ML19220B909
| ML19220B909 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/25/1969 |
| From: | Racquel Powell US ATOMIC ENERGY COMMISSION (AEC) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7904270648 | |
| Download: ML19220B909 (3) | |
Text
..
s
,.. % c.x
.e
,,NI
=,_.,.___
-o_
ATCN1!C ENE:.GY COV N ;55;C:,
. : s_
.a e s : :
.v x,
7.uly a,,.roy V
s J
==, r 4.,. D
~
.e
,/
"U.R'.' :
R. L. Iedasco, Chief, Reac:cr Project 3 ranch 2, DRL [
.e. r m._4 D ~... r.r.
Ac.c L m.._c.R.a-.r -v.
- n. _r e. s,
. pr..r_,,
u.Re.r...
v,.r r.
.a v
.e OCCKI"' NO. 3C-320 e
.o a.~
r....'~. - ( '.. ..-)
7-'
A C.. Ju.n.-.'O,
'c.60 ^ e '..-==_ M.31 f or a construction pe=it was reviewed by the ACRS.
The fc'icking are the principal areas which were discussed during the ACKS revies CRL & ACRS Meeting In the meeting with the C==ittee, we presented the matters
?. ch will require continued review or matters which we and the applicants were in disagree ent.
These catters are identified in section 19.0 Cc.clusion of our Reecrt to ACRS for TMI #2.
'4e reviewed the greuted tenden sur-eillance preposed by the appli-cants and-indicated cur pcsitica vas that the applicants should be required to provide embedded ins rumentation to provide a means of
=cnitoring the prestress condition of the centai= en: structure.
~ne ACRS indicated they could not support this positica recuiring e= bedded instrumentation for surveillance since they f elt the pec-posed pressure test with the tenden design =argin was adequate surveillance.
'4e indicated the research and development effor: to determine the ac ee: ability of the alkaline sediu thicsulf ate spray addi:ive was s till being reviewed.
It was indicated to the Cc=ittee that the use of the sodiu thicsulf ate additive appears to be an acceptable additive which is stable and cc patible with na = 3 C #cu "
d- ^e contai=ent providing a systen design includes a means of sa pling and controlling the spray solution pH to > 3.0 during and following the icss-of-coclant accident.
It was also indica:ed :o the Oc= i::ee that the DiI #2 was cc==itted to ins tallation of HIFA filters and reduction of contai=ent design leak rate to cc= ply with the Par: 100 guideline limits if sodium thiosulf ate iodine rencval constants are inadequate.
Aeolicants-DRL-ACRS Meeting
'he following catters were discussed with the applicants concerni. r
- he 21I 12 design and the applicants ' respense is indicated.
790427064 84-018
~
Files (50-320) July 25, 1969 (1) Greuted Tenden Surveillance
..Se
=y,_'4_ a - e.a_scn a.d
.'.e u-,.'"e'o-m.e ~.'. e. =, o.. - " _ _. ' - '., ~
n c
tenden design cargin.
The resul:s cf this cargin analysis were
.. c:
e. a_ s e m.e. e. ~ o ~ k.e n Fm. s ~m u,--
u. a_
u-...,a,e-2.
A ~.~_ee.k
- e..
-A
-v a
i
- A
-v
- he meeting report covering the July 9,1969 ORL reeting ~ith the applicants.
(2) Alkaline Sediu: Thiosulf a te The applicants indicated the research and develeprent effor: en alkaline sodiu= thiosulfate was cc=pleted and a draft reper: was e <_.. 3.e a. eve > cy s.sr.
- 1..., s < -a a. a, s o
.u. e C, __.<..,_,_
.u. a.
u n
.a.e i-a.. mea.3 v-
, a,
.4..,. ua,/ e tu.e ma,y u-w.e.3 4.. or su--,
--3 w
s us--
4,,
centrolling the spray solutica pH by per:1.ng the addi: ice of a
NaOH cr Na.,Se0- if requirad.
- a (3) Primarv Coolan Pu== F1rwh _ eel The applicants indicated to the Cc==10:ee that the flywheel material will be ultrascnic inspected during f abrica:icn and provisions will be made to provide access to the flywheel cc=ponents f or inservice inspection. 3&W indicated they had analyzed the gyroscopic effect on the flywheel during a des'gn basis eartha.uake. Alsc S&W indicated thev. would perform ad.1-tional analysis to deter =ine the ccnsequences of a flywheel failure.
Since ncne of these ccc=itsents are docu=ented, we vill foll:s us en these natters to get necessary documentation during cur post-constructica review.
(4) _ Failure to Scra en Anticirated Transients The Cc==ittee indicated to the applicants tha: :he consequences of failure of the control reds to scra: cn anticipated transients such as loss of turbine should be analyzed.
35W ag eed to revie.
the anticipated transients and the consequences of failure of the' centrol rod to scra=.
1p. e -
<,?
.o
.-. be a
.# '.'-w *o, '.=~-."'_.3
, o s. - c. -.. a-. -"- - '_ v- ".. a s '. =. ~m (3)
Staan 31ndinz Due to Stes: Genera:cr Tube Failure
-ine ae,'dre. s d.d'sa*.eA-
. o. '. a.
C--
.=_a_ *"a-
... e.. ".. - - : s. a-the ccid leg break with vent valves included 2 alicwance for e o..ev
.. a.s # e.. =.d.
.#. cu
.b..e s e r c..d '. v_ -- -S a.
.'-~a-~
s "; 3 = -.
gs w
84-019 M
Files (30-3:0) Juiv 23, 1969 during the bicwdcwn. 3&W indicated this energy transferred f rc= the secondary to the pri=ary coolant was ecual to 30 lbs/sec stea: injected into the pri=ary sys:e= vhich is e,s 4._,,........,, a'.' d ' a_ d s ea-3_..e.a a.
~.~ " e s.
a 35W also indicated tP ey had locked a a 100 lb s / s e c s t e a:
- 4.,.. ;ae n.a. n...a,-_
sec.,,_d..y -
p,.2
. :n.. n.< s-a
_,.u
-a0 ra4.,e. stea: generator tubes.
.40 adverse effect en cere
. s cccling was noted due to a stea= blockage.
(6) Sabe:aze The applicants indicated to the Cc==1 :ee the TMI site vill have a security fence and lighting around the site pe
'~a-a-and all buildings.
In addition all access :c the island site will have controlled access gates and building decrs will have centrolled access.
(7) Radiolvtic and Che=ical Hvdrecen Centrol 3&W presented to the Cc==ittee their analvsis of centrolline_
the hydrogen concentration below 4.1 v/o within the contain-
.. o 3., c s.. g a - - <
t.- g., p c.b. a * ' c a.l a -'Aeat b ", -u.3..-
s..
_ em...
.e e
3 at a controlled rate.
The 3&W analysis of the offsite deses are based upcn the containment edine being negligib.= a:
d
.n,
,.<._e u.e e..3._3
.a - <
.a n. t,., a.
u 2,,
o.
The Cc=uittee did not react unfavorably to the nethed cf purging previded the icdine re= oval rates could be supper:ed.
(3)
Cc==en Mcde Failure Analvsis
- n e", '. o.. e c -...*.".'...~3. c. a.". '. ac.
v e n-
.a.c.a a,s.o.k.e C-~~'.
ea.
aa their ins:ru=entation syste: for cen=ca =cde failures with LRL.
(9) Reactor Vibration Instru=entation 3&W indicated they had not censidered ins talling instrumentaticr
.o _, 4.c.
w... e. e a c. o. v '.'s. ~. d c a.
m" ".. 3... ~3^pe.a.'^-.
'.'..a_
C u- ~-.'.. a_ a.
.s e
c s.o.1 4... o;
- 4. s...~_,,,4..__....6..,_
3.. ou.1.a
._. c c a,.
6..e
,e
-w 4
4 4 _ c 4. ua-.,g..
aaa-
-r s
.j reac:cr :: detect changes in vibration characteristics as a =eare of early detectica cf an internal ec=c.onent detericration er failure.
f
. dh
.A -23 *j,,.n~,/_. /,w Pr_rncnd R. Pcwell, ?33-2, ~?l.
CC:
F.
Schroeder R.
S.
3cyd 2
-e...,...,
v
.s
.- 9,:, n.o s
~
- 2.,. d.w. 4 v...-_.3 w we
.-u 3
r.4.
ea.
a a.mo' 04
_2-
.s s.-
OD2."-
- e3 34 - 3
_