ML14073A061

Flaw Evaluation of SSW Discharge Piping Leaking Elbow, Calculation No. 1400287.302, Rev. 0

ML14073A061
Person / Time
Site:	Pilgrim
Issue date:	03/03/2014
From:	Tucker J A Structural Integrity Associates
To:	Office of Nuclear Reactor Regulation
References
1400287.302, Rev 0
Download: ML14073A061 (26)

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ATTACHMENT 4TO ENTERGY LETTER 2.14.023PILGRIM RELIEF REQUEST PRR-25Calculation Cover Page EC # 49514Flaw Evaluation of SSW Discharge Piping Leaking ElbowStructural Integrity Associates Calculation No. 1400287.302, Rev. 0(20 Pages)

ATTACHMENT 9.2 ENGINEERING CALCULATION COVER PAGESheet 1 of 2[] ANO-1 13 ANO-2 El GGNS [1 IP-2 [I IP-3 [E PLPf- JAF Z PNPS [1 RBS El VY [I W3El NP-GGNS-3

[I NP-RBS-3CALCULATION

()EC # 49514 (2) Page 1 of 20)COVER PAGE(3) Design Basis Calc. E-- YES NO (4) [Z CALCULATION Markup15) Calculation No: M1398 (5) Revision:

0(7) Title: Flaw Evaluation of SSW Discharge Piping Leaking Elbow ,1) Editorial DYES Z NO(9) System(s):

29(10) Review Org (Department):

(ii) Safety Class: (12) Component/Equipment/Structure Type/Number:

Z Safety / Quality Related PIPE / JF29-8-4[] Augmented Quality Programi-- Non-Safety Related(13) Document Type: CALC(14) Keywords (Description/Topical Codes):JF29-8-4, spool, SIA, Structural Integrity Associates, flaw, leak, rubber lining,1400287.302, 1400287-fREVIEWS(15) Name/Signature/Date (16) Name/Signature/Date (17) Name/Signature/Date Structural Integrity Assoc. John A. Tucker 3. Iq See IASResponsible Engineer

-- Design Verifier Supervisor/Approval Z ReviewerEi- Comments Attached E- Comments AttachedEN-DC-126 R005 ATAHMENT 19of3CALCULATION REFERENCE SHEETSheet 1 of 3CALCULATION CALCULATION NO: M1398REFERENCE SHEET REVISION:

0I. EC Markups Incorporated (N/A to NP calculations) 1.N/A2.3.4.5.11. Relationships:

Sht Rev Input Output Impact TrackingDoc Doc Y/N No.1. Specification M300 2-12 109 x 0 N2. M100-7250

-5 x 0 N3. __ 0 04. _ _0 05. 0 0 __III. CROSS

REFERENCES:

1. ASME B&PV Code,Section XI, App C, 2001 Edition w/ Add through 20032. ASME B31.1, Power Piping, 1967 Edition3. ASME Code Case N-513-34. Flow of Fluids Through valves, Fittings and Pipe, Crane Co,., Technical Paper No.410IV. SOFTWARE USED:Title: N/A Version/Release:

-- DisklCD No. --V. DISK/CDS INCLUDED:

Title: N/A Version/Release Disk/CD No.VI. OTHER CHANGES:EN-DC-126 R005 Structural Integrity Associates, Inc File No.: 1400287.302 Project No.: 1400287CALCULATION PACKAGE Quality Program:

Z Nuclear E] Commercial PROJECT NAME:Pilgrim Leaking Elbow Evaluation SupportCONTRACT NO.:10404807, Change Order No. 001CLIENT: PLANT:Entergy Nuclear Pilgrim Nuclear Power StationCALCULATION TITLE:Flaw Evaluation of SSW Discharge Piping Leaking ElbowDocument Affected Project Manager Preparer(s)

&Revision Pages Revision Description Approval Checker(s)

Signature

& Date Signatures

& Date0 1 -15 Initial IssueA-i -A-3Eric Houston Brad DawsonEJH 3/3/14 BPD 3/3/14Raoul GnagneLRG 3/3/14Robert McGillROM 3/3/14Page 1 of 15F0306-01 R1 j Structural Integrity Associates, Inc0Table of Contents1.0 IN TRO D U CTIO N ....................................................................................................

32.0 TECHNICAL APPROACH

.....................................................................................

33.0 DESIGN INPUTS / ASSUMPTIONS

......................................................................

44.0 C A LC U LA TIO N S .....................................................................................................

54.1 A pplied Loads ..............................................................................................

54.1.1 H o op S tress ........................................................................................................

54.1.2 A xial Stresses

................................................................................................

64.2 Stress Intensity Factor Calculations

.............................................................

74.3 Critical Fracture Toughness Determination

..................................................

85.0 R E SU L T S ......................................................................................................................

86.0 C O N C LU SIO N S ......................................................................................................

87.0 R E FERE N C E S ......................................................................................................

10APPENDIX A DRAFT CODE CASE N-513-4 PROCEDURES FOR ELBOW FLAWEV A LU A TIO N .......................................................................................

A -1List of TablesTable 1: Jic Values for A106 Gr. B Carbon Steel from NRC's Pipe Fracture Database

[10] 11Table 2: Axial and Circumferential Structural Factors [4] ................................................

12Table 3: Load Combinations for Circumferential Flaw Analyses

.....................................

12Table 4: Allowable Through-Wall Flaw Lengths (based on t = 0.312") ............................

12List of FiguresFigure 1. Pinhole Leak in Service Water Piping, 18-inch Elbow .......................................

13Figure 2. Sketch of Leak Location in Service Water Piping, 18-inch Elbow ...................

14Figure 3. UT Data (3/4 Inch Grid) for Service Water Piping, 18-inch Elbow ...................

15File No.: 1400287.302 Page 2 of 15Revision:

0F0306-OIRI jStructural Integrity Associates, IncY

1.0 INTRODUCTION

A weeping flaw, shown on Figure 1, was discovered near the extrados of a 90 degree elbow in the SaltService Water (SSW) piping at Pilgrim Nuclear Power Station (Pilgrim).

The leak is located on theJF29-8-4 pipe spool of the SSW system [1]. Ultrasonic testing has been conducted in order tocharacterize the flaw [1]. Allowable through-wall flaw lengths are determined using methods consistent with an upcoming revision of Code Case N-513-3 [2] as described below.2.0 TECHNICAL APPROACHThe flaw evaluation herein is based on the criteria prescribed in an upcoming revision of ASME CodeCase N-513-3.

This Code Case allows for the temporary acceptance of through-wall flaws in moderateenergy Class 2 or Class 3 piping. N-513-3 has been conditionally accepted by the NRC with thestipulation that, "The repair or replacement activity temporarily deferred under the provisions of thisCode Case shall be performed during the next scheduled outage,"

and is published in the latest revisionof Regulatory Guide 1.147 [3]. N-513-3 allows non-planar, through-wall flaws to be characterized andevaluated as planar (i.e., crack-like),

through-wall flaws in the axial and circumferential directions.

The evaluation criteria provided in N-513-3 are only for straight pipe since the technical approach relieson ASME Section XI, Appendix C [4] methods.

A new revision of the Code Case (N-513-4) includesrules for the evaluation of piping components such as elbows, branch tees and reducers.

Flaws in thesecomponents may be evaluated as if in straight pipe provided the stresses used in the evaluation areadjusted to account for geometric differences.

For elbows, hoop stress is adjusted by considering flawlocation and primary stress due to elbow ovalization from axial loads. For axial stresses, the stressscaling follows the same approach given in ASME Section III, ND-3600 [5] design by rule using stressindices and stress intensification factors for the adjustment.

Details are provided in N-513-4 fordetermining these adjusted stresses.

N-513-4 has not been approved by the ASME or reviewed by the NRC; however, it is recognized inASME committee that the technical approach is very conservative.

Simple treatment of pipingcomponent flaw evaluation using hand calculations was an important objective in the development of theapproach recognizing the trade-off being conservative results.

N-513-4 allows for more sophisticated analysis by the user.As stated above, Code Case N-513-3 evaluation criteria rely on the methods given in ASME Section XI,Appendix C. Linear Elastic Fracture Mechanics (LEFM) criteria are conservatively employed asdescribed in Article C-7000. Since a through-wall flaw is being evaluated, through-wall shape factorsFm, Fb and F are used which are given in Appendix I of the Code Case. Allowable flaw lengths aredetermined through iteration comparing calculated stress intensity factors to a critical fracture toughness defined in C-7200 of Section XI, Appendix C.This evaluation utilizes finite element methods (FEM) to calculate the primary membrane stress in thehoop direction due to ovalization from axial loads. Section 3.3 of the Code Case's new revision statesFile No.: 1400287.302 Page 3 of 15Revision:

0F0306-01RI jstructural Integrity Associates, IncOthat "Alternative methods may be used to calculate the stresses used in evaluation,"

which justifies theuse of FEM techniques.

Details of the Code Case N-513-4 evaluation procedure for elbows are given in Appendix A.3.0 DESIGN INPUTS / ASSUMPTIONS The SSW Code of Construction is ANSI B31.1 1967 Edition [6].Based on information provided by Entergy, the 18 inch elbow is located on SSW spool JF29-8-4

[1].The 90 degree elbow located on JF29-8-4 is a schedule 20, long radius elbow [7]. The design pressureand temperature are 10 psig and 100°F, respectively

[8].The elbow material is ASTM A-234 WPB [7] carbon steel. For the analysis, A106 Gr. B carbon steel isjudged to have equivalent material properties.

The nominal composition of the two materials isessentially the same and the minimum yield and tensile strengths are the same for both materials.

Inaddition, the longitudinal and transverse elongations are similar between these materials.

The applied moment loadings are obtained from the ME-101 output listings in Reference

[9]. Based oninformation provided by Entergy, the location of interest is node 22. The moments for each load caseare provided in three dimensions (MA, MB, and MC), which are combined by square-root-of-the-sum-of-the-squares (SRSS). The resulting SRSS moments at each location along the elbow (beginning, middle, and end) are compared for each loading, and the bounding moment is used in this analysis.

Determination of the fracture toughness, Jic, used in the evaluation is based on Section XI, Appendix C,C-8320 [4], which specifies that 'reasonable lower bound fracture toughness data' may be used todetermine the allowable stress intensity factor, Kic. The NRC's Pipe Fracture Encyclopedia

[10]contains numerous CVN test results for A106 Gr. B carbon steel at low temperature, which arereproduced in Table 1. The minimum reported value of 293 in-lb/in2 is used in the analysis for bothaxial and circumferential flaws.Finite element methods are used to determine the primary membrane stress in the hoop direction due toovalization from axial loads in Reference

[11]. A unit moment of 10,000 in-lbs is applied to the FEMand linearized stresses are extracted at paths in the axial direction from the flaw. A stress of 100 psiconservatively bounds the tensile hoop stress reported in Reference

[11]. This bounding stress isfactored based on the ratio of the applied moment for the applicable service level to the unit moment of10,000 in-lbs. The factored stress is used as described in Section 4.1.1 below.The following design inputs are used in this calculation:

1. Long radius 900 elbow OD = 18 inches [7]2. Nominal elbow thickness

= 0.312 inch (based on Schedule 20 piping [7])3. Design pressure

= 10 psig [8]File No.: 1400287.302 Page 4 of 15Revision:

0F0306-01 RI jstructural Integrity Associates, Inc!4. Design temperature

= 100'F [8]5. Young's modulus = 27,900 ksi [6, Table C-I]6. Allowable stress = 15 ksi [6, Table A-2]7. Enveloped SRSS Deadweight Moment = 43,973 in-lbs [9]8. Enveloped SRSS OBE Moment = 38,820 in-lbs [9]9. Enveloped SRSS SSE Moment = 72,789 in-lbs [9]10. Enveloped SRSS Thermal Moment = 22,047 in-lbs [9]11. Stress intensification factor, i = 3.98 [6]12. Jhc for axial flaws = 293 in-lb/in2 [4, 10]13. Jic for circumferential flaws = 293 in-lb/in2 [4, 10]14. Bounding primary membrane stress in the hoop direction due to unit moment load = 100 psi [11]Note that the wall thickness surrounding the flaw is greater than the elbow nominal thickness

[I].Therefore, the use of the 0.312 inch surrounding wall thickness is considered conservative.

The following assumptions are used in this calculation:

1. Poisson's ratio is assumed to be 0.3.2. Due to the flaw remoteness from a weld, residual stress effects are assumed negligible.

3. A corrosion allowance is not considered (the ongoing inspection requirements in Code CaseN-513-3 address the possibility of flaw growth during the temporary acceptance period).4.0 CALCULATIONS 4.1 Applied Loads4.1.1 Hoop StressFor the allowable axial flaw length, the hoop stress, Gh, due to internal pressure and elbow ovalization from the axial moments may be determined from Equation 9 of N-513-4 (see Appendix A):=( p0 2Rbend + R.Sin6 1 ( 1.95 )~ RMb (1)=( Pt L2(Rb,,d

+ Ro sin 0) h 92/3 )1where:p = internal

pressure, psigDo = outside diameter, int = wall thickness, inRbend = elbow bend radius (27 inches)Ro = outside radius, in0 = circumferential angle from elbow flank (see Figure 7 in Appendix A)File No.: 1400287.302 Page 5 of 15Revision:

0F0306-01 R1 tStructural Integrity Associates, Inc!h = flexibility characteristic

= t*Rbend/(R mean)2 [6]Rmean = elbow mean radius, inMb = primary bending moment, in-lbsI = moment of inertia, in4.Note that the first term of Equation I accounts for the hoop stress due to internal pressure and includes ascaling factor to account for the circumferential location of the flaw (assuming uniform thickness, pressure based hoop stress is a maximum at the elbow intrados, while a minimum at the elbow extrados).

At the flank, the pressure based hoop stress is equal to that of straight pipe. For the analysis herein, it isconservative to set 0 = 0 since the flaw is between the flank and extrados as shown on Figure 2.The second term of Equation 1 accounts for the hoop stress resulting from the axial moments acting toovalize the elbow. This term is replaced with the scaled primary membrane stress in the hoop direction as discussed in the previous section.Finally, N-513-4 limits the use of Equation 1 for h> 0.1. For this elbow, h z 0.11.4.1.2 Axial StressesFor the allowable circumferential flaw length, the axial stress due to pressure, deadweight,

seismic, andthermal loading is presented below. For axial membrane stress due to pressure, am, Equation 10 of N-513-4 is used:B,2tD (2)where Bi is an ASME Section III primary stress index for internal pressure.

N-513-4 sets this value to0.5.For axial bending stress, ab, due to deadweight and seismic moments, Equation 11 ofN-513-4 may beused:o-b = B2 (-R --b (3)where B2 is an ASME Section III primary stress index for moment loading.

From Figure ND-3673.2(b)-I of Reference

[5], B2 = 1.30/h2/3.For this elbow, B2 = 5.74.For axial bending stress due to thermal moments, (e, Equation 12 of N-513-4 may be used:O-e = i(Ro-eJ (4)File No.: 1400287.302 Page 6 of 15Revision:

0F0306-01 RI Structural Integrity Associates, IncOwhere i is the stress intensification factor. From [6, Appendix D], i = 3.98.4.2 Stress Intensity Factor Calculations For LEFM analysis, the stress intensity factor, Ki, for an axial flaw is taken from Article C-7000 [4] asprescribed by N-513-3 and is given below:KI = Kim + Kir (5)where:Kim = (SFm)Fah(7ta/Q) 0'5SFm = structural factor for membrane stress (see Table 2)F = through-wall shape factor for an axial flaw under hoop stress (given in Appendix I ofN-513-3)o-h = hoop stress, ksia = flaw depth (half flaw length for through-wall flaw), inQ = flaw shape parameter (unity per Appendix I of N-513-3)Kir = Ki from residual stresses at flaw location (assumed negligible).

Only the hoop stress influences the allowable axial flaw length which is a function of pressure andprimary bending stress.For LEFM analysis, the stress intensity factor, Ki, for a circumferential flaw is taken from Article C-7000 [4] as prescribed by N-513-3 and is given below:K1 = Kim + Klb + Kir (6)where:Kim = (SFm)Fmam(7ra) 0"5Fm = through-wall shape factor for a circumferential flaw under membrane stress (givenin Appendix I ofN-513-3) am = membrane stress, ksiKib = [(SFb)M + ae]Fb(7ta) 05SFb = structural factor for bending stress (see Table 2)ab = bending stress, ksiGe = thermal stress, ksiFb = through-wall shape factor for a circumferential flaw under bending stress (given inAppendix I of N-513-3).

Note that the through-wall flaw shape factors are a function of flaw length.Table 3 shows the specific load combinations considered herein for the allowable circumferential flawcalculations.

Since the load combination for Service Level C and D are equivalent, the more limitingflaw length associated with the Service Level C structural factors are presented.

File No.: 1400287.302 Page 7 of 15Revision:

0F0306-01 RI CStructural Integrity Associates, Inc!4.3 Critical Fracture Toughness Determination For LEFM analysis, the static fracture toughness for crack initiation under plane strain conditions, Kic, istaken from Article C-7000 [4] as prescribed by N-513-3 and is given below:K IC = RE' (7)V 1000where:J= material toughness, in-lb/in2E'= E/(1-v2)E = Young's modulus, ksiv = Poisson's ratio.Based on the design input listed previously, Kic is 94.7 ksi-in°5 for both axial and circumferential flaws.The allowable flaw lengths are determined iteratively by increasing flaw length until the stress intensity factor is equal to the static fracture toughness.

5.0 RESULTSTable 4 shows the allowable through-wall flaw lengths resulting from the analysis based on asurrounding nominal wall thickness.

The most limiting flaw length is 8 inches in the circumferential direction.

The UT results for the leaking elbow are shown in Figure 3 [1]. The leak is easily bounded inthe axial and circumferential directions by 8 inches. Thus, the acceptance criteria of Code Case N-513-4are met.Finally, Paragraph 3.2(d) requires that N-513-3 Equation 9 be satisfied (i.e., the remaining ligamentaverage thickness over the degraded area bounded by the limiting flaw size will resist pressure blowout).

The average remaining wall thickness requirement covering the degraded area from Equation 9 is 0.07inch (using a Chdj = 8 inches).

From the inspection data given in Figure 3, only the grids nearest to theleak are less than this value. Thus, this Code Case requirement is met.

6.0 CONCLUSION

S The flaw evaluation of the weeping flaw in a 18-inch elbow of the SSW piping at Pilgrim has beenevaluated using the methods of a pending revision to Code Case N-513-3 (designated N-513-4) currently in the ASME approval process (N-513-3 does not provide evaluation criteria for flaws in elbows, whileN-513-4 does). N-513-4 has not been approved by the ASME or reviewed by the NRC; however, it isrecognized in ASME committee that the technical approach is very conservative.

Table 4 shows theaxial and circumferential allowable flaw lengths based on a surrounding nominal wall thickness of 0.312inch. The most limiting flaw size is 8 inches in the circumferential direction.

The leak is easily boundedFile No.: 1400287.302 Page 8 of 15Revision:

0F0306-01 RI r Structural Integrity Associates, Inc!in the axial and circumferential directions by 8 inches (as shown in Figure 3). Thus, the acceptance criteria of Code Case N-513-4 are met.File No.: 1400287.302 Revision:

0Page 9 of 15F0306-OIRI VStructural Integrity Associates, Inc!

7.0 REFERENCES

1. Pilgrim NDE Inspection Report, File Name "JF29 4 8 O.dmsdr,"

February 25, 2014, SI FileNumber 1400287.201.

2. ASME Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws inModerate Energy Class 2 or 3 Piping Section XI, Division 1," Cases of ASME Boiler andPressure Vessel Code, January 26, 2009.3. Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI,Division 1," Revision 16, Nuclear Regulatory Commission,

October, 2010.4. ASME Boiler and Pressure Vessel Code,Section XI, Appendix C, 2001 Edition with addendathrough 2003.5. ASME Boiler and Pressure Vessel Code,Section III, Subsection ND, 2004 Edition.6. ANSI B3 1.1, Power Piping, 1967 Edition.7. Entergy Drawing Number M100-7250, Revision E5, "Service Water System E209B SSWBackwash Drain Piping,"

SI File Number 1400287.201.

8. Pilgrim Nuclear Power Station Specification Number M300, System 29 Service Water, SI FileNumber 1400287.201.

9. Pilgrim Nuclear Power Station Pipe Stress Calculation 638, SI File Number 1400057.201.

10. Pipe Fracture Encyclopedia, US Nuclear Regulatory Commission, Volume 1, 1997.11. SI Calculation Number 1400287.301, Revision 0, "Pilgrim Salt Service Water Discharge PipingElbow (JF29-8-4 Spool) Wall Thinning Stress Analysis."

File No.: 1400287.302 Page 10 of 15Revision:

0F0306-01 R1 V Structural Integrity Associates, Inc.mTable 1: Jic Values for A106 Gr. B Carbon Steel from NRC's Pipe Fracture Database

[10]A106 GradeB. '.B.....__

____.__.Database Reference Temperature

(°C) Temperature (OF) JIC (kJ/m') JIC (Ibrin/in

2) KIC (ksi-ins

)2 24 75 97 552 1332 24 75 336 1919 24916 25 77 81 464 12216 25 77 418 2386 27716 25 77 270 1542 22316 25 77 193 1104 18922 24 75 224 1278 20322 20 68 112 641 14422 20 68 117 668 14722 23 73 214 1223 19922 20 68 167 954 17522 20 68 223 1271 20222 20 68 108 617 14123 52 126 116 663 14623 23 73 103 590 13823 23 73 105 600 13923 23 73 93 528 13124 23 73 76 431 11824 23 73 82 469 12324 57 135 511 293 9725 23 73 77 437 11925 23 73 70 400 11425 57 135 62 356 10790 20 68 235 1342 20890 20 68 219 1251 20190 20 68 255 1456 21790 20 68 281 1605 22890 20 68 281 1605 22890 20 68 335 1913 24890 20 68 421 2404 27990 20 68 385 2198 26690 20 68 175 999 18090 20 68 172 982 17890 20 68 178 1016 18190 20 68 214 1222 19990 20 68 275 1570 22590 20 68 133 759 15790 20 68 140 799 16190 20 68 174 994 17990 20 68 111 634 14390 20 68 190 1085 18790 20 68 71 405 11490 20 68 110 628 14290 20 68 104 594 13890 20 68 104 594 13890 20 68 97 554, 13490 20 68 89 508 12890 20 68 88 502 12790 20 68 267 1525 2224-File No.: 1400287.302 Revision:

0Page 11 of 15F0306-OIRI CStructural Integrity Associates, Inc,Table 2: Axial and Circumferential Structural Factors [4]Service Level Membrane Stress, SFm Bending Stress, SFbA 2.7 2.3B 2.4 2.0C 1.8 1.6D 1.3 1.4Table 3: Load Combinations for Circumferential Flaw AnalysesLoad Combination Service LevelP+DW+TH AP+DW+OBE+TH BP+DW+SSE+TH C/DTable 4: Allowable Through-Wall Flaw Lengths (based on t = 0.312")Service Allowable Axial Flaw Allowable Circumferential Level Length (in) Flaw Length (in)A 16.0 13.2B 16.0 8.8C/D 16.0 8.0File No.: 1400287.302 Revision:

0Page 12 of 15F0306-OIRI CStructural Integrity Associates, Inc."Figure 1. Pinhole Leak in Service Water Piping, 18-inch ElbowFile No.: 1400287.302 Revision:

0Page 13 of 15F0306-01R1 Structural Integrity Associates, Inc!-Af '- ýýY"Toe'4,0C~7~o~4 N4.Figure 2. Sketch of Leak Location in Service Water Piping, 18-inch ElbowFile No.: 1400287.302 Revision:

0Page 14 of 15F0306-01Rl Itj-SIructural Integrity Associates, Inc!LOCATION AJ: AK: AL: AM: AN: AO: AP: AQ: AR: AS: AT: AU: AV:1 0.396 0.397 0.397 0.380 0.369 0.352 0.348 0.344 0.342 0.335 0.328 0.315 0,3282 0.398 0.396 0.393 0.371 0,334 0.353 0.347 0.343 0.345 0.341 0.337 0,311 0.3253 0.393 0.390 0.393 0.369 0.309 0.361 0.347 0.338 0.343 0.335 0.327 0.308 0.3264 0.387 0.389 0.389 0.383 0.150 0.051 0.109 0.336 0.299 0.336 0.327 0.308 0.3185 0.386 0.390 0.394 0.192 0.087 0.064 0.083 0.334 0.313 0.328 0.328 0.315 0.3206 0.389 0.388 0.392 0.108 0.352 0.362 0.332 0.333 0.334 0.298 0.292 0.317 0.3237 0.390 0.390 0.393 0.390 0.380 0.343 0.342 0.339 0.341 0.296 0.337 0.321 0.3238 0.385 0.388 0.392 0.388 0.386 0.366 0.360 0.356 0.349 0.349 0.348 0.327 0.326Figure 3. UT Data (3/4 Inch Grid) for Service Water Piping, 18-inch ElbowFile No.: 1400287.302 Revision:

0Page 15 of 15F0306-OIRI Appendix ADRAFT CODE CASE N-513-4 PROCEDURES FOR ELBOW FLAW EVALUATION File No.: 1400287.302 Revision:

0Page A- 1 of A-3F0306-OI RI 3.3 Through-wall Flaws in Elbows and Bent PipeThrough-wall flaws in elbows and bent pipe may beevaluated using the straight pipe procedures given in 3 1or 3.2(d) provided the stresses used in the evaluation areadjusted as described below to accouit for the geometrydifferences.

Alternate methods may be used to calculate the stresses used in evaluation.

The hoop stress, o,. for elbow and bent pipeevaluation shall be:-pD.'1[ 2R,_- + Rosin ÷1, owhereRb,, = elbow or bent pipe bend radius0 = circumferential angle defined in Fig-re 7h = flexibility characteristic Mb = resultant primary bending momentI = moment of inertia based on evaluation walltiickness,.

Equation 9 is only applicable for elbows and bentpipe where h > 0 1.The axial membrane pressure stress, o,,_ for elbowand bent pipe evaluation shall be:c B -fpB4ID° (10)( 2twhere B, is a primaty stress index as defined in ASMESection III for the piping item. B, shall be equal to 0.5for elbows and bent pipe.The axial bending stress, aob, for elbow and bentpipe evaluation shall be:where B, is a pimnary stress index as defined in ASMESection III for tile piping item.The thernal expansion stress, or,. for elbow andbent pipe evaluation shall be:wherei = stress intensification factor as defined in theCode of Record for the piping itemMl = resultant thermal expansion momentFile No.: 1400287.302 Page A-2 of A-3Revision:

0F0306-01 RI Figure 7 from N-513-4:FIG. 7 CIRCUMFERENTIAL ANGLE DEFINEDextradosFile No.: 1400287.302 Revision:

0Page A-3 of A-3F0306-01 RI ATTACHMENT 5TO ENTERGY LETTER 2.14.023PILGRIM RELIEF REQUEST PRR-25SSW Spool JF 29-8-4 NDE Data Sheet(4 pages)

UT Erosion/Corrosion Examination EntergySiteUnit PNPS / 1Summary No. SSW Pipe SpoolWOrKScopoe BOPProcedure:

Procedure Rev.:Work Order No.:CEP-NDE-0606 004.375247-04 Outage No.. NIAReport No.. BOP-UT-14-001 Page 1 ofCooke ASME Sec-XI, 2001-2003 Ada. CatJltem C-HJC7.10 Location "B" Aux BayD'dwn No M100-7250

==

Description:==

18" ElbowSst[in ID Service Water System (29)Component ID Pipe Spool JF29-84 Size/Lengtrr 18" 1 6"-12" Thickness/Diameter Sch..20118" L1i"iati0ol NA Component File No.. NA Start Time 9:45 Finish Time 14:10Calibration Information Partitioning Information Component Information CaLI=aton T

(In) Caorwiabon Times I initiais Component Bg"IVCol/Row EndinQCokRow component Geometry:

Pipe ElbowmeL..W M. UPST Ext NIA NIA Outside Diameter:

18" Grid Size 314".100 0.100 S , Main UPST. NIA NWA Thickness:

0.457 Min. Thickness:

0.0510.200 Verify 12:00 RDA Man1A8B0.200 0.211 Ven-y N2A RDA Main 1 A 881 Nominal Thickness 0.312 Tmin. 0.2700.300 0.299 Verity NIA NIA Main DNST. NIA WA0.400 0.400 Verity NWA N/A M. DNST EA. NIA MIA Min Thickness Location.

4 AO0.500 0.500 Final: 14:15 RDA Branch N/A N/A Max. Thickness Location 8 ZBranch Ext. NIA NIA Surface Condition.

SMOOTHInbtrument:

Transducer:

ReferencelSimulator Block: Temp. Tool:MamltaCtufer GE Manufacturer:

KBA Serial No.: 94-5570 Manufacturer Elcometer Mocei USM-GO Serial No. 01550W Type: 0..1-0.5" Serial No.. PNPTEM-288 Senai Nc USMGO12915119 Size 0.375" Freq. 5.0 MH RfSimulator Blok Temp.: 70 FCouplant:

G ai 66 Mo del: 113-50-001 0Type .Ultrage lRange 0.500 # of Elements:

2 Material/Component Temp.: 73 °F Batch No.. 05125mne-mets, ODStjuctions UT performed do to a through wall hole. See CR-PNP-2014-00815.

This is not a Code required exam.ReitS Accept Reject 7, Eval 41Avery,..

Ric ar D. (Rck A 2/6101 ,,,,,,,,,,,,.

,,ExaminerN/

Level NIA Signatur4' Date Site Review l ___ Signaturel,

..../ DateOther Level NIA Signature Date ANII Review Signature DateN/A .WA Lii/eq~ySupplemental ReportReport No.: BOP-UT-14-001 Page: 2 of 4Summary No. SSW Pipe SpoolFile Nam. SpkIl JF29-8-4Descrption 18" ElbowCreation 0 ate 2/25M2014 Prooe See UT ReportCai Comment See reportInspctor" R AVERYInstrument Type DMS GoVelCompany EntergyInstrument S.N : USMGO12015119 locity(in/us) 0.2360UnitsINCHNuonrer or Readings 468N~inuttt Uf OUSIrutS 0Nurner of Empties es; 0Number of Attachments:

0Range : 0,406 Points Below MinAlarm

0Mean 0 368 Standard Deviation

0.047Mnnin.m Vailue 0 051Minimum Value Loc. .4:AO.1Maximum Value 0457Maximum Value Loc. 6Z.1LOCATIO4 A B" C: D: E: F: G: H: 1: J: K L M: N:1 0.344 0.348 0.365 0.372 0.374 0.375 0.377 0.373 0.372 0.364 0.361 0.364 0.358 0.3592 0.346 0.356 0,365 0.370 0.372 0.376 0.373 0.377 0.375 0.370 0.367 0.367 0.364 0 3653 0.348 0.358 0,363 0.366 0.373 0.376 0.375 0.377 0.376 0.374 0.369 0.367 0.366 0,3664 0.354 0352 0.365 0369 0,375 0.379 0.381 0.380 0.380 0.380 0.372 0.367 0,366 0.3685 0,349 0.354 0.366 0,368 0.375 0.378 0.378 0.382 0.382 0.380 0.377 0.372 0.369 0.3726 0.353 0-357 0364 0.367 0.378 0.378 0.381 0.382 0.366 0.381 0.375 0.372 0.373 0.3727 0.354 0.357 0365 0.374 0.375 0.380 0.381 0.385 0.381 0.379 0.379 0.371 0.372 0.3718 0.360 0 359 0.363 0.374 0.373 0.363 0.369 0.382 0.380 0.378 0.377 0.377 0.374 0.372TOP CiL .o! PIPEDirection of Flow t-71 Supplemental ReportIlderoyReport No.: BOP-UT-14-001 Page. 3 of 4SuImrmary No SSW Pipe Spool1-2-0:~0.372! P:0.3710.378Q:R:S:U:V: L W:Y:Z': 1AA: IAB: IAC: IAD:1 r I r r r r 4 40: R I AA I AB I AC I AD ALAE:0.3800.3850.3860.3980.400 10,373 10.413 10.419 10.425 0.427 10.421 10.417 10.415 10.417 10.4130.4040.386 0.3980-404,0.3920.3980.401 I 0.409 I 0.411 I 0.419 I 0.431 0.428 I 0.428 I 0.421 I 0.422 I 0.417 0.4140.40510.3741038210383 096 0400 I 0.401 0.409 10.411 0.4231 0.427 0.428910.42830.421 10.422 0.419 0.415I040

__ __ 1 ______.1__

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__ ___7 0.373 0.380 0.383 0.394 0400 0.405 0.410 0.415 0.420 0.429 0.437 0.428 0.422 0.417 0.418 0.410 0.40440.374 0.382 0.383 0.396 0.400 10.405 0.409 0.413 0.423 0.427 0.429 0.423 0.421 0.418 0,419 0.415 0.4o35 0.378 0.384 0.385 0.400 0.403 0.407 0.412 0.416 0.426 0.428 0.429 0.431 0.427 0.423 0.423 0.421 0.4096 0.380 0.389 0.393 0.404 0.407 0.414 0.421 0.419 0.429 0.437 0.433 0.430 0.428 0.425 0.422 0.426 0.4087 0.380 0.387 0.390 0.400 0.406 0.412 0.416 0.419 0.430 0.433 0.430 0.4_30 0.427 0.425 0.423 0.426 0.414_0_3830-389 0.395 0.401 0.407 0.412 0.418 0.422 0.426 0.428 0.427 0.457 0.421 0.419 0.422 0.421 0.406F AG: AH: AI: AJ: AK: AL: AM: AN: AO: AP: AQ: AR- AS: AT: AU: AV:1 0.400 0.395 0.391 0.396 0.396 0.397 0.397 0.380 0.369 0.352 0.348 0.344 0.342 0.335 0.328 0.315 0.3282 0.393 0394 0.389 0.397 0.398 0.396 0.393 0.371 0.334 0.353 0.347 0.343 0.345 0.341 0.337 0.311 0.3253 0.394 0.390 0.388 0.389 0.393 0.390 0.393 0.369 0.309 0.361 0.347 0,338 0.343 0.335 0,327 0.308 0.3264 0.391 0.385 0.383 0.383 0.387 0.389 0.389 0.383 QAI 0.336 0.299 0.336 0.327 0.308 0.3180378 0.388 0.380 0.380 0.386 0.390 0.394 Ri ------ 0.-334 0.313 0.328 0.328 0.315 0.32061 0390 0.380 0.382 0.383 0.389 0.388 0.392 0.352 0.362 0.332 0.333 0.334 0.317 0.3237 0.398 0.385 0.385 0.380 0.390 0.390 0.393 0.390 0.380 0.343 0.342 0.339 0.341 0.337 0.321 0.3238 1-0.401 0.392 0.388 0.381 0.385 0.388 0.392 0.388 0.386 0.366 0.360 0.356 0.349 0.349 0.348 0.327 0.326AW AX:I AY¥:IAZ:-7'2S3-TiB A:: BB: BC: BD: BE: IBF: BG: BH: Bh:0o336I0.345 ' 0.346 I 0.3400.339 0.339 0.335 '0.338 0.333 1 0.332 0.338 0.341 0.33804 0 03400.3370.341 I0.344 0 .345~0.341 0.337 0.332 0.328 0.331 10.330 0.336 0.339 0.3430.341 0.344 03450.3320,3360.343 0.346 0.339 0.337 0.327 0.335 0.334 1 0.336 0.336 0.339 0.344T .. .... .... ..... ...... .... .... ..4 0.326 0.338 0.344 0.343 0.339 0.331 0.336 0.336 0.334 0.336 0.336 0.340 0.349: 0.331 0.337 0.343 0.345 0.341 0.339 0.333 0.339 0.335 0.335 0.330 0.346 0.3436 0.336 0.341 0.347 0.348 0-349 0.346 0.339 0.335 0.338 0,343 0.345 0.339 0.3450__.337 0.347 0.350 0.380 0.348 0.347 0.339 0.335 0.344 0.340 0.339 0.341 0.37708- .332 0.343 0.351 10.356 0.3511 0348 0.338 0.343 0.343 0.341 0.339 0.343 0.351.-) 7 Supplemental ReportEldWeý-"y

,.pArt No BOP-UT-14-O01 Page 4 of 4fin, a Ito SM~ Pipe Spool _______7 ý, ý