ML20148K421

Draft Sorv Procedure LOA-NB-02, Failure of Relief Valve to Seat Properly or Inadvertent Actuation of Safety Relief Valve

ML20148K421
Person / Time
Site:	LaSalle
Issue date:	05/29/1980
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML19345C352	List: ML20148K421
References
LOA-NB-02, LOA-NB-2, NUDOCS 8012040486
Download: ML20148K421 (4)

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- 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: .

a. SJppression Pool sater level INCREASES on Recorders 1)R-C3029 and lJR-CA031 on canel LPM 13J (Recorders 2JR-CM029 ano 20R-C9031 on .  !

panel 2PM13J).

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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).

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g. Generator load OEOREASES dith no change iq  !

Reactor Power.  :

1. I

n. DECREASE in steam flow on Recorder IC34-R607 l on panel 1H13-P603 (Recorder 2C34-R607 on panel  :

2H13-P603).  ;

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: l e

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.,. _i 8012040Wl# -

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• s LOA-NS-02 Revision 1 May 29, 1780 2

a. SJPPRESSION CHAMBER LEVEL HI on panel lH13-P601 (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).

a. ORYWELL AIR HJMIDIT7 HI on panel LPM 13J (2PM13J).

f. DRYWELL SUP P30L CHAMBER TEMP HI on panel IPM13J (2PM13J).

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g. ORYWELL SUP C4A98ER R ADIC ACT HI on panel LPM 13J (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.

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a. If the Relief Valve closes, it should be e

demonstrated opersole by performing L35-MS-R2,

- 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. > j.

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o. 14 %e. bli e.4 u\ve. e s.% t a s opsw g4+er oh tsu4 -Geov- E i 4 4ep c. 2. I'

.A4 c.@ +e e te s c. \ & , Nt.oc.e.E O -te , 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. I l

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- 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:  ;

a. R ED'JCE Rec i rc a; ;ti on Fl ow to minimum oy closing .

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).

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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 Pool temperature bel ow 130 F. t

3. LIMIT the Reactor Cool dosn Rate to 100 F/hr (T.S.

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LOA-NS-02  !

Revision'l '

May 27, 1980

" (finall j 4.' MAINTAIN vacuum in ene Main Condenser with tne SJAE, 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 l Pressure witn Relief Valves and START the Stean Condansing Mode of RiR in accordance with LOP-RH- ,

39, Steam ;ondensing Startup and Operation. l

a. If Suppression Pool temperature exceeds 120'F with the MSIV's closed, DEPRESSURIZE the Reactor to less than 203 .ssig at normal Coolcown Rates (T.S.3 6 2 1).

PERF3RM the applicable steps of LGP 3-2, Reactor i

- 6.

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) the Under mass fl ow rate appropriata of staan in the downcomer pipe. l i

aonor nal conditions unstacle steam condensation could I

! occur. Tnis instability sould result in a ouoblinginduce significant or

• cnugging orocess being set up wnich could For tne vibratory l oads on the containment structures. j LaSalle Plant tnis condansation instability region occurs

' at a localized o001 tamaergture F and steam nass of 150 performeo flos rate of 40 l om/sec f t . Analysis for the LSCS-FSAR (Amanament 37) and NRC Question 212 119 inoicates j

tnat, u7dar the, worst ooerati ng condi ti ons, tne condensation 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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