ML20092K221

Proposed Tech Specs Re Main Steam Sys Valve Testing & Operability

ML20092K221
Person / Time
Site:	Point Beach
Issue date:	02/21/1992
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20092K210	List: ML20092K203 ML20092K221
References
NUDOCS 9202250105
Download: ML20092K221 (3)

Text

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2.

Single Unit Operation - The turbine 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 driven 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 />.

Either 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 operating 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 />.

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Bij6Ed?jf"t h~s~ hitTihiifB6EE6EdTfT6nTf6F~thi~p}ZfBJgE6f?Tii[gg3 MiB LojiFilillityM Italii A reactor shutdown from power requires removal of core decay heat.

Immediate decay heat removal requirements are normally satisfied by the steam bypass to the condenser. Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption. Normally, the capability to return feedwater flow to Jg the steam generators is provided by operation of the turbine cycle feedwater non.

no system.

ooW The eight main steam safety valves have a total combined rated capability of ex 6,664,000 lbs/hr. The total full power steam flow is 6,620,000 lbs/hr, therefore ou

o eight (8) main steam safety valves will be able to relieve the total full-power n<

a steam flow if necessary.

m In the unlikely event of complete loss of electrical power to the station, decay o a.o.

heat removal wocid 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 Unit I faend=nt NO. 01

" nit 2

?::nd=nt No. 05 15.3.4-2a f;ril 20, 1035 l

I'.4.7 MAINSTEAM$$ TEM,GTOPVALVES 5

ADDlicability a_n MS,,

Applies to periodic testing _d__!sur_ve_il_l_anc..e of the main steam stop valves- _.,

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Ob.iective To verify the ability of the main steam stop valves to close upon signal [RQ

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SDecification AEEd5NSISM5Sf5MIYE15I The main steam stop valves shall-be tested under low flow conditions lfjlf

_., Tore.l,_,f_611_o_w.. ___t re::t:r shutdowns for major fuel

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reloading.

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(#pitMpilj{ssiiltBQl)R@ji] Closure time of five seconds or less'shall be verified.

The five seconds shall be measured from the time of signal initiation until the valve di:: is br: ght 10 : h lt by the d::hpet

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Basis The main steam stop valves serve to-limit an excessive reactor coolant system cooldown rate and resultant reactivity -insertion following a main steam break incident. Their ability to close upon signal should be. verified at each

scheduled refueling shutdown. A closure time of five seconds was selected as-being~ consistent _with the expected response time f6r instrumentation as detailed in the steam line break incident analysis.- The test procedure need not require steam to be flowing in the pipe.. St:ti

^nditica: re ::: pt:ble. The pre: n :

ef ficwing :te= cr : pre::ure difference will :::t the v:lve tight.

h_eck,a_ val ~ves.~ti, sit.,o_r~preve_nt the?bl_owdo,,w_n_, _h.

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15.4.7-1

. M:rch 23, 1987 n_4.

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References FSAR - Section 10.4 FSAR - Section 14.2.5 P

I Unit 1 Amendment ?!c.106 15.4.7-2 March 23, 1987 Unit 2 A=cndment !!c. 109 j

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