ML20076E197
| ML20076E197 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 10/05/1982 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton, Penton H Office of Nuclear Reactor Regulation |
| References | |
| 5138N, NUDOCS 8308240214 | |
| Download: ML20076E197 (6) | |
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Commonwrith Edison b
One First National Plaza. Chicago. Illinois 7 Address Reply to: Post O'hce Box 767
(
/ Chicago, Ilhnois 60690 x
i October 5, 1982 f
Mr. Harold R.
Denton, Director 8 (j g jg y g y Of fice of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Pipe Support Anchor Plates NRC Do cke t No s. 50-454, 50-455, 50-456, and 50-457 Reference (a):
July 6, 1982, letter from B.
J. Youngblood to L.
De lGeo rge.
(b):
August 9, 1982, letter from T. R.
Tramm to H. R.
Den t o n.
(c):
July 5, 1982, letter from Cordell Reed to J.
G.
Kepple r.
Dear Mr. Denton :
This is to provide additional information regarding the flexibility of baseplates for pipe supports at Byron and Braidwood.
NRC review of this information should close Outstanding Item 5 of the Byron SER.
The response to FSAR question 110.71 which was transmitted in reference (b) discussed the amplification factor used in the design of the four-anchor plate.
The load-displacement curve used originally in the computation of amplification factor was shown in Figure 3 of reference (c) and is enclosed with this letter.
The four anchor plate assembly has been reanalyzed based on a conserva-tive idealization of the load-displacement curve as plotted on the enclosed Figure 2.11.
This reanalysis confirmed the 1.0 amplifica-tica factor of the four anchor assembly.
The response to FSAR question 110.72 contained anchor plate descriptive information which did not include edge distances of the anchor bolts.
This information has been included on the enclosed revised Figure Q110.72-1.
A revised version of Table Q110.72-1 is also enclosed which contains corrections for Plate 1.
This information will be incorporated into the FSAR at the earliest opportunity.
8308240214 821005 gDRADOCK05000g g $gj
r o
H. R. Denton October 5, 1982
' One signed original and fifteen copies of this letter an the enclosures are provided for your review.
Please direct further questions on this matter to this office.
Very truly yours, M"
T. R.
Tramm Nuclear Licensing Administrator 1m Enclosures 5138N L
~
Page 2 of 5 ADDITIONAL INFORMATION REQUESTED ON RESPONSE TO NRC QUESTIONS 110. 71 AND 110. 72 Pu = 7.Ok With Pre-Load 7-Fithout Pre-Load 6--
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Page 4 of 5 ADDITIONAL INFORtRTIO:1 RECUESTED Ois RESPOtJSE TO NRC g)CSTIONS 110.71 MJD 110. 72 AMENDfGt:T ( IATER)
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8 anchors - 3/4" BYRON /BR AIDWOOD ST ATIONS FIN AL S AFETY AN ALYSIS REPORT
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FIGURE Q110.72-1 L
EXPANSION A?;CHOR PLATES
?,n TABLE 0110.72-1 AMPLIFICATION FACTORS FOR TYPICAL EXPANSION ANCIIOR BASE PLATES WITH WEDGE TYPE ANCHORS MAX. ANCIIOR M X.
ANCI!OR REACTION REACTION y
? LATE ANCHOR (FLEXIBLE PLATS (RIGID PLATE AMPLIFICATION g
NO.
ASSEMBLY LOAD ANALYSIS)
ANALYSIS)
FACTOR H
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1 9x9 x1/2 in.
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43.6 in-k (moment) 2.85 3.2 1.0
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33.7 k (tension) 7.0 5.62 1.25 dh 6 anchors 1/2 in.
199 in-k (moment) 7.0 6.62 1.06 m m 3
21x21x7/8 in.
114 k (tension) 16.0 14.25 1.12 3 :j 8 anchors 3/4 in.
900 in-k (moment) 16.0 14.7 1.09 g,j m _]
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