ML20205S799

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Rev 4 to Emergency Operating Procedure EOP-01-EPP-1M, End Path Procedure 1M
ML20205S799
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-1M, EOP-1-EPP-1M, NUDOCS 8811110178
Download: ML20205S799 (8)
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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT i

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END PATH PROCEDURE IM EMERGENCY OPERATING PROCEDURE: E0P-01-EPP-1M VOLUME VI Rev. 004 V0Bk*goOM'.uca'

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Approved By:

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Manager-Operati]ons l

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LIST OF EFFECTIVE PACES E0P-01-EPP-1H Page(s) Revision 1-2 4 3 2 4 3 5-7 4 8 2 i

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BSEP/Vol. VI/EOP-01-EPP-1M 2 of 8 Rev. 4 l

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i A. TITLE - End Path Procedure IM B. ENTRY CONDITIONS All control rods did NOT fully insert following a scram initiation.

Reactor pressure is less than 350 psig. Low pressure systems may be l injecting.

C. OPERATOR ACTIONS

1. IF the reactet CANNOT be shut dewn before supprossion pool temperature reaches 110'F, THEN EXIT this procedure and ENTER the ,

"Level / Power Control" flow path. '

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CAUTION DO NOT SECURE or PLACE an ECOS or RCIC in manual mode UNLESS by at least two ind ep e nd e nt indicationst ,

l. Misoperation in the automatic mode is confirmed. O,R I
2. Adequate core cooling is assured. l IF an ECCS or RCIC is placed in the manual mode, it will NOT initiate automatically. MAKE f requent checks of the initiating or ;ontrolling I.

parameter. VEEN manual operation is no longer required RESTORE the system to I automatic standby mode if possible. i

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2. RESTORE and MAINTAIN reactor vessel level between +170 and +200 inches. USE one or more of the following systems in an order that will minimize high conductivity feed to the reactort i

RPV Prosaure Range I System for Systen Operation '

a. Condensate - - - - - - - - - - - - - - - - - 200 - O psig i
b. Cendensote/ Booster - - - - - - - - - - - - - 350 - O psig

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c. Feed Pumps - - - - - - - - - - - - - - - - - 1250 O psig
d. C RD -------------------- 1490 - O psig i
e. RCIC - - - - - - - - - - - - - - - - - - - 1190 - 62 psig 7
f. HPCI - - - - - - - - - - - - - - - - - - - 1080 - 120 psig r
g. RHR -------------------- 200 - O psig
h. Core Spray - - - - - - - - - - - - - - - - - 300 - O psig BSEP/Vol. VI/EOP-01-EPP-1M 3 of 3 Rev. 2 l I

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3. IF the CRD Drive Water Pressure Control Valve, C11(Cl2)-F003, and tee in-service CRD Flow Control Valve, C11(C12)-F002A(FCO'B) have l been opened to aaintain reactor vessel level b3D the CRD System is no leager needed to neintain 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 gPm.
b. SHIFT the CRDHS Remote Flow Controller, C11(C12)-FC-R600, to the "AU10" position.

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

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/ d. OPEN and LOCK OPEN CRD Pump Condensate Return Isolation Valve.

l Ind. Ver. COR-V1 (lecated at CST). I i

l / e. IF Charging Water Header Throttle Valve, Cll(Cl2)-F034, Ind. Ver. was manipulated to raximiee CRD flow. THEN ClOSE and l l

IMMEDIATELY REOPEN 8) turns Charging Water Header Throttle Valve, C11(C12)-F034.

f. SET the setpoint tape on CRDHS Remote Flow Controller.

l C11(Cl2)-}'vR600, to between 30 and 80 gpm.

l-l g. ESTABLISH a drive water header differential pressure between 260 and 275 psid, as read on C11(C12)-PDI-R602 on RTGB Panel P603, by throttling closed Drive Water Pressure Control Valve, C11(Cl2)-F003.

l / h. IF CRD Pumps Suction Filters Bypass '.*alve, C0-V306, is open, i l Ind. Ver. THEN VERIFY a CRD pump suction filter is in service and CLOSE I l the CRD Pumps Suction Filters Bypass Valve, CD-V306.

i. IF both CRD pump suction filters are in service THEN ISOLATE and REPLACE the filter which has the highest dP.
j. If both CRD drive water filters are in service. THEN ISOLATE and REPLACE the filter which has the highest dP.
4. ENTER the Containment Control section of this End Path Manual and EXECUTE it concurrently with this procedure.
5. IF while executing this procedure, reactor vessel level CANNOT be determined OR reactor vessel flooding is req tired. THEN EXIT this End Path Procedure and ENTER the "Flooding Procedure" in the Cor.tingency section of this End Path Manual.

__ 6. IF reactor vessel level CAhKOT be maintained above +170 inches. THEN MAINTAIN re'e tor vessel le'.el above 0 inches.

7. IF reactcir 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-1M 4 of 8 Rev. 3 l '

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8. IF while executing this procedure reactor depressurization in required, THEN PERFORM the following stepst

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a. IF the reactor is NOT shut down, THEN EXIT this End Path Yrocedure and ENTER the "Level / Power Control" flow path.
b. IF the reactor is shut down, THEN DEPRESSURIZE the rea: tor per the following steps: >

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CAUTION ,

l Eg NOT DEPRESSURIZE below 120 psig UNLESS notor-driven pumps suf ficient to  !

maintain reactor vessel level are running and available for in,tection.

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,_, (1) JJ, the KSIVs are open, THEN RAPIDLY DEPRESSURIZE the reactor with the bypass valve opening jack.

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,_, (2) JU[ the reactor CANNOT be depressurized to the main 4 condenser, jgg2[ manually OPEN all ADS va' 'es. l

,_, (a) IF, any ADS valve CANNOT be opened, THEN OPEN SRVs yNTIL seven valves are open.

(b) JJ; less chan three SRVs are open AND reactor pressure l 4 is greater than 50 psig above suppression chamber  !

pressure, THEN ENTER the "Emergency Depressurization l Procedure" in the Contingency section of this End -

Path Manual and EXECUTE it concurrently with this l

procedure. 7 (c) CONTINUE in this procedure at Step 11. l j _,
9. JJ; the MSIVs are open, THEN MAINTAIN reactor pressure below 350 psig with the bypass valve opening jack or ENC pressure setpoint. l eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee***eeeeee*1eeee******enemeneaneesee CAUTION l Eg N0j[ DEPRESSURIZE below 120 pois UNLESS motor-driven pumps sufficient to  :

asintain reactor vessel level are running and available for injection.

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, 10. IF reactor pressure CANNOT be maintained with the EHC System AND l continuous pneumatic supply is available to the SRVs THEN OPEN SRVs 1 as necessary to maintain reactor pressure below 350 psig. USE j opaning sequence B, F. E. G A, C. J. H, and D. I

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ISEP/Vol. VI/EOP-01-EPP-1H 5 of 8 Rev. 4 f

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CAUTION E fuel failure is suspected, 3 NOT REJECT RWCU to hotwell.

,IF,an automatic isolation of a particular systera has occurred, g NOT attempt

o deisolate or restore the system UNTIL all available indications have been checked and are found to be normal.

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

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11. Reactor pressure control may be augmented Sy one or more of the following systems:
a. HPCI (in full flow test m.
b. RCIC (in full flow test scos)
c. Main Steam Line Drains
d. RWCU
e. Teed' pumps (in recirculation mode)
f. SJAEs (in full load)
12. IF a break outside Primary Containment is suspected. THEN PERFORM the following steps:
a. ISOLATE the break by remote or manual operation of the affected valves.
b. REFER to AOP-01.1.

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13. IF SJAE, stack, or MSL radiation monitors indicate fuel failure, YEEN PERFORM the following steps:

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a. NOTIFY E&RC to sample coolant.
b. MONTTOR ARMS, stack, and ventilation radiation monitors.

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c. IF high radiation or high airborne conditions exist, THEN REFER Y6 A0Ps 05 through 06.
d. PLACE the following valve control switches to "CLOSE":

(1) DW TLOOR DRAIN INBD ISOL VLV, G16-F003 (2) DV FLOOR DRAIN OTBD ISOL VLV, G16-T004 (3) DW EQUIP DRAIN INBD ISOL VLV G16-F019 BSEP/Vol. V!/EOP-01-EPP-!M 6 of 8 Rev. 4

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(4) DW EQUIP DRAIN OTBD ISOL VLV, C16-F020

e. NOTIFY radwaste to place Reactor Building equipment draiti tank pumps into the recirculation mode. f
f. DO NOT OPERATE the mechanical vacuum pumps.  !

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14. IF condensate booster pump suction conductivity is greater than  ;

E3 paho, THEN PERFORM the following stepst

a. RD10VE affected water boxes from service.  ;
b. REALIGN CRDs and CDDs to provide better ion removal, f
c. IF the Condensate /Feedwater System is NOT required to maintain reactor vessel level. THEN PLACF the Condensate System in long l cycle cleanup (0P-32).
d. DO NOT reject the hotwell to the CST. f
e. REFER to AOP-26.0. ,

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15. IF, while executing this procedure, any of the following systems f Ta'il or have failed, THEN ENTER the assoctahd procedure in the I System Recovery section of this End Path Manual and EXECUTE it  !

concurrently with this procedure: [

a. Conventional Service Water
b. Nuclear Service Water
c. Reactor Building Closed Cooling Water [

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d. Turbine Building Closed Cooling Water  !

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e. Instrument Air [

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f. Auxiliary Electric Power
16. NOTITY the 30$ to perform the following stepst
a. CONSULT PEP, section 2.1 i
b. NOTITY on-call CP&L supervision f
c. NOTIFY NRC per RCI-06.5
d. NOTIFY E&RC to sample coolant
e. IMPLEMENT 01-22. [

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17. CONTINUE to monitor suppression pool temperature. l BbEP/Vol. V!/EOP-01-EPP-1M 7 of 8 Rev. 4 [

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18. IF the reactor CANNOT be shut down before suppression pool Iimperature reaches 110'P, THEN EXIT this procedure and ENTER the "Level / Power Control" flow path.

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19. IF the MSIVs are closed. TH.tN REESTABLISH the main condenser as a i heat sink (OP-25).
20. WHEN all control rods are fully inserted, THEN CONTINUE in this procedure.

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21. IF RVCU has isolated AND an break in the RVCU System is NOT suspected, THEN RESET the Group 3 isolation and RESTART EUCU (OP-14).
22. IF the reactor recirculation pumps have tripped THEN RESTART the reactor recirculation pumps (OP-02).

__ 23. CONTINUE performing Containment Control. Local Emergency, and System Recovery Procedures UNTIL the exit cenditions ter the affected procedures are met.

24. RECORD required scram information in the Scram Report (07-22) snd Shift togs.

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__ 25. WRITE Vo'rk Request / Job Orders /LCOs so ensure that functional testing I is performed on those syn. ems in which jumpers were installed.

26. VMEN systems that require independent verit.aation for retur'. to service are shut down. THEN PLACE the systems in standby re,adiness per their respective ops. (Refer to Tatle 11.7.1 in ";1ume 1 Book 1- AP.)
27. IF reactor cooldown and depressuritation is to be commenced per the 505. THEN ENTER the General Plant Operating Procedure and EXECUTE it concurrently with this procedure.
28. VMEN:

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a. Reactor vessel level can be maintained a'ove +170 inches AND
b. Reactor pressure can be maintained below 1045 psig AND
c. Primary t.ontainment parameters are within the limits specified in the Containment Control Procedure.

THEN EXIT this procedure and ENTER the appropriate section of the General Plant Operating Procedure for hot standby OR cold shutdown as directed by the 505.

BSEP/Vol. VI/EOP-01-EPP-lM 8 of 8 Rev. 2

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