ML20138B481
| ML20138B481 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/07/1985 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20138B479 | List: |
| References | |
| NUDOCS 8510150371 | |
| Download: ML20138B481 (5) | |
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Docket No. 50-245 Millstone Nuclear Power Station Unit No.1 Proposed Revisions to Technical Specifications l-October,1985 0510150371 051007 PDR ADOCK 05000245 P
PDR l
%e systsi rey be manually initiated at any tine. We systm is autmatically initiatai m high reactor pressure in excess of 1085 psig sustained for 15 seccrds. %e tire chlay is prwided to prevent umeassary actuaticn of the systm durirn turbire trips.
Autanatic initiaticn is prwided to minimize the molant Ims folicwirg isolation frm the min cxndenser. Make-tp water to the shell cide of the isolaticn cxnknser can be prwided by the mrdensate transfer ptrps frm the cr:rdensate storage tank. %e vu&uate transfer ptrips are cperable frun cn-site power. %e fire protecticn systs is also available as make-tp water. An altermte method of cooliry the cxxe uptn imlaticn frun the min crntnser is by using the relief valves ard DCI subsystm in a feed ard bleed manner. %e minim shell side eter voltre in the isolaticn w&wr is 15,500 gallcns.
%e function of the Imlaticn Crnhnser ci2 ring a snall break accident is to assist the autanatic pressure relief systan in depressurizing the reactor as a backtp to the DCI systm. %e two effects of isolation ocnchnser depressurizaticn are: (1) the minimizatim of the reactx inwntcry Ims which ncrmily emws ci2rirg APR blowtkun; this reduces the tire of cxre uncxwery prix to refimding; ard (2) earlier orset of Icw prmwe core spray croling.
l Analysis pafwei by General Electric in Mart:h 1976, in sigxrt of extended operaticn of Millstone while the isolaticn cndenser was being retubed indicated that frun 40% rated poer, cuer 30 ninutes is available to initiate cperatcr acticn to mitigate the consequences of a less of all feechater. %is is based tpcn rarual depressurizaticn with APR ard molant stgplied by all UCI and core spray subsystas. %e DCI was asstred lost as part of the normechanistic asstrpticn of loss of feechater. %e a-ful mitigatico of this pmmleM event was no uncomrirg of the fuel. Operatcrs are instructed regardirg special procedures to be utilimd durirg this enb of plant cperticn.
F.
Etnapcy Cbolirq Availability he purpose cf Specificaticn F is to mne a minirun of cxxe coolirg aquipnent is available at all times. If, for exatple, cre are spray were cx2t of service and the sergency poer scurre which pcuered tre cppmite mre spray were cut of service, cnly two UCI pumps would be avai1^51a. Likewise, if two UCI ptrgs were out of service ard two mergency service water purps on the qposite side were also cut of servi, ro etntairnent cooling would be available. It is durity refuelirg M-that major mintenaroe is perfecxd ad ci2rirg stx:h tire that the Icw prmwe core coolirg systan rey be out of service dependiro cn the activities being perfctmed. Stecificaticn F allows rmoval of cne CRD rectunisn or fuel rmrwal and replaoment while the torus is in a drained conditicn witin2t uvuuising axe crolirg @ility. %e _pecificaticn establishes the mininun operable low pressure core moling systen, water inventcries, electrical pcwer stgplies ard other ackiitional retpironents %t rust exist to allow such activities as CRD mechanisu raintenance cr fuel rtrwal and replacement, to be perforred in parallel which other major activities. %e avialable core coolirg @ility for a potential drainirg of the reactcr vessel while this work is performed is based m an estimated drain rate and tre mintained ninirun eter lem1, in the refuelirg cavity to be stpplied to the reactcr B3/4 5-4
LIMITDE (DOITIOJ FOR OPEPATIO1 SURVEIIDNCE FEUJIIMBIP 6.
Except as specified in 3.5.F.7 when irradiatai fuel is in the vessel and the reactor is in the cold stutdmn conditicn, all law pressure core and ccntainment crnlirg subsystans mf be irgerable provickd tMt no work is beiro dxe which tus tM potential fo-drainiry the reactcr vessel.
7.
Men irradiated ftel is in the reactre vessel and tM reactor is in the refuel condition, control rod withdraal arrt rt@misu replaarent or fuel renoval and rep 1W. m/ be crnicted prtwidad that the followiry
<rrditions are satisfied.
(a)
The reactor vessl hea3 is removed.
(b)
The cavity is finrrhi.
(c)
The spm.t fuel pool gates are runaved.
(d)
Water level is maintained within the liraits of specification 3.10.C.
(e)
Either (i) both core spray systen, (ii) both Icw pressure mniant injection systen, or (iii) cre core spray ard Icw pressure coolant injecticn systan supplicd by irriperdnt electrical pwer shall be cprable x available for operaticn with tie roeprtive 4160 volt su; ply treaker(s) racked cut.
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LIMITDG GNauOi RR GEMITOi SRVEIIDNT NevJIRENNr (f) With the torus drained (i) the EOCS ccnfiguraticn required in 3.5.F.7(e) shall be aligred with the condensate storage tank and the omdensate swap tank sucticn valve V7-58 ladoed cpen, (ii) the condensate s u + tank shall contain at least 414,000 galinns of tr.ahle Water.
l (g) The. miniaun electrical power source requirement shall be the same as specified in p=cy@ 3.7.B.4.
(h) No idork will be perfctmed in the reactor vessel other than fuel sipping idtile a crmtrol rod drive housing is cpen.
(i) Fluel removal and relW will not be dre without a full complement of cxmtrol rods.
(j) nring fuel nounent to idock being &ne idtid has the potential fcr drainirg the vessel.
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