ML20071H125
| ML20071H125 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/19/1983 |
| From: | Lewis M LEWIS, M. |
| To: | NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD), PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8305240516 | |
| Download: ML20071H125 (1) | |
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N. I l b,,U Intervenor T/ min'c First Get of Interrogatories on PN Conten",ich t f
In compliance with the schedule established in the 2nd Frehearing Conference by the ASI2, Intervenor Lewin subnits the following interrogatories to th3 NRC Staff and the 1.icense-applicant.
Please une the"Definitionn and Instructions "
set up by the" Applicant (in hih Firnt Set of Interro:;atories and Request for Production of Occu:ents to EalarTre " dated July 21, 1932, on Pages 1 thru 4 inclusive.
I a. nuunittin;; the =.xe net. of interregatorien to the Staff and the Applicant, If the Staff and N AppliEnt confer en their answers to the interrogatories, please ctata 09 I" t he ot'if and the Applicant wish to precent only one cet of cc 2bined ansvera co the interrc;r.tcrica, state the level of agreenent: conplete *, partial, or dicagreenent in rhich elenen:n of the answer.
1.
Is preasuried +.hernal nhock a problen in ElRs,specifically Linerick 1 12?
- 2.
'! hat la tna canis fcr the conclusien that PS (prescurleed thernal shock) will not cauce a failure at Limerick of cafety related or inportant to safety structures?
or Conversely, to what extent do you conclude that cafety telc.ted and important to cafety will be affected and to what extent affected? (For instance, describe failure.)
Provide t$o actual nuuerical data that han Generated the answer to Interrogatory 3.
2, above.
Provide data, en1nulations, geonetries fron bluaprints, conputer run results, and pralernione.L opinions.
Vake your answer as cenplete as pescibla: tenpera'.ure cradients across the !?PV wall for a series of cool down rates Lor:p:1ture gradients acronc any other ctructure adversely affected (pipec, etc.
sensitirity analysin for the rationale for choosing teecific cool down rates.
ntrces levela and loads associated with the above cool d own rates total intenrated neutron flux calenlations and neasurenents specific to ac cual a.rtF in question and to reactorn of sinilar design to Linerick.
calculation of mnultant losn of RTndt due to above neutron flux Provida a definition of Pr rnurized Ther.a1 Shock and reference the dccunent wherein that definition lins. Similarly provide definitionn for "inportant to emO ah enfet" " and "caf f.y roh ted."
me g. Give thicknenson ?-d n?.terhl-that neutron flir-would hr.v' to penetrate betue.;
, Em or Qin
.M affeted nr.r m - m.(For inntanco distance betuern fuel and beltlir.o veld.)
O kg.
Have anj" tent enepnn" of alfected. aterials been irradiated and tested fron
+ mg Om E!Es of design cinilar te Linerick? Provide results and docunentation.
7 I, I',1rvin I. Lrris, cortify thit I an nailing thece interogatories to the entire Linerick OM
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