ML19308C949
| ML19308C949 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/25/1978 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19308C948 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8002110688 | |
| Download: ML19308C949 (1) | |
Text
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JAN 2 5 E'3 O
7 MEMORANDUM FOR:
T. Novak, Chief, Reactor Systems Branch,, DSS _
FROM:
F.
Check, Chief, Core Ferformance Branch, DSS
SUBJECT:
STIAM LINE _ BREAK ANALYSIS FO,R B&W RODDED, PLANTS Previous B&W hot channel thermal hydraulic analyses for the steam line break accident,had'in'di, cat'af) hat ap p rozi,'n'a't e ly ' '" L"] ~
~
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15% of the core would experience DNE.
This_is, based,on the,_
assumption that a radial-local peak of 1.61 would, correspond._
to an MDMBR of 1.30.
B&W has reevaluated the use of the original peaking distribution for the(dateruination of t'h a,, ' _
percent of the core in DNB for, the, TNI,- 2 stean line break,
analysis and found it to be extr,emely conservative for TMI-2, because the distributions were based _upon,a rodded plant, whereas TMI-2 is a bleed-feed core with rods nearly [g dis-,,
fully withdrawn.
The reevalma' tion', of ~t6a,'prid[cj:e'd ye'akid tribution indicates that there are no more than 5 fuel p'
~~
assemblies with predicted 'ia (' radial' ~i' local)' peaking
~ ' ~ ~~~
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factors greater than 1.60 incfuding the 5% 'nu~ clear hot pin ascertainty factor.
These 5' fmal asse'abife's ' rep'r~e~ sed 2. 8%" ' ~~
~
' ' ~
of the fuel in the core and it:horefore fasathan 3%'of thf
~ ~ ~'
core is now predicted to be 'in 'DHf"(MDNBR<1.3)~during th'e~
~~'
MSLR transient.
The AAR_ find's",the resultiin'g 'doie's'sec'ep[" tai >1e '
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new for this situation.
~~
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However, based on the previous analytical results it appears SL3 f or existing ro'ddid"p1'an'es sEo'u'fd "be',inv~estigated tha t the to assure that fuel failures _(fudi,, expefiancing','D[UBJ _s'ti1,1
~~
~~
result in acceptabla doses.
~
Faul S. Check, Chief Core Performance Branch
[_,
Division of Systens Safety cc:
D. Fieno L. Kopp J. Watt
,,,fENTRAL FILES JRR..RDG FILE R.
Meyer M.
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