ML20148K421
| ML20148K421 | |
| Person / Time | |
|---|---|
| Site: | LaSalle |
| Issue date: | 05/29/1980 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19345C352 | List: |
| References | |
| LOA-NB-02, LOA-NB-2, NUDOCS 8012040486 | |
| Download: ML20148K421 (4) | |
Text
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t LOA-N3-02 Revision 1 May 27, 1980 1
FAILURE OF A RELIEF VALVE T3' SEAT.)ROPERLY OR INADVERTENT ACTJATIJN OF A SAFETY RELIEF VALVE F
A.
SfMPT3MS 1.
A Safety Relief Valve stuck open may cause any or all of tne following to occur:
SJppression Pool sater level INCREASES on a.
Recorders 1)R-C3029 and lJR-CA031 on canel LPM 13J (Recorders 2JR-CM029 ano 20R-C9031 on panel 2PM13J).
i o.
Suporessi,1 Pool and Suppression Chamber temperatures INCREASE on Recorders ITR-CM337 and LTR-C.M038 on canel LPM 13J (Recorders 2TR-CM037 and 2TR-CM038 on panel 2PM13J).
i Saf ety/Rel i ef Val ve Leak Detector alarm ol panel 1.il3-P631 (2Hl3-P601).
d.
Downcomer piping te nperature INCREASE on Recorcer 1321-R614 on panel lHl3-PS14 (Recorder 2821-3 R614 on pinel 2413-P614).
3 ADS /SRV OPEN al arms on panei 1H13-P601 (2413-P601).
i f.
ADS /SRV OPEN indication light on panel 1H13-P601 (Zil3-P631).
l g.
Generator load OEOREASES dith no change iq j
3 Reactor Power.
I n.
DECREASE in steam flow on Recorder IC34-R607 on panel 1H13-P603 (Recorder 2C34-R607 on panel l
li i.
INCREASE in SJporassion C' dauber background radiati on on Recorder 1R7R-CM023 on panel IPM13J l
(Recorder 2RIR-CM323 on canel 2PM13J).
i J.
INCREASE in Saporessior Chamber humidity.
2.
The above'symptons may be accompaned by any or all of tne following alarms:
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- s LOA-NS-02 Revision 1 May 29, 1780 2
SJPPRESSION CHAMBER LEVEL HI on panel lH13-P601 a.
(2H13-Pb01).
o.
AJS or SAFETY VALVE LEAKING on panel 1H13-P601 (2H13-P601).
ADS VALVE FJLLY OPEN on panel LH13-P601 (2H13-P601).
I de SAFETY / RELIEF VALVE FULLY OPEN on' panel 1413-P601 (2413-P6]l).
ORYWELL AIR HJMIDIT7 HI on panel LPM 13J (2PM13J).
a.
f.
DRYWELL SUP P30L CHAMBER TEMP HI on panel IPM13J (2PM13J).
4 ORYWELL SUP C4A98ER R ADIC ACT HI on panel LPM 13J g.
(2PM13J).
I S.
AJTJMATIC ACTIONS i
L.
None.
i C.
IMMEDIATE OPERATOR ACTIJNS' l.
Atte np t to CLOSE tne Relief Valve manuall y,by 31 acing the control switch to JPEN, then oack to AUTO.
a.
If the Relief Valve closes, it should be j
demonstrated opersole by performing L35-MS-R2, e
Automatic Depressurization System Flow Verification for onditions 1,
2, and 3.
C3NSULT Tecnnical Speci fi ca ti on Secti on 3 5.2.
I to cetermine li mi tations resulting f rom ooserving i
a Relief Valve i noperable.
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r CAJTION Tha time interval netween the Rel ief Val ve becoming i
STJC< OPEN and tne Reactor being manually SCRAMMED should not exceed 10 minutes.
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4.
LOA-No-02 Revision 1 May 29. 1980 t
3 2.
TRANSFER AJxiliary Powar to Transformer 142 (242).
3.
ADJUST Raattor Watar Level as necessary to MINIMIZE the affect of void collaosa.
t 4.
SHJT30AN tne Reactor as follows:
R ED'JCE Rec i rc a; ;ti on Fl ow to minimum oy closing a.
tne Recirculation Flow Control V a l,v e s.
O.
SCRAM tne R2a: tor.
c.
PLACE the Reactor Moda Switch to SHUTDOWN.
i N_0. !.E Pl acing the Reactor Mode Switch to SHUT 00WN sill avoid a MSIV closure and loss of tne Main Condanser.
5.
VERIFY that the Turbina/Senerator and OCS's ara TRIPPE0.
6.
VERIFY that Reactor Power has decreased oy ooserving tha luclear instrunentation.
O.
SJBSEJUENr,PERATOR ACTIOVS 1.
INSERT the SRM and IRM detectors to MONITOR Reactor i
Poder.
CAJTION Tha tine interval Detween the Relief Valve becoming STJC( DPEN and tne commencement of Suppression Pool i
Cooling shoula not exceeJ 15 minutes.
Suporession 7
Pool temperature s,oul d not exceed 100 F (T.S.
3 5.2.1).
c 2.
INITIATE Suppression Pool Cooling in accordanca with LOP-RM-13, Suppression Pool Cooling Operation.
MONITOR Suppression Pool temperature.
Using one or two loop modes as 1ecessarg to maintain Suppression t
Pool temperature bel ow 130 F.
3.
LIMIT the Reactor Cool dosn Rate to 100 F/hr (T.S.
3 4.6.L).
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LOA-NS-02 Revision'l May 27, 1980
" (finall j
MAINTAIN vacuum in ene Main Condenser with tne SJAE, 4.'
and SYPASS steam to tha Condenser to CDOL 00dN and DEPRESSURIZ_E tne systen.
I CAJTION
(
dhan using Relief Valvas to control Reactor prassure, nanuall y actuate Ralief Valves in alphabetical ordnr orior to Reactor pressare seacning 1376 osig, to nini ni ze cycling of the lowest set Relief Valvas l
and naximize Suporassion Pool. mixing.
l 5.
If a Group 1 Isolation occurs, CONTROL Reactor Pressure witn Relief Valves and START the Stean l
Condansing Mode of RiR in accordance with LOP-RH-39, Steam ;ondensing Startup and Operation.
l If Suppression Pool temperature exceeds 120'F a.
with the MSIV's closed, DEPRESSURIZE the Reactor to less than 203.ssig at normal Coolcown Rates (T.S.3 6 2 1).
6.
PERF3RM the applicable steps of LGP 3-2, Reactor i
Scran.
7.
00NOJCT'an inspectio1 of the Pressure Suppression structure if required oer Tech"ical Specification 4.5.2.1.
t i
E.
DIS:USSION Staol a staan conder sati on in the Suopression Pool i s j
datarnined oy 2 factori:'i)
Local sater temperature i n the vicinity of tne downcomer, and li) mass fl ow rate of staan in the downcomer pipe.
Under the appropriata l
aonor nal conditions unstacle steam condensation could I
i occur.
Tnis instability sould result in a ouobling or induce significant cnugging orocess being set up wnich could vibratory l oads on the containment structures.
For tne j
LaSalle Plant tnis condansation instability region occurs F and steam nass at a localized o001 tamaergture of 150 Analysis performeo for the flos rate of 40 l om/sec f t LSCS-FSAR (Amanament 37) and NRC Question 212 119 inoicates tnat, u7dar the, worst ooerati ng condi ti ons, tne condensation j
instaolli ty region coul d oe avoided if the Reactor is scramned within 10 minutes, and Suporassion Pool Cooling initiatad witnin 15 minatas of the Rel i ef Val ve bec: ming stuck osen.
Operator actions assumed in this analysis have sean incorporated into tnis procadure.
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