ML20095D951

Proposed TS Re Operability of Main Steam Stop Valves & Nonreturn Check Valves

ML20095D951
Person / Time
Site:	Point Beach
Issue date:	04/16/1992
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20095D945	List: ML20095D943 ML20095D951
References
NUDOCS 9204270269
Download: ML20095D951 (1)

Text

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. 2. Single Unit peration - The turuina driven auxiliary feedwater pump may be out-of-service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> If the turbine friven auxiliary feedwater pump cannot be restored to service within that 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time period, the reactor shall be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. I:ither one of the two motor driven auxiliary feedwater pumps may be out-of-service for up to 7 days. If the motor  !

driven auxiliary feedwater pump cannot be restored to service within

, that 7 day period the cperating unit shall be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Dl.y ThFmainisteainistop %1ves[(MS-2017 and;MS-2018)(and;theinonireturnichsck I i valvbsL.(MSh20 7Aiand 85f2018A)'shallibeLopera6fe.t [1.flonelmainTsicamistsp pal vs lor "honicturn Jchec k3 val ve Eis ; I noperably bu ffopenJ; powe rl opefa tion gay corif f nue Tprovidsd Lthe 11noperabl e ;valVeT i s }es toF;editoj opetableis t'atus Wi thinj 41hoursRoth{rs t se Lths#sactorL: sh"al;1Lbe; pl a6edlin ;a ; h6t7shb.tdosti cond'ilt i;oniwi t_hi f the ifol l ow l.ng ; 61h ours1 11 thloni.iorimo re7 ma i n? s t'e afs t sp valfesfoEnon2retlirnTcheckjalves[inoperab.lsfsubseqseilt(oysa,tihnlin ths het"shbtifoQn conditi'6n(mayfproceedRovidedTthe"inoperablefValie#DalVss t

are' ma[ntithed;closeal JAnlihopersble msin steamistdBalW^65snWeturii che.ckivalde msf?howeveMe"opensd inlthe?ho;tfshutdownic6ndiLtionfforIthe perf6r'rdandeLofLtestingsto1 confirm opeFainlityL Basis A reactor shutdown from power requires removal of cure decay heat. Immediate .

decay heat removal requirements are normally satisfied by the steam bypass to the conder ser. Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generatcr is converted to steam ay heat absorption. Normally, the caphility to return feedwater flow to the ste1m generators is provided by operation of the turbine cycle feedwater system.

, The eighi main steam safety valves have a total combined rated capability of 6, W ,')0') lbs/hr. The total full power steam flow is 6,620,000 lbs/hr, therefore eight 18) main steam safety valves will be able to relieve the total full-power steam flow if necessary.

l In the unlikely event of complete loss of electrical power to the station, decay heat removal would continue to be assured for each unit by the availability of

either the steam-driven auxiliary feedwater pump or one of the two motor-driven auxiliary steam generator feedwater pumps, and steam discharge to the atmosphere Unft-i--Amendment-Av.-91 l- Udt 2 Amcndment--ho-95 15.3,4-2a Ape 44-4rh-4985 9204270269 920416 ,

PDR ADOCK 05000266  ;

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