ML19330C310

Reviews Reactor Turbine Bldg Design Parameter Verification. Structural Parameters Used in 1965 Blume Seismic Analyses of reactor-turbine Bldg Complex Reviewed.Encl Comparison Tables Provide Review Results

ML19330C310
Person / Time
Site:	Dresden
Issue date:	08/01/1980
From:	Janecek R COMMONWEALTH EDISON CO.
To:	Oconnor P Office of Nuclear Reactor Regulation
References
NUDOCS 8008080221
Download: ML19330C310 (4)

Text

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[^X Commonwealth l One First Nation 11 Edison Ptr, Chicago, Illinois l

. '  ! O '? Addr ss R: ply to: Post Offica Box 767

. \ / Chicago, Illinois 60690

August 1, 1980 Mr. Paul-0'Connor, Project Manager Operating Reactors - Branch 5 U.S. Nuclear Regulatory Commission Washington D.C. 20555

Subject:

Dresden 2 Reactor-Turbine Building j Design Parameter Verification j NRC Docket 50-237 j

- Re fe rence : a) Robert F. Janecek letter of March 4, 1980 l 1

to-D.L. Ziemann

Dear Mr. O'Connor:

In accordance with reference (a) Commonwealth Edison has ,

I reviewed the structural parameters (i.e. axial areas, shear areas, moments of inertia, and masses) used in the 1965 Blume seismic analyses of the reactor-turbine building complex at the Dresden 2 Nuclear Power Plant. Tables 1 through 3 compare the structural parameters calculated using as-built drawings and current procedures with the same parameters calculated and used in the 1965 analyses. These tables fulfill Commonwealth Edison's committment of reference (a).

Commonwealth Edison has reviewed the impact of using the new set of structural parameters (those calculated using as-built drawings and current procedures) on the seismic responses of the complex. In general, the responses are equal to or less than those presented in the report of the Senior Seismic Review Team (SSRT). The review concluded the new set of structural parameters reported in Tables 1 thru 3, if substituted in the dynamic model of the reactor-turbine building complex used by the SSRT in their evaluation of Dresden 2, would show these structures and equipment to contain, in general, even higher margins of safety than those given in the SSRT report.

If you have any questions concerning this matter please contaci this office.

One (1) signed original and thirty-nine (39) copies of this transmittal are provided for your.use.

Very truly yours,

/ $ ch Robert F. Janecek Nuclear Licensing' Administrator Boiling Water Reactors NPS:mnh' 5463A

' Attachment 800306 0 2M c >/

~

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TABLE 1 COMPARISON OF MASS DESIGN PARAMETERS Weight (kip)

Elevation

'"" "I*

(ft-In.) 1980 1965 Value Value Reactor Bullding 659-3 1,676 1,466 639-0 890 890 626-0 329 329 613-0 33,119 40,974 589-0 32,480 30,352 570-0 38,757 34,014 545-6 34,525 34,282 517-6 64,786 94,592 Turbine Building 622-6 3,577 2,774 601-0 332 260 580-111 382 314 561-6 71,673 98,243 1

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TABLE 2 COMPARISON OF STlFFNESS DtSIGN PARAMETERS. REACTOR BUILDING .

Axial A'rea, Shear Area,, Shear Area, Homent of Inertia Moment of inertla Axial Area, g.W (ft 2) 2 N-S (ft ) 2 E-W (ft ) @ N-S (ft'); 9 E V (fth)

Elevation N-S (ft2 )

(ft-in.) I 1965 1980 ~ 1965 1980 1965 1980 1965- 1980_ 1965 1980 1965 1980 value value value value value value .value value value ,

value value ..!ue 659 3.0 3.9 39 107* 10 7*' 1h7* 107*

to -- -- -- -

3.0 639-0 ,

639-0 ~

4.0 4.8 4.8 107

• 10 7* . 10 7* 107

• to -- -- -- -- 4.0 626-0 . ,

626-0 7.2 7.2 107* 107

• 10 7* to7*

to -- -- -- --

4.5 4.5 613-0 l 613-0 3,100 3,900 53,900,000 43,476,500 6,160,000 5,319,600 5,640 5.570 5,640 5.580 1,915 3,900 to 589-0 589-0 2,939 4,050 58,340,000 57,416,100 6,608,900 6,839,700 5,900 5,820 5,900 5,810 2,359 4.050 to 570-0 570-0 2,416 3,880 35,700,000 39,944,000 6,858,900 7,506,000 to 4,480 5,550 4,480 5,540 1,751 3.880 545-6 545-6 2,570 3,450 39,500,000 32,247,000 7,917,000- 7,157,600 4,900 4,930 1,997 3,450 to 4,900 4.940 517-6 517-6 4,151 4,630 63,206,000 62,353,000 16,500,000 16,230,100 8,480 8,820 8,480 8,820 4,159 4,630 '

to 472-6

• Assumed value.

_. ,y __ .~. y -

TABLE 3 .

CoMPARISGd oF STIFFNESS DESIGN PARAMETERS, TURBINE BUILDING Axial Area, Axial Area, Shear Area, Shear Area, Moment of inertia Moment of inertia

. Elevation N-S (ft2) E-W (f t2) N-S (ft2) E-W (ft2 ) @ N-S (f t") ~ @ E-V (ft")

II'~3"' 1980 1965 1980 55 1980 1965' 1980 1965 1980 1965 1980 1965 Value Value Value elue Value Value Value Value Value Value Value Value 622-6 to -- -- -- -- 107 , 107 , 8 8 107 . 107 128 128 601-0 .

601-0 to -- -- -- --

107

• 107

• 12.8 12.8 107

• 107

• 128 128 580-111 580-11) to -- -- -- --

10 7 107 13.8 13.8 107 107 128 128 561-6 561-6 to 6,622 628 6,622 1,980 2,314 1,037.4 2,711 329.7 170,780,000 77,000 20,100,000 858,700 513-6

• Assumed value.

r L__._____ _ . _ _ _ _ _ _