ML19220B964
| ML19220B964 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/21/1975 |
| From: | Kniel K Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19220B963 | List: |
| References | |
| NUDOCS 7904280013 | |
| Download: ML19220B964 (4) | |
Text
UNITED ST/TE3 OLEAR C E G U Li, T O H / C O *M.~.1
.4 W A h MIF4 G T O N. O. C.
- 0 5 3 5 Cocket i:a. 50-320 i!cycTier 21, 1975 Metrcpoli tcn Edison Company ATTil:
lIr. R. C. Arnold Vice President P. O. Box 542 Reading, Dennsylvania 19503 Gen tler.:en:
As a result of our continuing review of the Three ".ile Islanc ':uci.:r Staticn Final Safety Analysis Report, we have iden;ified the encles.
request fcr additicnal cnalysis, ihe need for and basic rervi rar.;n cs of this analysis.;;re conveyed to your staff in a reeting in Catnei e on October 30, 1975 during a discussicn of the analysis. nich had _
vicusly been parformed in response to second round questicn CJ2.7.
In order to maint:in our present expected licensing schedule, uc re~uir your response by January 20, 1975.
If you crnnot r:2t this date,
. case 1
inform us within 10 days of the receipt of this letter.
Sincerei",.
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Karl Knici, Chief Light. ater % actors 3 ranch s-2 Divisicn of Cecctor Licensing Enclosura:
Recuest for Aeditional Analysis c:s:
See page 2 7 904 2800 G S4~189
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ccs:
George F. Troubridge, Escuire Shaw, Pittman, Potts & Trcubridge 910 17 th Stree t, ii. '.l.
Washington, D. C.
20005 Chauncey R. Kepford, Esquire Chai rman York Ccr.mittee for a Safe Envi ron. ant General Delivery York, Pennsylvania 17:01 iir. Richard W. Hcward Projectl'enager GPU Service Corporation 260 Cherry Hill Roi.d Parsippany, iew Jersey 07054 fir. Thor.tas it. Crin:.: ins, Jr.
Safety and Licensic" *ienager GPU Service Corporation 2GO Cher:y Hill Road Parsippany, '!aw Jersey 07054 2
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84~189
REQUEST FOR ADDIT."AL N.; LYSIS s
.in_tt i.; L_ i a.
.u, m i, z ir 21.50 The staff rece,ces the follcuing ceii tional analyses of the
"'e Mile Island 2 alant relative to a postulated mcin stec" line. '~ -
inside contain*:cn to demonstrate that the plant. is safe f m cc h core and containment integrity standpoints.
The follcwing parameters must be considered in the analyses:
1.
A spectrum of steem line breaks insida of santainment; 2.
The mcst reactive rod stuck out',
3.
The worst single active failure affecting.
a.
core hencvior b.
contain:nent integri ty 4.
Availabili ty of offsi te power, i.e., wi th anci ' i tncus of f si te pcuer.
5.
As a consequence of the accident, consider the cossibility of other equip:aent f ailure, e.g., loss of react.cr ccolant pu""s or valve operation due to stecm environment.
For those secue.1ce of event: datei nined to be m.os t se /ere cci'.ti'eq to the core bchavior and contain ' ant integrity. t.ie fol l c.ii r.; cer u'. a are to be presented for the cases ahere operator ;ction
_y 2nd re; not be requi red.
a) reactor coolant system pressure; b) steam generator pressure; c) fluid temperature d) fuel and clad temperature; e) discharge ficw rate; f) steam line and feedwater ficc! rates',
g) safety and relief valve fic'.. rates ;
h) pressurizer and steam generater t.ater levels ',84-190
2 i) mass and energy transfer within containment; j) containment pressure; k) reactor pcwer; l) total core reactivity; m) hot and average channel heat flux; and n) minimum dcparture from nucleate boiling ratio (CNOR).
With each analysis provide a reference of pertinent events and actions including operator actions.
A table of portinent para:":ters for each of the accidents analyced which were not determined to be limiting.111 be satisfactcry Include miniinta DHCR, containment pressure, and a descri; Mon of of the accident.
In the event the consequcnces of a stecm. line brea' usir.g the ai et _
assumpticns are unacceptable, a probabilistic enslysis of the secuence of events that uvuld occur, including any neceswry cuerato action, should be performed to quantify the dcgree of risk involved.
In the event your analyses indicate unacceptable results for ^4 the-the core or containment integrity, indicate what design modi icW ns could be performad to assure safety.
84~191
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