ML20205K913

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Rev 4 to Emergency Operating Procedure EOP-01-EPP-2A, End Path Procedure 2A
ML20205K913
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-2A, EOP-1-EPP-2A, NUDOCS 8811010394
Download: ML20205K913 (8)
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Text

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7 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 END PATH PROCEDURE 2/.

EMERGENCY OPERATING PROCEDURE: E0P-01-EPP-2A VOLUME VI Rev. 004 w , k mumb88#

yd t* g, ott \SpecW' ' grps.

C ," ppt P**I Approved By: ' ~ 17) Date I 8[

//

Genefal Managpi /

Hanager - Operattons 8911010394 881025

[DR ADOCK 0500g324

4 LIST OF EFFECTIVE PAGES E0P-01-EPP-2A Page(s) Revision 1-2 4 3 2 4 3 5 4 6 2 7 4 8 2 BSEP/Vol. VI/EOP-01-EPP-2A Page 2 of 8 Rev. 4 J

A. TI,TLE - End Path Procedure 2A B. ENTRY CONDITION This procedure is entered from Flovpath 2, 3, 4, OR $ OR from the Contingency section of this End Path Manual.

C. OPERATOR ACTIONS

                                                    • t.***************************************************

CAUTION DO NOT SECURE or PLACE an ECCS or RCIC in manual mode UNLESS by at least two independent indications:

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

IF an ECCS or RCIC is placed in the manual mode. it will NOT initiate automatically. MAKE frequent checks of the initiating or controlling parameter. WHEN manual operation is no longer required, PESTORE the system to automatic / standby mode if possible.

                                                                    • ,.*********************+********************

r

~~

1. RESTORE and .4MINTAIN reactor vessel level between +170 and +200

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

RPV Pressure Range '

System for System Operation ,

a. Condensate 200-0 psig
b. Cendensate/ booster 350-0 psig i
c. Feed pumps 1250-0 psig a
d. CRD 1490-0 psig
e. RCIC  !!90-62 psig
f. HPCI 1280-120 psig
e. RHR 200-0 psig
h. Core Spray 300-0 psig J

BSEP/Vol. VI/EOP-01-EPP-2A Page 3 of 8 Rev. 2 m  ;

i .

4 f

~

2. IF the CRD Drive Vater Pressure Control Valve, Cll(Cl2)-F003, and We in-service CRD Flow Control Valve, Cll(Cl2)-F002A(F0028), have .

been opened to maintain reactor vessel level g 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 i t

~

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

Cll(Cl2)-)C-R600, to 100 spm. i

~

b. SHIFT e.he CRDHS Remote Flow Controller, Cll(Cl2)-FC-R600, to ,

the "AUT0" position.

c. IF both CRD pumps are running, THEN STCP one CRb pump.

/ d. OPEN and LOCK 01EN CRD Pump Condensate Return Isolation Valve, 5 E Ver. COR-V1 (located at CST). '

l, J / e. IF Charging Vater Header Throttle Valve Cll(Cl2)-F034, was  !

l E Ver. Enipulated to maximize CRD flev THEN CLOSE and IMMEDIATELY l REOPEN 8) turns Charging Water Header Throttle  !

Valve, Cll(Cl2)-F034.

s

~

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

Cll(Cl2)-TC-R600, to between 30 and 80 gpm.  !

' ~

g. ESTABLISH a drive water header differential pressure between l 260 and 275 psid, as read on Cll(Cl2)-PDI-R602 on RTGB Panel P603, by throttling closed Drive Water Pressure Control Valve, i i C11(Cl 2)-F003, i a '

i

h. '

/ IF CRD Pumpa Suetion Filters Bypass Valve, CO-V306, is open, 5 E Ver. YIIEN VERITY a CRD pump suction filter is in service and CLOSE ,

I l the CRD Pumps Suetion Filters Bypass Valve, CO-V306. [

1. IT both CRD pump suction filters are in service THEN ISOLATE ',

and REPLACE the filter which has the highest dP. [

t l

~

j. IF both CRD drive water filters are in service, THEN ISOLATE  :

Ed REPLACE the filter which has the highest dP.  !

~

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

l

~

4. IF vhile executing this procedure, reactor vessel level CANNOT be L THEN EXIT this f Eterstned End Path pre Ok reactor edure vesselthe and ENTER flooding is required.

"Flooding Procedur Mn the l

Contingency section of this End Path Manual. l

~

5. IF reactor vessel level CANNOT be maintained above +170 inches, THEN EINTAIN reactor vessel level above 0 inches.

BSEP/Vol. V1/EOP-01-EPP-2A Page 4 of 8 Rev. 3 J

~~

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.
7. IF while executing this procedure, reactor depressurization is i required, THEN PERFORM the following steps:

CAUTION DO NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient to maintain reactor vessel level are running AND available for injection.

              • enneeeeeeeeeee***********************n*****nme*************************
a. IF the MSIVs are open. THEN RAPIDLY DEPRESSURIZE the reactor with the bypass valve opening jack. '

l b. IF the reactor CANNOT be depressurized to the main condenser, i THEN manually OPEN all ADS valves.

(1) JF, any ADS valve CANNOT be opened. THEN OPEN SRVs UNTIL ,

j seven valves are open.

__ (2) Il[ 1ess than three SRVs are open AND reactor pressure 14 ,

greater than 50 psig above suppression chamber pressure.  :

THEN ENTER the "Emergency Depressurization Procedure" in  !

the Contingency section of this End Path Manual and  ;

EXECUTE it concurrently with this procedure. . ,

c. CONTINUE in this procedure at Step 10. ,
8. IF the MSIVs are open. THEN MAINTAIN reactor pressure below 1025 psig with the bypass valve opening jack or EHC pressure setpoint.
                • mane ****en*****meneena**************enee*****ne***********************

CAUTION EO NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps suf ficient to maintain reactor vessel level are running and available for injection.

                  • enesee*****ene*****ene*****ne****enee***e********************n*******

i

9. IF reactor pressure CANNOT be maintained with the EHC System A}El continuous pneumatic supply is available to the SRVs[D[ OPEN SRVs ,

as necessary to maintain reactor pressure below 1025 psig. USE { opening sequence B. F E. G. A. C. J. H, and D. l l i i l [ BSEP/Vol. VI/EOP-01-EPP-2A Page 5 of 8 Rev. 4  : I 

       **a***************************************************************************

CAUTION IF fuel failure is suspected, DO NOT REJECT RWCU to hotwell. IF an automatic isolation cf a particular system has occurri . DO NOT attempt l to deisolate or restore the system UNTIL all available indications have been checked and are found to be normal. DO NOT DISPATCH personnel to an area of a suspected break without consideration of adverse environments.

10. Reactor pressut. :entrol ay be augmented by one or more of the following systemst
a. HPCI (in full f'ow test mode)
b. RCIC (in full flow test t- .)
c. Main Steam Line Drains
d. RWCU
e. Feed Pumps (in recirculation mode)
f. SJAEs (in full load)
11. IF a break outside pr* mary containment is suspected, THEN PEPFORM the following stepst
a. ISOLATE the break by remote or manual operation of the affected valves.
b. REFER to AOP-01.1.
12. IF SJAF, stsck, or MSL radiation monitors indicate fuel f ailure, THEN PERFORM the following steps:
a. NOTIFY E6KC to sample coolant.
b. MONITOR ARMS stack, and ventilation radiation monitors,
c. IF high radiation or high airborne conditions exist, THEN REFE3 to AOPs 05 through 06.
d. PLACE the following valve control cwitches to "CLOSE."

(1) DW FLOOR DRAIN ISBD ISOL VLV G16-F003 (2) DW F100R DRAIN OTBD ISOL VLV, G16-F004 (3) DW EQUIP DRAIN ISBD ISOL VLV, G16-F019 BSEP/Vol. VI/E0P-01-EPP-2A Page 6 of 8 Rev. 2

ss (4) DW EQUIP DRAIN OTBD ISOL VLV, G16-F020

e. NOTIFY Radwaste to place the Reactor Building equipment drain pump f :to the recirculation mode.
f. DO NOT OPERATE the mechanical vacuum pumps.
13. IF condensate booster pump suction conductivity is greater than 0.3 pmho, THEN PERFORM the following steps:
a. REMOVE af fected waterboxes f rom service.
b. REALIGN CtVs and CDDs to provide better ion removal.
c. IF the Condensate /Feedwater System is NOT required to maintain reactor vessel level, THEN PLACE the Condensate System in the long cycle cleanup mode.
d. DO NOT REJfCT the botvell to the CST.
e. REFER to A0P-26.0.
14. IF while executing this procedure, any r f the following systems f ail e

or have failed THEN ENTER the associar,ed procedure in the System Recovery section of this End Path Manual and E.;ECUTE it concurrently with this procedure

a. Conventional Service Water
b. Nuclear Service Water
c. Reactor Building Closed Cooling litter
d. Turbine Building Closed Cooling Water
e. Instrument Air
f. Auxiliary Electrical Power
15. IF the MSIVs are closed, THEN REESTABLISH the main condenser as a heat sink (OP-25).
16. NOTIFY the SOS to perform the following steps: l
a. CONSULT PEP, Section 2.1.
b. NOTIFY on-call CP&L supervisor.
c. NOTIFY KRC per RCI-06.5.
d. NOTIFY E&RC to sample coolant.
e. IMPLEMENT 01-22.

BSEP/Vol. VI/EOP-01-EPP-2A Page 7 of 8 Rev. 4

17. IF RWCU has isolated AND a break in the RVCU System is NOT suspected, THEN RESET the Group 3 isolation and RESTART RWCU (OP-14).
18. IF the reactor recirculation pumps have been tripped. THEN RESTART reactor recirculation pumps (OP-02).

__ 19. CONTINUE performing Containment control, Local Emergency, and System Recovery Procedures UNTIL the exit conditions f or the af fected procedures are mer. __ 20. RECORD required scram information in the Scram Report (01-22) and Shift Logs.

21. VRITE Vork Request / Job Order /LCOs to ensure that functiona? testing is performed on those systems in which jumpers were installed.
22. WHEN systems that require independent verification for return to service are shut down. THEN PLACE the systems in standby readiness per their respective ops. (Refer to Table 11.7.1 in Volume I, Book 1-AP.)
23. IF reactor cooldown and depressurization is to be commenced per the SOS, THEN ENTER the General Plant Operating Procedure and EXECUTE it concurrently with this procedure.

l __ 24 WHEN

a. Reactor vessel level can be maintained above +170 inches 6EE
b. Reactor pressure can be maintained below 1045 psig AND
c. Prirary containment parameters are within the limits specified in the Containment Control Procedure.

THEN EXIT this procedure and ENTER the appropriate section of the General Plant Cperating Procedure for hot standby OR cold shutdown as directed by the SOS, 3SF.P/Vol. VI/EOP-01-EPF-2A Page 8 of 8 Rev. 2}}

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