RNP-RA/12-0119, Supplemental Response to Request for Additional Information Related to Relief Request (RR)-07 from Immediate ASME Code Repair of Refueling Water Storage Tank Drain Valve (SI-837) for Fifth Ten-Year Inservice Inspection Program...
| ML12340A441 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/11/2012 |
| From: | Wheeler S Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/12-0119 | |
| Download: ML12340A441 (13) | |
Text
Progress Energy Serial: RNP-RA/12-0119 NOV 1 12012
,ATTN: Document Control Desk U,S. Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 SUPPLEMENTAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST (RR)-07 FROM IMMEDIATE ASME CODE REPAIR OF REFUELING WATER STORAGE TANK DRAIN VALVE (SI-837)
FOR FIFTH TEN-YEAR INSERVICE INSPECTION PROGRAM PLAN By letter to the U. S. Nuclear Regulatory Commission (NRC), dated October 25, 2012, Carolina Power and Light Company, now doing business as Progress Energy, submitted a response to a request for additional information (RAI) received from NRC staff on October 16, 2012 (Agencywide Documents Access and Management System Accession No. ML12290A251) related to relief request (RR)-07 for the Fifth Ten-Year Inservice Inspection Program Plan for H.
B, Robinson Steam Electric Plant (HBRSEP) Unit No. 2, RR-07 was submitted to the NRC by letter dated October 5, 2012 (ADAMS Accession No. ML12292A386). RR-07 requested relief from the 2007 Edition, through the 2008 Addenda, of the ASME Section XI Code requireier'lt as stipulated in Paragraph IWC-3122.2 on the basis that compliance with the specified requirements would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. RR-07 was submitted after discovery of a through-wall flaw in the body of the Refueling Water Storage Tank (RWST) drain
- valve (SI-837).
In its October 25, 2012 response to the request for additional information, Progress Energy provided the requested information for RAI items 1(1), 2, and 3(3). In its responses to RAI items 1(2), 3(1), and 3(2) Progress Energy indicated that the requested information would be provided in a separate supplemental response pending finalization of the design of the clamp or completion of a calculation of the maximum leakage flaw size that does not challenge the RWST inventory make-up capability.
Enclosed, please find a supplementalresponse for items 1(2), 3(1), and 3(2) of the request for.
additional information received by Progress Energy on October 16.
This letter contains no new Regulatory Commitments.
Progress Energy Carolinas,Inc.
Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC29550
United States Nuclear Regulatory Commission Serial: RNP-RA/12-0119 Page 2 of 2 If you have any questions concerning this matter, please contact Mr. Richard Hightower, Supervisor - Licensing/Regulatory Programs at (843) 857-1329.
I declare under penalty of perjury that the foregoing is true and correct. Executed On:
Auove.14ýe- ~i tOM-Sincerely, Sharon A. Wheeler Manager - Support Services - Nuclear SAW/sjg
Enclosure:
Supplemental Response to Request for Additional Information Relief Request Number RR-07 Repair of Safety Injection Valve SI-837 cc: Mr. V. M. McCree, NRC, Region II Ms. A. T. Billoch-Colon, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP Unit No. 2
United States Nuclear Regulatory Commissidn ,:
Enclosure to Serial: RNP-RA/12-0119 Page 1 of 3 ENCLOSURE SUPPLEMENTAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NUMBER RR-07 REPAIR OF SAFETY INJECTION VALVE SI-837 H.B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 NRC REQUEST FOR ADDITIONAL INFORMATION (RAI)
By letter dated October 5, 2012, (Agencywide Documents Access and Management System Accession No. ML12292A386) Carolina Power and Light (the licensee) requested relief from the requirements of the 2007 Edition through the 2008 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, IWC-3122.2. The licensee proposed an alternative to repair a degraded drain valve that is connected to the Refueling Water Storage Tank (RWST) as discussed in Relief Request Number RR-07. To complete its review, the Nuclear Regulatory Commission (NRC) staff requests the following information:
- 1. Page 2 of the relief request states that the current leak rate does not challenge the RWST inventory make-up capabilities. (1) Provide the actual RWST inventory make-up capabilities (e.g., in gallons per minute) and discuss the source and delivery of the make-up coolant. (2) Provide the maximum leakage flaw size (approximation is acceptable) that would not challenge the make-up capabilities.
- 2. Page 4 of the relief request discusses the allowable through wall axial and circumferential flaw length. Submit the fracture mechanics calculation of the allowable flaw lengths.
- 3. (1) Provide the design drawing(s) and the stress analysis of the mechanical clamp. The design drawing(s) should show the dimensions (including weight) and how the clamp is installed on the valve (the final installed configuration).
Along with the stress analysis, provide the methodology, assumptions, and allowable stresses. Discuss if the stress analysis indicates the mechanical clamp will exert sufficient forces on the flaw to mitigate its growth and reduce leakage.
(2) Discuss if sealant is or is not used with the mechanical clamp to stop the leak.
(3) If after installation of the clamp assembly, the leak continues, discuss the acceptability of the weekly monitoring frequency and provide leak rate limits at which time corrective action would be taken. When establishing the leak rate limits, please discuss how these limits will ensure that adequate capacity will be maintained in the tank to ensure the design basis is maintained.
United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA!12-0119 Page 2 of 3 DISCUSSION Progress Energy provided a response to the above requested information by letter dated October 25, 2012 which provided the requested information for items 1(1), 2, and 3(3). The response to items 1(2), 3(1), and 3(2) indicated that a separate supplemental response would be submitted to provide requested information that was not available due to the pending completion of a calculation of the maximum leakage flaw size that does not challenge the RWST inventory make-up capability, item 1(2) and finalization of the clamp design, items 3(1) and 3(2). The requested information for RAI items 1(2), 3(1) and 3(2) are presented below.
Supplemental Response - RAI Item 1(2)
Progress Energy has calculated approximate maximum leakage flaw sizes that do not challenge the nominal RWST inventory make-up capability of 84 gallons per minute to be no less than 2.5 inches long with a width 0.377 inches and no less than 12.9 inches long with a width of 0.073 inches.
Supplemental Response - RAI Item 3(1)
Design drawings of the leak limiting mechanical clamping device Progress Energy plans to install are presented on pages 1 and 2 of the Attachment. The leak limiting mechanical clamping device is not designed to exert forces on the flaw in the valve body sufficient to mitigate its growth and/or reduce leakage through the valve body.
The mechanical clamp consists of a Furmanite box that is to be installed to enclose the entire valve. The Furmanite box is designed to provide a pressure boundary that prevents discharge from the leak through the valve body to the environment under expected pressures and temperatures. A copy of the stress analysis for the Furmanite box is presented on pages 3 through 7 of the Attachment.
The Furmanite box is designed such that all calculated stresses are less than allowable stresses for each material and that the materials are suitable for the intended use.
Supplemental Response - RAI Item 3(2)
Sealant will not be used to seal the leak through the body of the RWST drain valve (SI-837).
The clamping device is a Furmanite injection box with sealant injected at the interface between the outside diameter of the drain line and the inside diameter of the box to form an o-ring type seal. Sealant is applied both upstream and downstream of the valve. Sealant is also injected at the interface between the clamping surfaces of the Furmanite box to seal the box. The amount of Furmanite material injected will be monitored and controlled to prevent introduction of sealant material into the piping and/or valve.
United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/12-0119 Page 3 of 3 The installed clamping device (the Furmanite box) will provide a pressure boundary that encloses the valve and will prevent leakage to the environment. Leakage through the valve body may occur after installation of the clamping device (Furmanite box) into the free volume between the valve body and inside surface of the Furmanite box. The weight of such leakage is included in the weight of the clamping device used in assessing the capability to meet applicable structural requirements.
United States Nuclear Regulatory Commission Attachment to Enclosure to Serial: RNP-RA/12-0119 8 Pages (including cover page)
Pages 1-7 of Attachment B to EC0088526 7 pages
1 2 3 4 4
2 3 NOTES IF IN DOUBT ASK PARTS LIST DRAWING NO. CUS1209118-DWC-01 A REV.
MATERIAL SPECIFICATION: REMOVE ALL SHARP EDGES. Do Not Scale Off Drawing CLAMP IDENTIFICATION NUMBER TO BE ITEM DESCRIPTION ITY. MATERIAL SPEC.
PLATE -SA-240 GR.-316L / 316 PIPE - SA-312 GR.-TP 316L /316 STAMPED IN 0.375" HIGH LETTERS. 3/8" 1 STUD: 5/8"-11UNC X 4 1/2" LONG 28 SA-193 GR.-B8M CL. 1 INSPECTIONa REFER QAP 1316.3 45" 2 NUT: 5/8"-11UNC HEAVY HEX. 56 SA-194 GR.-8M 045.
m 3 PACKING. 3/8" SQ. GRAPHITE ( NOTE 10.) 0 A Co 7" 0)
B 716 5" PIPE 1"
.3 75" WALL THICK (D 0
1,, 45" C 2 3-/8- 4/5 (n 219/" -- I 0
( 10 NOTES: 3/8"7
- 1. SAFETY RELATED.
- 2. COMPONENT DESIGNATION: S1837.
- 3. PROCEDURE NUMBER: N-2012159.
C 4. PACKING GROOVE ON THE BORES AND SPLIT LINE: .375" WIDE X G-)
X .438" DEEP.
- 5. INJECTION POINTS INTO THE PACKING GROOVE: DRILL THRU 03/16".
DRILL AND TAP FOR 3/8"-16UNC X 3/8" DEEP. ONE BETWEEN STUDS AND 4/BORE/HALF.
- 6. PEENING GROOVE AROUND THE BORES: 3/16" X 3/16" X 60".
TECHNICIAN SCOTTIE ARROWOOD MFG/SHOP LAPORTE, TX.
- 7. ALL DIMENSIONS ARE TYPICAL UNLESS OTHERWISE SPECIFIED.
- 8. MEASUREMENTS WITH AN "*" ARE CRITICAL DIMENSIONS. WPS NO. WPSO004 JOB NO. 101-LS-104334 0
- 10. PLANT TO PROVIDE SAFETY RELATED PACKING. COMPOUND TYPE. FSC-N-1B,6B COMPOUND EST. 42 STICKS r) t(GN PRESSURE:. I nr Oc~ I ICopyeght 0 2006.
ten rht ond This drowing end oi1 right. therein (imcludingcopyright
'likerights) one the property of F.... ite Worldwide I UEE ,
E3- SCALE no. ond/-r its subsidiory coneponrie. ond must not be used. dostributed MAX. DESIGN TEMP: 150'F N.T.S to others or reproduced without the written permission or consent of
- urrenite WortdwtseInc. MAltkIML~t~lAJt hFTLtP"UI*JtM*I*
IFurmonite WorldwideInc. MAXIMISING ASSEr UPT1W D MIN. DESIGN TEMP: ALL0WE11SONI -
GEN.SRAEF DRAWING No.CUS1209118-DWG-O1 REV.'A ISTATUS RELEASED CONTENTS: REFUELING WATER GEN t
. MAHIMNNSlflL ~.1' .ZOi CUSTOMER NO: PR0026 SGENFABRICATION D-8'.i00 TOL-Wa' TITLE LEAK SEALING ENCLOSURE FOR 6" VALVE En --
--- - >6.'(12'. *0.12y CUSTOMER: >12.-, *o.i1so' SHEET TITTLE MANUFACTURING DETAILS SHEET 1 OF 2 h PROGRESS ENERGY FRACTION&A BUMi +1/8- -0.0 N/A Id DRAWN 9/24/2012 9/24/2012 LAST MODIFIED 9/24/2012 CHECKED 09/24/2012 APPROVED N/A I-E H.B. ROBINSON NUCLEAR ST. EHIJAZI EHIJAZI IJIM STORMER APPROVER L
1 2 3 44 2 3 IN DOUBT ASK Do Not Scale Off Drawing A 1/8" 45.
7 B
WELD REF. C,DoE.
WELD PROCEDURE QUALIFICATION (PQR) IMPACT TESTS ARE REQUIRED
--BUT SEE GENERAL WELDING NOTE 1 CHARPY V-NOTCH IMPACT TEST CRITERIA (3/8 X 3/8 IN SPECIMEN):
0.0151N MINIMUM LATERAL EXPANSION AT A TEMPERATURE NOT GREATER THAN 32 *F C WELD REF. A,B GENERAL WELDING NOTE 2 APPLIES GENERAL WELDING NOTES:
WHERE NOTE 1 APPLIES, THE INDICATED WELD PROCEDURE QUALIFICATION (PQR) IMPACT TEST REQUIREMENTS MAY BE WAIVED IF THE WELD CONSUMABLE CONFORMS TO SFA/AWS SPECIFICATION -5.4, -5.9, -5.11, -5.14, OR - 5.22 WHERE NOTE 2 APPLIES, THE WELD CONSUMABLE MUST CONFORM TO SFA/AWS SPECIFICATION -5.4, -5.9, -5.11, -5.14, OR - 5.22 S 0 2006. This drawingand oil rightst therein(nldn copyog SC oLCPyright THIRDANGLEF EA N
designright and oil like rights) are the propery of Fu aito Frnnnarmn its subsidiary conmporie,nand musat aTnS~~d/or WorldwideInc.
poroi rdi not ho used distrbute UR M A NITS 0 MAXIMISING ASSET UPTIME l'J D ALLDIMW NSIN CKM DRAWING No. REV Sý ib 0 ML SA o~ FH "CUS1209118-DWG-01 "A RELEASED o_,
GM MAWO-'ING TOL: *'O.01,-+/-O GEMFABRTION TOLt- TITLE C-4 -.o m'" SHEET
>0.
LEAK SEALING ENCLOSURE FOR 6" VALVESHEET OF FRACTlON&BUM +11/ 190TITLE MANUFACTURING DETAILS 2 2 hw (3)
ý-.. ,LJ C4 -)
DRAWN 9/24/2012 LAST MODIFIED 9/24/2012 CHECKED 09/24/2012 APPROVED N/A EHIJAZI EHIJAZI IJIM STORMER APPROVER -A
EC 88526 RO Attachment B - CUS12-09-118-PACKAGE 3 of 19 No. FWI-ENG-LS-XLT-003 issue: 2.6.1 U Fa I M A' E I' Work Book Template Enclosure Clamp Design 0 2005-2011 Furmanlte Worldwide Inc., 2435 North Central Expressway, Suite 700, Richardson, TEXAS 75080, USA.
This Work Book Is the property of Furmanite Worldwide Inc. It may not be copied, used or altered without the written permission of the company.
Oesign Bests FWt-ENG-LS-DS-O01 Rev.B Drocument Number CUSl20911e-XLS-"1 Revistson A 1Page Document Type Excel Spreadsheet Document Title LEAK SEALING ENCLOSUE FOR e' VALVE Engineering Job No. Customer PROGRESS ENERGY Clamp Number CUS12-09-118 Site H.S. ROBINSON NUCLEAR ST.
Created 09M441210Moditied 09A4112 Approved 090401? Document Status EHIJAZI EHIJAZI JIM STORMER RELEASED General Calculation SAFETY RELATED -COMPONENT DESIGNATION: $1837 -PROCEDURE NUMBER: N-2012159.
Notes:
Design and Operating Conditions:
Design Pressure 100 psI Void Injection Pressure 725 psi Operating Pressure Max. 25 psi Void Pressure 109.33 psi Design Temperature Max. 150 'F Test Pressure Oper*t*ig Temperature Max. 100
- DOesýgnTemperature Min.
Internal Corrosion Ailowance: Contents: REFUELINGWATER Structural Restraints Policy: Structural Restraint is not Required Enclosure Clamp Materials:
MatedalSpec., Grade, Class I Cond. I Temper/ Special Requirements, Ruling Temp. LimiI, Design Stress, Application Delivery Condition Section *F psi SA.240 Grade 310L, Plate 850 1225 SA-312 Grade TP310L, Stole. & wld. pipe 050 1 70.
Enclosure Clamp Bolting Materials:
Bllt Material Spec., Grade, Class I Cond. I Temper I Special Requirements, Temp. Limit, Design Stress, ,
Ruling SeonApplication SA-193 Grade SM Claw 1, Stud Boll t0S 18250 Enclosure Clamp Construction Details; Clamp Construction Type Welded Tube Ss Completed Clamp Fabrication to be Subject to Post Weld Heat Treatment?
Joint/Component Ref: C onetomponent Material Used (Prt A) Material Used (Part )
A.-Rek Lug toShe#*O.0* 4t PdPn Doubl.RNQ Lug:SJ40 Gdrde3f6L,P1tr MOShe A-3f2Gade TP316L,SWl. A .1d.pip.
a; R.L0, 0.Si.on LugfoE/ndCAP (PerirvPemov*Lon) Lug, "No24Ga~d.316L, Plao EndCp: SA-240Gradt31Q,*Plat#
C.,RoUf End Ca to Shell(FuH Pmnl~ftonaun~fpius FloodJ EndCW4t A.240Grd. 316L,PLO Sh.11:&A.30*Gld, TP316L,&. Am*wid pip.
D.-Ret.34 franchto$1ftU(SIt.OrNoR*Jnfor~mww Pr-nMShel1,"12tf G~d. TP~f6L,$m6*
.. pip. ManShell:SA417GradeTP36 rftt &w)dpipe
- E.Ret.24,FileHe~dtoShVl(Wuf + R11itWeld) =letHeadSA-240G-=.kSt LPW.t Shell:SA-312 Grde1PfLSfAL. A rd opip Cylindrical and Obround Shells and Shelf Sections:
Cylindrical Shell
Reference:
A B C D E F Shell External Diameter D, in 16 Shell Internal Diameter D, In 15.25 Component Shol Material Spec. 6A,312 Part B Material Type I Grade TP316L Size I Thickness In Unliited Design Stress S. psi 16700 Design Stress S psi 16700 Welded Joint EffldenecyFactor E I Min. Required Shell Thlckness I.,-, In 0,078 ACtual Shell Thick. less Corrosion Ailtw.) 1-c In 0,375 is Actuat Corroded Thickness S Required Thickness? Yea. OK Opeanings In Cylindrical Shells:
Shell Opening Reference A B C D Main$hellMotoriat Size I Thickness In Design Stress S, psi 16700 Material Spec. 5A-312 Type IGrade TP31SL BranchShellMaterilI Size i Thickness Unltnitred Design Stress 16700
______ .1 1. .1 7.525 0.0732 0.375 0.0732
[net 0.375 IUG-45 Branch (Nozzle Neck) Thickness Check:
[U-4().Reure TiknssuCorrosion Allowance ton 0,0732 riq., bul nouleass hu Inlol,,
Iain Reale In 0.0732 JUG-45(b)(4),Min. Thick. o1 Sid. Wall Pipe - C.A. In
EC 88526 RO Attachment B - CUS12-09-118-PACKAGE 4 of 19 FLJFt EVI~.EI rr~
Clamp Number CUS12-09-f11 3.ROBINSON NUCLEAR ST.
Openings In Cylindricl Shelas(Continued):
Limits of Relnforcreenrt.
Umits of Relnrrent parallel to Shell Wall L, In 9 Urn. of Reint. normal to Shell outwards L, In 0.375 UW-16(c) and (d) Weld Dinension Check; Leg Length of Outer Branch Fillet Weld In 0.375 Are Weld Dimensions Acceptable? Yes -OK UG-37 Required Reinforcement Area:
Joint Efficiency Factor for Main Shell E Angle Between Branch and Main Shell P go Required Reinforcement Area A Inf 1f116 Area Available in Shell A, In 0.83 Anea Available in Branch (Outwards) A, In- 0.5659 Area Available in Outer Branch Fillet Wid A,, In' 0.1406 Total Available Reintefcement Area Inr 1.537 Is Total Available Reinforcement Area z Required Area? Yes -OK Appendix 1-7 Requirerents tor Large Openings:
UG-36(b) Maximum Opening Size In 7.625 Additional Large Opening Requlrements Apply? Yes 2J3or Required Reinforcement Area A' inW 0744 Within 1-7ýa)()) Limit:
Area Available In Shell A', inn 0.83 Area Available within Appendix 1-7(a) Limits In- 1.537 2/3 of Required Reinforcement within Appendix 1-7(a) Limils? Yes-OK UG-41 Loads to be Carried by The WeAY$:
Total Weld Load a U(
Do wreldsmeet the U End Cape:
End Cap Reference A B C E F SMonrealSpec. gA-240 Type CGreds 316L End Cap Mate[al Size / Thickness In Urdltad Design Stress S, pSI 15450 Shell Internal Dlarmeter(- 2 x Positive Contrallne Offset) in 15.25 End Cap Bore Diameter In &615 End Cap Radius Ratio 0438 Minimum Required End Cap Thickness in 0.902 Actual End Cap Thickness End Cap Thickness less Corrosion Allowa Is Actual Corroded Thickness ? Required as-CO Flat Heads:
Flat Head Reference A Imatedal Spec. 84240 316L Flat Head Material i,.^ r^d ass d In D I Minimum Required Flat Head Thickness I-u In Actual Flat Head Thickness Flat Head Thick. less Corrosion Allowance -uc In I Is Actual Corroded Thickness k Required Thickness? Yes:
EC 88526 RO Attachment B - CUS12-09-118-PACKAGE 5 of 19 uocument Numoer CUS12091U0-XL--1 ,Revision A iPege 3
=ngmeenng
,Engineering uotbNO. Customer 'L~u.JP
- U$12-09-118 Isite H.B. F a,
Bolt Area Caluleallons:
Sector Type (Primary / Secondary) Primary Projected Area of Void In Half-Joint Plane A nIr 134.07 type Seal Segment 1 Contact Pressure psi ProjectedArea on Half-Joint In,' 12.563 Sector Parting Force F, Ibf 35934.4531 Soil Thread and Form ot. UNG Minor Diameter Area Aa In- 0,2071 in Bolt Materlol Specification, Grade, (Class / Cond. I SA-193 BM Solt Size 1 Temper/ Special Requirements) and Ruling Section (clma 1)
Design Strew PSI 18250 Number of Bolts 14 Tofrque (Coeft. of Friction 0.12) ft,lbf (N.m) 37(50)
Minimum SoftDesign Stress S. psi 18250 Required Boll Minor Root Area A In- 1.969 Recommended Bolt Minor Area In' Total Sector Bolt Area A In- 2.899 IsActual Root Area Z Required I Recommeeded Root Area? Yes - OK oitted Lug Calcolationo (at Design Condiion);
Component Lug Material Spec. SA-240 Part A Material Type I Grade 316.
Kizo / Thickness in Unlrrnted Design Strens SA psi 15450 Component Shell Matedal Spec. SA.312 Part B Matedal Type I Grade TP316L Slze I Thnickness In Unflnrlted Design Sirens Sa psi 16700 Design Stress for Lug Thickness S psi 1i4e0 Welded Joint Efficiency Factor E, 0.55 Bot Pre-Stress to be Applied? o,, psi 20000 Sector Bolt Pre.Load F, Ibf 57988 Lug Length Lu In 30.828 Effective Lug Length L', In 21 Bolt Offset from Shell Mid Plane / 0I o. in 1.188 Recommended Lug Edge Offset (from Bolt CIL) In 1,94 Log Edge offSet from Bolt Centmllne ura in 0,825 Lugr Edge Of sealfrom Bolt Centrellne 10 Ins 2 Minimum Required Lug Thickness _H_. in 0.731 1 Minimum Recommended Lug Thickness in 0.8573 Lug Thickness IHL In I Is Actual Lug Thickness Z Required I Recommended Thickness? Yes -OK Lug AfachmonentWeld Calcolttlons (at Design Corditlon):
Lug is Attached to Shell (Calculation Reference for Smallest): A Length of Weld In 26 Fillet Weld I (Top) Leg Length In 0,375 BuStWeld 1 (top) Preparatlon Depth In 0.375 Fillet Weld 2 (Bottom) Leg Length In 0.375 Seal Groove Depth (if located In weld) In 0.4375 Neld Equiv. Sire. ndlnc Are the Lug Attachment Weld Stress within Allowable Limits? Yes - OK
EC 88526 RO Attachment B - CUS12-09-118-PACKAGE 6 of 19 Eng Dnumeeing NJ .mber CUSa120118-XLS-01 lReviseon A Page 4 1= IVIM ^1M I ~ nineern lob No.
ostomer PROGRESSENERGY
~~ag -.- eura. )Clamp Number CUgS12-0U-118 Ito H.B. RtOBINSONNUCULERiST.
Low Temperature Impact Test, Post Weld Heat Treatment and NDT Requirements:
Joint I Component Ref. pnP.ti. A
- 0. """*F (P.rw 5IP....k) C D E Joint / Component Description LwIw (lSel s1., {n. L4 E.WCUp P-WlI* *.l PJLgnNo lEýtCaauo*aLO h.IlOS..On.Pl aRe*wmc*and) F ,d0lhl loh0(&lu.
FRe, W.4 Fee DImenslon e2, In LgTle*
L *m Dimension 03. In nCprk Dimension e2, In 0,5 Bc h*Te ~ ed[k SWC Tftw eg 4E EmUP,,6 D~~mens~~on ada______ UoFu Bnoocn c Sell I Noazde O~stide *thdI DIameter Dl, in f
Weld ESze I Thickness, in zeqdoInTe3est, E
Dimesio A Impostrnlt
,dditional Testst Eepansiod.
Reotuired? iiN Uolnllred Untemhed ln~lau
- ice RIndtin PatalPnertonWldO Uolrndl Udrted nmlied _______
so No ______ ______
PP.0.01510 U O N No No o*c* ,,,59 ngtb. Foed Uni0e ha
.*1.6 1.O litiieg
.52 Umtten e ~ 0.5.l~
__Lg Wdld, S Toit .I1
,dtoam ReEttnolercy l pa onPRu Tetolns pasor uetured? oWade No No NOl ON o ReoaloWed 0.05 NoK Deg ret ate RTUTpEcifnitd?
nt or qid 5 si3 P~-N3-alfSaEMns 0 Nxe Noe 0.075 Esamtrle Cor 0.075 Non on ClAss4 61,".1,¢ Non 0.15n 2 t6g e te te te e leemtEnlo
-eNCam-VLameM:03Eais~n ls Cyllndalal Shells; Incemel Diameter A BC Additional Ihepast Tet D Reurd I0 S E Centr4line Length Copernal 15,25 No Ce ntrali ne Ott set(Ceotreilne to Cu ntreilee) ND No NoN Internul VoSume PostnaWeldteHos Tr a m n1eu in In N umber Ott rd rSp cfe ?N 43 Gross/ nternol Clamp Volume ON internall~isuabe oN Length.- inA f t FA64,9 4e.1.n 22 7004 Cylindrieal Compoenets; inN 403 YeYs E:NCLOSED External 7004 Yse PIPING COMPONENTS Diameter VOLUME; A B C 0 S er ic Res ridion on P a ta1 in Centre[lne Leegth Enclosed Volume a io8eds " 7.&A0 Luglaioa Thickness KO
.nt Number Ott to In O3KO Off Require Degre ofrs 10 Clamp Vast Volume T Ex m n lo e 1F-.,141,51,r-52 e ComponentEMS00 (Grass inte inG N Total Enrdoned V olume ClaInpi sl Exaissio Clas 6e8.2 o eN neN Volume.o n MWs 7od Jo int Ef i ie c Fa t r0 Total oseeadCompoeent lea ina I 000.2 II.I Volume) 5511.
7100 1 - I.
In' 7100 Enclosure Clamp Mass:
Component Moes M ess 0n Bolts0.015 Ib 232,2 Namber sOfpl)f t
EC 88526 RO Attachment B - CUS12-09-118-PACKAGE 7 of 19 I* Iu MI I I;11ý,Tnb!_ CUS129118-YlXLS-01 Revision A Page 5 Customer PROGRESS ENERGY Iclamp Number CUS12-J9-118 Site H.S. ROBINSON NUCLEAR ST.
Enclosure Clamp Mass (Continued):
End Caps: A B CE F End Cap IShell External Diameter In IB End Cap Bore in 6.675 End Cap Thickness In I Number (of Pairs) Off 2 Component Mass lb 94.8 Flat Heads., A B C Flat Head I Shell xtmeralDiameter In Is Flat Head Thickness In 1 NumberOff 1 Component Mass lb 57.4 Total Mass of Clampas Calculated lb 453 Percentage Mass Allowance (uncalculated components, welds, etc.) 6.0%
Estimated Total Mass of Clamp as Supplied ib 410 Estimated Total Mass of Clamp as Installed lb 480 END OF REPORT