ML20003F493
| ML20003F493 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/15/1981 |
| From: | MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20003F494 | List:
|
| References | |
| 05-S-01-EP-3, 5-S-1-EP-3, NUDOCS 8104210404 | |
| Download: ML20003F493 (19) | |
Text
-
3PNI,D C,Ub NUCLEAR STAT:CN DiERGENCY PROCEDURE O
PLANT OPEPJ.TICNS MANUAL l
Vcit:me 5 04 S-01-EP-3 Sec'tien 1 Revision C Date:
EMERGENCY PROCEDURE CONTAINMENT CON' TROL SAFETY RELATED Prepared:
Date Reviewed:
~
Date Technical Review i
Reviewed:
Date Operations Superintendent Date Reviewed:
Nuclear Plant Quality Superintendent
(
Date
)
Approved:
t Assistant Plant Manager PSRC:
Date 1
List of Effective Paces:
Pace:
_Revisien :
[
l - 12 Rev. C l
l Attachment Rev. C l
81oinoych
GRAND GULF NUCLEAR STATION EMERGENCY PROCE*:URS
)PAGE 1 of/2 TITLE:
Centainment Control NO. 0 5 01-EP-3 REV. C 1.0 PURPOSE The~ purpose of this procedure is to control Containment and Drywell temperatures, pressure and level.
This procedure will be performed concurrently with the procedure frcm which it was entered.
2.0 ENTRY CONDITIONS
' NC7FE Enter the paragraph (s) of this procedure as required by the entry condition and perform only the' actions of that paragraph (s).
D05 to the c1cce coupling of all crntain: tent paraneters, when ene entry condition is met, all other paramenters listed below must be closely mmitored.
The paragraphs can and should be performed concurrently with each other as the entry conditions dictate.
Additionally, when the entry ccndition is cleared, the actions of this Emergency Procedure are not required and a return to normal operating procedures is encouraged.
The entry conditions for this procedure are any of the following:
Paracrach O
2.1 Drywell pressure above +1.75 psig 3.1,
O 2.2 Drywell temperature above 135 F 3.2 O
2.3 Suppression Pool tempera-g ture above 95 F 3.3s O
2.4 Suppressicn Pool level above 18'10" 3.4 O
2.5 Suppression Pool level below 18' 5.5" 3.4 O
2.6 Containment temperature above 90 F
.3.5 9
O
GRAND GULF NUCLEAR STATICN EMERGENCY PROCEDURE i..
l TITLE: Containment Control NO.
0 5 -S -ol-EP-3 REV.C FAGE 2 cf f2 3.0 OPERATOR ACTIONS Z:7 3.1 nonitor and control drywell pressure less than 15 esig and containment pressure less than 12 psig as follows:
NOTE If the drywell and containment require venting simultaneously by this paragraph, containment takes precedence.
((7 3.1.1
'dhen drywell pressure reaches +1.75 psig, confirm or initiate a reactor scram.
/[7 3.1.2 Containment Coolgng System - Containment Cooling mode -
if less than 212 F in the Containment.
Refer to SOI 04-1-ol-M41-1 at step later.
CAUTION i
Elevated suppression chamber pressure may trip the RCIC turbine on high exhaust pressure.
((7 3.1.3 ContainmentCoolgngSystem-DrywellCoolingmode-if less than 212 F in the Drywell.
Refer to SOI 0 4-1-ol-M'41-1 at s top later.
2:7 3.1.4 Drywell spray crire Protection System) by performing the following actions:
\\~'
z:7 l
a.
If drywell pressure increases to 15 psig, then shutdown the following equipment and spray the drywell to prevent exceeding the 20 psig Drywell l
design limit.
((7 (1)
Both Reactor Recirculation pumps
[ 7 (2)
Drywell coolers located on the 93' elevation of the drywell (4 total) 4:7 a.
soolA ane soo2A operated frcm panel P870, section 4 z:7 b.
sools and soo2s operated frem panel P870, section 10
((7 b.
Open SP64-F238 on panel F862.
l l
I
GRANO GULF UCCLEAR STATION EMERGENCY PROCE::URE I
TITLE: Containment Control NO. 05-S-01-EP-3 REV. C 2 AGE 2 of/7.
?
NOTC The Drywell Fire Pgotection System fusible links should have melted at 165'F.
f[7 c.
If the Auxiliary Building has isolated, the Drywell Fire Protection System can be activated by:
f[7 (1)
Open SP64-FA10A or SP64-FA10B (Auxiliary Building Isolation Bypass Unit 1), oE f[7 (2)
Rese't the Auxiliary Building Isolation Bypass Div I and Div II switches on panel P870, sections 3 and 9 and then opening SP64-F238 on panel P862.
f:7 3.1.5 If containment pressure reaches 7.5 psig, initiate con-tainment spray with the Containment Spray mode of RHR (Loop A preferred) for a period of time sufficient to maintain containment. pressure below 7.5 psig.
NOTE Containment spray should automatically initiate at 9 psig containment pressure, provided that +1.75 psig exists in the Drywell.
f:7 3.1.6 If the Centainment pressure cannot de maintained below 15 psig proceed to EP-5 (Rapid RPV Depressurization).
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GRAND GULF NUCLEAR STATION EMERGENCY PROCEOURE f
IUITLE:
Containment Control NO. 05-S-01-EP-3 REV. C PAGE 3 of /2 i
e f[/
3.2 Monitor and centrol drywell temperatures as follows:
f/
3.2.1 Operate all availabge drywell cooling when drywell temp-erature exceeds 135 F.
CAUTION Whenever temperature near the RPV water level instrument cold reference leg vertical runs increases above the calibration range, in-accuracies are introduced into'the indicated level.
The actual RPV water level may be below the elevation of the lower instrument tap with an indicated level reading on scale
~
if temperatures get too high.
/7 3.2.2 If the temperature near: the cold reference lea runs increases to the limits listed in the temperature column of TABLE A and the RPV water level decreases to that given in the indicated level celumn, then disregard the instrument for further reliability. '
Indicated LEVEL INSTRUMENT Temeerature Level Tvoe Rance Number agy 114 in.
Shutdown 0" to +400 in.
i
'B21-LR-R605 98 F
-115 in.
Wide Range
-160" to +60 in.
B21-UR-R623A&B B21-LI-R604 314 F 19 in.'
Narrow Range 0" to +60 in.
B21-LR-R608 B 21-LI-R60 6 A,B &C 380 F
-107 in.
Fuel Zone
-150" to +50 in.
B21-LR-R615 B21-LI-R610 t
1 TABLE A i:7 3.2.3 If temperature near the cold reference leg instrument verti-cal runs reaches the RPV saturation limit as determined from Figure A (next page) proceed to EP-5 (Rapid RPV Depressutiza-tion).
SEE FIGURE A - NEXT PAGE
EMIRGISCY PROCEDURI
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Centainment Centrcl NC. 05-S-01-EP-3 RIV.C PAGI 4ef/2 FIGURI i 1
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Drywell Spray is accomplished by utilizing the Drywell t
Fire Protecticn System
/7 3.2.4 If the drvwell temperature increases to 310 F, then spray the drywell in order to pravent exceeding 0
l the drywell design temperature of 330 F, as folicws in substeps a through c:
i l
1 Shutd'cwn the following eculpment:
O l
a.
O (1)
Both Reactor Recirculation pumps 1
I O (2)
Drywell ecclers located en the 93' elevation of the drywell (4 total) i O
(a) B001A and 3002A operated from panel P870, section 4 O
(b) 30013 and B002B cperated from panel P870, section 10.
_//
b.
C en SP64-F238 on panel P862.
l O
c.
If the Auxiliary Building has isolated, the Drywell Fire Protection Syste can be activated by:
l
/7 (1)
Ocen SP64-FA10A cr S?64-FA10B (Auxiliary Building Isolation Bypass Unit 1), or l
O (2)
Reset the Axuiliary Building Isolation Bypass l
Div I and Div II switches on panel P870, sections l
3 and 9 and then open SP64-F238 en panel P862.
O 3.2.5 If drywell temperature cannot be maintained below 330 F i
l procee-: to EP-5 (Rapid RPV Depressuri:Etion).
GF.A.'ID GULF NCCLEAR STATION EMERGINCY PROCEDUPI i
Containment Centrol NO. 0 5-S-01-E P-3 REY
- EAG', 5 c: /f.
C I
O 3.3 Monitor and control suppression pool temperature as follows :
O 3.3.1 Attempt to close any stuck open SRV.
O a.
If any stuck open SRV cannot be closed within approximately two minutes, from the time it was opened,seram the reactor.
NOTE The distribution of suppression pool temperature sensors and of SRV discharge points in the suppression pool are illustrated on Figure A..
Fesu F047N 00 F047A 344*
lto F0413 32*
F041D 4
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A=CREEN F051F IO473 240a 1200 a Cit 2tN D-m 3
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;;sge 1520 184*
1600
.gg3 Se tester followd by a color designates the ben color on suppression pool temperature recorders nT1-4045A, B, C, D, on panel IN1J-P970 FIGUPS A i
/7 3.3.2 If (1) adecuate core cooling does not require that RHR pumps be continuously operated in the LgCI mode and (2) suppression pool temperature reaches 95 F, then operate either RHR loop A and/or B in the:suppressicn pool cooling mode (04-1-01-E12-1, paragraph 5.3).
/_ 7 3.3.3 If suppression pool temperature reaches 110 F, then scram the reactor.
CAUTION Do not depressurize the RPV below 50 psig (RCIC low pressure isolation setpoint) unless motor driven pumps sufficient to maintain RPV water leval are running and available for injection.
O 3.3.4 Maintain greater than 50 psig RPV pressure unless motor driven ptmgs sufficient to maintain RPV level are running and available for injecticn as dete: mined by the following sequenm:
GRAND GU'F NUCLEAR STATICN
.rur.RcrN. C'> =.c.eC_e.. t.;;r
-u*
Centaiment Centrol NO. 05-5-01-EP-3 REV.C PAGE 6 cf 12 a.
Cbserie PPI water level indicatica to de+a: :im iniicated le/e1.
O
/ /
b.
Cicse ECC injection valve E51-F013.
/7 c.
Cbserie FFV water lewl and attec.<,. to raintain FFI water level with the retor driven injectica pl:ps which are : r.ni:g.
/7 d.
If PFJ water level mict be rain +*4.ed with de F "C injectica Falve E51-F013 closed, then open E51-F013.
M FFI water lemi can be raintai.ed with de PCIC injecticn O
e.
valve E51-F013 closed, then PCIC can be shutdown and the RPV c.ressure can be decreased to less t'v.n 50 e. sic..
_/7 3.3.3 Maintain Str=ressicn pcol water level greater than 14'6" in crder to raintain NPSH recuirements for ptr. ps taking a sucticn frc:n the st=pressi pcci with the folicwing vare.re li-itaticns:
HPCS, IPCS, and FliR - :axd::::n suppressicn pool tv atre of O
a.
C 21.'. F
~'
0
_/ 7 b.
RCIC - raxi:n=t sgressicn pocl tecrerarre of 140 F.
NTT Cooldcwn rates greater than 100 F/hr ray be reqc. ired when depresst= iring to raintain c
??/ presstre within the heat geirf te=erarre li-it as deter.imd by Fictre B.
_/__/
3.3.6
_I.f._ str.r.ression col ter:oeratre cannot te raintained belcw the heat capacirf ter.rera*~ "
d* as deterrined by Figtre 3, then rain *in
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GP.AND GULF NUCLEAR STATICN EMERGENCY PRCCEDURE UIdLE:
Containment Centrol NO. 0 5-S EP-3 REV.
C PAGE 7 cf 2
/
O 3.3.7 If sureression cool temperature and RPV pressure cannot be restored or maintained be3 w the heat cacacity temperature limit as determi.ned by Figure 3, then entel* EP-5 (Rapid RPV Depressurization)..
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GP.AND GULF NUCLEAR STAT:CN EMERGENCY PROCECURE l REV.C i -
PAGE 8 cf/2 TITLE:
Centainment Centrol NO.05-S-01-EP-3 j
1
_/_7 3.4 Monitor and control suppression pool water level as described in the following steps:
/_7 3.4.1 Maintain suppression pool water level between 18 '10" and
~
18' 5.5" as follows:
/7 a.
If high suppression pool water level (18'10") or low
~
Condensate Storage Tank level (2'0") occurs, then per-form the following:
(1)
Confirm automatic transfer of HPCS and RCIC suctions from the Condensate Storage Tank to the Suppression Pcol. by verifying the following:
(a) HPCS - E22-F015 opens and then E22-F001 closes.
(b) RCIC - E51-F031 opens and then E51-F010 closes.
//
b.
If the HPCS and RCIC sue.tiens did not automatically transfer as designe'd, then manually transfer the HPCS and RCIC suctions in the sequence listed in mbstep a.
/~7 3.4.2 Maintain Suppression pool water level greater than 14 '6" m_
in order to maintain NPSH requirements for pumps taking a suction from the suppression pool with the following temperature limitaticns:
a.
HPCS, LPCS and RHR - maximum suppression pcol g
temperature of 212 F b.
RCIg - maximum suppression pool temperature of 140 F.
i
/__/
3.4.3 If normal suncression pool makeup (04-1-01-Pil-2) cannot :aintain sc;pressicn pool water level abcve 18' 5.5" then scam the reacter and initiate SPMS.
l
[
/7 3.4.4 If an ECCS auto initiaticn signal is cresent, then initiate SPMS if it has not initiated automatically.
/~7 3.4.5 If suppression pool water level cannot be maintained above l
the Heat Capacity level limit as determined from Figure C, then proceed to EP-5 (Rapid RPV Depressurization).
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GRAND GULF NUCLIAR STA"!CN DiERGENCY PRCCIDURE
^AG~7 o#
Cm"4 rrent Centrol NO
- 05-3-01-EP-3
^ ~V
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3.4.7 g he.ry C::ntai. ent water level reaches later feet at O psig T
(cr:ntaiment presst=eb then terminate injection into the RW frc:a sources exterre.1 to the primary centtiment recardless of whether adequate core cooli:n can be assured.
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GRAND GULF NUCLEAR STATION EMERGENC'? PROCEDURE EITLE: ' Centainment Control NO. 0 5 -S EP-3 REv. C PAGE 11 of /l Z[73.5 Monitor and control Containment temperature as follows :
CAUTION Whenever temperature near the RPV water level instrument cold reference leg vertical runs increases above the calibratien range in accu-racies are i'ntroduced into the indicated level.
The actual RPV water level may be.below the elevatien of the lower instrument tac with an indicated level reading on scale if ' temperatures get too high.
/7 3.5.1 If the temperature near the cold reference leg vertical runs increases to the linits listed in the temperature column of TABLE C and the RPV water level decreases ro that given in the indicated level column, then disregard the instrument for further reliability.
' Indicated LEVEL INSTRUMENT Temperature Level Tvoe Rance Number a.7y 114 in.
Shutdown 0" to +400 in.
B21-LR-R605 98 F
-115 in.
Wide Range
-160" to +60 in.
B21-UR-R623A&B B21-LI-R604 314 F 19 in.'
Narrow Range 0" to +60 in.
321-LR-R608 B 21-LI-R60 6 A,B & C
~
380 F
-107 in.
Fuel Zone
-150" to '50 in.
321-LR-R615 B21-LI-R610 TABLE C
/[7 3.5.2 Operate the Centain=eng Cooling System when centainment temperature exceeds 90 F.
CAUTION Co not divert RHR pumps frcm the LPCI mode if con-tinuous LPCI is required for adequate core cooling.
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Containment Centrol NO.05-S-01-EP-3 REV. C PAGE 12 cf 12 C
/7 3.5.3 If Containment temperature reaches 185 F then initiate Containment spray per 04-1-01-E12-1 at step later.
_/7 3.5.4 If cntainment temperature cannot be maintained below 85 F then proceed to EP-5 (Rapid RPV Depressuri::ation).
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