ML20205S808

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Rev 5 to Emergency Operating Procedure EOP-01-EPP-1N, End Path Procedure 1N
ML20205S808
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-1N, EOP-1-EPP-1N, NUDOCS 8811110182
Download: ML20205S808 (9)
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CAROLINA POWER & LIGHT COMPANY BRUNSWICK SThAM ELECTRIC PLANT UNIT 0 END PATH PROCEDURE IN EMERGENCY OPERATING PROCEDUREt E0P-01-EPP-1N VOLtHE VI Rev. 005 Q a:;#'{ ,

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.o Approved By: h h AAS Gener.$ Mahager/

Datet I /

kf Manager-Operatio]ns Page 1 of 9 8811110187 001025 4 DR ADOCK ObO

LIST OF EFFECTIVE PACES EOP-01-EPP-1N Page(s) Revision 1-2 5 3 3 4 4 5-9 5 BSEP/Vol. VI/EOP-01-EPP-1N Page 2 of 9 Rev. 5 1

A. ,T;]' E - End Path Procedure 1N B. ENTR1 CONDITIONS

1. All control rods did NOT fully insert following a scram initiation.
2. Boren injection was commenced and was terminated when all control rods were fully inserted.

C. OPERATOR ACTIONS eneesen**** ease *eme*******nenamenenene***eeeeeeee********enee**eeeneeeeeeeeeen CAUTION DO NOT SECURE or PLACE an ECCS or RCIC in manual mode UNLESS by at least two independent indicatienst

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 automa-tically. MAKE frequent checks of the initiating or controlling parameter.

WHEN manual operation is no longer required. RESTORE the system to automatic /

standby mode if possible, e********************************************enenamenene******en**************

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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 will minimite high conductivity feed to the reactor:

RPV Pressure Range ,

System for System Operation i

a. Condensate - - - - - - - - - - - - - - - - 200-0 psig
b. Condensate / Booster - - - - - - - - - - - - 350-0 psig
c. Feed Pumps - - - - - - - - - - - - - - - - 1250-0 psig
d. CRD ------------------- 1490-0 psig
e. RCIC - - - - - - - - - - - - - - - - - - - 1190-62 psig
f. HPCI - - - - - - - - - - - - - - - - - - - 1280-120 psig
g. RHP ------------------- 200-0 psig
h. Core Spray - - - - - - - - - - - - - - - - 300-0 psig BSEP/Vol. V!/EOP-01-EPP-IN Page 3 of 9 Rev. 3 1

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2. IF the CRD Drive Water Pressure Control Valve C11(C12)-F003, and I the in-service CRD Flow Control Valve C11(Cl2)-F002A(F002B). have  !

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' been opened to maintain reactor vessel level AND the CRD System is (

no longer needed to maintain reactor vessel level. THEN PERFORM the following steps to restore the CRD System to normal operationt

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

Cll(Cl2)-FC-R600, to 100 gpm.

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b. SHIFT the CRDHS Remote Flow Controller. Cil(C12)-fC-R600, to  !

the "AUT0" position. I I

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

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

l Ind. Ver. COR-VI (located at CST).

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/ e. IF Charging Water Header Throttle Valve. C11(Cl2)-F034. vas Ind. Ver, manipulated to maximize CRD flow. THEN CLOSE and 1HMEDIATELY i REOPEN 8 1/2 turns Charging Water Header Throttle Valve. I C11(Cl2)-F034.

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

C11(Cl2)-TC-R600, to between 30 and 80 gpm. I

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. (

Cll(Cl2)-F003. L

/ h. IF CRD Pueps Suction Filters Bypass Valve. CO-V306. is open. 1 Ind. Ver. THEN VERIFY a CRD pump suction filter is in service and CLOSE I i the CRD Pumps Srction Filters Bypass Valve. CO-V306.

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1. IT both CRD pump suction filters are in service. THEN 150',. TE and REPLACE the filter which has the highest dP.

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IF both CRD drive water filters are in service. THEN ISOLATE l and RE' LACE the filter which has the highest dP. j l

l 3. IF while executing this procedure, reactor vessel level CANNOT be l determined OR reactor vessel flooding is required. TNFN i.XIT this Er.d Path Pr E edure and ENTER the "Flooding Procedur M n the j Contingency section of this End Path Manual, j '

4. IF reactor vessel level CANNOT be maintained above +170 inches. THEN r MAINTAIN reactor vessel level above 0 inches. I

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5. IF reactor vessel level CANNOT be maintained above 0 inches. THEN IIIT this End Path ProceEre and ENTER the "Level Restoration i Procedure" in the Contingency section of this End Path Manual.

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6. IF while executing this procedure, reactor depressurization is 6

required. Ti4EN PERFORM the following stepst {

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BSEP/Vol. VI/EOP-01-EPP-lN Page 4 of 9 Rev. 4 [

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f a

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, enaa***en** man ***ena*******aea************************************************

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

ee**een**nena****ene*********eneenanneeeeeee********n****enemanna*************

a. IF the MSIVs are open THEN RAPIDLY DEPRESSURIZE the reactor ,

with the bypass valve opening jack. l

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b. IF the reactor CANNOT be depressurized to the main condenser.  :

YEEN manually OPEN all ADS valve,t.

(1) 1F any ADS valve CANNOT be opened, THEN OPTN SRVs UNTIL seven valves are open, j

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(2) IF less tha three SRVs are open AND reactor pressure is

, greater than 50 pais above suppression chamber pressure, l THEN ENTER the "Emergency Depressurisation Procedure" in 4

the Contingency section of this End Path Manual and

- EXECUTE it concurrently with this procedure.

(3) CONTINUE in this procedure at Step 9.

l 7. IF the MSIVs are open. THEN MAINTAIN reactor pressure below 1025 psig l with the bypass valve opening jack OR EHC pressure setpoint.

I *****enemane***eeeeanene******ee****************************************a*****

CAUTION DO NOT DEPRES$URIZE below 120 psig UNLESS sotor-driven pumps sufficient to i

maintain reactor vessel level are running and available for injection.

enneneseeseeeeeeee***aneeeeeeee**eee***eneseen***nenee**eaneeseneneesenannee**

1 f 8. IF reactor pressure CANNOT be maintained with the EH; Srstem AND q

continuous pneumatic supply is available to the SRVs, THEN OPEN SRVs as necessary to maintain reactor pressure below 1025 psfi! USE j opening sequence B. F. E. G. A C. J. H. and D.

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Rev. 5 1

l BSEP/Vol. VI/EOP-01-EPP-1N Page 5 of 9 l

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i CAUTION l IF fuel failure is suspected. DO NOT REJECT RWCU to hotwell.  :

)  !

IF an automatic isolation of a particular system has occurred. DO NOT ATTEMPT l l

Io de-isolate or restore the systen UNTIL all available indications have been i checked and are found to be normal.

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

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9. Reactor pressure control say be augmented by one or more of the  !

i following systesst  ;

s. NPCI {in full flow test soda)  :

J l j

b. RCIC (in full flow test mode) j t

- c. Main Steam Line Drains r I f j __

d. RWCU (with return to vessel) L i
e. Feed Pumps (in recirculation mode) f t
f. SJAEs (in full load) .
10. IF ADS has been inhibited. THEN RESTORE ADS as followst i

/ a. PLACE the ADS LOGIC A INNIBIT. 321C-55A switch to "AUTO." }

Ind. Ver. .

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/ b. PLACE the ADS LOGIC B INNIBIT. 321C-558, switch to "AUTO." {

Ind. Ver. J l

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c. VERIFY annunciator AUTO DEPRESS TIMERS INITIATED (A-03 3-1) is i clear.

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11. IF the nitrogen instrument air backup isolation has been overridden.

IEEN PLACE the following switches to "0 PEN":

/ a. DIV I NON-INTRPT. RNA-SV-5262 Ind. Ver.

/ b. DIV II NON-INTRPT. RNA-SV-5145 Ind. Ver.

BSEP/Vol. VI/EOP-01-EPP-1N Page 6 of 9 Rev. 5

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12. IF jumpers were installed to bypass the Vessel Level Group 1 isolation, THEN REMOVE O.e following jumpers:
a. UNIT I only

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(1) In Cabinet XU-65, between Terminals 27 and 28 on Ind. Ver. Terminal Board TB-A.

' In Cabinet XU-66, between Terminals 27 and 28 on

, (2)

Ind. Ver. Terminal Board TB-A.

/ (3) In Cabinet XU-67, between Terminals 27 and 28 on Ind. Ver, Terminal Board TB-A.

/ (4) In Cabinet XU-68, between Terminals 27 and 28 on Ind. Ver. Terminal Board TB-A.

b. UNIT 2 only

/ (1) In Cabinet XU-65, between Terminals 43 and 44 on Ind. Ver. Terminal Board TB-A.

/ (2) In Cabinet XU-66, between Terminals 43 and 44 on Ind. Ver. Terminal Board IB-A.

/ (3) In Cabinet XU-67, between Terminals 43 and 44 on Ind. Ver. Terminal Board Td-A. ,

/ (4) In Cabinet XU-08, between Terminals 43 and 44 on Ind. Ver. Terminal Board TB-A.

13. IF a break outside primary containeent is suspcceed, THEN PERFORM the following steps:

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a. ISOLATE the break by remote or manual operation 'a the affected  ;

< valves.

b. REFER to AOP-01.1.
14. IF SJAE stack, or MSL radiation monitor indicates fuel failure, THEN PERFORM the following steps
a. NOTIFY E&RC to sample coolant.
b. IF high radiation or high airborne conditions exist, THEN REFER to AOP-05 through AOP-06.
c. PLAC3 the following valve control switches to "CLOSE"t (1) DW FLOOR DRAIN INBD ISOL VLV, G16-F003 (2) DW FLOOR DRAIN OTBD ISOL VLV G16-F004 BSEP/Vol. VI/EOP-01-bPP-1N Page 7 of 9 Rev. 5 l

2- .t; T (3) DW EQUIP DRAIN INBD ISOL VLV, G16-F019 (4) DW EQUIP DRAIN OTBD ISOL VLV, G16-F020

d. NOTIFY Radraste to place Reactor Building equipment drain tank pumpr,into the recirculation mode,
e. DO NOT OPERATE the mechanical vacuum pumpe
15. IF condensate booster pump suction conductivity is greater than 0.3 paho, THEN PERFORM the following steps
a. REMOVE affected waterboxes from service.
b. REALIGN CfDs 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 long cycle cleraup. (OP-32)
d. DO NOT REJECT the hotwell to the CST. ,

'e. REFER to AOP-26.0.

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j 16. IF while executing this procedure, any of the following systems fall or have failed. TH2N ENTER the associated procedure in the System '

. Recovery section of this End Path Manual and EXECJTE it concur?ently

  • with this procedure I
a. Convention.nl Service Water
b. Nuclear Service Water
c. Reactor Building Closed Cooling Water
d. Turbine Building Closed cooling Water
e. Instrument Air >
f. Auxiliary Electrical Power
17. NOTIFY the SOS to perform the following steps: l
a. CONSULT PEP-02.1.
b. NOTIFY on-call CP&L supervisor.
c. NOTIFY NRC per RCI-06.5. ,
d. NOTIFY E&RC to sample coolant.
e. IMPLEKENT 0I-22. l BSEP/Vol. VI/EOP-01-EPP-1N Page 8 of 9 Rev. 5 l
18. IF the MSIVs are closed, THEN REESTABLISH the main condenser as a heat sink. (OP-25)
19. IF RWCU has isolated AND a break in the RWCU System is NOT

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Espected, THEN RESET the Group 3 isolation and RESTART RWCU with return to reactor vescel. (OP-14)

20. IF the reactor recirculation pumps have tripped, THEN RESTART the reactor recirculation pumps. (OP-02)
21. MAXIMIZE RWCU operation to remove boron from r:racco ent.
22. CONTINUE performing Containment Control, Local Emergency, and System Recovery Procedures UNTIL the exit conditions for the affected procedures are met.
23. RECORD required scram information in the Scram Report (01-22) and Shift Logs.

24 WRITE Work Request / Job Orders /LCOs to ensure that functional testing is performed on those systems in which jumpers were installed.

25. WHEN systems that require independent verification for return to service are shut down, THEN PLACE the systems in standby readiness -r per their respective cps. (Refer to Table 11.7.1 in Volume I, Book 1-AP.)
26. IF reactor cool down and depressurization is to be coc:menced per the SOS, THEN ENTER the General Plant Operating *rocedure and EXECUTE it concurrently with this procedure.
27. WHEN:
a. Reactor vessel level can be maintaincd above +170 inches AND
b. Reactor pressure can be maintained belov 1045 psig AND
c. Primary containment parameters are within the limits specified in the Containment Control Procedtra, 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 SOS.

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l BSEP/Vol. VI/EOP-01-EPP-1N Page 9 of 9 Rev. 5 l

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