ML18136A336
| ML18136A336 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/28/1979 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18136A335 | List: |
| References | |
| NUDOCS 7912310506 | |
| Download: ML18136A336 (6) | |
Text
{{#Wiki_filter:.. e TS 3.6-1. 3.6 TURBINE CYCLE Applicabili tv Applies to the operating status of the Main Steam and Auxiliary Feed Systems Obiective To define the conditions required in the Main Steam System and Auxiliary Feed System for protection of the steam. generator and to assure the capability to remove residual heat from the core during a loss of station power. Specification A. A unit's Reactor Coolant System temperature or pressure shall not exc~ed 350°F or 450 psig, respectively, or the reactor shall not be critical unless the five main steam line code safety valves associated .J.6'1*
- .;ith each steam generator* in unisolated reactor coolant loops, are operable.
B. To assure residual heat removal capabilities, the following conditioqs shall be met prior to the commencement of any unit operation that would establish reactor coolant system conditions of 350°F and 450 psig which would preclude operation of the Residual Heat Rerr.oval System. \\ i ' rnc.*;1..c:w-* o,V-1'2':n
- 1.
Two of the th-r-ee auxiliary feed-water pumps shall be operable.
F TS 3.6-2
- 2.
A minimum of 96,000 gal of water shall be available.in the tornado missile protected condensate storage tank to supply emergency water to the auxiliary feedwater pump suctions.
- 3. All main steam line code safety valves, associated with steam generators in unisolated reactor coolant loops, shall~be operable.
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System piping;and-valves,Vrequired for the operation of the components "P.,_ 1_, 2., 3 i o.r,d C.. enumerated in Specification B.1, 2, and-3* shall be operable. "?,i.:'_: (~ ;r--e..:x:.to, pcwex. e.xceed-;..i",c\\ *\\07-1 -\\:\\,e. st-E:o.:,,'"\\ 2,,-r\\-.r~n c,uy,J~o..r'/ feec1,v,lo..,J:?Y' pui'nr S,\\,..:,__\\\\ b;c.. opc:\\--C-s.b\\(" __ The iodine - 131 activity *in the secondary side of any steam generator, in an unisolated reactor coolant loop, shall not exceed 9 curies. G. ):},, -i The requireLTtents of Specification B-2 above may be modified to allow utilization of protected condensate storage tank water with the auxiliary steam generator feed pumps provided the water level is maintained above 60,000 gallons, sufficient replenishment water is available in the 300,000 gallon condensate storage tank, and replenishment of the protected con-densate storage tank is commenced within two hours after the cessation of protected condensate storage tank water consumption. Basis A reactor which has been shutdown from power requires removal of core residual heat. Hhile reactor coolant temperature or pressure is greater than 350°F or
TS 3.6-3 450 psig, respectively, residual hea.t removal requirements are normally satis-fied by steam bypass to the cond~nser. If the condenser is unavailable, steam can be released to the atmosphere through the safety valves, power operated relief valves, or the 4 inch decay heat release line. The capability to supply feedwater to the genarators is normally provided by the operation of the Condensate and Feedwater Systems. In the event of complete loss of electrical power to the station, residual heat removal would continue to be assured by the availability of either the steam driven au.'Ciliary feedwater pump or one 0£. the motor driven auxiliary feedwater pumps and the 100,000 gallon condensate storage tank. A minimum of 92,000 gallons of water in the 110,000 gallon condensate tank is sufficient for 8 hours of residu.al heat removal following a reactdr trip and loss of all off-site el2ctrical power. If the protected condensate storage tank level is reduced to 60,000 galldns, the immediately available replenishment water in the 300,000 gallon condensate tank can be gravity-,feed to the pro-tected tank if required for residual heat rem.oval. An alternate supply of feed.- water tc the auxiliary feedwater pump suctions is also available from the Fire ?rot:ectj.on System. Main in the auxiliary feedwater pump subicle. The five main steam code safety valves associated ~ith each steam generator have a total combined capacity of 3,725,575 pounds per hour at their individual set pressure; the total combined capacity of all fifteen main steam code safety. valves is 11,176,725 pounds per hour. The ultimate power rating* steam flow is 11,167,923 pour1ds per hour, The combined capacity of the safety valves required by SiJe.cification 3.6 always exceeds the total steam flow corresponding to the m2Xiffium steady-state power than can be obtained during one, two or;three reactor / 1 .,61
4.8 AUXILIARY FEEDWATER SYSTEM ~nlicability Applies to periodic testing requirements of the Auxiliary Feedwater System~ _Q_bjective To verify the operability of the auriliary steam generator feed.water pumps and their ability to respond properly when required~ ~ification A. Tests and Fremienc-v 1..
- Eac.h ro::i tor driven au..""{i.liary steam generator f eedwater pump shall be flow tested for at least 15 minutes on a monthly basis t:o deIJ:;On.'3t::rate its operability.
2.* The turbine driven au..~iary steam generator feed~.;ater pump sh.al]. be flow tested for at le.a.st 15 minutes on a monthly basis to de!ronstrate its operab:iJ.ity.
- 3.
- The au:~iliary st:e.am generator feed-water pump discharge. valves sha.11 be exercised on a monthly basis.
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- During periods of extended reactor shu.tdow"D. the month..ly testing requirement 52',.
may be waived provided the component is tested prior to startup, Unit 1 Amendment No. 40 Unit 2 Amendment No. 39
II TS L~. 8-2 B. Acceptance Criteria t ~oc.:_11- ,_,.__. **~' These tests/\\shall be considered satisfactory if control board indication and subsequent visual observation of the equipment demonstrate that all components have o*perated and sequenced properly.
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__.:",(-_' (;c, i'., :,)\\.. c**,,.... \\r r-> -~ c_\\~- (-'-'<'"'\\_.. ( \\L, ---**~'-- \\\\._....:~ \\,_.._ \\.....* Basis On a monthly basis the auxiliary steam generator feedwater pumps will be tested to demonstrate their operability by recirculation_ to the 110,000 Gallon Condensate Storage Tank. The capacity of any one of the three feedwater pumps in conjunction with the water. inventory of the steam generators is capable of maintaining the plant in a safe condition and sufficient to cool the unit down. Proper functioning of the steai.-n turbine admissiori valve and the ability of the fee&~ater pumps to start will demonstrate the integrity of the system. Verification of correct operation can be made both from instrumentation within the Hain Control Room and direct visual observation of the pumps. References FSAR Section 10.3.1 Main Steam System FSAR Section 10.3.2 Auxiliary Steam System
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