ML20205S689

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Rev 4 to Emergency Operating Procedure EOP-01-EPP-2B, End Path Procedure 2B
ML20205S689
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/08/1988
From: Bishop E
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20205K904 List: ... further results
References
EOP-01-EPP-2B, EOP-1-EPP-2B, NUDOCS 8811110140
Download: ML20205S689 (8)
v • d • e


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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 END PATH PROCEDURE 2B EMERGENCY OPERATING PROCEDURE: E0P-01-EPP-2B VOLUME VI Rev. 004 Q .

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$'J Approved By: /- / tr/) Date: I TY

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LIST OF EFFECTIVE PACES E0P-01-EPP-2B Page(s) Revision 1-2 4 1

3 2 4 3 5 2 6-7 4 8 2 f

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i BSEP/Vol. VI/EOP-01-EPP-2B Page 2 ef 8 Rev. 4 t . _ _ _ - - - , -

F A. TITLE - End Path Procedure 2B i B. ENTRY CON'DITION Yhis procedure is entered fron Fievpath 2, 3, 4. OR~~

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f rom the "

Contingsney section of this End Path Manual.

C, OPERATOR ACTIONS ,

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CAUTION P DO~

!;0T SECURE or PLACE an ECCS or RCIC in manual mode UNLESS by at least two 1 dependent indications

1. Misoperation in the automatic mode is confirmed. OR i
2. Adequate core cooling is assured.

IF an ECCS or RCIC is placed in the manual mode, it vill NOT initiate automatically. MAKE frequent checks of the initiating or controlling  !

parameter, kHEN t snual operation is tio longer required, RESTORE the system to automatic / stand'; mode if possible.

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1. RESTORE and MAINTAIN reactor vessel level between +170 and +200 ,

inches. USE one or more of the following systems in an order that vill minimize high eenductivity feed to the reactor: {

RPV Pressure Range  !

System for System Operatio.' I

a. Condensate 200-0 psig ,
b. Condensate / booster 350-C psig
c. Feed pumps 1250-0 psig  ;
d. CRD 1490-0 psig
e. RCIC 1190-62 psig [

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f. HPCI 1280-120 psig [

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g. RHR 200-L psig [
h. Core Spray 300-0 pstg i i

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BSEP/Vol. VI/EOP-01-EPP-2B Page 3 of 8 'ev. 2 i

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2. IF the CRD Drive Water Pressure Control Valve, C11(C12)-F003, and the in-service CRD Flow Control Valve, C11(C12)-F002A(F002B), have been opened to maintain reactor vessel level b3D the CRD System is no longer needed to maintain reactor vessel level, THEN PERFORM the following steps to restore the CRD System to normal operations

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a. SET the setpoint tape on CRDHS Remote Flow Controller, '

C11(C12)-FC-R600, to 100 spm.

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b. SHIFT the CRDHS Remote Flow Controller, C11(C12)-TC-R(00, to '

the "AUT0" position.

c. IF both CRD pumps are running THEN STOP one CKD pump.

/ d. OPEN and LOCK OPEN CRD Pump Condensate Return Isolation Valve. l Ind. Ver. COR-V1 (located at CST). I

/___ e. IT Charging Water Header Throttle Valve, C11(C12)-T034, was Ind. Ver. manipulated to maximize CRD flow, THEN CLOSE and IMMEDIATELY l RIOPEN al turns Charging Vater Header Throttle Valve.

C11(C12)-T034.

f. SET the setpoint tape on CRDHS Remote Flow Controller, C11(C12)-FC-R600, to between 30 and 80 gpm.
g. ESTABLISM a drive water 1.aader differential pressure betweei; i 260 and 275 paid, as read on C11(C12)-PDI-R602 on RTGB Panel P603, by throttling closed Drive Vater Pressure Control Valve,  ;

C11(C12)-F003.

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/ h. IF CRD Pumps Suction Filters Bypass Valve, CO-V306, is open, and. Ver. THEN VERIFY a CRD pump suction filter is in service and CLOSE the CRD Pumps Suction Filters Bypass Valve, CO-V306.

I 1. IF both CRD pump suction filters are in service, THEN ISOLATE and RFPLACE the filter which has the highest dP.

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j. IF both CRD drive water 111tsts are in service. THEN ISOLATE and REPLACE the filter which has the highest dP.

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3. ENTER the Containment Control section of this End Path Manual and EXECUTE it concurrently with this procedure.

l 4. IT while executing this procedure, reactor vessel level CANNOT be determined OR reactor vessel flooding is required, THEN EXIT this End Path Procedura and ENTER the "Flooding Procedure" in the Contingency secti n of this End Path Manual.

5. IF reactor vessel level CANNOT be maintained above +170 inches THEN KAINTAIN reactor vessel level above 0 inches.
6. IF reactor vessel level CANNOT be maintained above 0 inches THEN EXIT this End Path Procedure and ENTER the "Level Restoration Procedure" in the Contingency section of this End Path Manual.

BSEP/Vol. VI/EOP-01-EPP-28 Page 4 of 8 Rev. 3

i 7 IF while executing this procedure, reactor depressuritation is required. THEN PERFORM the following steps e*******e******e****************************ee*****e*****************enenennes CAUTION DO NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps suf ficient to EIintain reactor vessel level are running and available for injection, eeeeeeeee**e.eee*****ene*********e ********eae*******eeeeee******ene**e**enene

a. IF the MSIVs are open. THEN RAPIDLY DEPRESSURIZE the reactor with the bypass valve opening jack,

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b. IF the reactor CANNOT be dep.essurized to the main condenser.

TREN mae*; ally OPEN all ADS valver.

, (1) IF any ADS

  • CANNOT be opened. THEN OPEN SRVs UNTIL seven valves

, open.

4 (2) IF less than three SRVs are open AND reactor pressure is l greater than 50 psig above suppreIsIon chamber pressure.

THEN ENTER the "Erergency Depressuritation Procedure" in

, the Contingency sectien of this End Path Manual and EXECUTE it concurrently with this procedure.

c. CONTINUE in this procedure at Step 10.
                                                                • ene**eeeee**e2 ***** *************************

CAUTION IF fuel failure is suspected. DO NOT REJECT RVCU to hotwell.

IF an automatic isolation of a particular system has occurred. DO NOT attempt to deisolate or restore the systen UNTIL all available indications have been checked and are found to be normal.

i DO NOT DISPATCH personnel to an area of a suspected break without consideration of adverse environments.

neeeeeeeeeeeeeeeeeeeee*** **eeeeeeeeeee**eemene**********ene****************
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8. w aintain reactor pressure below 350 psig with one or more of the following systems:

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a. HPCI (in full flow test mode)

, (

b. RCIC (in full flow test mode)
c. Main Steam Line Drains
d. RVCU
e. Feed Purps (in recirculation mode)

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f. SJAEs (in full load) 1 BSEP/Vol. VI/EOP-01-EPP-25 Page 5 of 8 Rev. 2

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j CAUTION I g NOT DEPRESSURIZE below 120 psig UNLESS actor-driven pumps suf ficient to l

maintain reactor vessel level are running and available for injection.

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9. IF reactor pressure CANNOT be maintained below 350 psig with the '

l above systems AND continuous pneumatic supply is available to the i

) SRVs THEN OPEN SRVs as necessary to maintain reactor pressure below i i 350 psig. USE opening sequence B F. E, C, A. C. J. H, and D. ll j 4 i l 10. IF a break outside primary containment is suspected, THEN PERFORM (

the following stepst j L

a. ISOLATE the break by remote or manual operation of the affected j

. valves. L i

b. REFER to AOP-01.1.  :

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11. IF SJAE, stack, or MSL radiation monitors indicate fuel failure. I TIIEN PERFORM the following stepst f

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a. NOTIFY E&RC to sample coolant.

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b. MONITOR ARMS stack, and ventilation radiation monitors. l
c. IF high radiation or high airborne conditions exist, THEN REFER j

to AOPs 05 through 06. i PLACE the following valve control switches to "CLOSE."  !

d.

(1) DW FLOOR DRAIN INBD ISOL VLV G16-F003 L l _

(2) DW FLOOR DRAIN OTBD ISOL VLV, C16-F004 i

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(3) DW EQUIP DRAIN INBD ISOL VLV, G16-F019 (4) DW EQUIP DRAIN OTBD 150L VLV, G16-T020 l _

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e. NOTIFY Radwaste to place the Reactor Building equipment drain j pump into the recirculation mode.

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f. DO NOT OPERATE the mechanical vacuum pumps.  !

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12. IF_ condensate booster pump suction conductivity is greater than 0.3 paho, TH E PERFORM the following stepst  ;

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a. RDt0VE af fected water boxes f rom service. {

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BSEP/Vol. VI/EOP-01-EPP-2B Page 6 of 8 Rev. 4 l

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b. REALIGN CFDs and CDDs to provide better ion removal.
c. IF the Condensate /Feedvater System is NOT required to maintain reactor vessel level. THEN PLACE the Condensate System in the [

long cycle cleanup mode.  ;

d. DO NOT REJECT the hotwell to the CST.

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e. REFER to A0P-26.0. I L
13. IF while executing this procedure, any of the following systems fail j or have failed, THEN ENTER the associated procedure in the System  ;

Recovery section of this End Path Manual and EXECUTE it concurrently l with this procedures i

a. Conventional Service Water  ;
b. Nuclear Service Water j i t
c. Reactor Building Closed Cooling Water  !

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d. Turbine Building Clesed Cooling Water
e. Instrument Air , (
f. Auxiliary Electrical Power L
14. IF the MSIVs are closed. THEN REESTABL?SH the mair, condenser as a heat sink (OP-25).
15. NOTIFY the SOS to perform the following stepst ll
a. CONSULT PEP, Section 2.1.
b. NOTITY on-call CP&L supervisor. l l _
c. NOTITY NRC per RCI-06.5.
d. NOTIFY E&RC to sample coolant.

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e. IMPLEMENT 01-22. lf !

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16. IF RVN has isolated AND a break in the RWCU System is NOT [

ouspeeved, THEN RESET the Group 3 isolation and RESTART RWCU j j (OP-14).

I 17. IF the reactor recirculation pumps have been tripped. TNEN RESTART  !

j them (OP-02). l f

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13. CONTINUE performing Containment Control, local Emergency, and System [
Recovery Procedures UNTIL the exit conditions for the affected [
procedures are met. [

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I l BSEP/Vol. VI/EOP-01-EPP-28 Page 7 of 8 Rev. 4  !

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19. RECORD reqeired scram information in the Scram Report (OI-22) and Shift togs. l

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20. VRITE Work Request / Job Orders /LCOs to ensure that functional t. ting i is performed on those systems in which jumpers were installed.

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.', WHEN systems that rtquire independent verification for return to service are shut down. THEN PLACE the systens en standby readinena ,

per their respective ops. (Refer to Table l'. 7.1 in Volume I. Book i 1-AP.)  !

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22. IF reactor cool' nm and depressurization are to be commenced per the  !

T3S. THEN ENTER the General Plant operating Procedure and EXECUTE it I concurrently with this procedure.

23. WHENt
a. Reactor vcssel level can be maintained above +170 ine.hes AND j i
b. Raaetor pressure can be maintained below 1045 psig ,

AND  !

e. Primary containment parameters are within the linits specified in the Containment Control Procedure.  ;

I THEN EXIT this procedure and ENTER the appropriate section of the I General Plant Opetating Procedure for hot / standby OR cold shutdown  !

as directed by the SOS.

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l BSEP/Vol. VI/EOP-01-EPP-2B Page 8 of 8 Rev. 2  ;

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