ML20248C197

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Rev 0 to Calculation 52091-C-022, Monticello Unit 1, Screening Evaluation of Vertical Tanks
ML20248C197
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 01/24/1995
From:
EQE ENGINEERING CONSULTANTS (FORMERLY EQE ENGINEERING
To:
Shared Package
ML20248C136 List:
References
52091-C-022, 52091-C-022-R00, 52091-C-22, 52091-C-22-R, NUDOCS 9806020081
Download: ML20248C197 (30)
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Text

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JOB NO. FA _ JOB UM-W h N h BY h DATE i-IN-W CALC. NO. C-oE SUBJECT 4WM%h CHKD #F DATE l-E'T TABLE OF CONTENTS Sublect Eaga Calculation Cover Sheet 1 Table of Revisions 2 Table of Contents 3 References 4 Objective 6 Summary 6 Tank Data 7 SLC Tank T-200 Data 8 Tank Seismic Response 9 Anchor Bolt Loads 14 j Anchor Bolt Capacities 16 Local Shell Stress at Anchor Bolt Lugs 20 ( }O 2HD289/vtkeen

EGE EQE MEWADONAL [] SHEET NO. A ' " ' " ~ " " " ~ ~ ' JOB NO. Em JOB OW-WMt t % ME BY M DATE l-7AM CALC. NO. C,-0W SUBJECT WAtA h CHK'D If NT DATE l-M-T REP.:RENCES 1. EOE Engineering Consultants, Procedure 52091-P-001, " Project Plan, Support of Monticello and Prairie Island IPEEE." 2. Reed, J.W., et al, "A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)," Electric Power Research Institute, EPRI NP-6041-SL, Revision 1, August 1991. 3. EQE Engineering Consultants, " Reactor Building Deterministic SSI Analysis for R.G.1.60 Design Spectrum," Calculation No. 52091.03-C-007, Revision O. 4. EOE Engineering Consultants, Calculation No. 52091-C-010, "Monticello Unit 1, Electrical Equipment Anchorage Screeming Based on Design Basis Evaluation." nb 5. Winston and Strawn, et. al., " Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment," Revision 2, prepared for the Seismic Qualification Utilities Group, June,1991. 6. Drawings Bechtel drawing numbers C-230, C-345 Tank vendor drawings, NSP Drawing Nos. NX-7879-6,7879-8 7. Haroun, M.A. and G.W. Housner, " Seismic Design of Liquid Storage Tanks," Journal of the Technical Councils of ASCE, American Society of Civil Engineers, April 1981. 8. Jack R. Benjamin and Associates, et al, " Industry Approach to Seismic Severe Accident Policy implementation," Electric Power Research Institute, EPRI NP-7498, November 1991. 9. Newmark, N.M. and W.J. Hall, " Development of Criteria For Seismic Review of Selected Nuclear Power Plants," prepared for U.S. Nuclear Regulatory Commission, NUREG/CR-0098, May 1978. O N 2HD289/vtkeen

5 m. EQE INTERNATKX!AL (" SHEET NO. - F JOB NO. Ftbh JOB U W - W M c_t h e M a th BY h DATE $ TAM CALC. NO. C-n't-SUBJECT MeWc4 h Y^ CHKD HNT DATE l-M'E 10. Veletsos, A.S. and Y. Tang, " Interaction Effects in Vertically Excited Steel Tanks," l Dynamic Resoonse of Structures, American Society of Civil Engineers, March 1986. 11. URS/ John A. Blume and Associates, Engineers, " Seismic Verification of Nuclear Plant Equipment Anchorage (Revision 1), Volume 1: Development of Anchorage Guidelines," Electric Power Research Institute, EPRI NP-5228-SL, Revision 1, Volume 1, June 1991, 12. EQE Engineering Consultants, Calculation No. 52091-C-005, "Monticello Un;t 1, Walkdown of Essential Equipment." 13. American Institute of Steel Construction, Manual of Steel Construction. Allowable Stress Desion, Ninth Edition,1989. 14. Wichman, K.R., A.G. Hopper, and J.L Mershon, " Local Stresses in Spherical and Cylindrical Shells due to External Loadings," Bulletin 107, Welding Research Council, April 1972. () 1 l bb l 2HD289/vtkeen

E EQE WrERNATIONAL %d SHEET NO, 6 " "~^* ~ A JOB NO. 5% JOB M5Y-NW eb hn BY h DATE l-MM CALC, NO. C-bit SUBJECT W Mta h h CHK'D N DATE l*'T OBJECTIVE The objective of this calculation is to screen essential vertical tanks following the approach in Reference 1. Detailed fragility evaluation is not required if the tanks are screened. Vertical tanks addressed by this calculation are the standby liquid control (SLC) tank T-200 and reactor building component cooling water (RBCCW) surge tank T-3. The SLC tank is judged to be the bounding case and will be evaluated. The RBCCW surge tank is smaller and is typically only partially filled. Screening and seismic evaluation of the SLC tank follows the recommendations of EPRI NP-6041-SL (Reference 2).

SUMMARY

Based on review of the SLC tank configuration and detailing, and previous vertical tank evaluations, the tank anchorage and local shell stress at the anchor lugs are judged to be controlling elements. Seismic response analysis followed the recommendations of EPRI NP-6041-SL. Seismic loads on the anchor bolts were determined using simplifying approximations which introduce significant conservatism. Capacities of the J-bolts were conservatively based on GIP Revision 2 acceptance criteria and were found to be greater than the applied loads. Local stresses in the shell at the anchor lugs were found to be very low. It is concluded that vertical tanks' encompassed by this calculation, the SLC and RBCCW surge tanks, are screened. /^s - 2HD289Mksen

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I ,y ., EQE #CERNATKX4AL L' m4 SHEET NO. Db ~~ JOB NO. #dLO'i \\ JOB ktW-FLedulse ckh BY h DATE \\-EA l CALC. NO. C-ott - SUBJECT hr-Mtd T4a CHKD @ DATE ) -2 C S f d"'y 5 b + b N@ 'T T t-l' h" C u U# + - { e-YuSffS 9.}Tj% W,. T--Q %QT U T^ 6 L' s) =o s y o,.ec7 s e to.s,0 co.os o s:%e%> cests9-e, s,- 9.L - t ta +" Uy N My_ (0 W y _ Cv v Y s W /h /s b 'p-r N /tt.p. n fsrt-1.E (.o c. t.s3 to 'C6 4%D>C0,W~LT ) + e,b u s + (.0 oS M a t e ' 6'c 1.9 + 5 :'1 O , 1 -- 1~,._ gm 1 l l O

O GENERIC MECHANICAL EQUIPMENT VERTICAL PUMPS RHR SW Pump SEWS and Photos Calculation 52091-C-019 HORIZONTAL PUMPS HPCI Pump SEWS and Photos Calculation 52091-C-054 I e } O

520'1\\-C-CCS hh Status Y N U Sheet 1 of Q k/ - SCREENING AND EVALUATION SHEET (SEWS) Plant Name: Monticello Unit: 1 PART A. DESCRIPTION Equip. ID No. P-109A to D Equip. Class _ Vertical oumo Equipment Description RHRSW oumos (4 total) FO$ Equipment Location: Bldg. @ Floor El. 911' Room, Row / Col Mobw Gf Manufacturer, Model, Etc. 6' v lm'. .'- - - de,4J.*I I. s 4 : - - 7 Seismic Input Elevation PART B. PUMP EVALUATION 1. Is pump of good seismic design? @N U N/A Base flexibility / PW6 NX 9625-1 FC B "~ W ~2 O"" "h ~~ i C gs Differential structural motion < J @ Gen cle- %pr~h oh ppiy eek adeIuek Y*M l Nozzles loadings Unsupported components / 2. No other pump concerns? hN U N/A is pump itself screened out? hN U PART C. ANCHORAGE EVALUATION y l$,C4. 1. Is strength assessment based on:~ f Judgement (supported by generic analysis)? Id/ Specific analysis? Set-Cse,uo.stoM -C-O M Other? ther 2. Is strength adequate? hN U N/A 3. Is stiffness adequate? N U N/A f ( l 2HD299nbNP sows

65209 I -C.- ODS Sheet 2 of b SCREENING AND EVALUATION SHEET (SEWS) O Equip. ID No. P-109A to D Equip. Class Vertical oumo 4. No other anchorage cor.cerns? Y@U N/A Is anchorage adequate? N U gh -[fg PART D. SYSTEMS INTERACTION EFFECTS fisnue$ge e j 1. Is pump free from influence by adjacent N U N/A elements? E rc w e e r % is y m y

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ddUgt-4eb>t.s,eJcasc10 k8.,Tbtr % N '*~T Pump contains essential relays Ni^*r ikM kW *" ~d I / Pump contains soft targets re Pib ) b p ol# -fL % y h b Flexibility of connected lines Collapse of nearby equipments or structures g#jf ' Masonry block walls // 2. No potential sources could flood or hU N/A spill onto pump g j, 4g ;-} hoy 3. No other interaction concerns? bN U N/A Of-ls pump free from interaction effects? hN U DESCRIBE POTENTIAL PROBLEMS INDICATED BY NO OR UNSATISFACTORY (Use additional sheets,if necessary) hndard pump Gon urh[6a, V c,lo o th a. pnekn h kerebt== dY &N SY he 4 dWd F-i hO P NA I pWp ok3 U,9 @ NN 4 m boueg calcJdbos & awotory>: ca^M k cona M ar)eh elr "eAN>u P cv$- p Ncho ge kw & wr gW - 5,000 W. O l 2HD299nbNP-sows

52 Doi 1-C-oo5 j3 f Sheet 3 of SCREENING AND EVALUATION SHEET (SEWS) Equip. ID No. P-109A to D Equip. Class Vertical oumo i i 1 i -IS PUMP FREE OF NEED FOR FURTHER INVESTIGATION / ANALYSIS? YES NO Evaluated by: %h Date: L~ l E ~ 6 Evaluated by: M4 Date: 3 ' IA ' D - - 2HD299nbNP-sews l

EQE INTERNATIONAL o,..s...,s. Q Q. JOB NO. U 09 l ' JOB MCiJ1 ( 6LL O l CALC. NO. 0 - 006 SUBJECT W A L 4 C O'A/ Al CHK*D DI41 DATE 3'11'Y l '$hD d Yong ,M i s %- V l ? >sfp' i 1 P T i-r s\\lV i w W ~ u Q hg %k 4 ( h e e

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