ML20205S793
| ML20205S793 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/08/1988 |
| From: | Bishop E CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20205K904 | List:
|
| References | |
| EOP-01-EPP-1L, EOP-1-EPP-1L, NUDOCS 8811110176 | |
| Download: ML20205S793 (9) | |
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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT i
t UNIT 0 i
END PATH PROCEDURE:
1L EMEilGENCY OPERATING PROCEDURE:
E0P-01-EPP-1L I
VOLUME VI l
1 i
Rev. 004 l
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i Manager - Operations
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8811110176 001025 PDR ADOCK 05000324 p
LIST OF EFFECTIVE PAGES E0P-01-EPP-1L Page(s)
Revision 1-2 4
3 2
4 3
5 4
6-7 2
8 4
9 2
BSEP/Vol. VI/EOP-01-EPP-1L Page 2 of 9 Rev. 4 i
A.
TITLE - End Path Procedure IL B.
ENTRY C0KDITION All control rods did NOT fully insert following a scram initiation.
C.
OPERATOR ACTIOy 1.
IF the reactor CANNOT be shut down before suppression pool remperature reaches 110*F. THEN EXIT this procedure and ENTER the "Level / Power Control" flow path.
CAUTION DO NOT SECURE or PLACE an ECCS or RCIC in manual mode UNLEF3 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 t:111 NOT initiate autecatically. MAKE frequent checks of the initiating or controlling parameter. VHEN manual operation is no longer required. RESTORE the system to automatic / standby mode if possible.
- i*******
2.
RESTORE and MAINTAIN reactor vessel level between +170 and
+200 inches. USE one Sr more of the following systems in an order j
that will minimize high conductivity feed to the reactor:
RPV Pressure Range l
System for System Operation 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.
RHR-------------------
200-0 psig h.
Core Spray- - - - - - - - - - - - - - - -
300-0 psig BSEP/Vol. VI/EOP-01-EPP-1L Page 3 of 9 Rev. 2 l
3.
IF the CRD Drive Water Preemu.m "ontrol Valve, C11(C12)-F003, and the in-service CRD Flow Control Valve, C11(C12)-F002A(F002B), have been opened to maintain reactor vessel level AND the CRD System is no longer needed to maintain reactor vessel level, THEN PERFOR}i the following steps to restore the CRD System to normal operation:
a.
SET the setpoint tape on CRDHS Remote Flow Controller, C11(C12)-FC-R600, to 100 gpm.
b.
SHIFT the CKDHS Remote Flow Controller, C11(C12)-FC-R600, to the "AUT0" position.
IF both CRD pumps are running, THEN STOP one CRD pump.
c.
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d.
OPEN ecd LOCK OPEN CRD Pump Condensate Return Isolation Valve.
Ind. Ver.
COR-Vi (located at CST).
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e.
IF Charging Water Header Throttle Valve, Cll(C12)-F034, l
Ind. Ver.
was manipulated to maximize CRD flow THEN CLOSE and IMMEDIATELY REOPEN Si turns Charging Water Header Throttle Valve, C11(C12)-F034 f.
SET the setpoint tape on CRDHS Remote Flow Controller, C11(C12)-FC-R600, to between 30 and 80 gpm.
i g.
ESTABLISH a drive water header differential pressure between 260 and 275 paid, as read on C11(Cl2)-PDI-R602 on RTGB Panel P603, by throttling closed Drive Water Pressure Control Valve, C11(Cl2)-F003.
/
h.
IF CRD Pumps Suction Filters Bypass Valve, CO-V306, is open.
l Ind. Ver.
THEN VERIFY a CRD pump suction filter is in service and CIOSE the CRD Pumps Suction Filters Bypass Valve, Co-V306.
1.
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 I
and REPLACE the filter which has the hig5est dP.
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ENTER the Containment Control section of this End Path Manual end i
EXECUTE it concurrently with this procedure.
5.
IF while executing this procedure, reactor vessel level CANNCT be determined OR reactor vessel flooding is required. THEN EXIT this End Path Procedure and ENTER the "Flooding Procedure"~in the t
Contingency section of this End Path Manual, 6.
IF reactor vessel level CANNOT be maintained above +170 inches. THEN MAINTAIN reactor vessel level above 0 inches.
r 7.
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 :.f this End Path Manual.
BSEP/Vol. VI/EOP-01-EPP-lL Page 4 of 9 Rev. 3
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8.
IF while executing this procedure reactor depressurization is required, THEN PERFORM the following steps a.
IF the reactor is NOT shut down. THEN EXIT this End Path Procedure and ENTER the "Level / Power Control" flow path, b.
Jy[ the reactor is shut down. THEN DEPRESSURIZE the reactor per the following stepst
- ene****an*******ce*****************,*****************=*********neamen********
CAUTION Djl NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient to maintain react.or vessel level are running and availablo for injection.
ta******************me*** mas***********en*********************ne**************
(1) JU[ the MSIVs are open THEN RAPIDLY DEPRESSURIZE the reactor with the bypass valve opening jack.
the reactor CANNOT be depressurized to the main (2)
JU[ denser, THEN manually OPEN all ADS valves.
con (a). IF any ADS valve Cf' JOT be opened, THEN OPEN SRVs UNTIL seven valves are open.
(b) Jg[ 1ess than seven SRVs are open AND reactor pressure is 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 11.
9.
JUi the MSIVs are open, THEN MAINTAIN reactor pressure below 1025 psig with the bypass valve opening jack or EHC pressure setpoint.
- een**************eenenenne**************************************************
CAUTION 00 NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient to maintain reactor vessel level are running and available for injection.
1
- e***************************a********************************
10.
IF reactor pressure CANNOT be maintained with the EHC System AND continuous pneumatic supply is available to the SRVs. THEN OPEN SRVs, as necessary, to maintain reactor pressura below 1025 psig.
USE opening sequence B. F E. G. A C, J. H and D.
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BSEP/Vol. VI/EOP-01-EPP-1L Page 5 of 9 Rev. 4 i
11.
IF whilt executing this procedure the main turbine has tripped THEN FERFORM the following steps:
a.
VERIFY or TRANSFER ;uxiliary power loads to SAT.
b.
OPEN or VERIFY OPEN generator PCBs 29A and 29B.
c.
VERIFY the following:
(1) Turbine MSV closed (2) Turbine CVs closed (3) Turbine CIVs closed (4)
Extraction nonreturn valves closed (5) All moisture removal valves opea
- (*********************************************************
CAUTION IF fuel failure is suspected, D0 NOT REJECT RWCU to hotwell.
IF automatic isolation of a particular system has occurred. DO NOT attempt to 2eisolate 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.
12.
Reactor pressure control may be augmented by one or more of the following systems a.
HPCI (in full flow test mede) b.
RCIC (in full flow test mode) c.
Main Steam Line Drains d.
RVCU e.
Feed Pumps (in recirculation mode) f.
SJAEs (in full load) 13.
IF a break outside Primary Containment is suspected. THEN PERFORM tee following steps:
a.
ISOLATE the break by remote or manual operation of the affected valves.
BSEP/Vol. VI/EOP-01-EPP-IL Page 6 of 9 Rev. 2
b.
REFER to AOP-01.1 14.
IF Condensate Booster Pump suction conductivity is greater than U~3 umho THEN PERFORM the following steps:
a.
REMOVE affected water boxes from service.
b.
REALIGN CFDs and CDDs to provide better ion removal, c.
IF the Condensate /Feedvater System is NOT required to maintain
~r actor vessel level, THEN PLACE the Condensate System in long cycle cleanup mode.
d.
DO NOT reject the hotvell to the CST.
e.
REFER to A0P-26.0, 15.
IF SJAE, stack, or radiation monitors indicate fuel failure, THEN
~~~
PERFORM the following steps:
a.
NOTIFY E6RC to sample coolant.
b.
MONITOR ARMS, stack, and ventilation radiation monitors.
c.
IF high radiation or high airborne conditions exist, THEN REFER T5 AOPn 05 through 06.
d.
PLACE the following valve control switches to CLOS 2:
(1) DW FLOOR DRAIN INBD ISOL VLV, G16-F003 (2) DW FLOOR DRAIN OTBD ISOL VLV, C16-F004 (3) DW EQUIP DRAIN INBD ISOL VLV, G16-F019 (4) DW EQUIP DRAIN OTBD ISOL VLV, G16-F020 e.
NOTIFY Radvaste to place Reactor Building equipment drain tank l
pumps into recirculation mode, f.
DO NOT OPERATE the mechanical vacuum pumps.
16 IF while executing this procedure, any of the following systems fail or have f ailed. THEN ENTER the associated procedure in the System Recovery section of this End Path Manual and EXECUTE it concurrently with this procedures a.
Conventional Service Water b.
Nuclear Service Water i
BSEP/Vol. VI/EOP-01-EPP-1L Page 7 of 9 Rev. 2
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 a.
CONSULT PEP. Section 2.1.
b.
NOTIFY on-call CP&L esp arvision.
c.
NOTIFY NRC per RCI-06.5.
d.
NOTIFY E&RC to sample coolant.
e.
IMPLEMENT 01-22.
l
- 18. CONTINUE to monitor suppression pool temperature.
19.
IF the reactor CANNOT be shut down before the suppression pool temperature reaches 110'F, THEN EXIT this procedure and ENTER the "Level / Power Control" flow path.
20.
IF the MSIVs are closed. THEN REESTABLISH the main condenser as a Eeat sink (OP-25).
21.
IF attempts to ins rt control rods per LEP-02 vere unsuccessful AND the reactor is not shut down. THEN EXIT this End Path Procedure and ENTER the "Level /Pover Control"~ flow path at the discretion of ths SOS.
22.
WHEN all control rode are fully inserted. THEN CONTINUE in this procedure.
23.
IF kWCU has isolated AND a break in the RWCU System is NOT suspected. THEN RESET the Group 3 isolation and RESTARl RWCU (OP-14).
24 IF the reactor recirculation pumps have tripped THEN RESTART the reactor recirculation pumps (OP-02).
25.
RECORD required scram information in the Scram Report (01-22) and Shift Logs.
- 26. WRITE WR/Jos/LCOs to ensure that functional tssting is performed on l
those systems in which jumpers were installed.
- 27. CONTINUE performing Containment Control Local Emergency, and System Recovery Procedures UNTIL the exit conditions for the procedures are met.
BSEP/Vol. VI/EOP-01-EP.'.-1L Page 8 of 9 Rev. 4
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- 26. WHEN systems that require independent verification for return to service are shut lovn. THEN PLACE the systems in standby readiness per their respect ive ops (, afer to Table 11.7.1 in Volume I, Book 1-AP).
J
. 29, IF reactor cool jovn and depressurization are to be commenced per-tee SOS, THEN ElTER the General Plant Operating Procedure and t
~~~
EXECUTE it conet trently with this procedure.
- 30. WHEN:
J Reactor vessel level can be maintained above +170 inches AND r
a.
b.
Reactor pressure can be maintained below 1045 psig AND Primary containment parameters are within the limits specified c.
in the Containment Control Procedure, j
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THEN EXIT this procedure and ENTER the appropriate section of General Plant Operating Procedure for hot / standby OR cold shutduvn as directed by the SOS.
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BSEP/Vol. VI/EOP-01-EPP-1L Page 9 of 9 Rev. 2
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