ML19220B894
| ML19220B894 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/23/1974 |
| From: | Stello V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7904270604 | |
| Download: ML19220B894 (3) | |
Text
.
UNITED STATES p
$' N Z'l ATOMIC ENERGY COMMISSION
- b.
i wassiscres. c.c. es4s
.W D./
' JEU,, ' 2 3 374 Docket No.
50-320 V. A. Mcore, Jr., Assistant Director for Light Water Reactors, Grcup 2, L Q1 QUESTICNS ON FSAR SECTION 4.2.1 FOR THREE MILE ISLAND UNIT 2 Plant Name:
Three Mile Island Unit 2
' icensing Stage:
OL Docket No.
EO-320 Responsible Branch LWR-2-2 and Project Manager:
- 3. Washburn Technical Review Branch Involved:
Core Perfor ance 3rsnch Requested Ccmoleticn Date:
July 19,1974 Description of Review:
Q1 Questions Enclosed are the Q1 questions for Three Mile Island Unit 2
~
covering section 4.2.1 of the FSAR.
-m
.n f
,&m./
2., - 7 Vic(tor Stellcq Jr., Assistant Director
<.c for Reactor Safety' Directorate of Licensing
Enclosure:
Q1 Questions cc w/ encl..
S. Hanauer, DRTA J. Handrie, L W. Mcdonald, L K. Kniel, L S. Washburn, L D. Ross, L L. Rubenstein, L R. Lobel, L 790427060'(
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pressures.uring DN3 as discusied in SectiCn 2.2-2.
In these CalCuiaticc.3, describe how transient fission cas release is ta ken into aC cur.:.
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u e ca u.3 What syste1 :ressure is assur.ed durir.g the C,'.3 transient?
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6.
What is the Cold He pressure in the fuel rods for T.'U-2 before irridi3ticr?
7.
What value is used for irradia:iCa gro.ith of the ZirCaley used for fuel assembly Cc cor...ts (sectiCn 4.2.1.3.2.1)?
8.
What is the Calculated h0: pressure in the '..Crst Case fuel rcd fcr T."I-2?
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ls the neti,% of perfor ling these calculations desc.~ibcd in 3 CDrical v s as so..
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exist at re.c ce 2;erature ccniitions fcr. hic'1 hycride fcr::a:icn r y cccur."
Al sg, discuss hC"! the limit is consistert with the ICi rargins over :j,ts,
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Describe in detail :P2 stress rupture calculations done to sho'." t'it the 3300 psis inter 31 tas pressure is a r.cunc design basis.
Did thesa
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the core for..nich the in:ernal p s pressure is gre:ter than tha ::c'".t n,. n,:.. r o e
9.
De sc rit.: in d:-t:il or refsrence the tssts reported in section a.2.1.2.-
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ran3lytical Verification Of these r'isuits attOO tt.d?
10.
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i.
36 a
a.
s a.
smua s
CO un0Ccf. 'tabl e..dar ha s 20o3 O c.e r ved.
Discuss ',ihy such damaged spacer grids cculd not ce,t es
.v. in T."J-2.
e
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