ML20078A538

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Forwards United Engineers & Constructors,Inc Recalculations of Edge Shear of Spent Fuel Pool Floor Slab & Support,Per O Rothberg of Structural Review Branch Request.Redundancy of Including Fuel Weight in Seismic Loads Removed
ML20078A538
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 09/20/1983
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To: Vassallo D
Office of Nuclear Reactor Regulation
References
LAP-83-414, NUDOCS 8309230315
Download: ML20078A538 (16)


Text

{{#Wiki_filter:* Carolina Power & Light Company SEP 2 01983

             . Director. of Nuclear Reactor Regulation Attention: Mr.'D. B. Vassallo, Chief Operating Reactors Branch No. 2
             ' Division of Licensing United States Nuclear Regulatory Commission Washington, DC     20555 3RUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 SPENT FUEL POOL EXPANSION

Dear Mr. Vassallo:

In a series of meetings and telephone calls during June and July of

 '             this year,'Mr. Owen Rothberg of the Structural Review Branch expressed concern over the way in which United Engineers and Constructors, Inc. , (UE&C) combined

, certain values in their calculations of the edge shear of the spent fuel pool floor slab and support. In particular, Mr. Rothberg questioned the use of SRSS for combining certain loads rather than using ABS methods. As requested by Mr. Rothberg, UE&C has recalculated these loads by removing the redundancy of including fuel weight in the calculation of seismic loads due to rack motion (referred to .n he attachments as the first

             . phenomenon) and summing by ABS method the loads produced by seicmic motion of the rack without f uel with impact loads of the fuel bundles (second phenomenon). As described in the attachments, by not " double-counting" the fuel bundle mass, the subsequent summation of loads shows at least a 13%

margin of safety. Mr. Rothberg also requested clarification of our May 5,1983 letter which referred to the Response Spectra Method in Regulatory Guide 1.92. Stress analyses were performed for both OBE and DBE conditions, based upon the shears and moments developed in the finite-element dynamic analysis of the seismic response. The Response Spectra Method was used to calculate these shears and moments. The maximum amount of sliding and the stability of the modules against overturning were determined by use of two independent time histories for each horizontal direction. Combination of the modal response was done by taking the square root of the sum of the squaras of the maximum representative values of the three spatial components of earthquake motion. This same method was used to combine the effect of the three components of earthquake motion. The basis for using this method is contained in the NRC Regulatory Guide 1.92, page 1.92-4, paragraphs 2.1 and 2.2.a. 8309230315 830920 \ i PDR ADOCK 05000324 ) j . P PDR 1

     '-                            411 FayettevHis Street
  • P. O. Box 1551
  • Raleigh, N. C. 27602 }
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I Should you have any further questions regarding this issue', please contact our staff. ~ Yours very truly.- 1 .

                                                           -o      -
                                                                     .$ % W S. 4   . mmerman Manager - Licensing JSD/ccc (7824JSD) 4 cc:     Mr..D. 0. Myers (NRC-RSEP)
              .Mr. J. P. O'Reilly (NRC-RII) 4-              Mr. S. D. MacKay (NRC) 4 I

i f f 1 . f i 4 t-I l !, ~ i i ) { I I i-

FORM 3500 I MEMORANDUM hmited engineers.-m Jon No. 7453.121 OFFICE. Philadelphia

 ~

Mc=o #1822 DEPT. Structural Technical Support DATE: August 12, 1983 T@: L. R. Scott - , COPIES: J. Katr DCC (3 Copies) S . Ahuj a SAG File S.A. Yeh SAG Day File FRoM:

  • R. H. Toland/S. A. Yeh **

SUBJECT:

Carolina Po'wer & Light Co=pany Brunswick Stea= Electric Plant Units 1 and 2 Soent Fuel Storage Ex:ansion

Reference:

MM #1802, fro = S.A. Yeh to J. Katz, dated 7/26/83, sa=e subj ect. Review and 7artial reworking of the analysis of the fuel pool floor slab and support has shown the =argin of safety with respect to shear to be at least 13% to 16%~ (greater than the previously indicated 2%) . Seis=le and i= pact loads. were co=bined by the absolute su==ation (ABS) method. Conservatis= in the generation of the loads was reduced. Discussion In their review of the supporting analyses for spent-fuel storage expansion, the NRC expressed concern for the indicated low =argin in edge shear of the fuel pool floor slab and support (localized area). The particular load ce=bination involves two dyna =1c loads, seis=ic a'nd~

 ,                   the i= pact effects of the fuel bundle within its cell due to seis=ic motion. The analyses co=bined these,two loads by the SRSS =ethod.                           .

While UE&C' holds that this =ethod is appropriate, the NRC required that the =argin-te deter =ined when the load cases are conbined by the ABS method. In order to de=enstrate a positive margin while co=bining by the ABS =ethod, it is required that conservatis=s in either the load l definitions', or the analysis, or both, be reduced. Reference 1 reco=-

                    = ended an approach wherein the load definitions be refined.                In this

! approach, an eff ective ' double-counting' of fuel bundle = ass is re=oved. l It'is our opinion that the =argin is actually greater .than the l 13: to 16% since the analyticall: predlyhd uplif t of the supporting truss will be of =uch lessor extat (or will not occur). It is this l uplift which causes the local higi shear. This rework of the analysis i has only factored down the load without accounting for the added benefit of reduced uplift. l l l l AC/.cW M eir uo C 3 uc 3.2189 t e t l , - _ _ _ _ - - . - ,. . - _ _ , . _ .,

L. R. Scott August 12, 1983 The revised calculations will be forwarded separately. If you have any questiens, please contact us. 1 A R. H. Toland, Manager / S. A. Yeh V Structural Analysis Group Structural Analysis Group RET /SAY:lrs e 0 i e i 4 e D 0 f I l f I .

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