ML20205S693
ML20205S693 | |
Person / Time | |
---|---|
Site: | Brunswick |
Issue date: | 04/18/1986 |
From: | Bishop E CAROLINA POWER & LIGHT CO. |
To: | |
Shared Package | |
ML20205K904 | List:
|
References | |
EOP-01-FP, EOP-1-FP, NUDOCS 8811110141 | |
Download: ML20205S693 (21) | |
Text
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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT tl NIT 0 TLOODING PROCEDURE l
l EMERGENCY OPER/. TING PROCEDURE: E0P-01-TP l
l VOLUME VI Rev. 003 Y
ONL ervtfite (
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/ INFO ve ,itsts,sa r .tp;tMtat,et*
msWsa ms ,cx FOR r rmntsyste ed opefot 'ats p dages.
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Mot t etasnrtstV y o14n f me
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cpe et rste krpe stats Approved By: . 4% I i Dater /) '
i GeneraVManager/
Manager - Operations ,
l l
Pare 1 of 9
~~
8911110141 081025 PDR ADOCK 05000324 P PDR
LIST OF EFFECTIVE PACES E0P-01-FP l Pane (s) Revision 1-7 3
, 8 1 9 3
{
l l
BSEP/Vol. V!/EOP-Oi-FP Page 2 of 9 Rev. 3
, A. TITLE - Flooding Procedure I i B. ENTRY CONDITIONS I
!. Reactor vessel level CANNOT be determined OR i i
- 2. Primary containment pressure CA_NNOT be maintained below 58 psig OR
- 3. Dryve11 temperature near vessel level instrument reference l 1egs has reached reactor eaturation temperature.
C. OPER/. TOR ACTIONS l
l 1. IF all control rods are fully inserted. THEN CONTINL'E in this l procedure at Step 15.
l
~~
l IIIT this procedure and ENTER the~"Level / Power Control" flovpath.
l l **************enee***ene********t***ese************e***eseenemena****ee******* [
CAUTION DO NOT DEPRESSURIZE below 120 psig UNLESS motor driven pumps suf ficient to l
maintain reactor vessel level are running and available for injection. ;
t see****eeeeeeene****e e***********eneseeenesee*****eeeme***eemen seeeeean **** t
- 3. TERMINATE and PRFVENT all injection to the reactor except SLC and ,
CRD. i i
4 w anually OPEN all ADS valves. l
l valves are open.
l
~~
- 6. IF lest than three SRVs are open AND reactor pressure is greater i tEan 50 psig above suppression chImEer pressure. TMFN ENTFR the "Emeraer.cy Depressurization Procedure" in the Continrency section of j thia r nd Path Manual and EXTCUTE it concurrently with this
^
procedure. '
l 7 IT three or core SRVs can be opened, THEN CLOSE the following !
valves: j
- a. MSIVs
- b. Main Steam Line Drain Inboard Isolation Valve. B21-F016 !
i
- c. Main Steam Line Drain Outboard Isolation Valve. 521-F019 [
l
- d. Steam Pressure Reducer Isolation Valves. El. -F052A and Ell-F052B.
BSEP/Vol. VI/EOP-01-FP Page 3 of 9 Rev. 3 !
l i
l
~~
- 8. IF motor driven pumps sufficient to flood the reactor att available ARD reactor pressure can be maintained below 200 palR _THEN CLOSE the following valvest
- a. RCIC Steam Supply outboard Isolation valve. E51-F008
- b. HPCI Steam Supply Outboard Isolation Yalve. E41-T003 i
~~
- 9. IF while EXECUTING the following step reactor vessel level can Ee determined AND reactor vessei flooding is NOT required, THFN RETURN to the End Path Procedure, neeeeeeeeeeeeeee**eseeeemeneseeeeeeeee(see**eeeeeeeeeee********eeeeeeeeeeeeeen CAUTION A rapid increase in injection to the reactor may induce a large power i
excursion and result in substantial core damage.
eenene*****ene****eeeeee**************eneneneneseensene*******enene e*****eee.
~~
- 10. UNEN reactor pressure is below the "Minimun Alternate Flooding Pressure" per the following table r i
Minimum t
Alternate Number of Flooding Open SRVs Pressure 7 105 6 125 5 150 4 185 3 245 l 2 370 1 735 3 THEN COMMENCE and SLOWLY INCFFASE injectien flov to tha reactor with i one or more of the following syst .mt to maintain reactor pressure
'; abeve the "Minimus Alternate Fl',oding Pressure." but as lov as eessible.
tvstem Pressure Panee Cendensate - - - - - - - - - - - - - - 200-0 pste Condensate /Socater - - - - - - - - - - 130-0 1sig Feed Pumps - - - - - - - - - - - - - - 1250-0 psig l HPCI - - - - - - - - - - - - - - - - - 1280-120 psia RCIC - - - - - - - - - - - - - - - - - !!Q0-62 psig i
RHR --- -------------- 200-0 psig l
i BSEP/Vol. V1/EOP-01-TP Page 4 of 9 Rev. 3 i
~~
- 11. IF reactor pressure CANNOT be maintained above the "Minimum Afternate Flooding Pressure". THEN i
~~
- a. CLOSE the Core Spray Inboard Injection Valves. E21-T005A snd l E21-T005B. ,
- b. START both core spray purps.
- c. SLOWLY OPEN E21-F005A to obtain 4625 spm. '
~~
- 12. IF reactor pressure CANNOT be maintained above "Minimum Alternate TIcoding Pressure.'i YIiEN SLOWLY OPEN E21-T005B to obtain 4625 spa.
- 13. IF reactor pressure CANNOT be maintained above the "Minimum Alternate Flooding Pressure." THEN PERFORM LEP-01. "Alternate Coolant Injection Procedure."
14 WHEN:
- s. All control rods are fully ins'rted OR
- b. The reactor is shutdown AND no boron has been injected.
THEN CONTINUE in this procedure at Step 20.
- e******************eeeeeeeeeeeeeeeeemene**ee****
- TION DO NOT DEPRESSURIZE below 120 psig t*NIESS motor-dri"en pumps suf ficient to l maintair: reactor vessel level are running and available for injection.
r eeeeee***eeeeeeeeeeeeeeeeeeeeeemene***eeeeeeeeeeee**eeeeen p eee*******eaeanne
~~
- 15. IF the MSIVs are open. THEN RAPIDLY DEPRESSURIZE the reactor with IEe bypass valve opening jack.
I 16 IT the reactor CANNOT be depressurized to the main condenser. THEN I mant>!1y OPEN all ADS valves.
4 IT any ADS valves CANNOT be opeted TNrN OPEN SRVs UNTIL seven valves are open, j f t
~~
I7 eater than 30 psia above suppt s a
' ,o chaeber pressure. THEN l ENTER the "Emergency Depressurina..on Precedure in the i rentingency section of this End Fath Manual and FXECUTE tt ,
cencurrently with this procedure.
/!-
r BSEP/Vol. V!/EOP-01-TP Page 5 of 9 Rev. 3 f
! 17. IF motor-driven pumps suf ficient to flood the reactor are available AND reactor pressure can be maintained below 200 psig, THEN CLOSE t
'tTe following valves 0 __
a, RCIC Steam Supply Outboard Isolation Valve, E51-F008
- b. HPCI Steam Supply Putboard Isolation Valve, E41-F003
- 18. WHUN reactor pressure is below 200 psig, THEN:
~~
- b. PLACE control switches for all other SRVa to "AUT0" OR "CLOSE."
- 19. IF three or mora SRVs can be opened. THEN CLOSE the following ,
valves:
- a. MSIVs
- b. Main Steam Line Drains Intoard Isoletion Valve, B21-F016
- c. Main Steam Line Drain Ootboard Isolation Valve, B21-F019
~~
- d. Steam Pressure Reducer Isolation Valves. E11-F052A and E11-F052B
- 20. IF reactor vessel level can be determined. THEN CONTINUE in this procedure at Step 29.
~~
- 21. IF the reactor vessel level CANNOT be determined, THEN INCREASE injection flow with the following systems UNTIL:
- a. Three or more SRVs are open, AND
- b. Reactor pressure is NOT decreasing, AND
- c. Reactor pressure is at least 100 psig greater than supprecsion chamber pressure.
(1) Condensate - - - - - - - - - - - - - - - 200-0 psig (2) Condensate / Booster - - - - - - - - - - - 350-0 psig (3) feed Pumps - - - - - - - - - - - - - - - 1250-0 paig (4) CRD - - - - - - - - - - - - - - - - - - 1490-0 psig
__ (5) RHR - - - - -------------- 200-0 psig (6) Core Spray - - - - - - - - - - - - - - - 300-0 psig (7) RCIC - - - - - - - - - - - - - - - - - - 119 0-62 p s ig (8) HPCI - - - - - - - - - - - - - - - - - - 1280-120 psig BSEP/Vol. VI/EOP-01-FP Psge 6 of 9 Rev. 3 1
i
,,e- , -- --,-r,av ------v ,,y -
,, .e
~~
- 22. IF reactor pressure CANNOT be maintained at least 100 psig greater than suppression chamber pressure, THEN PERFORM LEP-01 "Alternate Coolant Injection" concurrent 1v vith this procedure.
~~
- 23. THROTTLE injection flow as necessary to maintain reactor pressure at Jeast 100 psig above suppression chamber pressure.
24 FILL level instrument reference legs by:
- a. Msintaining reactor pressure at least 100 psig above suppression chamber pressure OR
- b. Notifying I&C to fill level instrument reference legs.
NOTE Drywell temperature near the level instrument reference legs is determined by:
- a. The average of Points 9 and 10 on CAC-TR-4426-1 and Points ;
8 and 9 on CAC-TR-4426-2 S3
- b. The average of Computer Points W109, W110. F147, and F148,
~~
- 25. WHEN dryvell temperature near the level instrument reference legs is less than 212*F, THEN CONTINUE in this pruredure.
NOTE The following may be used as indication of rea: tor vessel flooding:
SRV dischstge pipe thermocouples for the open SRVs show a tenperature change, Suppression pool level indication stabilizes.
Reactor pressure bed.ng maintained at least 100 psig above suppression chamber pressure.
~~
- 26. WHEN it can be determined that the reactor vessel is flooded, THEN RECORD the time and TERMINATE injection to the reactor from all -
sources.
BSEP/Vol. VI/E0P-01-FP Page 7 of 9 Rev. 3
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~-
- 27. IF reactor vessel level indication is NOT restored within the RIximum Core Uncovery T.ime Limit (see Figure 1) THEN RETURN to Step 21 of this procedure.
~-
- 28. WHEN reactor vessel level can be determined THEN CONTINUE in this l procedure at Step 32.
l l
~~
- 29. INCREASE injection flow to the reactor, with the following systems UNTIL reactor vessel level is increasing. I
- a. Condensate - - - - - - - - - - - - - 200-0 psig
- b. Condensate / Booster - - - - - - - - - 350-0 psig
- c. Feed Pumps - - - - - - - - - - - - - 1250-0 psig
- d. CRD - - - - - - - - - - - - - - - - 1490-0 psig
- e. RHR ---------------- 200-0 psig
- f. Core Spray ------------- 300-62 psig
- g. RCIC - - - - - - - - - - - - - - - - 1190-62 psig
- h. HPCI - - - - - - - - - - - - - - - - 1280-120 psig
~~
- 30. IF the reactor CANNOT be flooded with the available systems, THEN PERFORM LEP-01 "Alternate Coolant Injection."
- 31. CONTINUE flooding the reactor UNTIL suppression chamber pressure :an be maintained below 58 psig.
- 32. WHEN suppression chamber pressure can be maintained below $8 psig, TliEN RESTORE reactor vessel level between +170 and +200 inches.
- 33. EXIT this procedure and ENTEit the End Path Procedure IM or 2B as l appropriate.
BSEP/Vol. VI/EOP-01-FP Page 9 of 9 Rev. 3 l
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