ML20210V418

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Proposed Tech Specs 3.7.1.1 Revising, Plant Sys Turbine Cycle Safety Valves
ML20210V418
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/16/1997
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20210V414 List:
References
NUDOCS 9709230317
Download: ML20210V418 (12)
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Text

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Docket No. 50-336 B16724 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Main Steam Line Code Safety Valves Marked Up Pages September 1997 fDR DO 0503

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I n.a.v.1 Tutatur evetr 1ArtTY VALVE 1 Lllt!T!III ttWCITIM FOR OPERAT!M 3.7.1.1 All main steam line sede safety valves shall b OPEMBLE.

APPL 1tillLITY: M00tl l 2, and 3.

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{T4SitT A) y With/eth reacter seeladleeps and associat/stens generators in' s.

perable, e>eratip(s'er more main stena/ine cade safety valv6s ttien and with en e

s, either the,in, any 3 say proceed in Mocts I t

ed, 1

able valve is res d to

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at within t h CPEMBLE stat the Power Level h tris setpoint reduced per Table 3.7 1 otherwise, be in net HOT STAN05 ithin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> /d in HOT SHilTDOWN w) hin the fellowing ours.

autVE!LLAMCF REQUIREMENTS 4.7.1.1 toch sain steam line code safety valve shall be demonstrated CPEMatt, with lift settings as shown in Table 4.71, in accordance with Specificatten 4.0.5.

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glgl5 TONE-4811Tt 3/471 AmendmentNo.77.JJ7,JJJ,[f 1

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Insert A - Pace 3/4 7-1 a.

If one or more main steam line code safety valves are inoperable, restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.

If more than three main steam line code safety valos on a single steam generator are inoperable, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 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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MILLSTONE. UNIT 2 3/472 heenhentNo.h

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3/4.7-PLANT SYSTEMS BA$t$

3/4.7.1 TUR8INE CYCLE gg 3/4.7.1.1 SAFETY VALVE 5

'The OPERAl! LIT of the main steam line dsafetyvalvesensures that.the secondar system pressure will tied to within 1105 (1100

l psig)ofitsde gn pressure of 1000 ps ring the most severe anticipated s tem operational transion The maximum relieving capa y

is associst with a turbine trip fr 1005 RATED THERMAL POWER coi dent with an a umed loss of condenser h t sink (i.e., no steam bypes o

the con ser).-

he specified valve lift ettings and relieving capaci es are in ac rdance with the requiram ts of Section 111 of the A5 loiler nd i

essure Code,1971 Editio. The total relgeving capac y for all valves on all of the ste lines is 12.7x10 1bs/hr ch is 108 percent t

6

/ of the total secondary eam flow of 11.8x10 lbs/

at 1005 RATED THERMAL POWER..

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STARTVPand/

POWER OPERATION is allows e with safety valves _

inoperable withi -the limitations of the AC ON requirements on the basis of the r uction in secondary syst steam flow and THERMAL. POW required b e reduced reactor trip se ings of the Power Level-Hi channels. y e_ reactor trip setpoint ductions are derived on t following ases:

.For two loop operatio l

X 106.6 SP,=

y 47 l

where:

$P = redu d reactor trip setpoint in rcent of RATED l

/

TH L POWER i

y=

imum number of inoperab1 safety valves per steam line l

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d

%.tn.w..p;yf MILLSTONE - UNIT 2 8 3/4 7 1

insert B - Paae B 3/4 7-1 The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% (1100 psig) of the design pressure of 1000 psig during the most sever 6 anticipated system operational transient.

The limiting anticipated system operational transient is the closure of a main steam line isolation valve (MSIV).

The specified valve lift settings and relieving capacities are in accordance with the requirements of Section ill of the ASME Boiler and Pressure Code,1971 Edition.

The total rated capacity of the main steam line code safety valves is 12.7 x 10' lbs/hr.

This is sufficient to relieve in excess of 100% steam flow at RATED THERMAL POWER.

Plant operation is allowed in MODE 3 with a maximum of three inoperable main steam line code safety valves per steam generator. in MODE 3, the total relieving i

capacity of the main steam line code safety valves, assuming three inoperable main -

l steam line code safety valves per steam generator, is sufficient to remove the maximum possible decay heat load. Therefore, the remaining OPERABLE main steam line code safety valves have sufficient capacity to limit secondary system pressure to within i

110 % (1100 psig) of the design pressure of 1000 psig during the most severe anticipated system operational transient.

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I e

- h e r,7 M, 1 ^al

  • PLANT $Y$TEMS BASES 106.6 ower Level-H Trip $etpoin for two loop op [ation

=

X =

Total rol ving capacity g.35 x lob lbs/h all safety valv per steam 11 e in bs/ hour =

r Y =

Maxi e relieving ca city of any one afety valve

>0 in bs/ hour = 7.94 105 lbs/ hour 3 / 4. 7.'1. 2 AUXILIARY FEE 0 WATER PUMPS The OPERABILITY of the auxiliary feedwater pumps ensuges that the Reactor Coolant System can be cooled down to less than 300 F from normal operating conditions in the event of a total loss of off-site power.

s Any single cotor driven or steam driven pump has the required capacit/ to provide sufficient feedwater flog to remove reactor decay heat and reduce the RCS temperature to < 300 F where the shutdown cooling system may be placed into operation for continued cooldown.

/*

3/ 4. 7.1. 3 CONCENSATE STORAGE TANK

  • /

The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water {s available for cooldown of the Reactor Coolant System to less than 300 T in the event of a total loss of off-site power.

The minimum water volume is sufficient to maintain the RCS at HOT STANDBY conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam discharge to atmosphere,

,l3/4.7.1.4. ACTIVITY l'

The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction h m n.karaf N o.

ft MILL 5TONi: - UNIT 2 B 3/4 7-2

4 Docket No. 50-336 B16724

/

Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Main Steam Line Code Safety Valves Retyped Pages September 1997

J/4.7 PLANT SYSTEMS 3.4.7.1 TURBINE CYCLE l

1AFETY VALVES LIMITING CON 0! TION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:'

a.

If one or more main steam line code safety valves are inoperable, restore the inoperable valve [s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in HOT STANDBY within tie next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

If more than three main steam line code safety valves on a single steam generator are inoperable, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 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 />.

SURVEILLANCE REQUIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE, with lift settings as shown in Table 4.7-1, in accordance with Specification 4.0.5.

MILLSTONE - UNIT 2 3/47-1 Amendment No. JJ JJ7 JJJ. J77.

OtSt

THIS PAGE IN1ENT10NALLY LEFT BLANK MILLSTONE - UNIT 2 3/4 7-2 Amendment No. 77 0321

3/4.7 PLANT SYSTEMS

(

g,atre 3/J.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110%(1100 psig) of the design pressure of 1000 psig during the most severe anticipated system operational transient. The limiting anticipated system operational transient is the closure of a main steam line isolation valve (MSIV)

The specified valve lift settings and relieving capacities are in accordance with the requirements of Section 111 of the ASME Boiler and Pressure Code, 1971 Edition.

The total rated capacity of the main steam line code safety valves is 12,7 x 10* lbs/hr.

This is sufficient to relieve in excess of 100% steam flow at RATED THERMAL POWER.

Plant operation is allowed in MODE 3 with a maximum of three ino)erable main steam line code safety valves per steam generator.

In MODE 3 tie total relieving capacity of the main steam line code safety valves, assuming three inoperable main steam line code safety valves per steam generator, is sufficient to remove the maximum possible decay heat load. Therefore, the remaining OPERABLE main steam line code safety valves have sufficieit capacity to limit secondary system pressure to within 110% (1100 psig) of thi design pressure of 1000 psig during the most severe anticipated system operational transient.

i MILLSTONE - UNIT 2 B 3/4 7-1 Amendment No. 77. JJ.

0323

s PLANT _5YSTDil RAtri 3/4.7.1.2 AUXILIARY FEEDWATER PUMPS The OPERABILITY of the auxiliary feedwater pumps ensures that the Reactor Coolant System can be cooled down to less than 300'F from normal operating conditions in the event of a total loss of off site power.

Any single motor driven or steam driven pump has the required capacity to provide sufficient feedwater flow to remove reactor decay heat and reduce the RCS temperature to 300*F where the shutdown cooling system may be placed into operation for continued cooldown.

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available for cooldown of the Reactor Coolant System to less than 300*F in the event of a total loss of off site power. The minimum water volume is sufficient to maintain the RCS at HOT STANDBY conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam discharge to atmosphere.

3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction MILLSTONE - UNIT 2 83/47-2 Amendment No. JJ, JJ, JJ 0323

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