ML19268B953
| ML19268B953 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/25/1977 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910220668 | |
| Download: ML19268B953 (3) | |
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MDt0RMDUM FOR:
R. R. Go11er. Assistant Director for Operating 1.)
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D. G. Eise. hut. Assistant Director for Operational m;
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Technology. 00R
SUBJECT:
METROPOL!TM EDIS0rt COWANY - THREE HILE ISLMD 9;.
UNIT NO.1 - EVALUATION 0F CONTAIRMENT WITil HIGH OPERATING TEWERATURES A
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' Plant Name: Three Mile Island Unit il ~ '.
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Licensing Stage: Operating Plant
.9" Doctet M*sber: 50-289 Bmnch and Project Manager Requesti ssistance: ORB-4. G. Zwetzig 8
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Description of Request: TAC M474 A Requested Completion Data: February 7;,1977 m.
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' ' " Description of Response: ' Report
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Documents Reviewed:
- 1. Non routine 30-day Report 75-08
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Metropolitan Edison Cogany letter dated
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.J Following your request: TAC M474 dated January 4.1977. we have U.1,'?t:
reviewed the structural inforsation provided by the licensee non 4
i, routine 30-day report 75-03 and the additional structural inferration e
5 pmvfded by the licensee in his letter dated March 25,1977 in response to our quastions dated February 10, 1977.
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Scope of Review
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The licensee has identified two areas of possible concern: the reactor
'<l building structural integrity and the effect on critical corponents located within the reactor building. These concerns are due to the following phenomer.o:
s During the sumer months reactor building internal operating temperatures in excess of the 110*F sustained taccerature assuced in the FSAR have been experienced. Average tesperatures in excess of 130*F have been experienced above elevation 320 feet and 110'F=120*F below elevation 320 feet on days when wet bulb temperature has been greater than approx.
imately 75'F.
- u We have reviewed the infor ation provided by the licensee which covers
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ii. R. Goller APR 2 5 tFI 1.
Reactor building structural stsbility_
The methods used by '% licensee for the stress analpis of the l.
structure.
The critaria for acceptance of additional stresses generated by the _ higher thermi Iwds.
The effect of higher temperatures on the prestressing tendons.
.t The effect on the liner and leakage rMrteteristics and in the post LOCA conditions.
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The effect on componen.ts within the containrent Evaluation '
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The itcensee has used the Working Stass Design method of the ACI 318-63 lL
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. Code and the Ultimata Stremg'.h Design method of the same code. also ti.
the allowables free W ASME So11er and Pressure Vessel Code. Section !!!.
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. Civision 1 (Jan.1.',1975) to determine the structural stability of the
-t containment. All the loadin7 combinations listed in the FSAR have teen
' ', ^ ' S consMared with temperature stresses due to higher operating teaperature
.added to the stresses generated by.other pertinent loads. The effect r.
of higher tesperatures in the liner during 1.3CA has been investigatad.
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No liner bulging due to higher operating teriperature has been observed.
The effect on tendons is negligible. The licensee has used in the design of the containment a tanperature differential of about 90*F which is not,tzgeofe_d.,, Jiocays.cospressjg. stresses art.slightily increased.'n,o, addit tonal le,akage,Jhrough.,.t.he.1. inn.lLexpe.c.e.W..'s.
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5-A detailed study has been mace by the licensee of all safety related components located in the containment. The licensee has detarmined that all connents are conpatible with the increased operating tecoer-atures. It. should be noted that they are located restly below E1. 320 feet and that at this elevation the opurating tecterature is only slighly above the design opereths tenperatum: 120*F in lieu of 110'F. This increase is netligible.
.,I Conclusions and Reservations The conclusions of the licen'see are:
"In sueury the probability and consequences of an accident are not increased and the possibility of an accident not previously analynd has not been creatcJ by this kcreasef a temperature."
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For the nasons presented above, we concur with this conclusion.
[i We inve however the following rsservations:
bA In'the non routine 30-day Report 75-08 the licensee states tho follow-ing a
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- c. ' corrective Actions m t J
E In addition to the analyses sentioned above an investigation is in m
- ~. progress to locats any insulation ecnditions that may be contributing 1.
' ;,to a RB heat load greater than design. Further, efforts t' ave been and L
- 9. are being sede.to improve the indtattrial cooler perforrance.
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. ~ Ontil such time as the above actions are completed and the appropriate 4
corrective actions are taken the following action will be taken if RD 3
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I, average temperatures ri,sa.above 130*F. above 320' or 120'F below 320',
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(. It abould be noted that.the conditions' described above do not now exist
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'J Further, a FSAR n..ge 9being prepared to addness these increased ' '
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p,y We recorzand that the licensee'be requested to proceed as fast as possible ni
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'm r-V; be provided to the MRC not later than 90 days from the present date, and that our concurrence given above be considered as a temporary one,
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- ;.-wwhich may be cancelled at any time if the licenses does not honor his
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$f;i D. G. Eisenhut, Assistant Director
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