ML20086H985
| ML20086H985 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/27/1991 |
| From: | House K, Suttle G TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20086H977 | List: |
| References | |
| SCG-2M-0025, SCG-2M-0025-R01, SCG-2M-25, SCG-2M-25-R1, NUDOCS 9112100223 | |
| Download: ML20086H985 (9) | |
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l PAGE I T V A 10$ 34 (EN DES a 78)
4 BCO-2M-0025 PROJECT! SEQUOYAH NUCLEAR PLANT UNIT 1&2 CAIIUIATION DESIG1 VERITICATICN (INDEPDIDDTP RLVIEW) FOIN d
__ _ECG-2M-0025 0 calculation No. Revision Methcd of design verification (irriependent reviw) used (check method uscd):
- 1. Design Review /
- 2. Altermte Calculation
- 3. Qualification 'Ibst t.rustification (e.xplain tel m):
Mithq__2:d In the design review methed, justify the technical adoquacy of the calculation ard explain how the adequacy was veriflod (calculation is simi.lar to another, based on accepted hardbook methods, appropriato sensitivity studies included for confidenoa, etc.).
Mnnod 2: In the altermte calculaticn method, identify the pages where the alternato calculation has been includod in the calculation package ard explain why this methcd is adequato.
Method 3: In the qualification test method, identify the OA documented coatte(s) where testing adequately denenstrates the adequacy of this calculation and explain.
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i PROJECT: SEQUOYAH NUCLEAR PLANT U11IT: 1\2 CALCUIATICti DESIG1 VERIFICATIO!1 (INDEFB'DDTP Fr/IDY) FOM4 scc,- zM-oozs 1 Calculation No. Revision Methcd of design verification (irdependent reviw) used (check rothod tuxd):
- 1. Design Ttevi w
- 2. Alternate Calculation
- 3. Qualification Test Justification (explain balcu):
li2thcsL1: In the design review nethed, justify the technical adcquacy of tha calculation ard explain hw the adegaacy was verificd (calculation is siJnilar to another, banod on accepted hardbook rethods, apptr.priato censitivity studies included for confidence, etc.) .
Methgl 2: In the alternate calculation mothcd, identify the pages where the alternate calculation has been included in the calculation package and explain why this methcd is adcquate.
Method 3: In the qualification test rothod, identify the QA dccunented scurce(s) khere testing adequately demonstrates the adecpscy of this calculation ard explain.
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'Date (Irdeperdent RevicWy ks PAGE 'Al .1
Calculation SCC-2M-0025: Evaluation of Block Clamps at Welds Near Valves 0-67-1514 and 2-67-1513 Prepared: . O. u Date: ll- 2 l -9 I Checked: c /Mf A Date: //-2 /-9 [
Purnose:
The purpose of this calculation is to evaluate the structural integrity of two block clamps used to reinforce two leaking welds in the ERCW system. This adverse condition was documented in SQPER910339.
Diggunnign:
Two fillet welds in the ERCW system were found to be leaking by the system engineer. These welds are located on the relief The valve branch lines of valves 0-67-1514 and relief valves are immediately downstream 2-67-1513.
of the 082 and 2A1 CCS Heat Exchangers and are contained m in piping analysis problems N2-70-52A and N2-67-3A1, 9 respectively. The leaking welds were examined by vnsousu p*rtog g,9 Engineering and Plant personnel. It was determinedAthat gf the bond between the weld and coupling failed for thirtyX ;g'M degrees of the circumference, but the bond between the weld and 3/4" relief piping was intact all around. A two piece block clamp was machined to fit snugly over the leaking welds. A sketch of the clamps is shown below. Note, not to scale. O (g
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Calculation SCG-2M-0025: Evaluation of Block Clamps at I Weld: Near, Valves 0-67-1514 and 2-67-1513 l Prepared: Id. u Dato: ,
1/ 9/
Checked: [Ah/ e. Date: //-2/-7/
Re f ere nc_ng:
- 1. Pages B1 through B10 of piping analysis calculation N2-70-52A (RIMS 887 910717083). This is an evaluation of DCN-F3105, which rerouted the branch line containing 0-67-1514.
- 2. TACF-2-91-54-067
- 3. FRAMS, Auxiliary Building, Elev. 732.5 ft.
- 4. Piping isometric 47K450-238.
Askumotions: There are no assumptions which require verification.
C2mnptationst In order to determine structural integrity of the block clamp, the clamp and bolts must be adequate to withstand the forces and moments induced by the relief piping.
The bolts will obviously be the weak link since the
- 2'* block is essentially solid with holes bored out for the
( pipe and bolts. Examination of the block clamp for 2-67-1513 shows that it will have the higher bolt loads because the moments will be higher. Both relief lines are cantilevers and the moments will be highest at the fixed end. Page B5 of Reference 1 shows ample stress margin for the fixed end of the branch containing 0 ,
1514. Therefore only valve 2-67-1513 vill be considered in th[s analysis.
The forces and moments acting on the pipe will come from pressure, iendweight, thermal and seismic loading conditions. Deadweight and thermal are static and will not induce loading on the bolts. Pressure will cause an 6\
uplift load below.
calculated on the -Re-lic branchf veW4 ling,%pe T
et-pressure pressure force is for is used conservatism. The weight of the valve is subtracted from the pressure induced force.
Internal area of 3/4" sch. 40 pipe a .533 in'.
Design Pressure = 105 PCIG-150 PstG e5 Uplif t Imrce a h:ggG(.533) 25 lb. = if lb.
ively assuming a weld strength of 10,000 psi, ConsegzAg/r only DSF in8 of bond.gp weld surface are required to EAg prevent uplift. The M& degrees of intact weld surface pal provides significantly more than ini . CosE RVNnVEL.Y, von A Ye me, inr Ac r u pact MEA:(,7g)gg(g,3,, g,og ') - 35 of y) e554 gj,.7/g 3 a 2
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Calculation SCG-2M-0025: Evaluation of Block Clamps at i Welds Near Valves 0-67-1514 and 2-67-1513 Prepared: If)Mme Date: //-Al-9I Checked: k _k Date // 2/ #f /
Regarding seicm1 Sads. rigid range accolorations will be used since th. ranch line is rigid. Reference 3 gives the following accelerations, lL. H E .E Y18 OBE .1571 .1715 .0975 SSE .3141 .3423 .1856 there Since will be no vertical accelere' eismic uplite ions because are less gravity than wil lgl not have been overcome. A maximum acceleration of .40g's will be used in the computations. Reference 1 gives an assembly weight of 24.06 lb. A weight of 25 lb. will be used in the computations. Detail "A" of Reference 4 givac a branch length ot 8". A length of 10 inches will be uuod for conservatism.
The maximum moment is the product of the valve weight, acceleration and moment arm or 100 in-lb. Examination of the block arrangement shows that the tensile load on the bolts will be the controlling load. In the shear 2'* direction, the block itself Will absorb the load. The tensile load on the bolts is calculated below, wm Cwv > m.
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b u n e or we_c M GN GETwCEN FiLLYT wtLD g Ant mTAC 9 g97g #* AHO thvPL.uac BAS FAttta 50 9 S e ,, m .w 90 M The cou le produced by the bolts must restrain 100 in-lb. Y"/4I (100in- b)/ (1.1251n) (2 Bolts) = .L4. Ik ppI _qll, which is less that the allowable of 438 lb from Ref. 2.
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Calculation SCG-2M-0025: Evaluation of Block Clamps at l Wolds Near Valves 0-67-1514 and 2-67-1513 Prepared: kO. Wt. Dato: //- A l-91 _,,
Checked: 2kb'/Nr. Date: //-2/-7 /
EMEE.0IX:
The block clamps have been evaluated for their ability to provide structural support for the faulty welds for all loading conditions. The proucure induced uplift force will be adequately restrained by the weld material still bonded to the branch lines. Deadweight and thermal will not impact the block clampo. Seismic induced bolt loads are less than the allowable load specified in Reference 2.
f20.0G11LO19Bi The block clamps are adequate to provide ntructural integrity for the leaking wolds.
an
-4 -
ENCLOSURE 2 COMMITMENTS
- 1. TVA will repair or replace the af f ected weld material in accordance with the American Society of Mechanical Engineers code before restart (Made 2) from the currant Unit 1 Cyc)e 5 outage.
- 2. Structural integrity of the OB2 and 2A1 con:ponent cooling cystem heat exchangers will be ensured on a weekly basis, by monitoring the temporary alteration for further degradation. Weekly monitoring will continue until weld repair or replace: rent is cenq ete (bef ore t' nit i restart - Mode 2).
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