ML19210A336
| ML19210A336 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/25/1977 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| GQL-0365, GQL-365, NUDOCS 7910290568 | |
| Download: ML19210A336 (4) | |
Text
p,'SSION
' CO' DOCKET NUM BE R NRcgoRu IQ5 U.s. NUCLEAR REGULAT JO ~ 2. t *1
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NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL Y TO:
FROM:
DATE OF COCUMENT t:etropolitan Edison Company 3/23/77
'ir Robert W.
Reid Reading, Pa.
o,7g pgegiyg o R. C Arnold 3/28/77 8 LETTER O N OTO RIZ E O PROP (NPUT FORM NUMBER OF COPIES RECEIVED 50RiclN AL bNC LASSIFIE D j
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$/)I'*V DESCRIPTION ENCLOSU RE Ltr. re our 2/17/77 ltr...trans the following:
Consists of response to questions concerning excessive ambient temperatures in their Unit 1 Reactor Buildin;;....
- SYO.WLEDGED EM0fl U-P) 2-P) e y
Three !!ile Island Unit No. 1 RJL SAFETY FOR ACTION /INFORMATION vm7 Tun ASSIGNED AD:
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/ BRANCH CHIEF?
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/ PROJECT MANAGER:
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PROJECT MANAGER:
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1 INTERNAL DISTRIBUTION i
/ kG FIL )E SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY &
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HEINEMAN TEDESCO ENVIRO ANALYSTS
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SCHROEDER BENAROYA DENTON & M7 T ER
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/ GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH.
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HANAUER SIEWEIL OPERATING REACTORS YOUNG 3LOOD i
HARLESS PAWLICKI STELLO SITE TECH.
PROJECT MANAGEMENT REACTOR SAFETY OP'. RATING TECH.
GAMMILL BOYD ROSS
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SHA0 HULMAN HOUSTON ROSZTOCZY
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Anern FGR P.QGRf33 METROPOLil AN EDISON COMPANY POST OFFICE BOX 542 READING, PENNSYLVANI A 19003 TELEPHONE 215 - 929 ^E01 P r T " *. 5 - { ~_*l M [d u k
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March 25, 1977 I
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G@ 0365 Directcr of :iuclear Resetor Regulation Mr. Robert '4.
Reid, Chief Cperating Reactors 3 ranch #h
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U.S. IIuclear Regulat ry Cc= mission Washington D.C.
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By your letter dated February 17, 1977, you transmitted a request to answer three (3) questions concerning excessive ambient temperatures in cur 'Three Mile Island Unit 1 Reactor Building.
Attached is our response to those questions. As stated the telephone conversation with Mr. Zwetzig of the NRC cn March 22, 1977, this respense is being submitted one (1) day late. Should you require additicnal in-formation please c. tact either myself or Mr. D. G. Mitchell (Ext. 169).
Sincerely, n
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R. C. Arnold
' lice President RCA:DGM:pg Attschnent 1488 293 D 0 2'80 /of
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The temperature gradients during normal operation of the plant are in general sicvly increasing functicns of time.
Therefore, the additional creep of concrete has usually the time to relieve part of the te=perature stresses. Please indicate therefore:
a.
Whether the effect of the increase of concrete creep due to additicnal thermal stresses has been considered in the analysis, b.
Whether the Young's =cdulus of elasticity for ccccrete Ec has been adjusted to take care of this effect.
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1.
The increase in operating temperature has been investigated with regard to its effect on concrete creep coefficients used for the Eeactor Building analysis.
Althcugh creep ^ increases approximately linearly with temperature within the range of 32*F to 203oF, the 20*F increase in temperature has negligible effect en the creep coefficient of the Reactcr 3uilding concrete (1). Therefore, it was unnecessary to adjust the sustained Young's =cdulus for the concrete to account for the increase in normal operating te=perature.
CUES 1I_CN :
2.
Indicate with precision what load cc=binations have been considered in the analysis, especially whether tornado loads, seismic leads, etc.
have been assumed to act simultanecusly with the thermal gradients.
re,t v."m c cr.
.mm 2.
The load cc=binations which include tornado leads, seismic leads, and other leads considered in the original analysis of the Reacter Suilding are given in Table 5-2 of the Three Mile Islanc Nuclear Station Unit 1, Final Safety Analysis Repcrt (FSAR).
In essence, all 1 cad cc=binations in Table 5-2 of the FSAR (7, 8, 11 to lh, 17 00 2k) related to operating temperature were c0nsidered in the reanalysis.
The change in stresses due to the higher operating temperature was calculated and added to the stresses produced by cther loads in the controlling lead cc=binatiens (cc=binations 7 and 17 in Table 5-2 of the FSAR).
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3.
Indicate the effect of higher operating temperature en the liner.
~4e are particularly concerned abcut a possible buldging effect en the liner particularly at areas of penetrations, both during normal operaticn and i==ediately after a postulated LCCA. Therefcre, please provide your analyses displaying stresses and deformations and the results of ycur inspecticas during the high temperature conditicns.
1/ Three Mile Island Nuclear Station Unit 2, Preliminary Safety Analysis Eeport, Section 5, Appendix SJ:
"Repcr cn Recc== ended Ccncrete Creep and Shrinkage Values for Cc=putiqs Prestress_ing Lcsses', page 5J-5
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1488 294
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The effect of the increase in normal operating terperature of the liner would be an increase in the ncrual cperating stress. No liner bulging is predicted cr has been observed as a ree' tit of the elevated ncr a1 operating tenperatures.
The liner was designed to maintain leak tightness for all load ccc-binations mentiened in the response to question 2, which includes the LOCA.
As noted in Ncnrcutine 3C-day Report 75-08, it has been determined that none of the maximu= post LOCA temperatare and pressure conditiens specified in the FSAR would be exceeded. As a result, the increase in normal cperating temperature will have no effect en the function of the liner as a leakage barrier during either normal operation or during a postulated LOCA.
'41th regard to concerns about pcssible bulging effects en the liner, the liner anchor desig: tcck into account the possibility of bulging as described in the FSAR, page 5-kT.
Should bulging of the 3/8 inch liner occur, the anchcrs wculd retain intact as would the leakage barrier (i.e. the liner). The liner around major penetratiens is thickened and stiffened to such an extent as to preclude bulging.
1488 295