ML19207C002
| ML19207C002 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/17/1979 |
| From: | Broehl D PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML19207B999 | List: |
| References | |
| NUDOCS 7909060293 | |
| Download: ML19207C002 (3) | |
Text
t.m
.4w a
[
- - - = - : =
= ~ _
[...
~
~~==((..~ ~{
- T"
..c..,a,
.-.. - _' _ e. -,. s ;_.
..? : 2.
.,L. 4
?
4
.....c,.
,.,,,g _ gg,
.-.e.
~
'~~-:-*=. e,-
- :. m.,
. m,, -
.- n
- -. _ 2.: -
(~__y_ m_ 27'J..-d G:d EdK 'nc.23r/
" '- ~- y =: j s.,. _,
j i
_ _.- 4:_ _ _.,
r- >
.. j.
6
~
S_-
u...
OomW P>oeN Atss.a:Wce Presdent
,-...z,__.__,.._.__-___
.,uly 17, 1979.,,,,,,,,. - ~ - '__- -
.s_,._
-- r-g-
Trojan 'Euc1: ar I'1de Docket 50-344 s
s.
....................v.'..
I.icense l'.FF-1
-~' M ' '
-. -- -~.::---
~_,-:.'_-
..,......~.....~..1
-.. = - ~ -
....._g..,.:
=-=.-
3a.
~:<.,. c, -+. M,f,- -
,,-3 ;= _-;= jg-s'=;I.;= -
c Mr. E. H. Enn,e.lken,. Director U.S. Nuclear 2caulatory Cr---insion
-.. - -.. - u- =-:..,.
~
Region V
.=.a..-.a.
Suite 202 Welnut Creek Pls=a 1990 N.' California Blvd r
J. ' r.
. ~ - _ _.
-m..,,..
Unicut Creek'..CA 94596
...' __..m. _- c.._ 1 -- -
m-.
~
s-
~.,,
.Dacr. Sir:..
~'
. -:--..l-
__. E. k:^.2_-
.- =-
__m___--
IE Eulletin 79-14, e.'ated July 2,. l?79 enpreaned conccrn.nbout thy' _- _
necuracy. o'f'injut' 'infor:stion fe coisnic analf:cs~~cT_ h.370 _V ~r T Ef.fd "..
piping systers, acJ recucated verificatic: thc nnalytical an u: c.. t a -
cenfort: no inctclied cyste= cocli;;urations.. rne. yeri;ficeti:u7pr[T_ry.n.
~
required.cy.tais.oullatin is in.pr. ogress.
._c._._.
We have n'hich degree of confidence that the progran vill nor idancify.
any tafor: pro 312=s which vill affect th2 cperability of cufcty-r. elated piping systc=s at the Trojan Nuclect Plant, ter result in ca...-..-or m f1-cations to. piping ::strainta and supports. Tnis ecuc1'usien 'h E:'s3d'6n the results of:nuterous revicus and re evaluations involving ?Icfd ve'rificdioE~ ofpiping syste=s, cany of chich' have tchen r>1 cb fn~ the
~
les: 12 =anths.
A cu:::ary of these investigativa efforts.inc.ludes the _,
... f all.oul.ug:
L_ _, ;_ 7.,__
- 1.. Results..of. investigations initiated pursuant to other
~
~-
~-
IE Bulletina have revealed no cignificant diocrcpcicies."- '-'
Specifically,
-] J '
_ -y -...-.
y.. ;.;.-: _ _
a._
Appropriate co=puter codes were utill:e'd for.
'. w..J'...-.
. : ceia=ic analyses of safety-related piping,(IE.-
Eulletin 79-07).-
. 7 ".'*._ '. ':
- - _ _ - - -., _ ' ~.
~
b'.. Appropriate weights were utill:ed in annlyce_s
. ?_for cyctena with Vc1cn check valves (IE Eulle-
".' ~ y ; f. ";j O
- =-
... tin.79-04); and
. y
.m S
D
..%.mJ. {
- s. M 'pistes cad cuchor bolts did not identify nny concil _ _
- ' Field'inspectien ens t: sting of' pipe supp' ort' Ese",7,- ~
- [;
go.
' tions affecting the operability of cny Seicnic Cate: N'-
Q p
h Sl q 4.h,1M.. gory 'I piping cystem (IE Bulletin 79-02, nev. -1)f-
- ~;-,
^
M.
.... 4, 3
v
_v. m - __ _ _ _ _ _ _ _
m
__Y909360
. =;M _ _
i
._a
.m
..,.-s.
.. ~..~. : 2 :_'
. c5i - '; M 1
. - E,..* '$M_.' 5 2 :;-
,r -
-Q-M
=?
s.
....~--~=m_~
~
s
.s s
F=t's:d G ntm! Esc'zi:C=:.m/
- _ _1.1.
'. ' - - t.-
.--. __._=__=_-== Mr. R.
H.. E~%'elken
.1
.'..S.
m July 17, 1979
-. - # ; ;'2,-?
,~, - ~ rA.. m...
Page two-
,- m.
v-
- '-.- h'- l,.
2.
Ec-evaluation end codification of cupports.for.Scis-ifc-'352
'Citegory 'I pipi,ng in the Control-Au :111ary-Fuel Bu11 ding-- -
. ' Complex; to acco==odate' revioed SSE response 'c~pectra_hif.~ho'E.
yet identified any conditions which cifcet the operalfilitf.." '
.of[ oafety related syste=a- (Control Du11 ding proceedig)_.m.._
- - S.
- 3. ~ A survey of ccfety-related piping uns initiated in early'.
1978 to evaluate potential cdditional stresacs due.to -. f_ __
~
grouted vall penetraticas. This effort, uhich. involved.;, ;'
- a Unikdown~ of the piping and confir=.stics/closecut by drawing update to chow the location of vall panceratieda '.- ~
cn the piping iconstrica, did not identify cny ccadi-, -
_-[,
tionc which effected cyaten operability. (Licencec. Event _-_.. _ _
. ~fheport 73.'20, reports dated July 21, 1973, Octohir 6 _- J_ _ _
1978 and Decc=ber 25, 1973).
-.~. _~ _P__9.,_ -
- 4. : Dacign chances completed cince initici plant oper tion..,
have bacn controlled by = ca going design chen progren.
This progran includes tha clorecut of as-built dr.muin d hyl *
"tialki!ct.-i had =arhup of rI: sign drcuing ;, nhich' ar2 den
~
incorporated on the originals.
Esistionorren[dey(1gnl.1(,
,any, cre revicued and resolved.
In this =nnner, c continu-ing ' "cs-b'uilt" a tatus of ' design d:: vin;;s la cainhain C.
., p. s i.~ Prior to' initici operstica in 1975, the construction cenE'- '.
m,-
tractch provided details of the ac-built ccnfigura:ich ~ "-
of all critical piping to the designer for confirratica-against the stresa design iconetrics.
This review
- ~ '
' covered lall Sciacic Category I piping and other piplbsf_~ _" "
g whose. service condition nece ssitated stres s analysis;.,.- ;_.J....~.
Q__
-This review was conducted in parallel with a ainilar, _,m,,
M
.cohfir=s: ion /valkdown of Nuclear Class. I piping incide_ -.
3 rM Contcin=ent by en independent engineering ec=peny., In [
J.
addition to these checks, all the Seistic..Cctogory_I piping _
~-
2 QN system restraints were independently inspected by cu-f,_.
Architect-Engineer 's strena analysts to ensure that t_hef'.'
m c, 73 To]
as-built installction confor=ed_to the decign documento.
'ah i]
In' ench of the c!> ave revicua, the design ico=etrica were' r
.ccupared to the co-built inctallation to validate the Z '.' '~
4, *o t y"*
dcaign hacea of stresa cnnlysis calculation.. All.nigni-- l~.
'ficant piping and piping restraf ut data was inspeetc'd ch3_I _
devictions from design vere noted, evaluated, end r_eco'1,cd i
.pr or to initial operation.
__. r.i, -
_, n,
Thus, concidarable effort has been crpended to ' ensure' thlaccurcey'of--
design docu=enta, both prior to plcnt operation and during cub:cquent -
g p
c_:-'
_ O.
- -- ; _ c '
4 v.,.
,t.=
.-..-.-._.%g--.,_.._
_3.._a W.,y a Cs.e.,,u ' ::n.w :, C
.u
- /
- a.
r..wa-
-w.
Mr.
P.. H. Engelken n.
July 16, 1979
=
, Page -three
-.- ::.2: -
.~ -
.-: : - -.:1:
-- n --
' design changen'cnd re-evaluations of piping systems. ~ We are conf'iEent' that conditions identified during the inspections required by'Eulle-tin 79-14 vill not affese the operability of any cafety-reldtcd cfo'teh.
~
~
If any discrepancies are identified during th'c ccurse of tha~iefi'fication progran, they. vill be resolved in accordance with e.icting Technic 1 Specification requirenents.
Additional information concerning incpection cchedu.les and~dedigh-docunent list,inga_ vill be provided in accordence with IE Bulletin 79,-14.
Sincerely,
. - - ;~ ;-- -
J
- ...: ~- -- -
-.~ '- '~ ~~~
/s/ D. J. Brochl
~
jpc) -.
- -- ' _" ' T '_ :
DJB/,iE /4kkS3.1
.__i 5.#_ #
c: Director
~
....m.__2
- ~
w._.. _
Office of Inspection & Enforcement
- - ~-
Diree tor
- ? : F f.i'55=:-
_- -(
-Lw - f_:.
Nuclear Reactor Eegulation ATU;:
A. Schwencer
~
.=.
^_E Mr. Lynn Frank, Director State of Oregon
~ - ~
- -~,.. :1 ~-
Department of Energy
=
- v
-a.a+:.; :
~ -
- - '.M -
-. - -+ l '-,kL.-L 7
- -~
.x w s-
- I - I.. w re.5 _-
..--,-,-. e.. <., c. : ).,
y,y,,, o _ NP *./ '
_g_=.-=
. w - ~ - ~ a.
.-n.-..
-E
.m.
~ - -
.j.--.,.',..-
Q?f
&QOI
. ~ ~. ~7 L_. k.,,.,
~
1dbi((diMdlid((
- - = - ' - -
-S'-
~ ' '
.- - --~. ~ -
l~
.- -