ML19323D033

Emergency Operating Procedure EP/1/A/5000/19, Feedwater Line Rupture.

ML19323D033
Person / Time
Site:	McGuire, Mcguire
Issue date:	02/18/1980
From:	Cage G, Frye S, Mccraw N DUKE POWER CO.
To:
Shared Package
ML19323D015	List: ML19323D014 ML19323D018 ML19323D019 ML19323D023 ML19323D031 ML19323D033
References
EP-1-A-5000-19, NUDOCS 8005190557
Download: ML19323D033 (10)

Text

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

O ,

~

8 o os190 GM For:n SPD-1002-1 DUKE POWER CCMPANY (1) ID No: EP/1/A/5000/19 PROCEDURE PREPARATION Change (s) o to PROCESS RECORD 0 Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE: Feedvater Line Ruoture l

1 (4) PREPARED SY: Steve Frve DATE: 2/14/80 (5) REVIEWED SY: 6 M d DATE: d-/f'8d Cross-Disciplinary Raview 3 7: N/R: M j (6) TEMPORARY APPROVAL (IF NECESSARY):

3:

7 (SRO) Data: l 37: Date:

(7) APPROVID BY: A w. h Date: /- //- /d 67 /

(8) MISCELLANEOUS:

Reviewed / Approved By: Date:

Reviewed / Approved.By: Date:

i INFORWIl0N ONLY ,

EP/1/A/5000/19 DUKE POWER COMPANY McGUIRE NUCLEAR STA!!CN TEEDWATER LINE RUPTURE 1.0 Sv notoms 1.1 S/G flow mismatch CF greater than steam.

1.2 S/G flow mismatch Le CF flow (if rupture is between check valva and -

flow element).

1.3 Possible increase in Tave.

1.4 S/G 1evel decreasing.

1.5 Steam loop flow /CF flow mismatch.

1.6 Con *=4-unant humidity and pressure increase.

1.7 Contain=="t Sump Level increases.

2.0 Immediate Actions 2.1 Automatic 2.1.1 Reactor trip-curbine trip.

2.1.0 Safety Injection actuation.and Phase "A" Isolation.

2.1.3 Main staan isolation.

2.1.4 Possible Cont =%nant Spray and Phase B Cont =4nmaet Isolation.

2.1.5 E/S Sequencer Actuation.

2.2 . 6 Feedwater Isolation.

2.0 Manual 2.'.1 Ensure all automatic actions occur.

2.2.2 If Reactor fails to trip, refer to Reactor Trip procedure (EP/1/A/5000/01).

2.2.3 If Turbine fails to trip, refer to Turbine Generator Trip procedure (EP/1/A/5000/02).

2.2.4 *

• CA fails to start, manually start pumps and establish flow to S/G's.

CAUTION: Inaccurate Pressuri:er and S/G level readings will occur during accident conditions involving breaks inside ten-t ainman t . (This is caused by depressurization and/or reference leg heatup). Refer to McGuire Data Sook Curves l , and curves for correct .

conversions for actual level. Use backup instru=iantation (i.e.: CA Flow, SM Pressure, NC Pressure and Wide Range

~'h , Tc) .

3.0 Subsecuent Acti,on CAU'" ION : Do not place systems in nanual unless niscperation in automatic is apparent. If any system is placed in nanual, =ake frequent checks for proper opera-ion.

i l

3.1 Trip the reactor coolant pucips immediately if SI has actuated and NC pressure reaches 1250 psig.

3.2 Monitor operation of pressurizar Code Safety valves to remove decay beat.

3.3 If any pressurizar PORV's open on high pressurizar pressure, ensure ressaging at 2315 psig decreasing.

3.4 Announce the occurrence on paging systas.

3.5 If containment paramatars indicata that the break is outside of con-  ;

tain=nt, go to section 4.0 of this procedura. l 3.6 If Phase 3 isolation occurs, the RV pumps must be stopped. The reactor I coolant pumps must be tripped within 5 minutes if not previously trippa.d.

NOTE: Verify Phase 3 isolation and actuation of cone =4 - nt spray at 3 pais contm4-nt pressure if not done previously.

3.7 Place sesam dump centrol in " Pressure Mode" when NC Pressure and temperatura have stabilized.

3.8 If it is desired, reset Main Stesa Isolation and open .he isolation valves for the unaffected steam generators.

NOTE: Open MSIV bypass valves for unaffected S/G's and equaliza pressure befora opening Main Staam Isolation valves.

3.9 Isolata anC 4 =7 feedvater to the affected steam ganarator and control anr d !'ary feedvatar to the unaffected steam generators at no-load level

(=25%).

NOTE: Depress the Train "A" and Train "3" CA modulating valves rasets in order to regulate flow to -Ja steam generators.

3.10 If Phase 3 conc =4 - nc isolation has occurred and cour=4 - nc pressure is less than 3 psig, reset both trains of Phase 3 isolation and Train "A" and Train "3" Main Staam PORY resets if there is reasonable assurance that cont =4 - nt pressura vill not aga1= increase above 3 psig. Stop NS pumps lA and 13 and close the following valves:

INS-32A (NS Puusp 1A Disch. Cont =% =nt Isol. Outside)

INS-29A (NS Pump 1A Disch. Conen4-nc Isol. Outsida) 1NS-153 (NS Pump 13 Disch. Contmi-nt Isol. Outside)

INS-123 (NS P.uno 13 Disch. Cont =4-ett Isol. Cutside) 3.11 Open:

1KC-338-B (NC Pussp Supply Header Pent. Isol. Outsida) y l

1KC-424-3 (NC Pump Return Header Pent. Inside Isol.)

1KC-425-A (NC Pump Return Header Pent. Outside Isol.)

1KC-230-A (Train lA to R3 Non-Ess. Supply Edr. Auto Isol.)

and 1KC-3-A (Raacen 31dg. Non-Ess. Return Auto Isol.)

and/or lIC-228-3 (Train 13 to R3 Non-Ess. Supply Edr. Auto Isol.)

and 1KC-IS-3 (Reactor 31dg. Non-Ess. Return Auto Isol.)

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

_3 3.12 Open:

1RN-40-A (Non-Essential Header Supply 1A Isel.)

1RN-252-B (Non-Essential Header Supply to RB Pent Outside Isol.)

1RN-253-A (Non-Essential Header Supply to RB Pent. Inside Isol.)

1RN-277-B (Non-Essential Return from R3 Pent. Outside Isol.)

1RN-276-A (Non Essential Return from RB Pent. Inside Isol.)

3.13 When primary system temperatura, pressure and pressurizer level have stabilized reset the SI signal and the D/G load sequencers per one of the following steps:

3.13.1 If NC Hot Legs wide range temperature are >350*F, reset SI and stop ECCS pumps as necessary if:

Pressurizar pressure >2000 psig and stable or increasing, and:

Pressurizer level >20%, and:

At least one S/G has an indicated level in the narrow range, and:

NC Systsm is subcooled by >32*F.

CAUTION: Manually re-ins:iate safety injection if pressurizar pressura decreases by 200 psig or level decreases by 10" or Th is greater than 618*7.

3.13.2 If NC Hot Legs wide range temperatures ara <350*T, reset SI and stop ECCS pumps as necessary if:

Pressurizar pressura 700 psig and stable or increasing and:

Pressuriser level >20I, and :

At least one S/G has an indicated level in the narrow range, and: .

NC System is subcooled by >32*?.

NOTE: Manually re-initiate safety injection if pressurizar pressure decreases by 200 psig or level decreases by 10I or Th is greater than 350*F.

3.14 If for any reason all reactor coolant pumps are tripped, ensura that core decay heat is being removed by natural circulation.

Refer to OP/0/A/6150/14 (Decay Heat Removal by Natural Circulation) .

3.15 Start three upper and lower conten==nt ventihtion units.

3.16 Reset the control patmissive fer recirculation mode 1NI-184-B and 185-A.

3.17 Stop one of the Operating Centrifugal Charging Pumps.

3.18 Open: INV-150-B (Cancrifugal Charging Pumps Recirc.)

INV-151-A (Centrifugal Charging Pumps Recirc.)

3.19 Clase: 1NI-4-A (3.I.T. Inlet Isolation)

INI-5-B (3.I.T. Inlet Isolation)

INI-9-A (3.I.T. Discharge Isol.)

INI-10-B (3.I.T. Discharge Isol.)

3.20 Align the Centrifugal Charging Pump to take a suction from the volume Control Tank:

Open: INV-141-A (Volume Control Tk. #1 Outlet Isolation)

LW-142-B (Volume Control Tk. #1 Outlet)

Close: LW-221-A (Centrifugal Charging Pumps Suction from FW System)

LW-222-B (Centrifugal Charging Pumps Suction from FW System) 3.21 Throttla LW-238 (Centrifugal Charging Pumps Disch. Control) as necessary to supply '8 gym seal injection flow to each Reactor Coolant pump.

3.22 Stop the operating ND & NI pumps.

3.23 Energisa pressuricar heaters to aintain steam bubble. ]

3.24 Raset Phase "A" and verify that containmant monitors 1 EMF-38 (Con e=4 ment ,

I Particulata-Low Range), lEMF-30 (Containment Gas-Low Range) and 1 EMF-40 1 (Containment Iodina-Low Ranga) are not in an alarm condition. Raset the Conrndnment Ventilation isolation signals.

3.25 Notify Chemistry for sampla of NC System Baron Concentration f:cm the unaffected loop and verify shutdown margin per OP/0/A/6100/06 (Reactivity Balance Calculation).

3.26 Establish Instrument Air flow to Containment by opening:

NOTE: After opening each valve listad, allow tha Instrument Air Header Pressure to stab 11:a before opening the next valve.

1VI-129-B (Essential Supply from Tank "lA" Cont. Isol.)

~

171-160-B (Essential Supply from Tank "13" Cont. Isol.)

171-148-B (Non-Essential Upper Contain==nt Supply Cont. Isol.)

17I-150-3 (Non-Essential Lower Cone =4nmanc Supply Cont. Isol.)

IVI-362-A (Instrument Air to Rx Bldg. Annulus ! sol.)

3.27 Establish Component Cooling Water flow to the An # 47 Building Non-Essential Baader as follows:

Open the follewing valves:

1KC-1-A (Aux. Bldg. Non-ess. Return Auto Isol.)

1KC-2-B (Aux. Bldg. Non-ess. Return Auto Isol.)

Close the following valves:

1KC-56-A (ND HI 1A Auto Supply) 1KC-81-B (ND EI 13 Auto Supply)

As flow decreases, open:

1KC-30-A (Train lA to Aux. 31dg. Non .ss.

1KC-33-B (Train 13 to Aux. Bldg. Non-ess. Supply Edr. A no ! sol.)

3.2S Establish Nuclear Satvita water flow to Auxiliary Building as follows:

Open:

133-42-A (A3 Non-Essential Supply Isoi.)

1RN-63-B (AB Non-Essential Return Isol.)

1RN-64-A (AB Non-Essential Return Isol.)

3.29 F.stablish Seal Water Return by opening:

LW-94-A (N.C. ? umps Seal Return Contmimanet Isol. Insida)

LW-95-B (N.C. Pumps Seal Return Containment Isol. Outside)

NOTE: If Seal Injection flow was lost, slowly adjust LW-238 to prevent thermal sheck to the pump parts.

3.30 Close LW-241 (Ragena:*etive EI #1 Tube Inlet Control) 3.31 Open:  ;

1NV-244-A (Charging Line Conem n==at Isol. Outside) e LW-245-B (Charging Line conc =4mnant Isol. Outsida) 3.31 Establish the normal charging flow path by slowly throttling open 1NV-241 (Regenerative EI #1 Tube Inlet Control).

NOTE: As 1NV-241 is opened, adjust LW-238 as necessary to maintain Seal Injection flow.

3.33 Establish Latdown by opening in order as listad:

l LW-1-A (N.C. Latievn Isolation to Regenerative HI #1)

LW-2-A (N.C. Lacdown Isolation to Regenerative EI #1)

INV-7-B (Landown Cone ='n==nc Isolation Outside)

INV-459-A (High Pressura Latdown Control) NOTE: Open Slowly.

Afcar letdown line is warmed up, open NV-458-A (75 gym Lecdown Ori. fica Outlet Containment Isol.) and/or NV-457-A (45 spm Lacdown Orifica Outlet Cone =4n==at Isol.) and close LW-459-A (High Pressure ,

Landown Control).

3.34 Verify LW-124 (Low Pressure Latdown Control) is modulating to maintain Latdown Pressure at ~350 psig.

3.35 If stopped, start the M. Pump in the unaff ected "A" or "3" Loop per OP/1/A/6150/02A (NC Pity Operation).

3.36 Perform a Reactivity M ance per OP/0/A/6100/06 (Reactivity 3alance Calculation) and verify shutdown nargin equivalent to >1% 1K/K at 200*P. If necessary, borata the NCS per CP/1/A/6150/09 (3cron Con-centration Control).

3.37 3agin cooldown and depressurization per OP/1/A/6100/02 (Controlling Procedure for Unit Shutdown), while keeping the affected S/G isolated.

3.38 Refer to EP/0/A/5000/31 (No-dfication of Unusual Events).

3.39 If D/G is no longer required, and has been running >,1 hr., shutdown per OP/1/A/6350/02 (Diesel Generator).

3.40 Realign the following for sc,rsal operation when desired:

NI per OP/1/A/6200/06 (Safety Injection Systam)

VC per OP/0/A/6450/11 (Control Room Air Conditioning and Ventilation)

VJperOP/0/A/6450/$4 (Computer Room 7entilatica Systa=)

3B per OP/1/A/6250/08 (Steam Generator Slowdown Systi:) for unaffected generators only.

NV per OP/1/A/6200/01 (Chemical and Volume Control System)

PRT per OP/1/A/6150/04 (Pressurizar Relief Tank)

NCDT per OP/1/A/6500/01 (L* W d Wasta Recycle System)

KC per OP/1/A/6400/Cs (Component Cooling Water System)

RN per OP/1/A/6400/06 (Nuclear Service Water System)

Contain= ant Ventilation per OP/1/A/6450/01 (Cont =4 - ne Ventilation)

KF per OP/1/A/6200/05 (Spent Fuel Cooling System)

N7 per OP/1/A/6200/18A (Ice Condenser Refrigeration System)

FW per OP/1/A/6200/14 (Rafueling Water System)

VS to cour=4 - nt: Open IVS-12-B (Station Air to Unit #1 Cont 24 - nt Outside Isol.).

YM to contmi-nt: Open 151-115-B (Contadnment Outside Isol.)

NM per OP/1/A/6200/11 (Nuclear E nitoring and Sampling System)

Start three control rod drive ventilation fans.

l 0 Recuired Action for Feedline Rupture Unstream of Feedline Conta4nmaet Penetration 4.1 Monitor operation of pressurizar code safety valves to remove decay heat.

4.2 If any pressurizar PORV's open on high pressurizer pressure, ensure ressating at 2315 psig decreasing.

4.3 Announce the occurrence over plant paging system.

4.4 Place Stasa Dump Control in " Pressure Mode" whan NC Pressure and camperature have stab 111:e'd.

4.5 If it 'is desired, reset Main Steam Isolation and open the isolation valves for the unaffected steam generators.

NOTE: Depress the Train "A" and Train "B" CA modulating valves resets in order to regulate flow 'to the steam generators and depress Train "A" and Train "3" Main Steam PORV resets to enable use of SM PORV's.

Open MSIV bypass valvas for unaffected S/G's and equalise pressure before opening Main Steam Isolation Valves.

4.6 Isolate anrd7d=ry feedvatar to the affected steam generator and control 1

auxiliary feedvatar to the unaffected steam generators at no-load level <

( 25%).

4.7 'Aen primary system camperature and pressure have stablized and pressurize level has returned, reset the SI signal and the D/G load sequencers per :ne of the following steps:

4.7.1 If NC Hot Legs wide range :amperatures are >350*7, reset SI and stop ECCS pumps as necessary if:

Pressuriser pressure >2000 and stable or increasing, and:

Prassuri:e level >20%, and rising and:

i At least one S/G has an indicated level in the narrow range and:

NC System subcooled by >32*?.

CAUTION: Manually re-initiate safety injection if pressurizar pressura decreases by 200 psig or level decreases by 10% or Th is grutar than 618'F.

4.7.2 If NC Hot Legs wide range temperatures are <350*F, reset SI and stop ECCS pumps as necessary if:

Pressurizar pressure 700 psig and stable er increasing and:

Pressurizar level >20%, and rising and:

NC System subcooled by >32*7 and:

At least one S/G has an indicated level in the narrow range.

CAUTION: Manually re-initiate safety injection if pressurizer pressura decreases by 200 psig or level decreases by 10% or Th is greater than 350*F.

4.7.3 Reset the control per=1ssive for recirculation mode 1NI-184-B and 185-A.

4.7.4 Stop one of the operating Centrifugal Charging pumps.

4.7.5 Open: INV-150-3 (Centrifugal Charging Pumps Racire.)

t INV-151-A (Centrifugal Charging Pumps Racirc.)

4.7.6 Close 1NI-4-A (B.I.T. Inlet Isolation)

INI-5-B (B.I.T. Inlet Isolation) 1NI-9-A (B.I.T. Discharge Isolation)

INI-10-B (3.I.T. Discharge Isolation) 4.7.7 Align the Centrifugal Charging Pump to *Jun a suction from the Volume Control Tank:

Open: INV-141-A (7olume Control Tk. #1 Outlec ! solation) 1NV-142-3 (Volume Control Tk. #1 Outlet)

Close: INV-221-A (Centrifugal Charging Pumps Suction from FW System) 1NV-222-B (Centrifugal Charging Pumps Suc:1on from PW System) 4.7.8 Throttle 1NV-238 (Centrifugal Charging Pumps Disch. Control) as necessary to supply 'S gym seal injection flow to each Reac:or Coolant Pump. 1 4.7.9 Stop any operating ND & NI pumps.

4.7.10 Energize pressurizar heat.ars to maintain steam bubble.

4.3 Rese: Phase "A" Isolation and verify that contahment monitors 1 EMF-38 (Containment Particulate-Low Range), IIMF-39 (Containment Gas-Low Range),

and lIMF-40 (Contai-mant Iodine-Low Range) are not in an alar = condi: ion.

Rese: the Con nSmen: "antilation isolation signals.

4.9 Notify Chemistry for sample of NC System Boron Concentration from an unaffected loop and verify shutdown margin per OP/0/A/6100/06 (Reactivity Balance Calculation).

4.10 Establish Instrument Air flow to containment by opening:

NOTI: After opening each valve listed, allow the Instrument Air Header Pressure to stablize before opening the next valve.

171-129-B (Essential Supply from Tank "1A" Cont. Isol.)

lVI-160-B (Essential Supply from Tank "13" Cont. Isol.)

17I-148-B (Non-essential Upper Cont =4n==nt Supply Cont. Isol.)

1VI-150-B (Neu-essencial Lower Containment Supply Cont. Isol.)

171-362-A (Non-essencial Lower Cont =4nment Supply Cont. Isol.)

4.11 Roset Train "A" and Train "3" modulating valve resets.

4.12 Establish Component Cooling Water flow to the Aur1H = y Building Non-essential header as follows:

Open .he following valves:

lIC-1-A (Aux. Bldg. Non-ess. Return Auto Isol.)

IIC-2-B (Aux. Bldg. Non-ess. Return Auto Isol.)

Close the following valves:

1EC-56-A (ND EI la Auto Supply) 1KC-81-B (ND HI 13 Auto Supply)

As flow decreases, open:  ;

1KC-50-A (Train lA to Auz. Bldg. Non-ess. Supply Edr. Auto Isol.)

1KC-53-B (Train 13 to Aux. Bldg. Non-ess. Supply Edr. Auto Isol.)

4.13 Establish Seal Water Return by opening:

UN-94-A (N.C. Pumps Seal Return Containmaet Isol. Inside)

INV-95-B (N.C. Pumps Seal Return Concal.iment Isol. Outside)

NOTE: If Seal Injection flow was lost, slowly adjust 1NV-238 to prevent charmal shock to the pump parts.

4.14 Close UN-241 (Regenerative EI fl Tube Inlet Control) .

4.15 Open:

INV-241.-A (Charging Line Containment Isol. Outside) 2;V-245-B (Charging Line Cont =4 mant Isol. Outside) 4.16 Est(blish the normal charging flow path by slowly throttling open 1NV-241 (Regenerative EI 91 Tube Inlet Control).

NOTE: As 1NV-241 is opened, adjust UN-238 as nacessary to naintain l Seal Injection Flow.

4.17 Establish Lecdown by opening in order as listed:

INV-1-A (N.C. Letdown Isolation to Regenerative EI 41)

INV-2-A (N.C. Letdown Isolation to Ragenerative EI #1)

UN-7-B (Letdown Cont =4 ment Isolation Outside)

EN-439-A (High ?ressure *.ettown Control) NC I: Cpen slowly.

- w

)

After letdown line is warmed up open NV-458-A (75 gym Letdown Orifica j Outlat Contm4-nt Isol.) and/or NV-457-A (45 gpa Lerdown orifica outlet Conemit = nt Isol.) and close INv-459-A (High Pressure Letdown Control).

4.18 Verify INV-124 '(Low Pressure Lerdown Control is modulating to maintain Letdown Pressure at approximately 350 psig.  !

4.19 Open *.he following valves:

1RN-63-3 (AB Non-Essential Return Isol.)

1RN-64-A (AB Non-Essential Return Isol.)

1RN-42-A (AB Non-Essential Supply Isol.)

1RN-40-A (Non-Essencial Header Supply 1A Isol.)

4.20 If D/G is no longer required and has been running ,

>,1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, secure the diastl l generators per OP/1/A/6350/02 (Diesel Generators).

4.21 If stopped, start the NC Pump in the unaffected "A" or "3" Loop per l CP/1/A/6150/02A (NC Pump Operation).

4.22 Perform a Reactivity Amlanca per CP/0/A/6100/06 (Ranctivity Salance Calculation) and verify shutdown margin >l". ik/k at 200*F. If necessary j borata the NCS per OP/1/A/6150/09 (Boron Concentration Control).

., 4.23 Begin cooldown and depressurization per OP/1/A/6100/02 (Controlling Procadure for Unit Shutdown).

4.24 Refer to IP/0/A/5000/32 (Alert).  ;

4.25 Realign the following for nor:nal operation when desired: l N! per OP/1/A/6200/06 (Safety Injection Systam) l VC per OP/0/A/6450/11 (Control Room Air Conditioning and Ventilation)

VJ per OP/0/A/6450/14 (Computer Room Ventilation System)

BB per OP/1/A/6250/08 (Steam Generator Slowdown System) for unaffected Steam Generators only.

NV per OP/1/A/6200/01 (Chemical and Volume Control System)

PRT per OP/1/A/6150/04 (Pressurizar Relief Tank)

, NCDT per OP/0/A/6500/01 (Liquid Wasta Racycle System) i KC per OP/1/A/6400/05 (Component Cooling Water System)

RN per OP/1/A/6400/06 (Nuclear Service Water System)

Containment Ventilation per OP/1/A/6450/01 (Contai - nt Ventilation)

KF per OP/1/A/6200/05 (Spent Fuel Cooling Systan)

NF per OP/1/A/6200/18A (Ice Condenser Refrigeration System) ,

FW per OP/1/A/6200/14 (Rafueling Ware.c system)

VS to Containment: Open IVS-12-3 (Scaion Air to Unic #1 Containment Outside Isol.)

YM to Contai-nt: Open l!M-l'.5-3 (Containment Outside Isol.)

NM per OP/1/A/6200/11 (Nuclear Monitoring and Sampling Syscam) l I

i

-- e- ,,m.- - + - ---1