ML20003H366
| ML20003H366 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/28/1981 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20003H362 | List: |
| References | |
| NUDOCS 8105050666 | |
| Download: ML20003H366 (2) | |
Text
!
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"