ML20077A811
| ML20077A811 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/04/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077A809 | List: |
| References | |
| NUDOCS 9411280026 | |
| Download: ML20077A811 (3) | |
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( $p#fj NUCLEAR f1EGULATOnY COMMISSION E
UNITED STATES Mf4 /
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SAT ETL fy4t i)AT10tL fr/ THL DEFJCr OF INCI FP PW !OP. PEGU! nTJnq RU A.If 0 TO /N #T U ' f N _ ] t! /m 1 Q 10 r@TIf1' Of fW lO LICf t' NHS. DJ'? 70 /WD DPP;75 PUDI IC SU"/ Ki Fl FCir!C & C.
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.DO W f i m 50 2/.2 /4 50-311-1.0 IN W uw U gN Bf lotter datml August 19, 1994, as supplc nie.I October 4, 19', Public Ser iu Ele:t ric & Cas Commy (the license -) submit t ad a re<;m,1 for chang',
to the Sdm Nuclear Generating Stat ion, Unit liu s, I and 2, Technical Sp, :i f icat ion s (15).
The requ"3 ted change, would revise the sten genera' water lu low and low level trip setpoints.
The chany, woubt in<:rm. ' the or, 't ing urgin relat ive to stmun generator lewl which would help preclbJo unn >m. ary read m trips an l an iliary feodaat ur sy 4t er. (AfW) actuations during pl w t evol. ions inolving steam generator water level changt.
The supple: mtal letter provik, ad !ilional infornation, but ds, not change the initial proposed no signific mt h u.nds consideration determb,ation.
2.0 I WiU"t!.109 lhe propowd change, are bs, ! on reduced channel uncertainties that have been cah ulated by the licens'. usinj a setpoint methodology consistent with the Instro ent Society of k erita (ISA) Standard, S67.04 1982, "hetpiints for Nuclear Safety Palat ed Instru: o tat ion," which is endorsed by Regula!nry Guide (P0; 1.105, Revisic.a (Re /.) 2, "Instrunntation Setpoints for Nuch tr Safety Rel at ed Ins t run ><n t at ion. " Th; redn' tion in channel uncertainty is prhaarily the result of replacing the Rasemount 1153 series level transmitters with Row,suunt 1154HH trun mitter.s.
The total acciih nt unt vtainty with the Rosemount 1153 series transmitters result +..d in a 15.3% narrus r,r span (NRS) error.
This accident uncertainty with the Rosemount 1154HH trar
'ters was reduced to 7.407% NRS.
Bamt on t'
reduced uncertainties, the 3etpoints and allowable values can be reduc :.1 anu still ensure the analytical limit of 0.0% NRS is met with exce_,s margin.
9411280026 941104 PDR ADOCK 05000272 P
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. The steam generator water low-low level signal initiates a reactor trip and actuation of'the AfW system. This signal is used as a prim try protection signal for postulated de.ign basis euents including loss of norml feedwater, l o s t. of off site poer, and festater line lo sak The proposed chtnges would revise the stean generator wit er low-loa l i setpoint, in TS Tables 2.2-1 and 3.3-4, from 21G4 flRS to 79.0% firs, an ali m blu value from a14.8% tiRS t o 23. 0 '> liRS. The propned setpoint and ally l>le value wMid ensure the i
analytical limit of 0.0: fu is r t with en margin. The propo M redurLions to the sotpoints and allowable valuc, for the 1 los and low stemn l
gerinratm 1r signals wo"ld not af fect the pii.haility of any transient that the prutectic signals ar o
.ignnl to miti ;a'. The chanys wanld redum the d-probability of unnec essary r eactor t rips no! Au<i t iary feedaat ar (AfW) system actuation by providing greater oj ting gin fu plant evolut ions involving ste m gennrator chang.
(e.g., plant stu i;p).
T here fo re, the pn ud ch uqpw do not involve anj increase in the prob bility of an au.ident l
pre iumly evaluated.
The t.to genm ator w3' low lesel signal coiraid.?nt with the stean flow / feed flow r ich signal initiates a reactor trip. This signal is not credib l in the safdj analy;is, but incr es as tha ov.wll reliability of the RPS. lhe proposed changa, would revise the stx a geraine water low level an !
~
stec/fembater flow ni:utch setpoint, in TS Table 2.2-1, from 2257 tms to 210.0/ fM, and t h" allowabl" value f mm 2244 fa to 29.0a flits.
Be w it is not credited in the safety analyt i; re is no analytical limit associated with the sina generator watnr low level signal.
The uncertainties calculated for the stue g w rator wator lt level signal are id-ntical to those of the low low signal.
Tht reduction in the low level setpoint would incroe 1:
margin available for stean geni rator vider level recovery when a flo;. M tch Condition eilsl5 lht propnsed change, to TS Basis 2.2.1, Roactor Trip System Instrun tion Sot pints anJ 1S Caw, 3/4.3.1 and 3/4.3.?, Protectiv and Engineerin, SafMy features Instruent ation are to clarify th (;eneral r ationship but a n setpnints, allue.Y" values, and analytical limits us J in the safety a n al y.; i s.
These changes are based on the improved Westinghouse Standard TSs fiUR!G 1131 Da<os 3.3.1.
The licensee has provid-d jnstifiutien for differences bete a fiUREG-1431 and the propose! changcts i
fiUHf fb l431 refen
's "RTS/ESFAS Setpoint Methndalogy Study." The lic.ns
's setpoint method;1u y is not based on the "RIS/E5FAS Setpoint Methedolo;,/
s Studj", but rather ISA Standard 567.04-1932 s.hich is widely used in industry and is enJorsed by RG 1,105, Rev. ?.
fiUREG -1431 re fer to t he CH?MEL DPGATIDW TEST (Luf) as the test which is capable of detect ing th,se rwasurewnt uncertainties co:rpr
'ng the differences betw&n the trip setpoint and the alioWable value. lhe liconsee's bases refer to a CHlm:KL IUK fl0E TF (CFF), which is equivalent to the COT in l;UREG-1431.
The Cii is defined and 3pecif ie! in the licensee's TSs
4 1
i e
e d,
NUREC-1411 includes a paragiaph that discusse the ability to te.t channels on -l i n e "to veri fy that the signal or sotpoint accuracy is within the specified alloru _e requin ' mt: of [U:
1 Ch ap t e r f;].
The lice: Ws j
baso do n,t include a pa yrgh with tnis informtion and Uf Sf" Chap!" C dni not s,
- i fj chann d " allow m > rt pire d s" Hcn r/er, the lica n
's l
l ISs anj Hm,
define test t w i m..
,J s in suf ficient detail so th.:t a j
parajeoph similar to th pn tjra% in NURFG 101 i s nct nec es tug.
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i l
l We br/e revim -l lho l icen; > 's calcul at ic f or th steam genorfor wat> i
]
l low-law and lm, leul setpints amt allc a b value s that w ee s6.it tm!
i Oct A 4, 101, aml hw fc.un ! t he t o be con id + nt with the gui:blinu sp & ificl in I? Stnelnd 5',/.00-19';'
4 Da
"! on t hi a!
tho :. t a f f f i m !. t h e prop-
! c h m >. t o tk Sa' I
CN u it ie j st at ion t! nit Nm 1 and 2, 15 Tahl:
2.2-1, ls lable 3.3 ; and Ua l
2.2.1, 3/;.1.1 and 3/4.3.? at:cep' M e.
I 3.0 S1Ai! CnN M p f luN 1
In acrocl + o with the rm 'i s '. i un's regul v i on., the !L : Jer % Stato eg c ; 31 r
was notific1 of the pr p I i3 3uam of the a--
ats The Stat-o f f icial h x' n a c e m '_ s.
4.0 INVlf V ; f/l UW.!m u f f p I
lhe ao n t sts chany a regin gnt with r"y.'
t in im,t all at i: n m us of a fa ility co~p: e nt located within the 1 J ris t e:! ar a a' defin 1 in 13 CFR Part P A NFL staff has d4 " ained tha t th > ac m en; > invul, nn signi!
4nt i n c r e ; ^., in tho ac.m n's, and no si ni fic u t ch<uy in th; t yp.,
g l
of anj ef f im ots that tw be i oleau ! of f site, and that tha is no j
significant increas in im!ividual or con ;1ative co upational radiP ion j
expu w.
The Con :ission ha. nrevico dy iswd a proposed firatig that the l
am nJ; sots involve no signifit. ant haurds c onsideration, anJ there has ben no 1
pnM ic com,ent or such finding (59 i n /,71T;0). Au ordingly, th( asyn.L ents l
meet the eligibility criteria for categ'u ital mlusi set furt h in 10 Cf R 51.22(c)(9).
Pursuant to 10 CFR 51.22(h) no envirom otal impact stateent er enviruna> ental assessment nen! be pr ep u s! in cun m t ion with the issuance of the aendments.
l
- 5. 0.( ON r. l. U. S I ON 1
The Comission has concluded, based on the co sida atior-c <ne t! above, i
that:
(1) there is reasonable assurance that tho h" dth and safeij of the public will not be endan n ed by operation in the proposm! rrat, (?) such act ivi t ies will be cont'
.t ed in co;pl ianc + with the Co m ission's reg,0>ti" ar ' (3) the issuance of the as
~nts will not bo inimical to th.. c t. :
a d<
o w and security or to the hr d th an ! safety of the p blit.
Prinric d Contributors: B. fiarcus H. Dalukjian D3 t.
%t H 4, l W,
.