ML18039A534
| ML18039A534 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/13/1997 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18039A528 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR CD-Q2999-940343, CD-Q2999-940343-R02, CD-Q2999-940343-R2, NUDOCS 9810020148 | |
| Download: ML18039A534 (60) | |
Text
ATTACHMENT 8-2 0
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o RBCBN UNE CALCULATIONS SHEET 1 TITLEr X LANTZUNIT QUALZFZCATZON OF'ABLE TRAY AND CONDUZT SYSTEMS BY A46 PROGRAM BFN Unit 2 PREPARING ORGANIZATION r(EY NoUNs (consult RIMs DEscRIFToas LzsT)
NE-Civil CONDUIT CABLE TRAY, SEISMIC A46 OUTLZER BRANCH/PROJECT IDENTIFIERS these ca)cu)at(rms are issued, preparers must ensure that rho orriinal (RO) RIM8 aceessr'oa number I' QIM in.
CD-Q2999-940343 Rev (for RIMSp use) RIMS accession number APPLICABLE DESIGN DOCUMENTS RO R14 '96 0124 105 GIP FOR SEISMIC VERIFICATION OF NUCLEAR PLANT EQUIPMENT AND R'l4 '96 0220 119 BFN-50-C-'7104 RLcL 9 VO 813 1..0 SAR SECTION(S) UNID SYSTEM(S)
N.A 999 R3 Revxsion 0 Rl Safety-related2 Yes JL No 0 DCN No. (or Indicate N/A) Statement oi Problem 73988sa Prepared RESOLUTION OF OUTLIERS FOR A46 WAZXDONN FOR RACILY Checked
'YSTEM. '- THIS CALCULATION C. O. P IS PREP2Q&D IN RESPONSE TO Revxeved NRC UNRESOLVED SAFETY C. O. Pa ISSUE, USI A-46.
pppz J. Val nte. l&c-Date r(<<ali) Reiaird j 'fe5 C h'o U z.o LLst all 3.
pages added by T.s f~'L )(.
5rire a//ccirci 'fee L3 i(o E this revxsxon List all pages deleted by this revxsion fez.
List all pages changed by this revxsion L cg~.
Iculatxoa revxsion (A)
(P)
Enttre calculation Selected pages ORIGiiNAL Abstract TheaecCaXCu?atlO'ni:COritain 'uaVerifXed"-aaaumPtf One tÃaT. muat be" Verified later. Yee 0 NO g, grz caiccpla(icop coniain opccr'ai'repirrmenrr and/or lipniA'net conciiiionr )er Revision 0: This calculation addresses the limited Analytical Review cases and other outliers from A-46 walkdown. Calculations are based on guidelines given in Generic Implementation Procedure (GIP) for seismic verification of Nuclear Plant Ecpxipment.
Rev. 0 Total page count l2.2 gEtR. f Pr Ck!RNITE ic gg- (g)AC)
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TiQe: QVALZFZCATZON OF CABLE TRAY AND CONDVZT SYSTEMS REVISION LOG BY A-46 PROGRAM CD-Q2999-940343 Revision Date No. DESCRIPTION OF REVISION 0 Original Issue uht-~ouzel WF ~CNA77o 4 PnlZ urer t egL vt TRRNSpoewgR~ Af BL 6ZI Z>>.
Ravtgru 'sy y Sll $ 4 g APPFll~'i< A, Elle P S4
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CALCULATIONDESIGN VERIFICATION(INDEPENDENT REVIEW) FORM Calculation CD- Rev. 0 Method of design verification (independent review) used (check method used):
~ ~
1.~ Design Review
- 2. Alternate Calculation
- 3. Qualification Test Justification (explain below):
Method 1: In the design review method, justify-the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, based on accepted handbook methods, appropriate sensitivity studies included for confidence, etc).
Method 2: In the alternate calculation method, identify the pages where the alternate calculation has'been induded in the calculation package and explain why this method is adequate.
Method 3: In the qualification test method, identify the QA documented source{s) where testing adequately demonstrates the adequacy of this calculation and explain.
The above calculation revision so noted has been reviewed by. the Design Review Methodology and has been determined to.'be technically adequate based on the design input information contained herein using accepted handbook and/or computer applications and sound engineering practices and techniques.
I I7-iE Desi+ Verifier Date This sheet added by Revision 0
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CALCULATIONDESIGN VERIFICATION(INDEPENDENT REVIEW FORM Calculation CD - < ~ ~~~~+3Rev.
Method of design verification (independent review) used (check method used):
- 1. Design Review
- 3. Alternate Calculation
- 3. Qualification Test Justification (explain below):
'Method 1i In the design review method, justify the technical adequacy of the calculation and explain how the adequacy was verified (calculation is similar to another, t
based on accepted handbook methods, appropriate sensitivity studies induded for confidence, etc).
Method 2: In the alternate calculation method, identify the pages where the alternate calculation has been induded in the calculation package and explain why this method is adequate.
Method 3: In the qualification test method, identify the QA documented source(s) where testing adequately demonstrates the adequacy of this calculation and explain.
The above calculation revision so noted has been reviewed by the Design Review Methodology and has been determined to be technically adequate based on the design input information contained herein using accepted handbook and/or computer applications and sound engineering practices and techniques.
Design Verifier Date This sheet added by Revision
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TVAN CALCULATIONDESIGN VERIFICATION(INDEPENDENT REVIEW) FORM CD&2999-.940343 Calculation No. Revision Method of design verification (Independent review) used:
- 1. Design Review X
- 2. Alternate Calculation 0
- 3. Qualification Test 0 Comments:
This calculation Revision has been reviewed by the Design Review methodology and has been found to be technically adequate based on the design input information contained herein using accepted handbook and/or computer applications and sound engineering practice and technique.
0 :~ s.)s ari. I e Independent Reviewer date
'IVA40533 [08-9TJ 'age 1 of 1 THIS PAGE ADDED BY, REVISION Z NEDP-2-2 I0845-9TI
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TITLE: PAGE 4 OF QUALZFZCATZON OF CABLE TRAY AND CONDUZT SYSTEMS CALC CD~2999-940343 aY A46 PROGRAM PREP BYACL . DATE I- a '9 a CHKD BY ~ DATE I. ig, . gg
'TABLE OF'ONTENTS ZTEM PAGE CALCULATION COVER SHEET REVISION LOG INDEPENDENT REVIEW FORM TABL'E OF CONTENTS PURPOSE ASSUMPTIONS REQUIREMENTS / LIMITING CONDITIONS REFERENCES DESIGN INPUT DATA AREA DESIGNATION 12
'UTLIER STATUS
SUMMARY
TABLE 13 COMPUTATIONS a) ANALYTICAL REVIEW 14 b) QUALIFICATION OF OUTLIERS 26
SUMMARY
OF RESULTS 60 CONCLUSION 61 APPENDIX A Al OUTLIER SEISMIC VERIFICATION SHEETS(OSVS)
AND OTHER FIELD NOTES.
APPENDIX B Bl a) COPY OF WORK REQUEST 4 C165042 & C030587
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TITLE: PAGE 5 OF QUALIFICATION OF CABLE TRAY AND CONDUIT SYSTEMS CALC CD~2999-940343 BY A46 PROGRAM CHKD BY ~
PREP BY AC g . DATE ~~ ib . V(,
DATE u(- IC -gC 4
PURPOSE AND BACKGROUND:
THE PURPOSE OF THIS CALCULATION ZS TO QUALIFY EXISTING CABLE TRAY AND CONDUIT SUPPORTS BY A-46 PROGRAM. THE METHODOLOGY FOR THIS PROGRAM DOES NOT ATTEMPT TO EVALUATE THE ACTUAL SEISMIC RESPONSE AND SYSTEM PERFORMANCE DURING AN EARTHQUAKE BUT RATHER TO SHOW THAT. THE CABLE TRAY AND CONDUIT SUPPORTS ARE AT LEAST AS RUGGED AS THOSE THAT PERFORMED WELL AS EVIDENCED BY PAST EXPERIENCE.
FIELD WALKDOWN FOR A-46 PROGRAM WAS PERFORMED FOR ALL CABLE TRAY AND CONDUIT SUPPORTS LOCATED IN REACTOR BUILDING UNIT 2 (EXCEPT CONTROL BAY AND REFUELING FLOOR AREAS), DIESEL GENERATOR BUILDING UNIT 1 & 2 AND OTHER COMMON AREAS NOT PREVIOUSLY COVERED UNDER UNIT 3 QUALIFICATION BY A-46 PROGRAM.OUTLZERS WERE IDENTIFIED AS PER THE GIP WALKDOWN PROCEDURE. A FEW ANALYTICAL SAMPLES WERE SELECTED IN THE FIELD BASED ON THE CONSIDERATIONS OF RACEWAY SUPPORT CONFIGURATION AND HEAVY LOADS ON THE SUPPORTS.
ASSUMPTIONS:
O UNVERIFIED ASSUMPTIONS ARE MADE IN THIS CALCULATION. ANY ASSUMPTIONS MADE ARE WITHIN THE GIP GUIDELINE OR DESIGN CRITERIA BFN-50-C-7104.
REQUIREMENTS/ LIMITING CONDITIONS:
THIS CALCULATION DOES NOT GENERATE ANY REQUIREMENTS OR LIMITING CONDITIONS WHICH LIMIT SYSTEM OR PLANT OPERATION FROM THAT CURRENTLY DOCUMENTED IN THE I
DES GN/ PL'ACE SPEC IAL REQUIREMENTS ON A SAFETY EVALUATION~ OR PLACE SPEC IAL REQUIREMENTS ON THE PHYSICAL CONFIGURATION THAT ARE GENERALLY OUTSIDE THE
.-.STATED PURPOSE OF THE CALCULATION.
0 TITLE: PAGE 4 OF QUALIFICATION OF CABLE TRAY AND CONDUXT SYSTEMS CALC CD-Q2999-940343 BY A46 PROGRAM PREP BYb C N DATE /-ld -'Pg CHKD BY~ DATEoi-Ia, q
REFERENCES:
- 1. GENERIC IMPLEMENTATION PROCEDURE (GIP) FOR SEISMIC VERIFICATION OF NUCLEAR PLANT EQUIPMENT BY SQUG.
- 2. AISC STEEL CONSTRUCTION MANUAL 8TH EDITION.
- 3. EPRI REPORT NP-7151, "CABLE TRAY AND CONDUIT SYSTEM SEISMIC EVALUATION GUIDELINES " EPRI, MARCH 1991.
- 4. EPRI REPORT NP-5228, REV. 1, "SEISMIC VERIFICATION OF NUCLEAR PLANT EQUIPMENT ANCHORAGES'PRIi JUNE 1991
- 5. EPRZ REPORT NP-7150, "THE PERFORMANCE OF RACEWAY SYSTEMS ZN STRONG MOTION EARTHQUAKESi EPRIi MARCH 1991
- 6. EPRI REPORT NP-7152, "SEISMIC EVALUATION OF ROD HANGER SUPPORTS FOR ELECTRICAL RACEWAY SYSTEMS," EPRI, MARCH 1991.
- 7. P-W INDUSTRIES CATALOG FOR CABLE TRAY SYSTEM.
- 8. NEMA STANDARD VE 1-1984, "METALLIC CABLE TRAY SYSTEMS".
- 9. BFN MARS REPORT, CEB-88-05-C R1.
- 10. CIVIL DESIGN STANDARD DS-C1.7.1.
- 11. DESIGN OF WELDED STRUCTURES BY BLODGETT.
- 12. UNZSTRUT NUCLEAR POWER ENGINEERING CATALOG.
- 13. DESIGN CRITERIA BFN-50-C-7104.
- 14. TVA CALC. 4 CD Q0000 931227 QUALIFICATION OF CABLE TRAY AND CONDUIT SYSTEM BY A-46 PROGRAM.
- 15. WORK REQUEST 4 C165042 & C030587
- 16. Left blank
- 18. TVA CALC. 0 CD Q0999 -885541 ANGLE SECTION PROPERTIES.
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'tiIIS SH".a"I ADDEO a Y REV.~
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TVAN CALCULATlONCLASSIFlCATION FORM CALCULATIONINFORMATION:
Plant BFN Unit 2 Identifier CD-Q2999-94P242 Rev.
Issue Date N/A Title System(s), Component, Feature or Subject of Calculation 999 Cable Tray and Conduit SYSTEESDESCRIPTION (AS NEEDED)
Systems Safety system System No.
X Safety-related feature 999 Q Nonsafety system ., System No. RKV MStGt4 ptttttt ~ii.'-'ate> ~t' Q Nonsafety-related feature Q Quality-related system X Quality-related feature 999 Non Quality related system Non Quality related feature p Plant environment (EQ, etc.)
Appendix R Civil structures Q Instrumentation (PAM, etc.)
I p Licensing Q Other Calculation Category C03, CIO Final Classification:
X Essential Q File Only Q Cancel Q Engineering Output Q Desirable Q Superseded Q Obsolete CI Preparer Date 08-13-97
~ Gromek Checker ~ Date Verifier ( Date 7VA 40537 [08-97J Page 1 of 2 NEDP-24 [0845-97)
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THIS SHE~ AODFD BY REV.
ge jeren ceo C eonhnued)
TVAN CALCULATIONCLASSIFICATION FORM Identifier:
REV OESlGN Dh pygmy ~~ PhTF I 'KZ Preliminary Classification X Essential Q File Only Q Cancel Q Engineering Output Desirable Superseded Q Obsolete Q CALCUL'ATIONCLASSIFICATION JUSTIFICATION:
Preparer Krystyn H. Gromek The supports evaluated in this calculation are for safety related and quality related cable trays
.and conduit. Therefore, this calculation is classified as essential.
Checker Q Agree with classification Q Disagree - comments required Verifier Q Agree with classification Q Disagree - comments required WA 40537 [08-97I Page 20f 2 NEDP-24 [0845-97I
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TITLE: PAGE + OF QUALIFICATION OF C2DELE TRAY AND CONDUIT SYSTEMS CALC CD-Q2999-940343 BY A46 PROGRAM
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PREP BYA Cg,.DATE>>-i& 9C CHKD BY DATE ui-)a -9'g DESIGN INPUT DATA:
- 1. CABLE TRAY WEIGHT INCLUDING 4" OF CABLE AND FLAMASTIC FILL 25 PSF.
TYPES'YSTEM 2 CABLE TRAY STANDARD LADDER NO 1 402 i RUNGS SPACED AT 6
- 3. STRUCTURAL STEEL MAT'L A36 UNLESS OTHERWISE NOTED.
- 4. WELDING ELECTRODE ~ E70XX.
- 5. CONCRETE f'c ~ 3000 PSI.
- 6. GIP BOUNDING SPECTRUM VS SSE GROUND RESPONSE SPECTRUM ANCHORED TO 0.2g AT 5o DAMPING SINCE BOUNDING SPECTRUM COMPLETELY ENVELOPES SITE SPECTRUM, THE FZND1NGS OF EXPERZENCE DATABASE ARE VALID FQR THIS SITE (REFER SHEET 9).
- 7. REACTOR BUILDING SEISMIC RESPONSE SPECTRA FROM MARS REPORT (REF. 9),
SUPERIMPOSED ON ROD FATIGUE BOUNDING SPECTRA ANCHORED TO 0.33, 0.50, &
0.75g. THIS INFORMATION WILL BE USED FOR'OD FATIGUE EVALUATION (REFER SHEET 10).
DIESEL GENERATOR BUILDING SEISMIC RESPONSE SPECTRA FROM MARS REPORT (REF 9) SUPERIMPOSED ON ROD FATIGUE BOUNDING SPECTRA ANCHORED TO 0 33i 0.50, & 0.75g. THIS INFORMATION WILL BE USED FOR ROD FATIGUE EVALUATION (REFER SHEET 11).
- 9. STRENGTH GAIN OF CONCRETE DUE TO AGING (FROM 3000 PSZ TO 3600 PSZ) MAY BE CONSIDERED.
- 10. ANCHORAGE TYPE;
--.THE PROMINENT ANCHORAGE TYPE USED FOR THIS PLANT HAS BEEN SELF DRILLING EXPANSION ANCHORS(SSD'S) . OTHER TYPES SUCH AS WEDGE BOLTS AND UNDERCUT ANCHORS, WHICH HAVE HIGHER STRENGTHS THAN SSD'S HAVE ALSO BEEN USED. IT I S POSSIBLES PARTICULARLY IN EARLIER STAGES OF CONSTRUCTION (LATE 60 S AND EARLY 70'S), THAT LEAD CINCH ANCHORS MIGHT HAVE BEEN USED IN SOME PLACES. LEAD ANCHORS PER GIP ARE OUTLIERS AND THEIR ALLOWABLE PULLOUT AND SHEAR VALUES PER REF. 10 ARE LESS THAN THOSE OF SSD'S. HOWEVER GZP DOES NOT REQUIRE THE REMOVAL OF EACH AND EVERY BOLT TO VERIFY THE ANCHOR TYPE AND THEREFORE IN CASES'HERE THE TYPE OF ANCHOR 'IS NOT KNOWNiTHE t
ANCHORS WILL BE ASSUMED TO BE SSD'S. NQ SIGNIFICANT DEGRADATION OF THE FUNCTIONALITY OF THE SUPPORT IS LIKELYI IFi INFREQUENTLY AND UNKNOWN TO THE ENGINEER, AN INSTALLED LEAD ANCHOR ZS EVALUATED USING SSD ALLQWABLES. THE JUSTIFICATION FOR THIS CONCLUSION IS DOCUMENTED IN TVA CALC. 4 CD-Q0999-940356.
IF THE TYPE OF ANCHOR IS KNOWN OR DETERMINED TQ BE A LEAD ANCHOR, THE SUPPORT SHALL BE TREATED AS AN OUTLIER AND EVALUATED ACCORDINGLY.
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TITLE: PAGE + OF QUALZFZCATZON OF CABLE TRAY AND CONDUZT SYSTEMS CALC CD~2999-940343 BY A46 PROGRAM PREP BY ac% DATE ~, i6.y<
CHKD BY Aq DATE ul-/b. gg DES IGN INPUT DATA (CON'):
- 11. EXPANSION ANCHOR CAPACITIES: (Ref 1, Appendix C)
PULLOUT CAPACITY GIP CAP. x (3600/4000) ~ 0.9 x GIP SHEAR CAPACITY GIP CAP. x (.65+3000/10000) 0.95 x GIP ANCHOR BOLT SIZE (IN) PULLOUT CAPACITY (LBS) SHEAR CAPACITY (LBS) 3/8 0. 9 x 1460 1314 0. 95 x 1420 1349 1/2 0.9 x 2290 2061 0.95 x 2380 2261 5/8 0.9 x 3170 2853 0.95 x 3790 3600 3/4 0.9 x 4690 4221 0.95 x 5480 = 5206 ALLOWABLES FOR SSD'S PER REF.10 ARE MORE CONSERVATIVE AS COMPARED TO THE VALUES CALCULATED ABOVE. IT IS THEREFORE ACCEPTABLE TO ALSO USE ALLOWABLES FOR SSD'S PER REF.10.
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TITLE: PAGE /Z OF QUALIFICATION OF CABLE TRAY AND CONDUIT'YSTEMS CALC CD~2999-940343 BY A46 PROGRAM PREP BYACP- DATE ~'lt-yg CHKD BY'cf 'DATE Ol-Is-y(
THIS, CALCULATION COVERS THE WALKDOWN OF THE FOLLOWING AREAS IN UNIT 2
.(REFER WALKDOWN INSTRUCTION NUMBER CEB-012)
AREA NO. DESCRIPTION OF AREA REACTOR BLDG NE CORNER ROOM EL. 519 & 541'-6" REACTOR BLDG SE CORNER ROOM EL. 519 & 541'-6" REACTOR BLDG SW CORNER ROOM EL. 519 & 541'-6" REACTOR BLDG NW CORNER ROOM EL. 519 & 541'-6" 17 REACTOR BLDG EL.565 18 REACTOR BLDG EL.593 19 REACTOR BLDG EL.621'-3" REACTOR BLDG EL. 639'0"
, DRYWELL ALL ELEVATIONS 38 TORUS OUTSIDE TORUS 41 ~ HPCI ROOM 43 DIESEL GENERATOR BLDG EL.565'6" DIESEL GENERATOR BLDG EL.583'-6"
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TITLE PAGE /9 OF QUALZFXCATXON OF CABLE TRAY AND CONDUIT SYSTEMS CALC CD-Q2999-940343 BY A46 PROGRAM PREP BYA c g . DATE/-ig - W4 CHKD BY ~ DATE oi- Ig -pi OUTLIER STATUS
SUMMARY
TABLE AREA NO PROBLEM TYPE OF CORRECTIVE ACTION REMARKS NO. PROBLEM QUAUFIED MODIFICATI MAINTENAN ON CE 17 17<1 Overspan/ Required Cable Tray Reactor Loose cables bldg. EL565 unrt 2 17%2 Overspan Conduit 18 18%1 Loose cables Required Cable Tray Reactor bldg. EL593 1842 Overspan Conduit unit 2 18%3 Anchor Conduit Cable Tray 19 Reactor bldg. EL621 unit 2 Anchor Cable Tray 1942'943 Anchor Cable Tray 26 26%1 Missing Required Conduit Drywell unit Clamp 2
3841 Required Conduit New support 38 to resolve Torus unit 2 the outlier.
Friction yes Conduit Clamp 43 Diesel Conduit Generator bldg EL 565.5,unit 1&2 44 Anchor Conduit Diesel Generator bldg EL Conduit 583.5,unit 182 Note: Area designation numbers are taken from Walkdown Instruction ¹ Wl-CEB-012
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TITLE PAGE 45 OF QUALIFICATION OF CABLE TRAY AND CONDUIT SYSTEMS CALC CD~2999-940343 BY A46 PROGRAM PREP BYTE@ W DATE l-l6- Q6 CHKD BY &y'ATEoi-ra -yg OUTLZER NO. 19 02
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TITLE PAGE 46 OF QUALIFICATION OF CABLE TRAY AND CONDUIT SYSTEM CALC CD~2999-940343 BY THE A46 PROGRAM PREP BY ~C~ DATE I-/6-'I6.
CHKD BY ~ DATE oi-i6-3L EVALUATION OF PROBLEM NO. 19-02:
CONCERN:
A CABLE TRAY. SUPPORT HAS EDGE DISTANCE VIOLATIONS ON ZTS ANCHOR BOLTS.
THE VIOLATION IS ON THE NORTH ANCHOR BOLT FOR THE VERTICAL MEMBER AND ON THE SOUTH ANCHOR BOLT FOR THE KNEEBRACE. THE SUPPORT ZS LOCATED APPROXIMATELY 3'-6" EAST OF R9 AND 10'-0" SOUTH OF COLUMN LINE S. SEE ATTACHED SKETCH.
RESOLUTION:
THIS CONCERN ZS SIMILAR TO PROBLEM NO. 19-03. AS DEMONSTRATED IN PROBLEM NO 19-03/ THIS SUPPORT ZS SEISMICALLY RUGGED BY COMPARISON.
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TITLE PAGE 47 OF QUALZFZCATZON OF CABLE TRAY AND CONDUZT SYSTEMS CALC CD~2999-940343 BY A46 PROGRAM PREP BY/~t" < DATE I I6-'76 CHKD BY DATE ot- gg. y g OUTZ ZER NO. 19 03
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TITLE: PAGE 48 OF QUALZFZCATZON OF CABLE TRAY AND CONDUZT SYSTEM CALC CD~2999-940343 BY THE A46 PROGRAM PREP BY/CA DATE I-Ig-gg CHKD BY DATE ot-g, EVALUATZON OF PROBLEM NO. 19-03:
1.) A CABLE TRAY SUPPORT HAS EDGE DISTANCE VIOLATION ON ZTS ANCHOR BOLTS. THE VIOLATION IS ON THE NORTH ANCHOR BOLT FOR THE VERTICAL MEMBER. THE SUPPORT ZS LOCATED APPROXIMATELY 10'0" EAST OF Rll AND 9'3" SOUTH OF COLUMN LINE S. SEE ATTACHED SKETCH.
DATA:
NO. OF TRAY TIERS ~ 6 SUPPORT SPACING = 7'-6" SUPPORT TYPE NO,. ~ 2B-A-8-6 (SEE DWG 48N1101)
ROD SIZE = 3/4A DIA.
NO. OF RODS ~ 2 TRAY SIZE ~ 18" WIDE ANCHOR. BOLTS:
FOR ROD ATTACHMENT (3) -3/4" DIA. 3 UNIT THREADED BOLT ANCHOR FOR KNEE BRACE ASSY (14)-3/4" DIA SSD TRAY CROSS MEMBERS ARE L2x2xl/4 LATERAL RESTRAINT MEMBERS:
W6x15.5 VERTICAL (2) L2-1/2x2xl/4 KNEE BRACE ST 7WF17xl'-0" GUSSET PLATE FOR KNEEBRACE AND VERT. MEMBER PL7/16x6x0-10" GUSSET PLATE FOR KNEEBRACE AND BASEPLATE 5/8" DIA A325 BOLT FOR METAL TO METAL CONNECTION L2-1/2x2-1/2xl/4 FOR TRAY CROSS MEM. TO VERT. MEM. CONNECTION
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TITLE PAGE 4 9 OF QUALIFICATION OF CABIZ TRAY AND CONDUIT SYSTEMS CALC CD~2999-940343 BY A46 PROGRAM PREP BY 8 < i< DATE I -l6- V4 CHKD BY ~ DATE ul- tC .yg EVALUATION OF PROBLEM NO. 19-03:(con't)
DEAD WEIGHTS:
CABLE TRAY = 25(7.5) (18/12) ~ 281.25 LBS/EA ROD ~ 1.503 (8.5) = 12.78 LBS/EA L2x2xl/4 ~ 3.19(23/12) = 6.11 LBS/EA W6x15. 5 15;5 (5) ~ 77. 5 LBS KNEEBRACE ~ 7.2 (6.7) ~ 48.24 LBS ST 7WF17xl'ON = 17 LBS L2-1/2%2-1/2xl/4 = 6 (4. 1) (1) 24. 6 LBS 5/8" DIA BOLTS ~ 22 (0. 331) ~ 7 LBS CHANNEL CSxl3.75 = 13.75(2) = 27.5 LBS VERT. MEM. BASEPLATE ~ .75 (10) (17) (490/1728) ~ 36 LBS
'. KNEEBRACE BASEPLATE =.75 (10) (24) (490/1728) ~ 51 LBS GUSSET PL FOR KNEEBRACE ='.4375(6) (10) (490/1728) 5/8" THICK PLATES ~ . 625 (3. 5) (6. 5) (490/1728) (6) = 24 LBS 7 LBS TOTAL SUPPORT DEAD WEIGHT, Wt 281.25 (6) +12.78 (2) +6. 11 (6)+77.5+48.24
+17+24.6+7+27.5+36+51+7+24 = 2070 LBS EFFECTIVE DEAD WEIGHT TO BE CONSIDERED FOR DEAD WEIGHT ANALYSIS:
EAD WEIGHT, DW 27. 5+12. 78 (2) +6 (6. 11) +281. 25 (6) +24. 6/2+6 (0. 331) 17920 SEISMIC 'ACCELERATIONS
" AT ELEVATION
-'" 639'-0" (ZPA):
'BE SSE VERTICAL ~ 0.09g 2 (0- 09) 0. 18g N-S 0.20g 2(0.20) = 0.40g E-W = 0.22g 2(0.22) - 0.44g EQUIVALENT'TATIC LATERAL LOAD = Wt x 2.5 x 0.44 2070(2.5)(.44) = 2277 LBS CHECK- 1: DEAD LOAD CHECK:
DEAD LOAD CHECK IS PERFORMED IN THE ROD HANGER ASSEMBLY ONLY, IGNORING VERTICAL W6 MEMBER AND KNEE BRACE. IF THIS PASSES, THE EDGE VIOLATION ON ANCHOR FOR VERTICAL MEMBER SHALL NOT MATTER.
EXPANSION SHELL AT CEILING:
CONSIDERING (3) -3/4B DIA. SSD CAPACITIES:
PULLOUT ~ 4221 LBS SHEAR ~ 5206 LBS MAXIMUM PULLOUT FORCE PER BOLT I P P = DW/3 = 1792/3 = 597.33 LBS < 4221 LBS IR P/Pa - ~
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597.33/4221 = 0.142 < 1.0, O.K
~ ~ ~
CHANNEL CSxl3.75:
CSx13.75 IS ADEQUATE TO TRANSFER THE DESIGN LOADS TO THE ANCHORAGE BY ENGINEERING JUDGMENT.
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TITLE: PAGE 5o OF QUALIFICATION OF CKBLE TRAY AND CONDUZT SYSTEMS CALC CD~2999-940343 BY A46 PROGRAM PREP BY PER-DATE (-lg- V6 CHKD BY DATE i -/4- 95 EVALUATION OF PROBLEM NO. 19-03:(con't)
(2) -3/4B DIA RODS-MAXIMUM TENSION FORCE PER ROD, F ~ DW/2 ~1792/2 = 896 LBS.
TENSILE STRESS, FT ~F/A,~ = 896/0.302 ~ 2967 PSI IR ~ 2967/(0.33x58000) ~ 0.155 < 1.0, O.K TRAPEZE CROSS MEMBERS: (L2x2xl/4): (PROPERTIES PER REF. 18)
M = (281. 25 + 6. 11) (20/8) = 718. 4 ZN-LBS My Mz = 718.4(0.707) 508 IN-LBS
=
fby 508/0.3902 1302 PSZ fbz = 508/0.1902 2671 PSI IR ="t1302+2671) /21600 '.184 < 1.0, O.K THE REMAINDER OF THE SUPPORT ZS JUDGED TO BE WITHIN DESIGN ALLOWABLES, THEREFORE'UPPORT IS 0 K FOR DEAD LOADS CHECK 2: 3 X DEAD LOAD VERTICAL CAPACITY CHECK CHECK ONLY EXPANSlON ANCHOR AT CEILING:
PULLOUT FORCE ~ 3(597.33) 1792 LBS < 4221 LBS, O.K IR 1792/4221 0.425 < 1 'g O.K CHECK 3 DUCTILITY CHECK FOR LATERAL MOTION, THIS SUPPORT WILL EXHIBIT DUCTILE RESPONSE WITHOUT CONSIDERING THE LATERAL RESTRAINT.
ANCHORAGE CHECK:
MOMENT CAP. ~ 4221(10) = 42210 IN-LBS ROD PLASTIC MOMENT CAP. ~ 90000(1.7) (0.024) = 3672 IN-LBS 42210 IN LBS > 3672 IN LBSt THEREFORE'UCTILE ROD END IS CONSIDERED PIN CONNECTED BECAUSE NUTS ARE ONLY PRESENT AT THE TOP. OF THE CHANNEL FLANGE. ROD FATIGUE CHECK IS NOT REQUIRED.
THEREFORE'UPPORT IS SEISMICALLY RUGGED.
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TITLE: PAGE 8'g OF QUALIFICATION OF CABLE 'TRAY AND CONDUXT SYSTEMS CALC CD~2999-940343 BY A46 PROGRAM PREP BY A~~ DATE l 16-94 CHKD BY AP DATE as.iy. y~
OUTLIER NO.44 '01
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TITLE: PAGE 57 OF QUALZPZCATZON OF CABLE TRAY AND CONDUZT SYSTEMS CALC CD~2999-940343 BY A46 PROGRAM PREP BY /c W DATE t-g,- Pg CHKD BY ~ DATE di.ib.g@
EVALUATZON OF PROBLEM NO. 44-01:
CONCERN:
TWO 3/4" DIA ALUMINUM CONDUITS 'ARE SUPPORTED BY TRAPEZE ROD HANGERS. THE CONCRETE SHELL ANCHORS ARE PROTRUDING ON 3 OUT OF FOUR SUPPORTS- SEE ATTACHED SKETCH.
RESOLUTZON:
THE CONCERN WAS ALREADY ADDRESSED AS A DISCREPANCY NO. 57-65 PER PZ 85-02. THE INTRODUCTION OF SUPPORT 48B810-65 CORRECTED THE DISCREPANCY.
A MAXIMUM SUPPORT SPAN OF 16'0" WHICH IS GREATER THAN THE ACTUAL SPAN OF 9'-0" HAS BEEN CONSIDERED PER REVIEW OF THE SUPPORTING CALCULATION SKETCH'l BFEPC80597 ~ THEREFORE'OR THE PURPOSES OF THIS GIP EVALUATIONS CONDUZTS AND SUPPORT ARE JUDGED TO BE SEISMICALLY RUGGED DUE TO VERY SMALL LOAD.
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PROBLEM NO. 1~ ( o S V5 S).
OUTLIER IDENTIFICATION,DESCRIPTION, AND LOCATION BUILDING 'EACTOR AREA NO.: 19 ROOM OR ROW/COLUMN: R9-R10/S - T FLOOR EL: 621.25 ITEM (CIRCLE ONE) CABLE TRA CONDUIT
- 2. OUTLIER ISSUE DEFINWON
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.)
Cable and conduit racewa s inclusion Rules SHEET III APPEHQIX NO Other Seismic Performance Concerns CALC HO Limited Analytical Review 403(
CO 02S S9 S 3 RO Other
- b. Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item to be verified for seismic adequacy.):
- 1) A Cable Tray support has edge distance violations on its anchor bolts. The viola tion is on the north anchor bolt for the vertical member and on the south anchor bolt for the brace. The support is located approximately 3' 6" east of R - 9 and 10' 0" south of col. line S. See attached sketch.
- 3. METHOD OF OUTLIER RESOLUTION (OPTIONAL)
Support is acceptable per calc. ¹ CD-Q2999-940343
- 4. CERTIFICATION The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outtier issues listed on this page will satisfy the requirements for this item to be verified for seismic adequacy:
Approved By:
Anand C. Relwani. %~M c. -I 7 PRINT OR TYPE NAME'r SIGNATURE DATE O. Pascua 9-/7- g4 lNT OR TYPE NAME IGNATURE DATE
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BROWNS FERRY UNIT 2 OUTUER SEISMIC VERIFICATION SHEET (OSVS)
PROBLEM NO. ~1 (05'I/5 'I+/
- 1. OUTLIER IDENTIFICATION, DESCRIPTION, AND LOCATION BUILDING: DIESEL GENERATOR BLDG AREA NO.:44 ROOM OR ROW/COLUMN: 21' 0" north of south wall FLOOR EL.: 583.50 ITEM (CIRCLE ONE) CABLE TRAY CONDUIT
- 2. OUTLIER ISSUE DEFINITION
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidelines could not be satisfied.)
Cable and conduit racewa s Inclusion Rules SHEE'T NO Rgt, Other Seismic Performance Concerns v APPENOIX NO 4 Limited Analytical Review CALC NO Other CO 02999 940343 IIO
- b. Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider this item to be verified for seismic adequacy.):
- 1) Two 3/4" dia aluminum conduits are supported by Trapeze rod hangers. The concrete shell anchors are protruding out on 3 out of 4 supports. See attached sketch.
- 3. METHOD OF OUTLIER RESOLUTION (OPTIONAL)
Supports are acceptable per calc. ¹ CD - Q2999 - 940343
- 4. CERTIFICATION The information on this OSVS is, to the best of our knowledge and belief, correct and accurate, and resolution of the outlier issues listed on this page will satisfy the requirements for this item to be verified for seismic adequacy:
Approved By:
Anand C. Relwani 4 WC R.~ 9- Ze- <'I+.
PRINT OR TYPE NAME SIGNATURE DATE sar O. Pascua BINT OR TYPE NAME GNATURE DATE
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