ML19220D070

Forwards Info Re Containment Peak Temp Profile & Bldg Spray Pump Head Curves

ML19220D070
Person / Time
Site:	Crane
Issue date:	02/28/1978
From:	Herbein J Metropolitan Edison Co
To:	Varga S Office of Nuclear Reactor Regulation
References
GQL-0321, GQL-321, NUDOCS 7905160469
Download: ML19220D070 (10)

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METROPOLITAN EDISON COMPANY ncs

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u POST OFFICE 80X 542 REACING, PENNSYLVANI A 19603 TELEPHCNE 215 - 929-0601

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Director of :iuclear Reactor Regulation s-Attn:

Mr. Steven A. 'la ga, Chief h

O[gg g 7 light ~4ater Reactors Branch :To. L gr U. S. :Tuclear Regulatory Cc==ission

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Three Mile Lland :Tuclear Staticn Unit 2 (CC-2).

/C;lgg Operating License !!c. DPR-73 Occket !c. 50-320 C- * '" ent Peak Temperature Profile and Euilding Spray Pu=p Head Curves Attached are revised fig 2res and pages pertaining to the Ccatainment Peak

"'emperature Profile and Building Spray Pu=p Head curves.

':his s5'-"' 4 "pdat e that infer ation fcrvarded to you en Februa y 1,1978, as part of the attach-nents to GOI 0131.

' ese vill be inccrporated into a future asent.snt and are being prcvided at this time to help expedite your review.

f ycu have any questicns, please contact me er :'r. J. Stair (F.:ct. 113) of m

a~...

,/53nc erely,

/

J. G. Eerbein

' lice President-Ceneration u un :o r.S : c,j g Attachments:

CC-2 FSAR pages 6.2-68 and 153-22; Figures 153-10, Sheet

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h. Ha-ley Silver Divisien cf Reactor licensing U. S. :Tuclear Reg:.latory Cc==ission

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O Table 6.2-l'_.

NPSE REQUIREMENTS FOR THE REACTCR SUII. DING S? RAY Pt.',MPS AND THE DECAY EEAT RE'dOVAL PUMPS Decay Heat Re=cval Pu=ps Reactor Building Spray Pu=ps Suction Flow NPSE NFSH NFSH Flew NPSH NFSH NPSH Fro =

gp=

Avail.

Reg'd Margin gp=

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Margin ft.

ft.

ft.

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a a

3 orated

• 3000 117.4 7.0 110.4 1500 117.4 12.0 105.4 b

b Water 64.4 57.4 68.4 56.4 Storage Tank Desi7.

6 c

e 3000 21.9 '

7.0 14.9 1500 21.9 12.0 9.9 Reactoc*

Bldg. Kuncut Su=p 4150 17.37-13.24 4.63 1740*

13.6f 16.5 2.1 Corresponds to a level of 53'-5" in 3 era:ad Water Storage Tank.

a.

b.

Corresponds to a level of 7'-0" in 3 crated Wa:er Storage Tank..

c.

Assu=es te=porary strainer in. suction. line en pu=ps has been rec:cved

- f-

-d.

Masd m calculated DH flaw -m w'-" x pcs: 4,9.d T:= ens. in t5e c=re " tife.;;

~

line between check valve C ~Tiia ani Me enem ficci - -%

stnf21x c. r.1-

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valve (DH-7-123A) fully coe:

E.ang: ters cecling fs: pr:vided by"cpening DH-7-7A or 3 to divert. a. %+ an: ci tha ** t-harga of the. Decay Eeat Re=cza.1.

pu=p to the suction of the Makeup (MU) pu=ps.

~he suction require =ents of

~ ~ ' -

the MU pu=ps do not change significantly, and a suction head of 43.2 feet is provided :o the MU pu=ps in this 2 da.

Assu=es that "l:v cent ci Tal.ve (35-7 A/3) has 'ceen th: :: led by cpera cr e.

before recirculati:n : de at 60 psie-building pressre.

f.

?'.n12:= 'iFSI conditiona cc ur at a

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s'- :

'a OcA

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en table 6.2-ila.

Sung va:ar is ass'-ad satration te=peratre of 250 ?

Ocr espending to centai=ent pressure of 29.3 psia e-va:cr pressre

1. d of 29.3 psia.

For su=p terperatres abcve 212 7 an equilibriu: satr atica ecndition is 9

assu=ed between sun te=perature

'.d centa'--=

pres:r e.

Althcush the 3?S' calculatics takes

--aA '- '- centain=ent press r e f:r su=; te=pe;2:,.res abcTe 212 F, the intent Of Re;; late:-/ Ouide 1.1 is =e because containment pressure is assu=ed equal to the vapor pressure correspcading to the sump t enperatur e.

+ A 7' ' ' ' " ' - 'i?SH f:r n0=inal "_ v vo s - -~ ~ '

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conta' ent is nore than adequate to handle any boil-off o#

e=ergency feedwater thrcugh the affected stea: generator.

Operator action vill be taken to isola:e e=ergency f eedvater to the affected steam generator in the 1cug ters.

Even withcut operator action, the contad ent pressure :-,d-s well belev the design pressure throughout the transient.

Due to the high enthalpy of fluid released during the steam line break accident, the centain=en: vapor te=perature vill be in a superheated state during the first portion of the blewdcwn.

For the steam line break with turbine stop valve failure, the centain-

=ent vapor te=perature reached a peak value of h36F and exceeded l

the design te perature of 286? f or an interval of apprcx1=ately l

75 seconds.

Ecvever, due to the nature of cendensing hea: transfer f rom the at=osphere to containment structures and equip =ent, sur-face ta=peratures were =uch lower than vapor te=perature during the transient.

The peak te=perature of the outside (centa1.._.ent at=os-phere side) of the centad-ant steal liner was caly 2257 and the peak te=perature of the incarnal concrete surfaces was only 220F.

S"d' arly, equip =en: inside conta1=:ent reached a peak surface te=perature of less than 270F.

As shown in Figure 153-10, in less than 100 seconds, conta en: vapor ta=perature and equip =ent sur-d face te=perature have co=e into equd ' *briu=.

Since vapor te=cera-

- ture is belev the LCCA qualificatio:r te=perature of 236F,.~it can

- be concluded that thi.r te=perar:re transient does nee represent a

ore severe envirot "t thac.the enviro t.1.n 4tich..the equip =ent

_hl{i r

was qttnH fied.

.;c.

The integrity of the steam generater duri=g the rupture of the secondary piping is discussed in Chapter 5.

It is cencluded in Chapter 5 that the prd=ary-to-secendary bcundary can na"--'d-its integrity in the event that a secondary pipe ruptures.

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