A Vital Instrument Distribution Panel i 4.2.1 Transferring Vital Instrument Distribution Panel To Alternate Source t 4.2.2 Transferring Vital Instrument Distribution Panel To [ Normal Source 1 4.2.3 Energizing The Sequencer A(B) During System Operation 4.2.4 De-energizing The Sequencer A(B) During System l Operation 4.3.1 De-energizing A Vital Instrument Distribution Panel I i 4.3.2 7.5KVA Inverter anutdown i 4.3.3 10KVA Inverter Shutdown 2.0 PRECAUTIONS AND LIMITATIONS 2.1 PRECAUTIONS 2.1.1 When transferring the power source of a vital instrument j distribution panel, ENSURE that the opposite train (s) bistables are not tripped so the momentary loss of power will not produce a signal that causes a reactor trip. 2.1.2 When Instrument Distribution Panel 2AY2A or 2BY2B is de-energized, Control Room Isolation ano Containment Ver,tilation Isolation will actuate if not blocked. 2.1.3 When Instrument Distribution Panel 2AY2A or 2BY2B Sequencer Board is energized, Containment Ventilation and Control Room i Isolations may occur due to voltage transients if not blocked. 2.1.4 When Instrument Distribution Panel 2AY1A or 2BY1B is energized i Containment Ventilation Isolation may actuate due to power being restored tL TR A(B) SSPS INFUT/ OUTPUT CABINET 5. l [ l i Printec June 18, 1991 at 1b:42

APPrM By Pmcodure Number Rev J. D. Williams Vcgtle Electn,c Gen: rating Plant s1 13431-2 10 Dets Ar,---d Page Numte 6/18/97 120V AC 1E VITAL INSTRUMENT DISTRIBUTION SYSTEM 2 of 15 2.2 LIMITATIONS 2.2.1 The 120V AC Vital Instrument Distribution Panels shall be energized in Modes 1, 2, 3, and 4 per Technical Specification LCO 3.8.9. 2.2.2 The 120V AC Vital Instrument Distributio~n Panels shall be energized in Modes 5 and 6 per Technical Specification LCO 3.8.10. 2.2.3 The Class 1E 120V inverters shall be OPERABLE in Modes 1 through 6 per Technical Specification LCO 3.8.7 and LCO 3.8.8. 2.2.4 The 120V AC Vital Instrument Distribution Panel Supply Breakers are interlocked so that only one breaker at a time can be closed. 2.2.5 The inverter DC input voltage shall be between 105-140V DC. 2.2.6 The inverter AC input voltage shall be between 414-506V AC. 2.2.7 While in Modes 1, 2, 3, and 4, no more than one 120V AC Vital Instrument Distribution Panel shall be powered from the regulated transformer backup power supply at any one time during routine preventative maintenance on the associated inverter. 2.2.8 The doors to Control Buil' ding Rooms B26, B29, B31, and B36 should be opened if cooling is lost. 3.0 PREREQUISITES OR INITIAL CONDITIONS 3.1 The 125V DC power is available to the inverters. 3.2 The 480V AC power is available to the regulated transformers. 4.O INSTRUCTIONS 4.1 STARTUP 4.1.1 If required, ALIGN the 120V AC 1E Vital Instrument Distribution System per the applicable section of 11431-2, "120V AC 1E Vital Instrument Distribution System Alignment". Pfantec June 12, 1997 at 1$342 9 i

.._..-_.m Approved By Procedure Number Rev Vogtis Electn. Gen 2 rating P12t c J. D. Williams 13431 2 10 l Date Approved Page Number 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM I 3 of15 4.1.2 7.5KVA Inverter Startup 7 y CAUTION j The 7.5 kVA Inverters should not be j operated at less than 20 amps of load. for longer that. 72 hours. NOTE Section 4.1.4 should be used to energize l a de-energized panel and Section 4.2.2 for transferring a panel to its normal source. 4.1.2.1 ENSURE OPEN the Instrument Distribution Panel AC Breaker from i the associated inverter as listed in Table 2. 4.1.2.2 ENSURE that the following breakers on the inverter are OPEN. a. Rectifier AC Input Breaker (ICB), b. Battery Input Breaker (2CB), c. Inverter DC Input Breaker (3CB), d. Inverter AC Output B'reaker (4CB). 4.1.2.3 CLOSE the Inverter DC Supply Breaker at the associat-d 125V DC switchgear as listed in Table 1. 4.1.2.4 CLOSE the Inverter Battery Input Breaker 2CB. 4. 1,. 2. 5 DEPRESS and HOLD the Inverter Pre-charge Pushbutton. 4.1.2.6 After 5 seconds, CLOSE the Inverter DC Input Breaker 3CB. 4.1.2.7 RELEASE the Inverter Pre-charge Pushbutton. 4.1.2.8 VERIFY proper operation of the inverter by observing appror.ir.ately 120V AC on the Inverter AC Output Voltmeter 2VM. 4.1.2.9 CLOSE the Inverter AC Output Breaker 4CB. I Printed June 18, 1991 at 15:42

. ~ ~ - - _ _.. -... -. ~. - - ~ - ~ - - ~ - APPned By J. D. Williams Vcgtle Electn,c Grnerating Picnt d Procedure Numba Rev 13431-2 10 Date Approved Pagt Number 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 4 of15 4.1.3 10KVA Inverter Startup NOTE Section 4 1.4 should be used to energize a de-energized panel and Section 4.2.2 for transferring r. panel to its normal source. 4.1.3.1 ENSURE OPEN the Instrument Distribution Panel AC Breaker from the associated inverter as listed in Table 2. 4.1.3.2 ENSURE the Inverter AC Input Power, Battery Input, and AC Output Breakers on the inverter are OPEN. 4.1.3.3 PLACE the Inverter Transfer Switch to INVERTER. 4.1.3.4 CLOSE the Inverter < Supply Breaker at the associated 480V AC Motor Control Cente. ."CC) as listed in Table 1. j 4.1.3.5 CLOSE the Inverter DC Supply Breaker at the associated 125V DC switchgear as listed in Table 1. 4.1.3.6 CLOSE the Inverter AC Input Power Breaker. 4.1.3.7 VERIFY proper operation of the inverter by observing the following indications on "the inverter. a. AC Input voltmeter 480V AC, b. Input Frequency 60 Hz, c. AC Output Voltmeter 120V AC. 4.1.3.8 CLOSE the Inverter Battery Input Breaker. 4.1.3.9 CLOSE the Inverter AC Output Breaker. 4.1.3.10 OPEN the Inverter AC Input Power Breaker. Independent verification required. 1 l Pranted June 16, 1997 at 1b:42 t

l Appoved By Procedure Number Rev J. D. Williams Vogtle Electr. Gen: rat.ing Phnt 13431-2 10 ic o un g roved P.se s-be 6/18/97 120V AC 1E VITAL INSTRUMENT DISTRIBUTION SYSTEM 5of15 4.1.4 Energizing A Vital Instrument Distribution Panel CAUTION When Instrument Distribution Panel 2AYlA or 28Y1B is energized Containment Ventilation Isolation may actuate due to power being restored to TR A(B) SSPS INPUT / OUTPUT CABINETS. NOTE The Vital Instrument Distribution Panels-are normally energized from the inverters. 4.1.4.1 If energizing 2AY2A or 2BY2B, PERFORM Steps 1, 2, and 3 of Checklist 1. 4.1.4.2 To energize a Vital Instrument Distribution Panel from the inverter source, PERFORM the following: a. START UP the inverter per Section 4.1.2 or 4.1.3 of this procedure, b. CLOSE the Instrument Distribution Panel AC Breaker from the associated inverter as listed in Table 2. 4.1.4.3 To energize a Vital Instrument Distribution Panel from the regulated source, PERFORM the following: a. CLOSE the Regulated Transformer Supply Breaker for the associated instrument distribution panel as listed in Table 2, b. CLOSE the Instrument Distribution Panel AC Breaker from the associated, regulated source as listed in Table 2. 4.1.4.4 VERIFY proper operation of the instrument distribution panel by observing approximately 120 AC on the Instrument Distribution Panel Voltmeter; independent verification required. 4.1.4.5 If energizing 2AY2A or 2BY2B, COMPLETE Steps 4 and 5 of Checklist 1. 4.1.4.6 If energizing 2AYlA or 2DY1B and the Containment High Flux at Shutdown Alarm fuse was previously pulled, then INSTALL FU3 in Auxiliary Relay Cabinet 3 2NCQARC. 4.1.4.7 If Containment Ventilation Isolation actaated while resLuring power to 2AY1A or 2BY1B, RESTORE equipment to normal by initiating 11886-2, " Recovery From ESF Actuation". Pfar.Le3.IUhe I L*, 1997 at lbl42

m _ _ _ Approved Dy Procedure Nurnber Rev J. D. Williams Vogtle Electric G:nerstm.g Plant 13431-2 10 t Das Approvsd Page Number L 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 6 of 15 4.2 SYSTEM OPERATION 4.2.1 Transferring Vital Instrument Distribution Panel To Alternate 3 Source l CAUTION To preclude any unwanted actuations from opening Instrument Distribution Panel AC Breaker, 18032-2 and the 120V AC Load Database should be reviewed. 4.2.1.1 ENSURE the Regulated Transformer Supply Breaker for the associated instrument distribution panel, as listed in Table 2 i is CLOSED. NOTE Steps 4.2.1.4 and 4.2.1.5 shall be performed as quickly as possible to minimize the time the instrument distribution panel is de-energized. 4.2.1.2 If transferring 2AY2A or 2BY2B, PERFORM Steps 1, 2, and 3 of Checklist 1. 4.2.1.3' If transferring 2AY1A or'2BYlB and Source Range Detectors are in service, at the discretion of the USS, DEFEAT actuation of the Containment High Flux at Shutdown Alarm by pulling FU3 in Auxiliary Relay Cabinet 3 2NCQARC. 4.2.1.4 OPEN the Instrument Distribution Panel AC Breaker from the inverter as listed in Table 2. 4.2.1.5 CLOSE the Instrument Distribution Panel AC Breaker from the regulated source as listed in Table 2. 4.2.1.6 VERIFY proper operation of the instrument distribucion panel by observing approximately 120V AC on the Instrument Distribution Panel Voltmeter; independent verification required. 4.2.1.7 SHUT DOWN the inverter per Section 4.3.2, Steps 4.3.2.2 thru 4.3.2.6, or per Section 4.3.3, Steps 4.3.3.2 thru 4.3.3.6 of this procedure. 4.2.1.8 If transferring 2AY2A or 2BY2B, COMPLETE Steps 4 and 5 of Checklist 1. 4.2.1.9 If Containment Ventilation Isolation actuated while transferring puwer, RESTORE equipment to normal by initiating 11886-2, " Recovery From EST Actuation". 4.2.1.1Q.If transfer of 2AY1A or 2BY1B is complete and Containment High Flux at Shutdown Alarm fuse was previously pulled, then INSTALL FU3 in' Auxiliary Relay Cabinet 2NCQARC. Pn nte: June 16, 1997 at 15:42

. -. - - - ~. - - - -. -... ~ -. ~ _ - -. ~.... . _ -,. _. _. -.. ~,, Approved By Procedure Number Rev J. D. Williams Vogtle Electn. Generstm.g Pirnt i c 13431-2 10 DW Approved Page humber 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 7 of15 4.2.2 Transferring vital Instrument Distribution Panel To Normal Source i CAUTION When Instrument Distribution Panel 2AY2A i or 2BY2B is de-energized Control Room and i Containment Ventilation Isolations will actuate if not blocked per Checklist 1. t 4.2.2.1 STARTUP the inverter per Section 4.1.2 or 4.1.3 of this procedure. CAUTION i To preclude any unwanted actuations from opening Instrument Distribution Panel AC Breaker, 18032-2 and the 120V AC Load Database should be reviewed. l NOTE Steps 4.2.2.4 and 4.2.2.5 shall be performed as quickly as possible to minimize the time the instrument distribution panel is de-energized. 4.2.2.2 If transferring 2AY2A or 2BY2B, PERFORM Steps 1, 2, and 3 of l Checklist 1. i 4.2.2.3 If transferring 2AY1A or 2BY1B and Source Range Detectors are in service, at the discretion of the USS, DEFEAT actuation of the Containment High Flux at Shutdown Alarm by pulling FU3 in Auxf.liary Relay Cabinet 3 2NCQARC. 4.2.2.4 OPEN the Instrument Distribution Panel AC Breaker frora die regulated source as listed in Table 2. 4.2.2.5 CLOSE the Instrument Distribution Panel AC Breaker from the inverter as listed in Table 2. 4.2.2.6 VERIFY proper operation of the instrument distribution panel by observing approximately 120V AC on the Instrument Distribution ) Panel Voltmeter; independent verification required. 4.2.2.7 If transferring 2AY2A or 2BY2B, COMPLETE Steps 4 and 5 of Checklist 1. 4.2.2.8 If Containment Ventilation Isolation actuated while transferring power, RESTORE equipment to normal by initiating 11886-2, '" Recovery From ESF Actuation". 4.2.2.9 Jf transfer of 2AY1A or 2BY1B is complete and Containment High Flux at Shutdown Alarm fuse was previously pulled, then INSTALL FU3 in Auxiliary Relay Cabinet 3 2NCQARC. erantea aune 2e, 199< at 23:42 i

1 PProved By Vogtle Electn. Gscersting Plant d Procedure Number Rev 1 D. Williams c 13431-2 10 i Date Approved Page Number i 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 8of15 4.2.3 Energizing The sequencer A(B) During System Operation CAUTION When the sequencer is energized during system operation Containment Ventilation i and Control Room Isolations may occur due to voltage transients if not blocked per Checklist 1. f f 4.2.3.1 PERFORM Steps 1, 2, and 3 of Checklist 1. 4.2.3.2 ENERGIZE Sequencer A(B) as follows-a. In the Manual Test Cabinet, PLACE the Sequencer Power Switch to ON, I b. ALLOW the sequencer circuits to charge for 10 seconds, c. If not running, in the Card Rack Cabinet, RESET the ATI-1 i

Module, d.

If the ATI-1 Module is not stepping, REPEAT Step 4.2.3.2b, e. In the Card Rack Cabinet, DEPRESS the illuminated card reset lights to reset the Undervoltage Bistable Cards (A3-1, A3-2, A3-3, A'3 - 5, A3-6, A3-7, A3-9, A3-10, A3-11, i A3-13, A3-14, A3-15), f. In the Manual Test Cabinet, DEPRESS the Undervoltage Alarm Light to reset the Undervoltage Alarm, g. In the Manual Test Cabinet, DEPRESS the SEQ Logic Failure Button to reset the Sequencer Logic Failure Alarm, l h. COMPLETE Steps 4 and 5 of Checklist 1. 4.2.4 De-energizing The Sequencer A(B) CAUTION When the Sequencer is de-energized during system operation, Containment ventilation l and Control Room Isolations may occur due { to voltage transients if not blocked per Checklist 1. t 4.2.4.1 PERFORM Steps 1, 2, and 3 of Checklist 1. I I Printec. June 16, 1997 at 16:42 I

. - ~ _ _.-.- - - - Approved By Procedure Number Rev Vcgtle Electn. Geercting Pl:nt 1 D. Williams. c 1343j.2 10 Date Approved Page Number 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 9 of15 4.2.4.2 DE-ENERGIZE Sequencer A(B) as follows: a. In the Manual Test Cabinet, PLACE the Sequencer Power Switch to OFF. i b. COMPLETE Steps 4 and 5 of Checklist 1. i 4.3 SHUTDOWN 4.3.1 De-energizing A vital Instrument Distribution Panel 1 CAUTION i When Instrument Distribution Panel 2AY2A or 2BY2B is de-energized Control Room and l Containment Ventilation Isolations will actuate if not blocked per Checklist 1. 1 NOTES i l a. Prior to de-energizing a panel, review Technical Specification LCO 3.8.9 or LCO 3.8.10. I b. Refer to 18032-2 and the 120V AC Load Database for guidance prior to de-energizing panel. c. De-energizing pa'nels 2CY1A or 2DY1B will render the train related ESF Chiller inoperable due to loss of instrument power to 2-FIS-1802 or 2-FIS-1803 (NSCW flows to ESF Chillers) 4.3.1.1 If de-energizing 2AY2A'or 2BY28, PERFORM Steps 1, 2, and 3 of Checklist 1. 4.3.1.2 If de-energizing 2AY1A or 2BY1B and Source Range Detectors are in service, at the discretion of the USS, DEFEAT actuation of the Containment High Flux at Shutdown Alarm by pulling FU3 in Auxiliary Relay Cabinet 3 2NCQARC. 4.3.1.3 OPEN the Instrument Distribution Panel AC Breaker from the inverter as listed in Table 2. 4.3.1.4 ENSURE the Instrument Distribution Panel AC Breaker from the regulated transformer, as listed in Table 2, is OPEN. 4.3.1.5 VERIFY the instrument distribution panel is completely ] de-energized by observing zelu volta un Line VILal Instrument i Distribution Panel Voltmeter. 4.3.1.6, _ SHUT DOWN the inverter per Section 4.3.2, Steps 4.3.2.2 thru 4.3.2.6, or per Section 4.3.3, Steps 4.3.3.2 thru 4.3.3.6, of this procedure. erantes June 1e, 1992.t 15:42

.. -.... -. _. - _ -..... _ _ - _ _ _ _ _ _ ~... _. ...._..m. ___m__ Approved By Wgtle Electn. Generating Picnt d Procedure Number Rev c J. D. Williams 13431-2 10 Date Approved Page Number 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 10 of15 i 4.3.1.7 OPEN the Regulated Transformer Supply Breaker for the associated i instrument distribution panel as listed in Table 2. j ~ 4.3.2 7.5KVA Inverter Shutdown i .4.3.2.1 If the associated instrument distribution panel is to remain energized,. TRANSFER the panel to the alternate source per Section 4.2.1 of this procedure. 4.3.2.2 OPEN the, Inverter AC Output Breakers (4CB). f i 4.3.2.3 OPEN the Inverter DC Input Breakers (3CB). 4.3.2.4 OPEN the Inverter Battery Input Breaker (2CB) l 4.3.2.5 OPEN the Inverter DC Supply Breaker at the associated 125V DC switchgear as listed in Table 1. } 4.3.2.6 VERIFY the inverter is completely shut down by observing zero volts on the Inverter AC Output Voltmeter. 4.3.3 10KVA Inverter shutdown I 4.3.3.1 If the associated instrument distribution panel is to remain energized, TRANSFER the panel to the alternate source per Section 4.2.1 of this procedure. l 4.3.3.2 OPEN the Inverter AC Output Breaker. ~ 4.3.3.3 OPEN the Inverter Battery Input Breaker. 4.3.3.4 VERIFY the inverter is completely shut down by observing zero I volts on the Inverter AC Output Voltmeter. 4.3.3.5 OPEN the' Inverter DC Supply Breaker at the associated 125V DC switchgear as listed in Table 1. 4.3.3.6 OPEN the Inverter AC Supply Breaker at the associated 480V AC MCC as listed in Table 1. 4.4 NON-PERIODIC OPERATION NONE enntec June a, m2 at n:42

. ~... -.. --._- -.- I Approved By rrocedure Number Rev J. D. Williams Vogtle Electn. Genemtm.g PI::nt al 13431-2 10 c ~ o.ie Arr...a r., somber 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 11of15

5.0 REFERENCES

5.1 ONE-LINE DIAGRAMS 5.1.1 2X3D-AA-G01A Main One-Line 120V AC 1E Instrument System 5.1.2 2X3D-AA-G02A 120V AC 1E Instrument Distribution Panels 5.1.3 2X3D-AA-G02C 120V AC 1E Instrument Distribution Panels j 5.2 FSAR Section 8.3 5.3 Technical Specification LCO 3.8.7,

3. 8. 8, 3.8.9 and LCO 3.8.10 5.4 TECHNICAL MANUALS 5.4.1 2X6AR07-3 7.5KVA Inverters 2AD1II, 2BD1I2, 2CD1I3, 2DD1I4 5.4.2 AX3AQO3-34 10KVA Inverters 2AD1I11, 2BD1I12 5.5 PROCEDURES 5.5.1 11431-2 "120V AC 1E Vital Instrument Distribution i

System Alignment" 4 i 1 END OF PROCEDURE TEXT i 4 m P:intec June 18, 1997 at 16:42

~m . ~. _.. _ _.. _ _. _......-... _.. _ _...__ _ ___.. _ - _._.._... m. APP'oved By Procedure Number Rev J. D. Williams Vcgtle Electn,c G nerating Plant s1 13431-2 to Date Approved Page humber 6/18/97 = 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 12 of 15 TABLE 1 i 7.5KVA INVERTERS I INVERTER DC SUPPLY DC BREAKER AC SUPPLY AC BREAKER 2AD1Il SWGR 2AD1 2AD1-10 NA NA 2BD1I2 SWGR 2BD1 2BD1-10 NA NA 2CD1I3 SWGR 2CD1 2CD1-09 NA NA 1 2DD1I4 SWGR 2DD1 2DD1-09 NA NA f 10hTA INVERTERS e INVERTER DC SUPPLY DC BREAKER AC SUPPLY AC BREAKER 2AD1I11 SWGR 2AD1 2ADI-04 MCC 2ABB 2ABB-43 2BD1I12 SWGR 2BD1 2BD1-04 MCC 2BBB 2BBB-43 I l i 1 l .Printec June 141, 1997 at 15:42

.. - -. _, _ ~. ~ Approved By Procedure Number Rev Vogtle Electn G:n ratirg Phnt J. D. Williams c 13431-2 10 Date Approved Page Number 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 13 of15 TABLE 2 l 120V AC VITAL INSTRUMENT PANELS NORMAL SUPPLY ALTERNATE SUPPLY PANEL INVERTER PANEL BRKR REG XFMR SPLY BRKR PANEL BRKR 2AY1A 2AD1Il 2AY1A-02 ABC09X ABC-09 2AY1A-01 2AY2A 2AD1I11 2AY2A-02 ABB40X ABB-40 2AY2A-01 2BY1B 2BD1I2 2BY1B-02 BBA07X BBA-07 2BY1B-01 2BY2B 2BD1I12 2BY2B-02 BBB40X BBB-40 2BY2B-01 2CY1A 2CD1I3 2CY1A-02 ABA07X ABA-07 2CY1A-01 2DY1B 2DD1I4 2DY1B-02 BBC09X BBC-09 2DY1B-01 9 4 Printea.:une.lu, 1991 at 16:42

. ~.. ~. - ~. ~... -... ~.. -. - -. -. - = - _ _ ~. - Approv'd W Procedure Number Rev J. D. Williams Vogtl2 Electn. GEncratm.g Pinnt c 13431-2 to Date Approved Page Number 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 14 of 15 CHECKLIST 1 Sheet 1 of 2 t i Panel 2AY2A (2BY2B) and/or Sequencer A(B) De-energization/Energization NOTE I An LCO action should be entered when removing ESFAS equipment from service. 1. At the OESF BLOCK Control Room Isolation by placing RM OSA f INTAKE RAD HIGH 2-HS-12195C to TEST / BLOCK: a. For 2AY2A or Sequencer A, PLACE to TEST / BLOCK CHAN I, } 2-RE-12116; Independent verification required, I ( b. For 2BY2B or Sequencer B, PLACE to TEST / BLOCK CHAN II, [ 2-RE-12117; Independent verification required, i c. HAVE Chemistry turn OFF power to the associated DPM. 2. To block Containment Ventilation Isolation, PERFORM the following: a. For 2AY2A or Sequencer A, in Control Building RB-07, close to the associated DPM, UNLOCK CVI BLOCK PANEL 2-1609-P5-CB1,'and PLACE 2-HS-13259 to BLOCK 2-RE-0002; Independent verification required, b. For 2BY2B or Sequencer B, in Control Building, RB-38, i close to the associated DPM, UNLOCK CVI BLOCK PANEL 2-1609-P5-CB2, and PLACE 2-HS-13260 to BLOCK 2-RE-0003-Independent verification required. i 3. To prevent damage of associated Radiation Monitor DPMs, PERFORM i the following: I a. For 2AY2A or Sequencer A, HAVE Chemistry turn OFF power to: 2-RX-0002 2-RX-0005 2-RT-0005 2-RX-13119 2-RX-13120 b. For 2BY2B or Sequencer B, HAVE Chemistry turn OFF power to: 2-RX-0003 2-RX-0006 j 2-RT-0006 i 2-RX-13121 2-RX-13122 i i P antec June 16, A pri at 1b:42

L w-ar A % son ne. J. D. Williams , $13 Electn. Gen 2ratm.g Plzt - KA c 13431-2 10 Date Weved Page Number 6/18/97 120V AC IE VITAL INSTRUMENT DISTRIBUTION SYSTEM 15 of15 CHECKLIST 1 Sheet 2 of 2 4. When the panel has been re-energized, NOTIFY Chemistry to restore power to and reset the following as required: a. For 2AY2A or Sequencer A: '2-RX-12116 2-RX-0002 2-RX-0005 2-RT-0005 2-RX-13119 2-RX-13120 b. For 2BY2B or Sequencer B: 2-RX-12117 2-RX-0003 2-RX-0006 2-RT-0006 2-RX-13121 2-RX-13122 5. When hotified that the Radiation Monitors have been restored and no High Radiation Alarms exist, a. PLACE 2-HS-12195C to OFF. Independent verification

required, NOTE The clearing of annunciator ALB05B04,

" BYPASS CNMT VENT ISO HI RAD TEST" may be used as independent verification that 2-HS-13259 and/or 2-HS-13260 is in the NORMAL position. b. For 2-RE-0002 PLACE 2-HS-13259 to NORMAL. Independent verification required. LOCK CVI BLOCK PANEL 2-1609-PS-CBl. c. For 2-RE-0003 PLACE 2-HS-13260 to NORMAL. Independent verification required. LOCK CVI BLOCK PANEL 2-1609-P5-CB2. d. ENSURE all seismic clips are engaged for CVI Block Panel. Printec June 18, 1997 a; lbs42 s

s This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You willbe allowed access to any item normally used to perform this task. REMEMBER: All steps required for this task are to be simulated. Plant equipment is not to be operated. Initial Conditions: The crew is responding to a loss of SANb using 18032. Assigned Task: .he USS has directed you to " Transfer 2.AN A to its alternate supply using 13431-1 ". Task Standard: 120V Vital Bus transferred to its alternate power supply. 1 9 2

9 SOUTHERN h COMPANY Energy to Serve Your World" PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE RQ-J P-37061-001-01 OPERATE CONTAINMENT HYDROGEN RECOMBINER I Revision 17 April 2,1998 4 Written By

d, S cu 44,rce Date:

4/2/98 Approved By : d, S cu4aece Date: 4/2/98

l RQ-JP-37061-001-01 JPM INFORMATION OPERATOR'S NAME: ) EVALUATION DATE: / / 1 JPM TITLE: Operate Containment Hydrogen Recombiner l REVISION: 17 4/2/98 j COMPLETION TIME: 7 minutes Application: RO/SRO j Task Number 20014 K/A Number: 028000A401 RO: 4.0 SRO: 4.0 10CFR55.45 Ref.: 6,12 l t Evaluation Method [ ] Performed [ ] Simulated Evaluation Location [ ] Simulator [ ] Control Room [ ] Unit 1 [ ] Unit 2 Performance Time: minutes i OVERALL JPM EVALUATION [ ] SATISFACTORY [ ] UNSATISFACTORY Examiner Comments. k l Examiner's Signature: 1 i 3

RQ-JP-37061-001-01 INSTRUCTIONS TO EXAMINER This JPM is based on 13130-1. Verify this JPM is in accCrd with the latest procedural revision prior to use. Cues preceded by a "@.. " one provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM. REQu! RED lTEMS: 1. 13130, Post Accident Hydrogen Control 2. PTDB Tab 13, H Recombiner Reference Power 2 3. Calculator COMPONENT LOCATION: Control Building 1E 480 VAC Swgr Rooms (nolprovidedin procedure) DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Star.dard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task. REMEMBER: All steps required for this task are to be simulated. Plant equipment is not to be operated. INITIAL CONDITIONS: The crew has implemented 19251 following a large LOCA on Unit N The following containment parameters have been recorded: i H concentration 5% 2 pre-LOCA temperature - 120"F post-LOCA pressure 10 psig. AsslGNED TASK: Per 19251-C, the USS has directed you to " Start Unit 1 Hydrogen Recombiner A by initiating 13130-1, Post Accident Hydrogen Control". TASK STANDARD: Containment hydrogen recombiner operating at the post-LOCA power setting. 4

L- ) RQ-JP-37061-001-01 JPM STEPS ' START TIME: STEP 1 SAT De UNSAT Os Determine recombiner pressure factor 50 . Pressure factor of 1.41 to 1.44 determined using Figure 1 STEP 2 CRITICAL (+) SAT De UNSAT De Energize the hydrogen recombiner 50

• Power Available light lit au Power Adjust Potentiometer at 0 demand e

wO + Power Out switch in ON wD e Red power out light lit STEP 3 SAT De UNSAT De Warm up hydrogen recombiner su . Power Adjust potentiometer raised to attain: (1) 4 to 6 KW for 10 minutes 9 to 11 KW for 10 minutes 18 to 22 KW for 5 minutes CUES: - (1) At each level inform the operator the stated times have been attained. i STEP 4 CRITICAL (+) SAT Oe UNSAT De Determine recombiner post-LOCA setting Note: Accepteble bend 16r post-LOCA power setung is (1.41 x current RFP) to (1.44 x current RFP). Prowde Reference Power values (per ettechtnent) when requested. ~ wD e Reference power setting determined using PTDB Tab 13 'i wO + Post-LOCA power setting determined within acceptable band j 1 l 5 \\ 1 l

RQ4P-37061-00101 JPM STEPS STEP 5 i CRITICAL (*) SAT De UNSAT De l increase recombiner power to the post-LOCA setting Note: H2 RecombmerPost-LOCA Setungs: 1A' 57 4 An 1kW 18: 60.9-62.2 kW ' j, , y& yf Q 63.4 64.8 k& 28: 58.7-60.0 kW a0 + Power Adjust potentiometer raised to attain post-LOCA power setting a0 . Requests containment hydrogen concentration sampling. (1) CUES: (1) "The SSS is directing sampling per Sections 4.2.1 and 4.2.2." STEP 6 SAT Oe-UNSAT De Report to USS i l a0 . Recombiner in service i STOP TIME: Field Notes 1 i I i i j i i 6 I I

RQ JP-37061-001-01 PTD3 HYDROGEN RECOM21NER REFERENCE POWER SETTINGS P t From PTDB Tab 13 t t Unit 1 Train A: 40.5 KW Unit 1 Train B: 43.2 KW 'i Unit 2 Train A: 45.0 KW Unit 2 Train B: 41.65 KW 1 1 i l 7

I SYSTEM KNOWLEDGE QUESTIONS JPM: 110 SYSTEM: Hydrogen Recombiner OUESTION: 1 K/A: 028 K5.02 Knowledge of the operational implications of the Flammable Hydrogen Concentration as they apply to the Hydrogen Recombiner. (3.4/3.9) OUESTION: At what range of hydrogen concentrations are the recombiners used and whyr g ANSWER: 0.5 - 6.0% Tech Specs state that the desian of the recombiners is to keep the Hydrogen concentration below the 4.1% flammability limit. If concentration is greater than 6%, TSC will evaluate possibility of explosion. ) Ref Allowed: NO

REFERENCE:

LO-LP-29140-06. Containment Electric Hydrogen Recombiner

JPM: 110 SYSTEM: Hydrogen Recombiner QUESTION: 2 K/A: 028 A1.02 Ability to 3redict and monitor changes in containment pressure associated with operating t1e Hydrogen Recombiner controls. (3.4/3.7) OUESTION: a. Explain how an increase in containment pressure would affect the operation of the Hydrogen Recombiner. ANSWER: As containment pressure increases; air density increases: a higher power rate is needed to maintain proper recombination rate. -QUESTION: b. Explain how an increase in containment temperature would affect the operation of the Hydrogen Recombiner. ANSWER: As containment temperature increases: air density decreases; a lower power rate can maintain proper recombination rate. Ref Allowed: YES REFFRENCE: LO-LP-29140-06. Containment Electric Hydrogen Recombiner

p. 12

Q JPM: 110 QUESTION: 2 a. Explain how an increase in containment pressure would affect the operation of the Hydrogen Recombiner. j b. Explain how an increase in containment temperature would affect the operation of the Hydrogen Recombiner. 8 l 2 ) j

JPM: 110 QUESTION: 1 . At what range of hydrogen concentrations are the recombiners used and why? i i 1 1 l l 4 l l l-I l t-

l This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you \\ understand the task before beginning. You will be allowed access to any item normally used to perform this task. REMEMBER: All steps required for this task are to be simulated. Plant equipment is not to be operated. n Initial Conditions: The crew has implemented 19251 follos.ing a large LOCA on Unit e The following containment parameters have been recorded: l H2 concentration 5% pre-LOCA temperature 120 F post-LOCA pressure 10 psig. Assigned Task: Per 19251-C, the USS has directed you to " Start Unit S Hydrogen Recombiner A by initiating 13130-9.. Post Accident Hydrogen Control" ll Task Standard: Containtnent hydrogen recombiner operating at the post-LOCA power setting. 2

~... V i.Vogtih Electric Generating Picit ' 1: Approved By Procedure Number Rev ..a.,- J. D. Williams e 33330 2 11 p.=9 pow P.p swee 8/27/97 POST-ACCIDENT HYDROGEN CON'1ROL 1of23 1.0 PURPOSE This procedare provides instructions for operation of the Containment Hydrogen Monitoring System, the Electric Hydrogen Recombiners, the Post-LOCA Cavity Purge System, and the Post-LOCA Containment Hydrogen Purge System during normal and post-LOCA conditions. Instructions are provided in the following sections. If entering this procedure for Post-Accident Containment Hydrogen reduction, then initiate Section 4.4.1. 4.1.1 Placing The Containment Hydrogen Monitoring System In Standby 4.1.2 Placing The Electric Hydrogen Recombiners In Standby 4.1.3 Placing The Post-LOCA Cavity Purge And Post-LOCA Containment Hydrogen Purge Systems In Standby 4.2.1 Containment Hydrogen Monitor 2-1513-P5-HMA Operation (Hydrogen Measurement) 4.2.2 Containment Hydrogen Monitor 2-1513-P5-HMB Operation (Hydrogen Measurement) 4.4.1 Post-LOCA Electri'c Hydrogen Recombiner Operation 4.4.2 Diluting Containment Hydrogen Concentration Using The Service Air System 4.4.3 Post-LOCA Containment Hydrogen Purge System Operation 2.0 PRECAUTIONS AND LIMITATIONS 2.1 PRECAUTIONS 2.1.1 Adhere to all applicable radiological controls. 2.1.2 Train A Hydrogen Monitor Supply Valves 2-HV-2792A, 2-HV-2792B, 2-HV-2791B, and Return Valve 2-HV-2793B may be opened in Modes 1, 2, 3, and 4 under administrative control as described in the basis for Technical Specification LCO 3.6.3. 2.1.3 Train B Hydrogen Monitor Supply Valves 2-HV-2790A, 2-HV-2790B, 2-HV-2791A, and Return Valve 2-HV-2793A may be opened in Modes 1, 2, 3, and 4 under administrative control as described in the basis for Technical Specification LCO 3.6.3. Printed August 28, 1997 at 14:00

__.. _m I Approved By L Vogtl2 Electn.. Generating. P'latt L ! Proccdure Number Rev -,1 J. D. Williams [ c a 13i30 2 11 s Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 2 of 23 2.1.4 This proceduie does not administrative 1y control opening of both 1RC and ORC Hydrogen Monitor Valves (on toe same penetration) as + 4 allowed in Technical Specification LCO 3.6.3 Note 1. j i 2.2 LIMITATIONS i 2.2.1 Technical Specifications require the Hydrogen Monitors and the j Electrical Hydrogen Recombiners to be operable as follows: ) a. Per Technical Specification LCO 3.3.3, as part of the Post Accident Monitoring Instrumentation in Modes 1, 2 and 3, l I b. Per Technical Specification LCO 3.6.7, two Hydrogen Recombiner Systems in Modes 1 and 2. 5 2.2.2 When first energized, the Hydrogen Monitors require a 6 hour 2 warm-up period in standby before accurate readings may be obtained. 2.2.3 Hydrogen Recombiners should not be operated if containment i hydrogen concentration is greater than 6% in dry air 4 1 2.2.4 In Analyze Mode, Low Analyzer Flow, Analyzer Cell Fi. Ore, Low Calibration Gas Pressure, Low Reagent Gas Pressure, .,tc !!ot Box Temperature and switching between Standby and Analyze M, des will j generate a Common Failure Alarm. In Standby Mode, low analyzer flow End analyzer cell fa'ilure are bypassed. l f 3.O PREREQUISITES OR INITIAL CONDITIONS d ] 3.1 Hydregen Monitor sample line heat tracing is operating. l i i i I i l i k Printed August 26, 1997 at 14:00

D liiarns

vogtl2 Electric Gen 5 rating Plart -

[3Y3[3.$"** ['[ Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 3 of 23 i 4.O INSTRUCTIONS 4.1 STARTUP 4.1.1 Placing The Containment Hydrogen Monitoring System In Standby 4.1.1.1 PERFORM Section A of 11130-2, " Post-Accident Hydroge'n Control Alignment", if required. 4.1.1.2 PERFORM Checklist 1 to align Containment Hydrogen Monitoring System remote - opereted components for system startup. NOTE The Hydrogen Monitors require a 6 hour warm-up period in STANDBY before accurate readings may be obtained. i 4.1.1.3 On Centrol Room Panel QPCP, PLACE OFF/ STAND BY/ ANALYZE Handswitch 2-HS-22900 in STANDBY and VERIFY SYSTEM ON light illuminates. 4.1.1.4 At local Containment Hydrogen Monitor Panel 2-1513-PS-HMA 1 (Auxiliary Building Level B), PERFORM the following: i a. If no lights are lit, PRESS the Circuit Breaker ON Pushbutton located inside the panel, b. ENSURE FUNCTION SELECTOR Switch 2-HS-22902 in SAMPLE, c. If Common Failure Light is lit, RESET by depressing RESET Button 2-HS-22955. 4.1.1.5 On Control Room Panel QPCP, PLACE OFF/ STAND BY/ ANALYZE Handswitch 2-HS-22901 in STANDBY and VERIFY SYSTEM ON light i13uminates. I 4.1.1.6 At local Containment Hydrogen Monitor Panel 2-1513-PS-HMB (Fuel Handling Building Level A), PERFORM the following: a. If no lights are lit, PRESS the Circuit Breaker ON Pushbutton located inside the panel, b. ENSURE FUNCTION SELECTOR Switch 2-HS-22903 in SAMPLE, I c. If Common Failure Light is lit, RESET by depressing RESET Button 2-HS-22956. i e 1 Frinted August 26, 1997 at 14:00

...- -.. ~ Approved By Proced.are humber Rev yogtle Electric Gen 2 rating Plant: 13130-2 11 J. D. Williams Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 4 of 23 4.1.2 Placing The Electric Hydrogen Recombiners In Standby 4.1.2.1_ ENSURE both Electric Hydrogen Recombiners are off at their local control panels in Control Building Level B: a. ENSURE OFF Power Out Switch on 2-1513-P5-ERA, b. ENSURE OFF Power out Switch on 2-1513-P5-ERB. 4.1.2.2 PERFORM Section B of 11130-2, " Post-Accident Hydrogen Control Alignment" if required. 4.1.2.3 At 480V AC Switchgear 2AB05, CLOSE the Electric Hydrogen Recombiner 2-1513-P5-ERA Feeder Breaker 2AB05-08; independent verification required. 4.1.2.4 At 4 80V AC Switt,hgear 2BB07, CLOSE the Electric Hydrogen l Recombiner 2-1513-PS-ERB Feeder Breaker 2BB07-08; independent verification required. 4.1.3 Placing The Post-LOCA Cavity Purge And Post-LOCA Containment Hydrogen Purge Systems In Standby 4.1.3.1 PERFORM Section C of 11130-2, " Post-Accident Hydrogen Control Alignment" if required. 4.1.3.2' PERFORM Checklist 2 to align the Post-LOCA Containment Hydrogen Purge System remote - operated valves for standby. e Printed August 26, 1997 at 14:00

.__._._._m._ .= -. _. _. _ Approved By A Procedure Number Rev Vogtl1 Electric Gen: rating Plant, al 13130-2 11 1 D. Williams Date Approved Page humber 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 5 of 23 42 SYSTEM OPERATION 4.2.1 Containment Hydrogen Monitor A 2-1513-P5-HMA Operation (Hydrogen Measurement) CAUTION The Hydrogen Monitor Isolation Valves must remain closed except during Hydrogen Monitor operation while in Modes 5 or 6 or during post accident conditions to ensure containment integrity is maintained. NOTE The Hydrogen Monitors require a 6 hour warm-up period in STANDBY before accurate readings may be obtained. 4.2.1.1 If the following conditions exist then notify maintenance to implement 28834-2 to provide power to Containment Isolation Valves 2-HV-2791B and 2-HV-2793B:

a. A post accident condition (LOCA) exist AND,

b. 125 VDC Bus 2BD11 is riot available AND,

c. Containment Hydrogen Concentration is required.

4.2.1.2 ENSURE the Hydrogen Monitor A sample line heat tracing temperature is greater than 260*F. a. At Heat Tracing Panel 2-1817-U3-007B, READ the temperature i for circuit Cl-1 and Cl-2, b. If less than 260*F, NOTIlA the Control Room immediately. 4.2.1.3 OPEN the H2 MONITOR A SPLY ISO IRC: a. 2-HV-2792A, b. 2-HV-2792B. 4.2.1.4 OPEN H2 MONITOR A SPLY ISO ORC 2-HV-27918. ) 1 4.2.1.5 OPEN H2 MONITOR A RTN ISO ORC 2-HV-2793B. 4.2.1.6 PLACE OFF/ STAND BY/ ANALYZE Handswitch 2-HS-22900 in ANALYZE. 4.2.1.7 ENSURE Function Selector Switch 2-HS-22904 in Sample position. Frititeo August 28, 1997 at 14:00

A Procedure Nurnber Rev pg gy m...... -. tr

Vogtla Elec., ic Gen:r,,a..;-ting;Pir.ti A" 13130-2 11 J. D. Williams Date Approved Page Nurnber 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 6 of 23 4.2.1.8 Momentarily DEPRESS Remote Control Selector Pushbutton 2-HS-22944 and VERIFY Sample Light LIT.

NOTE Indication of hydrogen concentration,is available within 30 minutes of initiating flow through the monitors. This is accomplished by operating the monitors in standby during normal plant operation. (CO 2999) 4.2.1.9 NOTE containment hydrogen concentration as indicated by CONTAIN H2 MONITOR TRN A 2-AI-12979 on QMCB when indications stabilize. j 4.2.1.10 When hydrogen monitoring is no longer desired, PLACE OFF/ STAND BY/ ANALYZE Handswitch 2-HS-22900 in STAND BY. 4.2.1.11 CLOSE the Hydrogen Monitor A Isolations by placing their Control Switches to CLOSE: ) i a. 2-HV-2792A, b. 2-HV-2792B, c. 2-HV-2 '; 91B, d. 2-HV-2793B. i i Prir$tec August 2b, 1997 at 14:00

Approved By s s ....r. A Procedure Number Rev J. D. Williams N1ogtli Ele.....ctric Ge...r.n; rating ~ Plant. ik : 13130-2 11 i Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 7 of 23 4.2.2 containment Hydrogen Monitor B 2-1513-P5-HMB Operation (Hydrogen Measurement) CAUTION The Hydrogen Monitor Isolation Valves j must remain closed except during Hydrogen Monitor operation while in Modes 5 or 6 or during post accident conditions to ensure containment integrity is maintained. NOTE The Hydrogen Monitors require a 6 hour i ,4 warm-up period in STANDBY before accurate j readings may be obtained. 4.2.2.1 If the following conditions exist then notify maintenance to implement 28834-2 to provide power to containment isolation valves 2-HV-2791A and 2-HV-2793A:

a. A post accident condition (LOCA) exist AND, j

i b. 125 VDC Bus 2AD11 is not available AND, c. Containment Hydrogen Concentration is required. ? 4 I 4.2.2.2 ENSURE the Hydrogen Monitor sample line heat tracing temperature j is greater than 260*F. j i a. At Heat Tracing Panel 2-1817-U3-007A, READ the temperature for circuit Cl-1 and Cl-2, b. If less than 260*F, NOTIFY the Control Room immediately. l 4.2.2.3 OPEN H2 MONITOR B SPLY ISO IRC: a. 2-HV-2790A, b. 2-HV-2790B. 4.2.2.4 OPEN H2 MONITOR B SPLY ISO ORC 2-HV-2791A. i 4.2.2.5 OPEN H2 MONITOR B RTN ISO IRC 2-HV-2793A. 4.2.2.6 PLACE OFF/ STAND BY/ ANALYZE Handswitch 2-HS-22901 in ANALYZE. 1-4.2.2.7 ENSURE Function Selector Switch 2-HS-22905 in Sample position. 4.2.2.8 Momentarily DEPRESS Remote Control Selector Pushbutton 2-HS-22945 and VERIFY Sample Light LIT. (CO 0033) k Printed August 28, 1991 at 14:00

~ ~._..,. i Appr2ved by Procedure Number Rev L D. Williams Nogtl2 Electn,c Gen: rat,ng Phntt 13130-2 11 i Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 8 of 23 j NOTE Indication of hydrogen concentration is available within 30 minutes of initiating flow through the monitors. This is accomplished by operating the monitors in standby during normal plant operation. (CO 2999) 4.2.2.9 NOTE containment hydrogen concentration as indicated by CONTAIN H2 MONITOR TRN B 2-AI-12980 on QMCB when indications stabilize. 4.2.2.10 PLACE OFF/ STAND BY/ ANALYZE Handswitch 2-HS-22901 in STAND BY. 4.2.2.11 CLOSE the Hydrogen Monitor B Isolations by placing their control switches to CLOSE: a. 2-HV-2790A, i b. 2-HV-2790B, c. 2-HV-2791A, d. 2-HV-2793A. 4.3 SHUTDOWN NONE 4.4 NON PERIODIC OPERATION 4.4.1 Post-LOCA Electric Hydrogen Recombiner Operation (CO 5757) CAUTION An Electric Hydrogen Recombiner may require up to 75 kilowatts of power during post-LOCA operation. If emergency power is being supplied by the Emergency Diesel Generators, ensure their loading is maintained within limits. NOTE Hydrogen Recombiners should not be operated if containment hydrogen concentration is greater than 6% in dry' air. 4.4.1.1 NOTE pre-LOCA containment temperature from 14000-2, " Operations Shift And Daily Surveillance Lcgs". Printed August 29, 1991 at 14:00

_......._.-_._._.s_._______.m. k Approved By Vogtle Electric Genhrating Pirntt 1 ' Precedure Number Rev i J. D. Williams 33330 2 11 Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 9 of 23 4.4.1.2 NOTE and RECORD post-LOCA containment pressure from 2-PI-0934, l 2-PI-0935, 2-PI-0936, and 2-PI-0937. 4.4.1.3 DETERMINE and NOTE the recombiner pressure factor using Figure j 1. 4.4.1.4 START one Electric Hydrogen Recombiner at its local' control j panel. i l a. VERIFY the POWER IN AVAILABLE light is ON, h l l b. ENSURE POWER ADJUST Potentiometer is set to zero. c. PLACE. POWER OUT SWITCH in ON, j J l d. VERITY the pilot light above the switch comes on, I NOTE POWER OUT meter response will lag POWER ADJUST Potentiometer adjustments. I' e. MONITOR POWER OUT meter and slowly RAISE POWER ADJUST to j j obtain between 4 and 6 kilowatts, } ) f. MAINTAIN between 4 and 6 kilowatts for 10 minutes by j l adjusting POWER ADJUST as required, l g. MONITOR POWER OUT and slowlv RAISE POWER ADJUST to obtain between 9 and 11 kilowatts, h. MAINTAIN between 9 and 11 kilowatts for 10 minutes by adjusting POWER ADJUST as required, i. MONITOR POWER OUT and slowly RAISE POWER ADJUST to obtain between 18 and 22 kilowatts, 5 j. MAINTAIN between 18 and 22 kilowatts for 5 minutes by [ adjusting POWER ADJUST as required, k. OBTAIN the current Hydrogen Recombiner Reference Power (kw) from PTDB Tab 13 and MULTIPLY by the pressure factor determined in Step 4.4.1.3 to obtain the post-LOCA power

setting, l

I l l Printect August 28, 1997 at 14:00 i

_.. _ ~. _ _ _. Approved By m.- A Procedure Number Rev , :@' fEl ctn.. Gen ratin,g Planti sl, c J. D. Williams 33330 2 11 Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 10 of 23 CAUTION Do not exceed 75 kilowatts power output. i 1. MONITOR POWER OUT and slowly RAISE POWER ADJUST to obtain the post-LOCA power setting, m. MAINTAIN the post-LOCA power setting by adjusting POWER ADJUST as required. 4.4.1.5 MEASURE and RECORD containment hydrogen concentration through sampling per Section 4.2.1 and/or 4.2.2.of this procedure. 4.4.1.6 WARM UP the second Electric Hydrogen Recombiner at its local control panel: a. VERIFY the POWER IN AVAILABLE light is ON, b. ENSURE POWER ADJUST Potentiometer is set to zero. i c. PLACE POWER OUT SWITCH in ON, d. VERIFY the red pilot. light above the switch comes on, NOTE ~ POWER OUT meter response will lag POWER ADJUST Potentiometer adjustments. e. MONITOR POWER OUT meter and slowly RAISE POWER ADJUST to obtain between 4 and 6 kilowatts, f. MAINTAIN between 4 and 6 kilowatts for 10 minutes by j adjusting POWER ADJUST as required, g. MONITOR POWER OUT and slowly RAISE POWER ADJUST to obtain I between 9 and 11 kilowatts, h. MAINTAIN between 9 and 11 kilowatts for 10 minutes by l adjusting POWER ADJUST as required. l t b Printed August 28, 1997 at 14:00

~ -. - - ..~ Approved By ating Pl:nt.. 13130-2 11 J. D. Williams Nogtl3 Electric Gen :r. Procedure Number Rev on.4pova r ges -nba 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 11of23 4.4.1.7 Periodically MONITOR the power output of each Electric Hydrogen Recombiner and ADJUST as required: a. MAINTAIN the warmup recombiner output between 9 and 11 kilowatts, CAUTION Do not exceed 75 kilowatts power output. 1 b. MAINTAIN the operating recombiner output greater then or l equal to the post-LOCA power setting. I 4.4.1.8 Periodically MONITOR all three temperature channels of each recombiner using the TEMPERATURE CHANNEL SELECTOR Switch and the TEMPERATURE meter. NOTE Recombiner temperatures should rise and then stabilize between 4 and 5 hours after startup. 4.4.1.9 When the operating recombiner temperatures begin to stabilize, DETERMINE the difference between the reading of each channel with the reading of each of the other two channels: a. If the smallest temperature difference is greater than or equal to 60*F, temperature indication is unreliable. PROCEED to 4.4.1.11, b. If one temperature channel differs from both of the other two by 60*F or more, this channel is considered I unreliable. DELETE this channel when determining average recombiner temperature. 4.4.1.10 MAINTAIN the average temperature of the operating recombiner between 1250 and 1450*F by adjusting POWER ADJUST if required. 4.4.1.11 About 24 hours after startup of the first Electric Hydrogen Recombiner: a. NOTE and RECORD containment pressure from 2-PI-0934, 2-PI-0935, 2-PI-0936, and 2-PI-0937, b. MEASURE containment hydrogen concentration through sampling per Section 4.2.1 and/or 4.2.2 of this procedure. Printed August 2b, 1997 at 14:00

__.m ___.m. .__.. ~ .__m.. A - Procedure humber Rev Approved By ~ .s 1 D. Williams avegtis Electric Gen.: rating;PI nt' ? A. 33330 2 11 Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 12 of 23 i 4.4.1.12 If containment hydrogen concentration is greater than 3.5 i percent or has risen by more than 0.5 percent above the previous l value, RAISE recombiner output: a. If the present power output of the operating Electric Hydrogen Recombiner is less than 71 kilowatts, RAISE its output by 4 kilowatts, b. If the present power output of the operating recombiner is greater than or equal to 71 kilowatts, PLACE the warmup 4 recombiner in full operation as follows: (1) NOTE pre-LOCA containment temperature from surveillance logs, (2) NOTE current containment pressure on 2-PI-0934, f 2-PI-0935, 2-PI-0936, and 2-PI-0937, (3) DETERMINE and NOTE the recombiner pressure factor using Figure 1, (4) OBTAIN the current Hydrogen Recombiner Reference Power (kw) from PTDB Tab 13 and MULTIPLY by the pressure factor to obtain the post-LOCA power

setting,

• CAUTION Do not exceed 75 kilowatts power output.

NOTE POWER OUT meter response will lag POWER ADJUST Potentiometer adjustments. (5) MONITOR warmup recombiner POWER OUT and slowly RAISE POWER ADJUST to obtain the post-LOCA power setting, (6) MAINTAIN the post-LOCA power setting by adjusting POWER ADJUST as required. 4.4.1.13 If containment hydrogen concentration has risen less than 0.5 percent above the previous value, PROCEED to 4.4.1.15. Printed August 28, 1997 at 14:00 ~ -.

. -..__..-. ~ -.=...... -.-.- -. .. - -. ~ - - - - - - -.. -. - Approved By g ;vcgtle Electric. Gen rating'. Plant l.I .n s Procedure Number Rev J. D. Williams 13i30 2 11 Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 13 of 23 l 4.4.1.14 If containment hydrogen concentration has fallen or remained i constant over the 24 hour period since last measurement: a. NOTE the containment pressure recorded 24 hours ago, b. NOTE the containment pressure recorded in 4.4.1.11a, c. If containment pressure has changed over the past 24 hours, ADJUST operating recombiner power output: (1) DETERMINE and NOTE the new recombiner pressure factor using Figure 1, (2) MULTIPLY the reference power setting (PTDB Tab 13) by the new pressure factor to obtain the new post-LOCA power setting, NOTE POWER OUT meter response will lag POWER ADJUST Potentiometer adjustments. (3) MONITOR POWER OUT meter and slowly ADJUST POWER ADJUST to obtain the new post-LOCA power setting, (4) MAINTAIN the new post-LOCA power setting by adjusting POWER ADJUST as required. 4.4.1.15 Periodically MONITOR and ADJUST the recombiners per 4.4.1.7 through 4.4.1.10. t ) t l l ) 1 i F 1 i ? Printed August 28, 1997 at 14:00 f

.. -.._ - _ _. __~. -. Approved By A Procedure Number Rev J. D. Williams v'6gtl1Electnc Gtnerstm.g Plant A 13130-2 11 1 i Date 4prswd Page Namba 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 14 of 23 4.4.1.16 About every 24 hours, MEASURE containment hydrogen concentration and ADJUST the recombiners per 4.4.1.11 through 4.4.1.14. 4.4.1.17 REPEAT 4.4.1.15 and 4.4.1.16 throughout the remainder of the recombiner operating period. 4.4.1.18 When Electric Hydrogen Recombiner operation is no longer required (containment hydrogen concentration at less than 0.5%), 1 SHUT DOWN each recombiner at its local' control panel as f611ows: j a. LOWER POWER ADJUST potentiometer setting to zero, b. PLACE POWER OUT SWITCH in OFF, j c. VERIFY the red pilot light above the switch turns off. 4.4.2 Diluting Containment Hydrogen Concentration Using The Service Air System j l CAUTION i Do not perform this section if containment pressure is greater than 40 psig unless so directed by the Emergency i Director. ' NOTES a. Containment design pressure is 52 psig. 1 I b. Containment Isolation Phase A Train A and Train B signals must be reset to open 1-HV-9385. 4.4.2.1 OPEN SERVICE AIR CNMT HDR ISOL 2-HV-9385 as follows: a. PLACE 2-HS-9385A on Main Control Room Panel QPCP to OPEN, b. HOLD Control Switch on Panel QPCP in OPEN until 2-HV-9385 is fully open. l 4.4.2.2 OPEN one SERVICE AIR CNMT POST LOCA PURGE Valve using its Control Switch on QPCP: a. 2-HV-9380A, b. 2-HV-9380B. 4.4.2.3 CHECK Service Air Header 2-PI-9377 and Instrument Air Dryer To SCS Equipment 2-PI-9361 pressures on Main Control Room Panel QMCB. Printed August 26, 1997 at 14:00

_m. __m_m. m__ Approved Dy dogtle.El:ctn. G:nerating Plat ' d Prcredure Number Rev J. D. Williams c 13130 2 11 Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 15 of 23 4.4.2.4 If air pressures fall to 80 psig or less, SERVICE AIR DRYER SUPPLY INLET ISO 2-PV-9375 isolates service air to dryers; RESTORE purge air flow as follows: UNLOCK and CLOSE Service Air Containment Building Supply a. Header Isolation 2-2401-U4-056, b. RESET 2-PSL-9375 on Instrument Rack 15 on Turbine Building Level 1 near the powdex vessels to restore Service Air

Supply, THROTTLE OPEN 2-2401-U4-056 to maintain air pressures on c.

2-PI-9377 and 2-PI-9361 greater than 85 psig. 4.4.2.5 MONITOR containment hydrogen concentration through sampling and per Sectjsn 4.2.1 and/or 4.2.2 of this procedure. 4.4.2.6 MONITra containment pressure 2-PI-0934, 2-PI-0935, 2-PI-0936, [ and '.-PI-0937. If pressure rises to 40 psig or to the value spe,cified by the Emergency Director, TERMINATE dilution per Step 9.4.2.7. 4.4.2.7 When containment hydrogen concentration falls to 3.5%, TERMINATE dilution as follows: a. CLOSE SERVICE AIR CNMT HDR ISOL 2-HV-9385 using Control Switch on Control Room Panel QPCP, b. ENSURE CLOSED both SERVICE AIR CNMT Post-LOCA Purge Valves using their control switches on Panel QPCP: (1) 2-HV-9380A, (2) 2-HV-9380B. 4.4.2.8 Periodically MONITOR containment hydrogen concentration and REPEAT this section as required to maintain the concentration below 4.0%. Printec August 28, 1997 at 14:00 +

m. .1_ .m. _. - Approved By -1 A Wogtle Elec:tn Generating Plrt < ik-Procedure humber Rev J. D. Williams c 13130-2 11 Date Approved Page Number ) 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 16 of 23 4.4.3 Post-LOCA Containment Hydrogen Purge System operation (CO 2998, CO 4320) .~_ ) CAUTIONS a. The Post-LOCA Containment Hydrogen Purge System is to be operated only if the I containment hydrogen concentration cannot be maintained below 4% by other means. b. The Post-LOCA Containment Hydrogen Purge System is designed to operate with a maximum pressure of 3 psi downstream of I CNMT POST LOCA PURGE EXH DUCT CONTROL VLV 2-TV-2693. i NOTE i If plant conditions warrant, the Emergency Director may waive the Gaseous Release Permit requirement. I 4.4.3.1 INITIATE a Gaseous Release Permit. 4.4.3.2 ENSURE containment atmosphere is sampled and analyzed. 4.4.3.3' ENSURE the Service Air Sy' stem is operating. i 4.4.3.4 ENSURE compliance with the'ODCM Section 3.1.1 Table 3-1 for the gaseous effluent monitoring requirements. 4.4.3.5 ENSURE the Auxiliary Building Heating Ventilation And Air conditioning System is operating. 4.4.3.6 PLACE Disconnect Switch at Local Heater Control Panel 2-1508-N7-001-H01 to ON. 4.4.3.7 PUSH RESET Button at Local Heater Control Panel 2-1508-N7-001-H01 and VERIFY that reset red light is ON. CAUTION Due to high radiation area potential, ensure Containment Inside Isolation Valves 2-HV-2624A and 2-HV-2624B are closed and remain closed during the performance of the next step and until personnel have exited the area. 4.4.3.8 UNLOCK and OPEN CAPCS Post LOCA Purge Exhaust Isolation 2-1508-04-012. Printed August 28, 1997 at 14:00

Approved By 7 1 A Procedure Number Rev i J. D. Williams JWogtliElectric Gen rating Pinnt sL 13130-2 11 Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 17 of 23 4.4.3.9 ENSURE all conditions of the Gaseous Release Permit that must be satisfied prior to the release are met, unless the permit requirement has been waived by the Emergency Director. NOTE i The Containment Ventilation Isolation Train A signal must be reset to open 2-HV-2624A. The Train B signal must be reset to open 2-HV-2624B. 4.4.3.10 OPEN one CTB POST LOCA PURGE EXH IRC ISO VLV using its Control Switch on Main Control Room Panel QHVC: a. 2-HV-2624A, b. 2-HV-2624B. 4.4.3.11 PLACE CNMT POL ' LOCA PURGE EXH DUCT CONTROL VLV 2-HS-2693 to the MOD position to initiate containment venting. 4.4.3.12 VERIFY CAPCS Post LOCA Purge Exhaust 2-UI-2693 flow rises to between 450 and 500 standard cubic feet per minute using 2-UI-2693. 4.4.3.13 MONITOR 2-UI-2693, plant vent stack flow using 2-UI-3693, and vent stack radiation and' ENSURE compliance with the Gaseous Release Permit, if required. NOTE Containment Isolation Phase A Train A and Train B signals must be reset to open 2-HV-9385. 4.4.3.14 OPEN SERVICE AIR CNMT HDR ISOL 2-HV-9385 as follows: a. PLACE Control Switch on Main Control Room Panel QPCP to

OPEN, b.

HOLD Control Switch on Panel QPCP in OPEN until 2-HV-9385 is fully open. 4.4.3.15 OPEN one SERVICE AIR CNMT Post LOCA Purge Valve using its Control Switch on QPCP: a. 2-HV-9380A, b. 2-HV-9380B. 4.4.3.16 CHECK Service Air Header 2-PI-9377 and Instrument Air Dryer To SCS Equipment 2-PI-9361 pressures on Main Control Room Panel ,OMCB. Printed August 28, 1997 at 14:00

Approved 11y .. t . tnc A ~ Procedure humber Rev n ' Wg. itElec....... Gen:, rating Pla.nt - A 13130-2 11 J. D. Williams o u ggovw reseNumba 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 18 of 23 4.4.3.17 If air pressures fall to 80 psig or less, SERVICE AIR DRYER SUPPLY INLET ISO 2-PV-9375 isolates service air to dryers; RESTORE purge air flow as follows: UNLOCK and CLOSE Service Air Containment Building Supply a. Header Isolation 2-2401-U4-056, b. RESET 2-PSL-9375 on Instrument Rack 15 on Turbine Building Level 1 near the powdex vessels to restore Service Air

Supply, c.

THROTTLE OPEN 2-2401-U4-056 to maintain air pressures on 2-PI-9377 and 2-PI-9361 greater than 85 psig. 4.4.3.18 When containment hydrogen concentration falls to 3.5%, TERMINATE the purge as follows: a. CLOSE SERVICE AIR CNMT HDR ISOL 2-HV-9385 using Control Switch on Control Room Panel QPCP, b. ENSURE CLOSED both SERVICE AIR CNMT Post LOCA Purge Valves using their Control Switches on Panel QPCP: (1) 2-HV-9380A, (2) 2-HV-9380B, c. ENSURE CLOSED both CTB POST LOCA PURGE EXH IRC ISO Valves using their Control Switches on Control Room Panel QHVC: (1) 2-HV-2624A, (2) 2-HV-2624B, d. CLOSE CNMT POST LOCA PURGE EXH DUCT CONTROL VLV 2-FV-2693, e. PLACE Disconnect Switch at Local Heater Control Panel 1-1508-N7-001-H01 to OFF, f. CLOSE and LOCK CAPCS Post LOCA Purge Exhaust Isolation 2-1508-U4-012, g. COMPLETE processing of the Gaseous Release Permit if initiated. 4.4.3.19 Periodically MONITOR containment hydrogen concentration and MAINTAIN it less than 4.0%. Printed August 28, 1997 at 14:00

~ Ulb , o we ti riectnicen:rans riast c t 73o'."2 EE si a " ""~ c Date Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 19 of 23 5.O REFERENCES 5.1 VEGP FSAR Section 6.2.5

5. 2

• PROCEDURES 5.2.1 13305-2,

" Auxiliary Building Heating, Ventilation, And Air Conditioning System" 5.2.2 13710-2, " Service Air System" 5.2.3 13901-2, " Heat Tracing" 5.3 P& ids 5.3.1 2X4DB213-1 Purification And Clean-up System 5.3.2 2X4DB213-2 Purificatien And Clean-up System 5.3.3 2X4DB214-2 Containment, Control Rod Drive Mechanism, Cavity, And Reactor Support Cooling System 5.3.4 2X4DB203 Equipment Building Heating, Ventilation, And Air Conditioning System 5.3.5 2X4DB186-1 Service Air System 5.3.6 2X4DB175-2 Instrument And Service Air System 5.4 ELEMENTARY DIAGRAMS 5.4.1 2X3D-BG-B02U Purification And Clean-up System: Hydrogen i Recombiner 5.4.2 2X3D-BG-B02V Purification And Clean-up System: Hydrogen Recombiner 5.4.3 2X3D-BG-B02X Containment, Control Rod Drive Mechanism, Cavity And Reactor Support Cooling System 5.4.4 2X3D-BG-B02Y Containment, Control Rod Drive Mechanism, Cavity And Reactor + Support Cooling System 5.4.5 2X3D-BG-B04A Purification And Clean-up System: 2-HV-2624A 5.4.6 2X3D-BG-B04B Purification And Clean-up System: 2-HV-2624B 5.4.7 2X3D-BG-B05B Purification And clean-up System: 2-HV-2790A, B, 2791B And 2793B 5.4.8 2X3D-BG-B05E Purification And Clean-up System: 2-HV-2791A, 2792A, B And 2793A ) Printed August 20, 1997 at 14:00 4

Approved By A Procedure Number Rev J. D. Williams fogtts Electric'Generattg Plant. A 33330 2 11 Date Appr*ved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 20 of 23 5.4.9 2X3D-BG-B05F Containment Building Electrical Hydrogen Recombiner System: 2-HV-2793A 5.4.10 2X3D-BG-B05G Containment Building Electrical Hydrogen Recombiner System: 2-HV-2793B 5.4.11 2X3D-BG-B05M Containment Building Electrical Hydrogen Recombiner System: 2-HV-2790B 5.4.12 2X3D-BG-B06F Purification And Clean-up System: 2-HV-1508-012 5.4.13 2X3D-BG-B06H Containment Post-LOCA Purge Exhaust Duct Isolation Valves 5.4.14 2X3D-BH-R01D Service Air System 2-HV-9380A 5.4.15 2X3D-BH-R01E Service Air System 2-HV-9J80B 5.4.16 2X3D-BH-R01H Containment Service Air Header Isolation 2-HV-9385 5.5 TECHNICAL MANUALS 5.5.1 AX5AA05-43 Containment Hydrogen Monitor 5.5.2 1X6AE01-38 Electric Hydrogen Recombiner END OF PROCEDURE TEXT I s a s I ] 4 Printed August 26, 1991 at 14:00

Approwd Dv ~ Procedure Number Rev J. D. Williams th,gtle Electric'Ghnimting Plant ~ A. 1 13130-2 11 D:Ae Approved Page Number ) 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 21 of 23 Figure 1-Dry Containment Recombiner Power Correction Factor Versus Containment Pressure, 0.0 psig Initial Pressure 1.7 PRt-LOCA I+6 C087 AI NM EN T TEMP (AATUAE 60*F 90cp 1 1.5 '20 ' / C / u / ~ / l.4 /) O ff l <w /) // l.3 2 ff S / f Y / w ) s.2 f g . ma"' / O.I 1.0 0 2 4 6 8 10 12 14 POST-LOCA CONTAINMENT PRESSURE (PSIG) \\ 1 Printea April 2, 1998 at 15:35 J

. -..~.-- - ~ Appiroved By W vogtifElectn1.Ge._i :nerating Plant r 1 e ~ <..,....c-Procedure Number Rev c J. D. Williams 33330 2 11 Dans Approved Page Number 8/27/97 POST-ACCIDENT HYDROGEN CONTROL 22 of 23 Sheet 1 of 1 CHECKLIST 1 CONTAINMENT H2 MONITORING SYSTEM REMOTE-OPERATED COMPONENTS ALIGNMENT FOR SYSTEM STARTUP CONDITION LINEUP VERIFICATION COMPONENT DESCRIPTION REQUIRED (INITIALS) (INITIALS) 2-HS-22900 H2 MONITOR A OFF FUNCTION SELECT 2-HV-2792A H2 MONITOR A CLOSED SUPPLY ISO IRC 2-HV-2792B H2 MONITOR A CLOSED SUPPLY ISO IRC 2-HV-2791B H2 MONITOR A CLOSED SPLY ISO ORC 2-HV-2793B H2 MONITOR A CLOSED RTN ISO ORC 2-HS-22901 H2 MONITOR B OFF FUNCTION SELECT 2-HV-2790A H2 MONITOR B CLOSED SPLY ISO IRC 2-HV-2790B H2 MONITOR B CLOSED SPLY ISO IRC 2-HV-2791A H2 MONITOR B CLOSED SPLY ISO ORC 2-HV-2793A H2 tiONITOR B CLOSED RTN ISO ORC 2-HV-8221 CNMT ATMOSPHERE CLOSED PASS SAMPLE ISOLATION Reviewed By: " ~ Date Prarited August 28, 1997 at 14:00 L- : }

Approved By gogtidEINtn..Genersting Plant 1 J.+ a ' Procedure Number Rev J. D. Williams e c 9 j3130 2 11 Date Approved Page Number 8/27/97 POST-ACCIDENT INDROGEN CONTROL 23 of 23 1 CHECKLIST 2 POST-LOCA CONTAINMENT HYDROGEN PURGE SYSTEM REMOTE-OPERATED VALVE ALIGNMENT FOR STANDBY t CONDITION LINEUP VERIFICATION COMPONENT DESCRIPTION REQUIRED (INITIALS) (INITIALS) 2-HV-2624A CTB POST LOCA CLOSED PURGE EXH IRC ISO VLV 2-HV-2624B CTB POST LOCA CLOSED PURGE EXH IRC ISOLATION 2-FV-2693 CNMT POST CLOSED i LOCA PURGE EXH DUCT CONTROL VLV 2-HV-9385 SERVICE AIR ~ CLOSED CONTAINMENT HEADER ISOLATION 2-HV-9380A SERVICE AIR CLOSED CNMT POST LOCA PURGE 2-HV-9380B SERVICE AIR CLOSED CNMT POST LOCA PURGE Revieweo Sy: Date Printed August 28, 1991 at 14:00 L J}}