ML20003H366

Tech Specs 1.2 & 2.2 Re Bases for Safety Relief Valve Setpoints

ML20003H366
Person / Time
Site:	FitzPatrick
Issue date:	04/28/1981
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
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ML20003H362	List: ML20003H361 ML20003H363 ML20003H366 ML20003H367
References
NUDOCS 8105050666
Download: ML20003H366 (2)

Text

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.- 9 ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGE RELATED TO BASES FOR SAFETY / RELIEF VALVE SETPOINTS 1

POWER AUTHORITY OF THE STATE OF F W YORK JAMES A. FITZPATRICK NUCLEAR POLER PLANT DOCKET NO. 50-333 APRIL 28, 1981 i

I l

I l 8105050 blab

I I . 2 arul 2. 2 ilASES .IM tal'I' line reactor coolant pruneurs lusunetas y AllSI Ceule pesimits prammisro transiente up to integr it y le an impor t arit Isar s less las t lio 20 toon cassit over t ino ele:alajin geressuint es (12 fit at ps evention of uncontrolled s aluaua or 1,150 - 1,1110 psig). Tlus asafest y lisel t f i solose prrutuct s. It lu uuuential t i e.i t. pr enuus es of 1,175 polg lu s o rna nne e .1 t o t lie l

time Integr ity of tint o tunind.e t y leu pa ss- lowout cluvation of t iee Itc act os s 'e wil a sit t ecto.1 lay estatillulaisig a tireuunin l i na l t. Syut ews, t o lee oleuerved f or til l opu r a t I sig con 11 -

t iones anil wisenever t liero tu 1 aillat eel Tlio analyste in Nt'IM-24242, Supplernont al foul in tints reactor versuel. Steload 1.lconuing Solani t t a l fo .hsmoe A.

FitzPatrick Huclear Powot Plant Italuad 1, 116e pressure safety limit of 1,325 lus ig reintisar y 1900, uluum t inat. t lies sam l ei u t etam as momuured lay the venual uteaue upacu inoletion valve clounto t r aris tent , witle promasure Indicator is agulvalesit to f lisia s c r asi, l es tlin erioist. eseven e ovetrit r es -

1,375 pul9 at tine lovent. e tuvat ion of uulting directly in a no.sctor coolant the stcact or Coolant Syst em. The 1,175 uyut es- pn eustare i ncr earao. Tlio rnactor psig v.aluo is derivod tusse tho doulun ventol piena.ut e cauto limit of 1.37*: pulg, paeemus um of th s reactor prouaitre glosn in TSArt Sect ton 4.2, la alaivo ilus voswel and reactor coolant. esyuteim Inak promuuso produced ley the event alusve.

pipling. The respectivo doulun prouuureu Tiniu , ti.e prema.uso safety l leni t (1,1/$ pulg) aro 1250 pulg at 575"r for tho scactor le woll atnivo the peak pecuutira that can veuunt, 1140 psig at 5611"r for t he ru- r u e.u l t. f om s eauonalit y empuct ant over preuuua n ci rcul ast l ani muction piping and 1274 poly t a an:s f ont e. l'igun o 7 in in.im24242 prouent u at 575"r f or tiies disclian go piptsig. Tho the curvo produced by tiilu analyulu.

prosesuso safety limit waes chouen au tlin Ituact os- lironunire is cosit t ention s t y l eid i cat ed lowe r o f t he p r euuur es t r asiu lesit as pe rmi t t eil lie t lies cont a ol roe.m dian-! sus espes .it t eni.

by tlie applicalslo dets tyri costuta s 19f.*> A!. Hit Ito!!ur and Pressun o wouuul ce=to, Suctlon A safesty liselt is appt lud to the liculihnal III for the preusiese vuuuest anul 19fe9 ANSI Ilea t. Itenu> val eyestem (801143 ) when it les operalisuj l

p11.1 Codo for t he reactor coolant nyut em i n the ulnit down cooling mule. 4thon oposatirig i

piping. *line ASHE iksilesr and Pe eranules ist f lin uhigt etown ciH3) j gig ma ple, tho l(jll($ jg Vo u ua l C<ulo pe r sil t u p r ensuis t o t r anu t ent es l eic linded in t lio e u.ictos c. .o l a n t t.y u t eis.

ugs to 10 percesit. cves alculgn pe cu:inin o l

(llut s 1,250 - 1,175 polg), amid t ho The numerical distribution of nafety/ relief valve set points shown in 2.2.1.n (2 0 1090, 2 63 1105, 70 1140) is justifimi iy analyses denctibed in the General Elect ric r eport NIJO- }

24129-1, Supplement 1, and annus es t hat the structural acceptance triteria net forth in the Mark 1 Cont ainment Short Term P oqram, for prot ect ion of torus inteqrity, are natisfiel.

Amendment No. 49 2"