ML19323D023

Emergency Operating Procedure EP/1/A/5000/04, Steam Generator Tube Failure.

ML19323D023
Person / Time
Site:	Mcguire, McGuire
Issue date:	02/15/1980
From:	Frye S, Mccraw N DUKE POWER CO.
To:
Shared Package
ML19323D015	List: ML19323D014 ML19323D018 ML19323D019 ML19323D023 ML19323D031 ML19323D033
References
EP-1-A-5000-04, EP-1-A-5000-4, NUDOCS 8005190546
Download: ML19323D023 (13)

Text

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Form SPD-1002-1 DUEI POWER CCMPANT (1) ID No: EP /1/ A /5000 /0L PROCEDURE PREPARATION Change (s) O to j

PROCESS RECORD 6 Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE: Steam Generator Tube Failure (4) PREPARED BY: Steve Frye DATE: 2/14/80 (5) REVIEWED BY: # N 6LcO~ DATE: 24 6 -8d Cross-Disciplinary Review 3 7: N/R: Nr?

(6) TEMPORARY APPROVAL (IF NECESSARY):

Sy: (SRO) Date:

Sy: Date:

(7) APPROVED BY: W,L- (#

y Date: f "/f' IO u

(8) MISm TangCUS:

Reviewed / Approved 3y: Date:

Reviewed / Approved.By: Date:

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INFORM \ TION ONLY 1

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EP/1/A/5000/04 DUKE POWER COMPANY McGUIRE NUCLEAR STA!!CN STEAM GENERATOR TU3E FAILURE CASE "I": Tube Leak within the Capability of Both Centrifugal Charging Pumps CASE "I!": Majcr Tube Rupture cygg nzu TUBE LEAK k r.IN THE CAPABILITY OF BOTE CINTRIFUGAL CHARGING PUMPS 1.0 Svmotoms 1.1 lEMF-33 "Cond. A.E. Exh. E1 Gas Rad." alarm.

1.2 lEMF-34 "S/G Sample Ei Rad" alarm.

1.3 7CT level decrease or abnormal increase in frequency of auto makaup.

1.4 Possible pressuri:er level decrease initially.

1.5 Possible pressuriser pressure decrease initially.

2.0 I:mnediate Action 2.1 Automatic 2.1.1 Charging flow increaeos.

2.1.2 Pressurizar backup heaters energi:e.

2.1.3 Possible S/G blowdown isolation.

2.2 Manual 2.2.1 Insure all automatic actions occur.

2.2.2 If pressurizer level is decreasing or if nor=al charging is at max 1= rum flow, change letdown from 75 gpm orifice to 45 gym orifice.

2.2.3 Start addi.icnal charging pumps as necessary to maintain pressurizar level.

2.2.4 Isolate all UEI Acetunulator discharge valves.

3.0 Subsequent Action CAUTION: Do not place systems in manual unless misoperation in automatic is apparent. If any system is placed in manual, =ake frequent checks for proper operation.

3.1 Announce occurrence over plant paging system.

3.2 If for any reason press trizar level cannot be :naintained open all UE!

Accumulator discharge va.'ves, manually initiate SI and refer to CASE !!

of t.Ms procedure.

l 3.3 If for any reason all reactar pumps are tripped, ensure that core decay i

heat is being removed by natural circulation. Refer to OP/0/A/6130/la (Decay Heat Removal 3y Natural Circulation) .

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3.4 Iden:ify the affec:ed steam generator by:

l Increase in effected S/G 1evel.

Increase in affec:ed S/G pressure.

Decrease in CF flow to affected S/G or in accordance with OP/1/3/6250/08 (Sceau Genera:or 31cwdown).

3.5 Determine the leakage race by perfor:ning PT/0/A/4150/013 (Reactor Coolant System Leakage Calculation) and sfer to McGuire Station Technical Specifica:Lons (3.4.6.2) for appropriate actions.

3.6 When it is determined which Steam Generator is affected notify Chemistry :o determine activi:7 level and leakage race in affected Steam Generator per CP/0/3/8100/45.

3.7 Align the affected Steam Generator to the Steam Generator Slowdown Recycle System per OP/1/3/6250/08 (Steam Genera:or Slowdown) and notify Chemistry of potential input to Rad Wasta System.

3.8 Align the unaffected Steam Generators for normal blowdown per OP/1/3/

6250/08 (Steam Generator 31cwdown) .

3.9 Refer to McGuire Technical Specifications (3.7.1.4)- and deter d*e i'**:s im-posed by secondary coolaut activity level and pri: nary to secondary leak race. '

3.10 Refer to EP/0/A/5000/31 (Notification of Unusual Events).

3.11 Notify Heal:h Physics to determine ac:ivi:7 released from :he air ejec-cors and/or steam relief actuation.

3.12 If gaseous release linics (10C7R-20, Appendix 3) have been exceeded 1:nple-men: EP/0/A/5000/34 (General Emergency).

3.13 If necessary, shutdown and cooldown per OP/1/A/6100/02 (Controlling Procedure for Uni: Shutdown).

CASE "II" MAJOR TU3E RUPTURE 1.0 Symptoms 1.1 Rapid decrease in pressurizer pressure and level.

i 1.2 Pressure and level increasing in affec:ed Steam Generator.

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1.3 Steam loop flow /C7 flow mismatch.

1.4 "1 EMF-3 s/G Sample Hi Rad" al?.r=.

t t 1.5 "1 EMF-33 Cond. A.I. Exh. E1 Gas Rad" alar =.

I 2.0 I::nnadia:c Action 2.1 Au:omatic 2.1.1 Safety Inj ection Actuation and Phase "A" ! scla:icn.

( 2.1.2 Reactor Trip-Turbine Trip.

2.1.3 S:aa= Genera:or 31cwdown ! solation.

2.1.4 I/S Sequencer ac:na:icn.

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2.1.5 CA Pumps star: and feed steam generators.

2.1.6 Feedvater icolation.

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2.2 Manual 2.2.1 Ensure all au:omatic actions occur.

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

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

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

2.2.5 Verify all pressurizer PORV's are closed.

! 3.0 Subsecuent Action CAUTION: Do not place systems in manual unless misoperation in automatic is apparent. If sly system is placed in manual, make frequent checks for proper ept. ration.

3.1 Verify all Emergency Core Cooling components have assumed : heir safeguards status. Manually align any that did not.

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3.1.1 During Upper Head Injections Groups 3 & 4 completely lighted, Groups 1, 2, 5, 6, & 7 completely dark.

3.1.2 After Upper Head Injection Groups 3, 4, & 6 completed lighted, Groups 1, 2, 5, & 7 completely dark.

3.1.3 If either train of the 30P ES7 Components =eni:or lights in Group 1 and Group 4 are out of sequence w1:h :he other lights in : heir respective group, the OAC cust be interrogated to obtain a printout of misa11gned 30P IST Components.

NOTE: If :he Phase A Contmi nan: Isolation Monitor 'ights are also out of sequence, manually ini:iate Phase A Cont =1 = ant Isola: ion.

3.2 Trip :he reae:or coolant pumps if SI actuated before r2 aching 1250 psig.

3.3 f.nnounce occurrence over plant paging system.

3.4 Identify :he affected steam generator by:

Rapid increase in affec:ed S/G 1evel.

Rapid increase in affected S/G pressure.

CAUTION: If the affec:ed Steam Generator is "3", unlock and close ISA-2 .

(Main Steam 13 :o Aux. FDWPT No. 1 Maintenance Isolation). If the affected Steam Generator is "C", unlock and close 1SA-1 (Main Steam IC to Aux. FD'4PT No.1 Main:enance Isola: ion) .

3.5 Secure all feedwa:er flow to the affec:ed Steam Generator and : rip NC P,:=o in affec:ed loop.

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_4 3.6 Control Aur'11ary feedwater :o the unaffec:ed steam generators and mm'ntain no-load level ( 25").

NOTE: Depress :he Train "A" and Train "B" CA modulating valves rese:s in order to regulate flow to the steam generators.

3.7 If the OAC is inoperable, perfor= 30P ESF Components alignment checklist.

Enclosure 4.1.

3.8 Reset the SI signal the D/G load sequencers and Phase "A" ! solation.

NOTE: Reset Train "A" and Train "3" modulating valve resets.

3.9 Immediately commence Reactor Coolant System cooldown per OP/1/A/6100/02, (Controlling Procedure for Uni: Shutdown). If Reactor Coolant Pumps are off, depressurizer through the Auxiliary Spray or Power Operated Relief Valves as necessary.

3.10 'When Reactor Coolant System pressure is <J100 psig. , close che main Sceam Isolation valve for :he affac:sd loop.

NOTE: Pressurizar heaters can be energized as necessary to maintain NCS Pressure.

3.11 Utill:e Main Steam Isolation Valve 3ypass en affected S/G =c preven:

overpressurization.

3.12 Verify the power operated relief valve for affected S/G is closed.

3. 3 If for any reason all reac:o coolan: pumps are tripped, ensure that core decay heat is being removed by natural circulation. Refer :o OP/0/A/6150/14 (Decay Heat Removal by Natural Circulation).

3.14 Star: :hree upper and lower con ==4 - n: ventilation uni:s.

3.15 Reset the con::ci permissive for recirculation mode 1NI-184-3 and 1N M 85-A.

3.16 Reset the containment ventila:1on isolation signals.

3.17 Notify Heal:h Physics to determine activi:y released from the air ejectors and/or steam relief actuation.

3.18 Refer :o EP/0/A/5000/32 (Alert).

3.19 Realign systems :o normal when condi: ions warrant.

3.20 If gaseous release id*:s (10C7R-20, Appendix 3) have been exceeded implement EP/0/A/5000/34 (General Emergency).

3.21 Notify Chemistry to determine :he extent of contamina:ica to :he secondarf systam. Refer to Technical Specifications (3.7.1.4).

3.22 Notify Cham.stry to constantly moni:or NC Sys:em boron concentration to ensure that dilu:icn does not occur due :o S/G draining into NC System.

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