ML19256D142
| ML19256D142 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/05/1968 |
| From: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910170632 | |
| Download: ML19256D142 (4) | |
Text
a P00R ORIGINAL Peter A. y.crris, Dimeter Divicica of Reactor Licen:in; P0.en. % C L, w.m.y r.T -PL,-., e.u.- _ 4 C,..u.,..r e. c _-.., v. w. r,,-.--.
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The items listed belov are identified as felicv-On ite=2 to ne :::::...._.
per=it review of Mat-Id's Th-ee Mile I: land Station, fer
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per=it was issued in !by 1%5. A mee:1:;; vin be hele. vi:h th: 2;p ___..
discuss the fcliev-cn items. Your Oc=:enta ar: requ;.::c.i.
1.
Research and Development Iters a.
Sodius Thicsulfate k'e stated in cur Safety Etaluation, en pace 50, that ce tc'._.
2 the needed 5 2-redu:tien factor for the 2-hcur de:e couli ;c : __ ~
by the sodius thiosulfate-sodium hydroxide spray systen.
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..2.
tim (February 5,1%S), ve have adopted a =cre ccusert:tive e. '.z._.
procedure. For e.u cple, the same spray s/ste= design was prev._
Crystal River and, using cur present =cthods of evaluatica, m a removal factor of 3 7 for the 2-hour dese. Le cheuld civi; :_ :
that we require 1'.provements in their sprsy cystem da:ica (cr, 7 ; ___
their containment decign which nov has a leah-rate :pe:ificatic :: ^
at design pressure).
b.
Other R&.D P c rars The other pregrams include: once-thrcuch 3: ens Zener tcrj ::n:r.
c.
drives; in-core neutron de c:ters; the-_.21-hydra. li pr cr22:;
- 2 cooling aspects; ar.d xenon escillations.
- a plan to ash nha
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to present at the meetin; a :.=:ary des:ription of the prc:r:::
on each iten and the anticipated schedule fer ccupic:':.:.
2.
Initial Decision of AS'.3
- To items were raised in the Initial Decision of a fellcv-:
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3 Safety Etaluation(2.Z.
Cc=bined Seismic a:d LCC A Lcais (p.
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cf 3.Z. ; alac p. :-
a.
Additional infor=ation was 71-esented en Cr/s,c' 31 rcr-- : -r
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Question 9 11.
We vill ash fer a prog 2.:: repc and :27 2 ::.-
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c.
Separation of Centrcl and SafetJ ('a. 13 c.' 2.2. )
We said in the S.E. that we vcu'.d revicu the final design f ;..
instru=entaticn syste:: in which the same airc.C is use.1 for :...#.
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the fullest extent practicabic." At the Mc -Id ::etin; we " '
discuss changes, if any, Me -Ed preposes to =a22.
'.le shculd 21 c ::
3 what infomation we vill require in a final detailed design (s :...
prin'. 3, test data, fa1. lure analy:es, etc. ).
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of cur current position.
d.
Reacter Building Fan Ccclers (3.2. p. 20)
We should review the status of design of the fan ecclers, in pr:ici__
the shaft seals and vinding insulation. As stated in the 3.2., 7: =~-
i.' pose further testing cc a prototype unit. Or reviev cheuld act: _.
advance of the POL, and schedule shculd be discussed at the re::in; vith Met-Ed.
Dilution Syste= Cent cis (S.E. p. 21-22) e.
We vill review the final design en terca dilution syster ccc.rcle f:r reviev against T""-279
- le shculd dis:uss prelimina-/ des'.c :. :"
meeting, as none was offered in the ?3A2, f.
GDC No.11 (3.E. p. 22)
'n'e need an expanded cutline as to the procedres to be :.sel *r/.'.27-21 in going to "ccid shutdr :" free withcut the centrcl recn.. b : -::.
should be esecuraged to provide this at an early inte as it 2:1 d ;_..
their final design. Me -Ed caly reluctantly agn ed to ccepl/
'_ch :.'_
interpretation.
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Form AEC.1tn (Rev. 9-53)
U S GOVER%uE%7 PR'%T'%G CFF:Cl 1W--0-214 C9
Peter A. Morris NOV 5 1953 Pressure 7essel The=al 3 hoi.c (3.E. p. 24 )
g.
We said in the S.E. that we would review the :al:ulational details cn precoure vessel themal shcch when available. Since that state =en:
vas =aie, several 3Zn plants have ceen prc:essel through the CP prcee: 3.
We have Occtinued te revie' this proble=, withcut final resciution.
We should notify Met-Ed that we require fcrual filing of the EG*n',:al u-laticus to date. We should also discuss pessible design changes tc mini =1:e the.~al check effect.
h.
Quality Assurance (S.E. p. 29)
Since the CP for this plant was processed nder to ehe increased e=phasis by DRL, QA vill be a significant follev-on 1.az.
- Per ce=o frc= 3oyd to Morris of Septe=ber 23,1968, Dr. 3e
- % vill be notified of the =ee*,-
ing.)
1.
Failed Pael Element Detector (S.E. p. 43)
We stated that we vould review any proposals cade by the applicant in this rega:ti. The applicant should provide us with his current status of design. We should further state cur info.~stion require =ents, which include ti=e response, sensitivity, redundancy, etc.
h.
Hearing Transcript Failed Pael Ele =ent Detectcr (pp. 260-26h):
See 3-1 above.
a.
b.
Splitting Scra: Bus (pp. 315-319)
The applicant stated that he was going to =cdiP/ the scrs= buses se that failure of one bus to release reds muld not prevent a reactor scra=.
We vill ask Met-Ed for design details, Pressure Vessel Inspection (pp. 33h-336) c.
We vill ask 3&W if there is any progress en re=cte UT, er other =eans, for iospectica cf the reactor vessel.
d.
Quality Assurance (pp. 342-347): See 3-h above.
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Fc11cv-On Ite=s en Ai:~: lane Harienin:
y We need to review the desi;n, er deterine the schedule, for th?
a.
final analysis ?f all st: actures intended to su:-tiye the design basis crash. Only the acntainment.23 reviewed during the CP
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.i Form AEC-318 iRev. 9 J' u.s sowte%*tst remTr*c:nu 'me-o-2544.9
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'.isted en page 'l of the Addendun Oc hc Safety Praluatica.
Our Safety realuation.Wiendus (cf April 26,1cdo) states en page 2.
5 that detailed calculations vill be perfc=ed by the applicant during :o;
- .:-20 tion to illustra.e the ability of the Ocntain=ent to withsta d an airplane strike on the cylinder vall.
(The d::e was considered previcusly. ) These calculations shculd be re tic.ci.
/ 5 Roger 3. Boyd, Assistant Director for Reactor Projects Division of Reactor Licensing r 4..
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Form AEC 318 (Rev. J-m u S. IsOW199 PENT Pm%Tl4G CFFICE. :W2$ 4-4.'.s