ML20083F760

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Forwards Revised Temp Limits for Reactor Vessel,Per Amend to App G to 10CFR50.Only Cooldown Curves for Byron Unit 1 & Braidwood Unit 2 Must Be Changed to Incorporate New Closure Flange Limitations
ML20083F760
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 01/03/1984
From: Tramm T
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
7905N, NUDOCS 8401100362
Download: ML20083F760 (4)
v • d • e


Text

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. N _ Commonwealth Edison O ) one First Nationat Plaza. Chicago, lihnt s C Address Reply to. Post Office Box 767  !

Chicago. lilinois 60690 January 3, 198h a

Mr. Harold R. Denton, Director q, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 Reactor Vessel Temperature Limits NRC Docket'Nosi-50-454/455 and 50-456/457

Dear Mr. Ot7 ton:

4 This is to provide revised temperature limits for the Byron i and Braidwood reactor vessels. These revisions were made necessitated by the May 27, 1983 amendment of Appendix G to 10CFR50.

i _The heatup and cooldown temperature limit curves for all of L the Byron /Braidwood reactor vessels have been reviewed against the

amended Appendix G requirements. Only the cooldown curves for Byron

I 1 and Braidwood 2 must be changed to incorporate the new closure i flange limitations. Revised copies of those curves (FSAR figures 3.4-3a and-3.4-5b) are enclosed with this letter. Also enclosed is Table I, showing the data used in this review.

These two cooldown curves are to be incorporated into the plant Technical Specifications. They will not be incorporated into the FSAR since it is not our intent to keep current the proposed technical specifications contained in the FSAR.

i We understand that the amended Appendix G provides an option for analyzing closure flange region stresses to demonstrate

, that they are less limiting than the beltline region. If that were

! done, the special limitations on the enclosed curves would be j unnecessary. At some point in the future we expect to pursue that option but for new we will abide by the limits shown in the FSAR, and as shown in the enclosed curves.

l Please direct questions regarding this matter to this office. -

One (1) signed original and fif teen (15) copies of this letter and the enclosuret are provided for NRC review.

Very truly yours, t N

' B401100362 840103 T. R. Tramm PDR ADDCK 05000454 Nuclear Licensing Administrator A PM g Enclosures 7905N- g

. l

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TABLE I: Data used for P-T' curves' evaluation per 10CFR App. G Vessel Closure Flange RTl 0F (RT +90)0F (RT +120)0F Preservice Hydro. 20%P psig NOT NOT NOT Pressure P psig Byron l' 60 150 180 3107 621.4 Byron 2 0 90 120 3107 621.4 Braidwood 1 -20 70 100 3107 . 621.4 Braidwood 2 20 ,

110 140 3107 621.4

1. Reference Temperatures, RT , were obtained from B/B FSAR Q251.

NOT 1239R/2

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BYRON STATION FIN AL S AFETY AN ALYSIS REPORT

' FIGURE 3.4-3a

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REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICABLE TO 32 EFPY .';

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AMEN 0 MENT 38 MAY 1982 3000

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BR AIDWOOD STATION F~lN AL S AFETY AN ALYSIS REPORT FIGURE 3.4-5b

( BRAIDWOOD UNIT 2 REACTOR COOLANT SYSTEM C00LDOWN LIttITATIONS APPLICAGLE UP TO '.6 EFPY 3 / 4 . /.' - 3 2 c

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