ML031750593

Request for Relief from American Society of Mechanical Engineers (ASME) Code for Replacement of ASME Code Class 3 Piping

ML031750593
Person / Time
Site:	Sequoyah
Issue date:	06/14/2003
From:	Salas P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031750593 (34)

Text

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 June 14, 2003 10 CFR 50.50(a)(3)(ii)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket No. 50-327 Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT (SQN) - UNIT 1 - REQUEST FOR RELIEF FROM AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE FOR REPLACEMENT OF ASME CODE CLASS 3 PIPING This letter provides a request for relief to delay repair on a section of ASME Code Class 3 piping within SQN's essential raw cooling water (ERCW) system. At the present time, a pin-hole leak exists on an 8-inch diameter carbon steel pipe in the essential raw cooling water (ERCW) header 1B return piping to the 1B ERCW discharge header on Unit 1.

TVA has evaluated the operability of the ERCW system with regards to: (1) the structural integrity of the pipe, (2) effects of spray on adjacent equipment, and (3) ERCW flow rate requirements. TVA's evaluation for operability indicates that the ERCW system will perform its design basis function and surrounding equipment is not adversely affected.

Leakage from the pipe is currently less than one gallon per minute. The small amount of leakage has been evaluated and does not impact system function or plant operation. TVA will monitor the leakage weekly in accordance with SQN's Generic Letter (GL) 90-05 program. A mechanical pipe clamp to limit leakage will not be installed at this time.

Pmted on nrycled per

U.S. Nuclear Regulatory Commission Page 2 June 14, 2003 TVA will replace the affected section of pipe prior to startup from the Unit 2 Cycle 12 refueling outage (scheduled to begin November, 2003). Until pipe replacement is completed, performance of a weekly visual and a quarterly ultrasonic examination will be performed to assess the pipe degradation rate.

This relief request is being submitted under 10 CFR 50.55(a)(3)(ii) and is provided in accordance with the guidance of NRC GL 90-05. However, it should be pointed out that Unit 1 is currently in mode 3, starting up from the cycle 12 refueling outage. NRC approval of this request is requested by June 14, 2003, to support entry into mode 2 and above. provides the request for relief. Enclosure 2 provides TVA commitments contained in this letter. Enclosure 3 provides the TVA evaluation. This letter is being sent in accordance with NRC RIS 2001-05. If you have any questions about this change, please telephone me at (423) 843-7170 or J. D. Smith at (423) 843-6672.

Lic msFi7-and Industry Affairs Manager Enclosures cc (Enclosures):

Mr. Michael L. Marshall, Jr., Senior Project Manager U.S. Nuclear Regulatory Commission MS 0-8G9A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739

ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT (SQN)

REQUEST FOR RELIEF - ESSENTIAL RAN COOLING WATER (ERCW)

ENGINEERED SAFETY FEATURES (ESF) HEADER 1B RETURN PIPING UNIT: SQN Unit 1 COMPONENTS: 8-inch Nominal Pipe Size (NPS), Schedule 40 carbon steel pipe SYSTEM: ERCW ASME CODE CLASS: 3 FUNCTION: This section of piping returns cooling water to the 1B ERCW discharge header.

CODE REQUIREMENT: When an American Society of Mechanical Engineers (ASME),Section XI code repair or replacement is performed, it is required to be performed in accordance with ASME,Section XI, IWA-4000 or IWA-7000, respectively, in order to restore the system' s structural integrity back to its original design requirements.

BACKGROUND: On June 13, 2003, a through-wall leak was discovered in the ERCW system. The leak is located in an 8-inch diameter carbon steel pipe in the ERCW ESF header 1B return piping to the 1B ERCW discharge header. The leakage from the piping was determined as less than one gallon per minute by the system engineer at the time of discovery. The system engineer has reviewed the design requirements for this system and has determined that this amount of leakage does not affect the operability of the system. The small amount of leakage from the pipe is not spraying on any electrical equipment or causing any flooding concerns. Problem Evaluation Report (PER) 03-008909-000 has been written to document this condition.

NRC Generic Letter 90-05 evaluation requirements were addressed for the through-wall flaw. An ultrasonic examination was performed of the affected area. This information was used to perform the structural El-1

integrity calculation required by NRC GL 90-05 by the through-wall method. The results of this evaluation show that the largest calculated stress intensity factor "Kn of 26.3 ksi (in) 0 5 is less than the 35 ksi (in)05 criteria for ferritic steel. Based on the above, TVA determined the structural integrity of the ERCW system is not impaired.

The preliminary root cause for the piping degradation is considered to be due to microbiological induced corrosion (MIC). The PER will require examination of the piping once it is removed to confirm the root cause along with any other corrective actions. Since the preliminary root cause is considered to be MIC, no additional areas were examined since MIC cannot be predicted as to its location. SQN has had numerous examples of MIC leakage with no threat to operability or structural integrity. Therefore, no other areas were examined. The leakage has not caused any flooding or spraying onto any adjacent electrical equipment. The amount of leakage does not affect the system flow requirements as well.

SQN is currently completing a refueling outage of lengthy duration due to steam generator replacement. The unit is in Mode 3 and close to completing the surveillance requirements to enter Mode 2. Removing this portion of the ERCW system from service will place Unit 1 in an action statement of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Due to the design of the ERCW system, the removal of this portion of the ERCW system will also place Unit 2 in a 72-hour action statement. This is because the ERCW 1B ESF header also supplies ERCW cooling to the Unit 2 Component Cooling System for safety-related cooling loads.

Removal of this portion of the ERCW system will result in an unnecessary delay for returning Unit 1 back to service and will necessitate placing Unit 2 into a cold shutdown condition.

This is due to the location of the leak in the ERCW piping. The location is in a very congested area with limited access for the craftsman to work. Since discovery of the leak, there has not been sufficient time to adequately review the effected area to determine what scope of work is required to perform an ASME Code repair or replacement.

E1-2

Without the proper review and planning, the necessary materials cannot be determined and obtained.

PROPOSED TEMPORARY NON-CODE REPAIR: Based upon the above, TVA requests relief from ASME code. TVA plans to leave the piping "as is." The leakage is negligible and does not present a maintenance or operational problem.

Additionally, the pin-hole opening in the pipe usually closes itself, thereby limiting or stopping the leakage, due to the debris associated with river-water systems. The GL 90-05 evaluation shows that this piping still has sufficient strength. Based on the continued monitoring discussed below, TVA will reevaluate the need for additional housekeeping measures as appropriate.

ALTERNATIVE REQUIREMENTS: Engineering will perform a weekly walkdown and assess the operability of the system. Any changes which affect system operability or structural integrity will be evaluated. An ultrasonic examination will be performed every three months to assess the piping degradation rate. Based upon the weekly walkdowns and ultrasonic examinations, an engineering evaluation will be performed to determine if further remedial measures or corrective actions are needed. An ASME Section XI repair or replacement will be performed before the completion of the Unit 2 Cycle 12 refueling outage which is currently scheduled to start in November 2003.

E1-3

ENCLOSURE 2 TVA COMMITMENTS

1. TVA will replace the effected piping in accordance with the American Society of Mechanical Engineers code prior to startup from the Unit 2 Cycle 12 refueling outage (currently scheduled to begin November 2003).

2. Engineering will perform a weekly walkdown and assess the operability of the system. Any changes which affect system operability or structural integrity will be evaluated.

3. An ultrasonic examination will be performed every three months to assess the piping degradation rate. Based upon the weekly walkdowns and ultrasonic examinations, an engineering evaluation will be performed to determine if further remedial measures or corrective actions are needed.

E2-1

ENCLOSURE 3 SEQUOYAH NUCLEAR PLANT (SQN)

TVA EVALUATION E3-1

IVAN CALCULATION COVERSHEET/CCRIS UPDATE Page REV 0 EDMS/RIMS NO, EDMS TYPE: EDMS ACCESSION NO (N/A for REV. 0)

CEB 800425 026 calculalions(nuclear)

Cale Tite:

SUMMARY

OF PIPING ANALYSIS N2-67-3A1 CALCID lTE ELANT EANC l UMBER l CUR REVlEWV l CURRENT CN NUC SQN CEB N2-67-3A-1 38 39 lAPPLIOL NEW CN NUC Entire calc E Selected pages g No CCRIS Changes 0 ACTION NEW 0 DELETE 0l SUPERSEDE 0 CCRIS UPDATE ONLY O (For cak revision, CCRIS REVISION I& RENAME 0 DUPLICATE O3 (Verifier Approval Signatures Not Required) been reviewed and no CCRIS changes required)

UNITS SYSEMS ,UN=IDSSQN-2-HEX-070-001 5A, SQN-2-HEX-070-001 5B, 001&002 067 SON-0-HEX-070-0012A, SQN-0-HEX-070-012B, SQN-1-HEX-070-0008A, SON-1-HEX-070-OOB, SON-2-HEX-072-0030 DCN.EDC.NIA PPLICABLE DESIGN DOCUMENT(S) 1.2-47K450-63, -66, -67, -71,-238, -253; CLASSIFICATION N/A I 1-47K450-69.-70; 471<450-65 U2AC) E.

QUALITY SAFETY RELAED? L EIE SPECIAL REQUIREMENTS DESIGN OUTPUT SARrTS AFFECTED RELATED? (I yes, OR ayes) ASSUMPTION AND/OR L1MIBNG CONDMONS? ATACHMENT?

Yes [D No Yes 10 No O Yes O No E) Yes O No CD Yes O No CD Yes D No 0R PREPARER ID PREPARER PHONE NO PREPARING ORG BRANCH) VERIFICATION METHOD NEW METHOD OF ANALYSIS JCCORNWE 423 643-8230 CEB DESIGN REVIEW 03 Yes No PREPARER SIGNATU DATE CHECKER SIGNATURE DATE J. C. Comwefl Z. ______ ___-P VERIFIER SIG RE ' DbATE' A P IGNA7TL d DATE I /CO4NS6r ___ p&/j~j J /t,

____D__iez STATEMENT OF PROBLEM/ABSTRACT THIS CALCULATION DOCUMENTS THE RIGOROUS ANALYSIS OF SQN ESSENTIAL RAW COOUNG WATER SYSTEM PIPING FROM THE STEEL CONTAINMENT VESSEL PENETRATIONS X-59 AND X-63 TO HEADER IA AND 2B. THIS INCLUDES PIPING FROM THE CONTAINMENT SPRAY HEAT EXCHANGER IAAND COMPONENT COOLING HEAT EXCHANGERS OB1,0B2, IAI, 1A2, 2A1, AND 2A2.

ALL REQUIREMENTS OF THE APPUCABLE DESIGN CRITERIA ARE MET.

R39 INCORPORATES EVALUATION OF THROUGH WALL FLAW IDENTIFIED ON PER 03-008909-000.

MICROFICHEIEFICHE Yes 0 No Q FICHE NUMBER(S) TVA-F-T000731 AND TVA-F-T000732 (CREATED BY REVISION 33)

D LOAD INTO EDMS AND DESTROY C LOAD INTO EDMS AND RETURN CALCULATION TO CALCULATION LIBRARY. ADDRESS:OPS I B SON O LOAD INTO EDMS AND RETURN CALCULATION TO:

TVA 40532 07-20011 Page 1 of 2 NEDP-2-1 0792D01 -

TVAN CALCULATION COVERSHEET/CCRIS UPDATE z

Page CALC ID TYPE ORG PLANT I L

BRANCH Kil IMRD I RFV I I '-~~-~-

I CN I NUC_I SON CEB I N267-3A- I 39 1

. w ALTERNATE CALCULATION IDENTIFICATION AMR~ EM 1 _ COORAZIM FRM EintzL Yes O CATEGORIES KEY NOUNS (A-add, D-delete)

ACTION KEY NOUN 6 KEY NOUN CROSS-REFERENCES (A-add, C-change, D-delete)

ACTION XREF XREF XREF XREF XREF XREF aCODE TYPE PLANT BRANCH NUMBER REV A P PR SQN MEB 03-008909-000 I I Page 2of2 NEDP-2-1 107-09-~~~~~~~

CCRIS ONLY UPDATES:

Followio arec Lred orywhen maM keywrdcoss reference CCRIS tsand pa-ge I of form NEDP-2-1 Is not Incuded:

PREPARER SIGNATURE PREPARER PHONE NO.

DATE I EDMS ACCESSION NO.

CHECKER SIGNATURE DATE TVA 4032 07-2001 Page 2of2 NEDP-2-1 0749 20011

TVAN CALCULATION RECORD OF REVISION CALCULATION IDENTIFIER N2-67-3A1 Page i-ab TKle

SUMMARY

OF PIPING ANALYSIS N2-67-3A1 Revision DESCRIPTION OF REVISION No.

39 REVISED TO ADD EVALUATION OF THROUGH WALL FLAW AS IDENTIFIED ON PER 03-008909-000.

Sections 3.7 and 3.9 of the SAR and the Technical Specifcatons have been reviewed by J. C. Comwvell, and this revision of the calculation package does not directly o Idirectly Impact the Information (text, graphs or tables) In the SAR or Inthe Technical Specifications.

Pages added: R39 cover sheet (2 pages), l.eb, P.1 through P.20 Pages deleted: None Pages replaced: I Pages revised: .1 Total number of pages of the entire calculation = 1584 Total number of pages In this selected page revision fncluding filing Instructions) =26 The last page of the calculation is Z.

Prepared: Date: /#' /:5 Checked: BVX Date: -i1 23/L.

Legibility evaluated and accepted for issue.

This applies to all pages.

I Signature Date This page added by revision 39.

Page ii TVAN CALCULATION DESIGN VERIFICATION FORM Calculation Identifier N2-67-3A1 Revision 39 Method of design verification used:

1. Design Review 09

2. Aitemate Calculation 0 Design Verifier //dX, Date 6/1i3/03

3. Qualification Test 0 __I Comments:

The subject calculation at the revision level noted above has been found to be technically adequate In that computations, judgments, assumptions and logic are In accordance with generally accepted methodologies.

This revision utilizes historical methods established for review of analysis calculations. The calculation conforms to standard RAH and NE procedures for calculation preparation and documentation. This calculation is technically adequate for this revision in Its format and content.

Page 1 of I TVA 40533 [12-20001 WA 40633 12-20001 Page of v NEDP-2-4 112-04-20001 This page replaced by revision 39.

Wli CALCULATION SHEET Document: N2-67-3A1 Rev: 29 lPlant: SQN, UO IPage: .1

Subject:

Summary of Analysis N2-67-3A1 Prqeared By..La Date: fth3/ir Checked By. Date: iZ/A!Ls5 TABLE OF CONTENTS SECION DESCRIPTION PAGE Appendix F Evalaion of Temporary Configuration F.1 by DCN-M11500 Appendix G Evaluation of Sampling Une Additon G.1 by DCN-Ml 1473 Appendix H Evaluafion of MIC for Weld 14478-1 H-1 XClR30 50ltq p>RM-INWArto~ 6F JMA$ ALLOwASL'E APPEPUPi r 464 sh* rLAVJ LWCk tAk e wELD FVj1,A7¢trOh0A, o 4l I 74q APPEN'ax S2sJ99tfr(

For f PRX&"IVi4LjVEs 6Q2sT369PER) e"1 4Iq9s t),p,rEDI K Ai.;wnU W ,q4j. 7-r/O Ai APPED I X L 1C/g6ttD0 / CoRRSoA) gs p, AEp Jr tD f P/P( Sp L PEC EVAL f 1 2 /E/

P3 i-i fCk.zlrr19 AMI I>\ M bIALUAW 09 "FIC-ta'no CAkwtl15 V.1 A.so. - WV4i-AS KXs D2bA t.4 & D 2a 0

,4PAFNIDJX N M.I S--X4:VA- 0VvJ-M0A fJ cv Z-Z2-oz S/zvO ArxR'jAJb O l goR 1 Fvt

~ 4 ,- (Szror

• N~~r u I ~ a -u1>AuL To&w 4- i ~f 4I i '

APPwbIc P &A-a-UM-l Of -7tVG4, ot-4c14 hPL<k - APf OS -00otn 0o-_Jo

TVAN CALCULATION SHEET Document: N2-67-3A1 l Rev.: 39 Plant: SQN/1&2 Page: P.1

SUMMARY

OF PIPING ANALYSIS N2-67-3A1 Prepared By  : Date:4L I.

Checked By: Date:: /jrj APPENDIX P EVALUATION OF THROUGH WALL FLAW PER 03-008909-000 This page added by revision 39.

Page 1 of 6 Problem N2-67-3A1 R39 Prepared: eri tQ5 Page Checked: _ 6____

Purpose:

The purpose of this evaluation is to determine the minimum required wall thickness Tmin) for the existing Essential Raw Cooling Water 8" sch 40 return piping from EBR & MCR AIC coolers. The segment of straight pine evaluated is located on isometric 1.2-47K450-66 between nodes 892 and 901 at elevation 683'-9". This calculation is in sUPport of UIC12 outage.

Assumptions:

There are no assumptions which require later verification.

Evaluation:

All stress values were retrieved from calculation N2-67-3AI. microfiche TVA-F-T000731 for the Permanent condition, nodes 892, 892A. 893. 893A. 893B.

893C. 895.895A. 895B. 897, 897A. 897B. 899.9Q0. 901 (members M522. M522A through M522M1.

Temporarv operating condition does not affect this area and therefore output data on microfiche TVA-F-T000732 does not arnilv for this evaluation.

Determine the minimum reauired wall thickness due to 0.3*Tnom (Tmint) and Hoop Stress Tminh):

P:= 16 lbf Design Pressure

.2 Outside Diameter of 8" sch 40 D:= 8.625-in Sh:= 15000-psi Allowable Stress Tnom:= 0.322-in Norninal Pipe Wall Thickness d:= D- 2 Tnom Inside Diameter d= 7.981in 4 om = 16.813 in Znom:= 0.0982.- Nominal Section Modulus DT

_ D Tuom

,om =-2 - Nominal Mean Radius Rnom= 4.151 in based on HOOP Stress:

Insed on .3 X TM.

P-D Tmint:= .3 Tnom Tmnh:. 2.(Sh + 0.4 P)

Tmint = 0.097 in Tmih= 0.046 in This page added by revision 39.

Page 2 of 6 Problem N2-67-3A1 R39 Prepared: /t 0>/3-03 Page p 3 Checked:__ 6--

1. Check Equation 8 Stresses based on computer analysis:

stressg:= 869.psi Sustained Stress from TPIPE Post Processor S8:= Sh D - trstg tcd~8 := 0.040.in Mean Radius rm8 = 4.292 in rm8O = 2 dinn8:= D tea Znun8:= 0.0982- D Znn8 = 2.305 m i:= 1.000 i7 5 := 0.75-i ii= .765times i. i7 5 = 0.75 sif:= f1> i7 5 ,1,i 7 5) sf=TheSIFused in code eauation comnarison (.75ior 1.0 which ever is created sif = 1 p.d2 Pnom D)2 g2 Pnom= 952.98 psi (stressg) Znom Ma: ~~sif Ma = 14610.861 in bf Bending Moment due to sustained stresses P din82 Ma sif R;8:= qg Eag = 14843.053 psi SRg Eqg:= 2 2 Z-IS SRg = 0.99 D - dmg c Equation 8 stresses below allowable of 15000 psi. Therefore, OK Minimum reauired thickness for Ea 8: tesg = 0.04in This page added by revision 39.

Page 3 of 6 Problem N2-67-3A1 R39 Prepared: ,% 6A-/03 Page t Checked: "3v 3

2. Check Equation 11 stresses based on computer analysis:

Sc:= 15000-psi Sa:= 1.25- Sc + 25-Sh Sa = 22500 psi S 1I:= Sa+ Sh S1 = 37500 psi Equation 11 allowable stress.

stressth:= 421-psi Expansion stress from TPIPE Post Processor.

test :=O0 2 i rmll D-ttI Mean Radius rmll = 4.302in 2

dmni:= D - 2testil Znl := 0.0982- D Znjl = 1.161 in3 D

i:= 1.000 i7 5 := 0.75-i 5I=.75timesi. i75 = 0.75 sif:=i > i75,I,i 7 5 ) sif = The SIF used in code eauation comparison (.751 or 1.0 which ever Is reater) sif= I stessth,Znom MclI = 7078.449 in. lbf Bending moment due to thermal stresses.

Mcll:=- i P dminl r Ma sif ) MCI i

-qll := D d 2 + +- Eql = 35816.182psi SRII := Eql SR1 1 = 0.955 D2 2 ~Zmin

.1 ) Zminll SI Eauation 11 stresses below allowable of 34250 sl. Therefore, OK.

Minimum reauired thickness for Ea 11:

tctll = 0.02in I This page added by revision 39.

Page 4 of 6 Problem N2-67-3A1 R39 Prepared: t%* 6'/o3-Page ,I) Checked: 6-/3

3. Check Equation 9U stresses based on computer analvsis:

Sgu := S 1.2 Equation 9U allowable stress. Sgu = 18000 psi stress9U:= 2985-psi Occasional lOBE) stress from TPIPE Post Processor.

tet9U:= 0.083-in D - test9U D -Mean tst =0rmgU:= Radius rmgU = 4.271 in 2

djngu:= D - 2 t9U D - dU 3 Zmin9U:= 0.0982- D zmi9uU= 4.712Mn i:= 1.000 i 75:= 0.75-i = .7times i. i 75 = 0.75 sif:= if(1 > i 75, 1,i7 5) sif-The SIF used In code equation comparison (.75i or 1.0 which ever is areater) sif= 1 (stress9u). Znom Mb9u = 50188.056 i&lbf Bendinc moment due to occasional (OBE) stresses.

sif P din9U2 MbgU sif Mar sif Eq9u EqU:= ++ EqgU = 17787.803 psi SRgU = 0.988 DE2-_4 n9U2 Zmin9U Zmin9U S9U Equation 9U stresses below allowable of 16440 PsI. Therefore. OK.

Minimum required thickness for Ea 9U: testgU = 0.083 in This page added by revision 39.

Page 5 of 6 Problem N2-67-3A1 R39 Prepared: 4'-1 6/703 Page g' Checked: - ,G

4. Check Eauation 9F stresses based on computer analysis:

S9F:= Sh. 2.4 Eauation 9F allowable stress. SgF = 36000 psi st"ss9F:= 5226-psi Occasional (SSE) stress from TPIPE Post Processor.

testgF:= 060-in rm9F = tesF Mean Radius rmgF = 4.282 in dhingF:= D tet9F D - dnF4F 3 Zmn9F = 0.0982- D____= 3.434i i:= 1.000 i7 5 := 0.75i = .75 times . i75 = 0.75 sif:= if1 > i75,1,i 75) sif The SIF used In code eauation comparison .75i or 1.0 which ever Is greater) sif = 1 Znpm (strssgF)

Mb9F:= si,f MbgF = 87866.928 in lbf Bendinci moment due to occasional (SSE) stresses.

P dmin9F MbgF Sif Ma sif Eq9F:= + + - EqgF = 35472.609 psi Eq9F D2 in9F2 Zmin9F Zmin9F SR9F := SRgF = 0.985 S9F Eauation 9F stresses below allowable of 32880 nsi. Therefore, OK.

Minimum required thickness for Eq 9F:

testgF = 0.06in

5. Check Pine Rupture stresses based on comuter analysis:

Pipe Rupture Is not reciuired for this seament of plina This page added by revision 39.

Page 6 of 6 Problem N2-67-3A1 R39 Prepared: AS 6-3-o?

Page P7 Checked: 6 -/3 I Summary of Tmin Values:

Tmint = 0.097 in L, required for 0.3 x Tnom T inh = 0.046 in T-jj required for Hoop Stress testg = 0.04 in recuired for DW Bendinc Stress testli = 0.02i recWuired for DW + Thena1 Stress test9U = 0.083 in ,required for OBE Bendinq Stress test9F = 0.06 in u required for SSE Bendinc Stress Deterrnine Tmins Based on Actual Piping Stresses Tmin: = if(Tmit> Tmjh, TmintTmin Tmm := if(TM > testg, Tmin, test)

Tniin: = Tmin > etl1, Tmin,testi1)

Tnmn:= if(T,m > test9U, Tm, test9U)

Tmin:= if(Tm > test9F, Tmin, test9F)

Tnin reauired equal to the laraest of the above values: Tmin = 0.097 in Tmin based on 0.3 x Tnom.

Conclusions:

The Tmin for this segment of piping Is 0.097" based on Tnom.

This page added by revision 39.

Page 1 of 10 N2-67-3A1 R39 Net Section Evaluation Page , Checked L4L4eL MATHCAD ANALYSIS ROUTINE PART I - NET SECTION PROPERTIES The following process computes the net elastic section properties for a degraded section on isometric 1,2-47K450-66 for straight pipe between nodes 892 and 901 at elevation 683'-9' This is 8'sch 40 ERCW return piping from EBR & MCR A/C Coolers. This evaluation uses Mathcad software to implement the net sectionproperty calculationprocedure developed in CEB-CQS-449. The evaluation is done for leakage crack for PER 03-008909-000.

STEP Ll - INPUT DATA Ro:= 8.625 in - Pipe Outside Radius tnom:= 0.322-in - Nominal Pipe Wall Thickness n:= 20 - Nmber of Constant Thickness Are Segments Used to Model Degradation. The gnd as applied to the piping contains 20 divisions.

j:= .. n Segment Data:

(where 1 and tr, are the segment length (m) and remaining thickness (n) of each segment j)

L.:=

tr.

2.008. in 0.213 in I.500 in 0.139-in 0.250- in 0.094-in 0.500-in 0.0. in 0.250 in 0.126- in 2.008-in 0.255 in 2.008 ir 0.280. in 2.008 in 0.280-in 2.008 in 0.280. in 2.008. in 0.269 in 1.355. in 0.230 in 1.355. in 0.230- in 1.355-in 0.230-in 1.355-in 0.230- in 1.355.in

0. 135 in 0.250- in 0.230- in 1.631*in 0.230. in 1.631-in 0.230- in 1.631-in 0.230. in 1.631. in P.210 in This page added by revision 39.

Page 2 of 10 N2-67-3A1 R39 Prepared t1 e-s3-43 Net Section Evaluation Page D, eA Checked gaem The total pipe circumference is:

LC := E L LC = 27.097 in i

The total cross section is:

LM := if(trj S 0.0in,L, 0 in) LMi:= X L LMTi = 27.097 in j

STEP L2 - FIND TH CENTROI) OF THE DEGRADED SECTION A. Compute the total cirmferential length (LT) and the average thickness (t,,)for the section:

LT:= ELi LT = 27.097 in LT- LC = 0in j

If LT - Lc is zero the length adjustments are mathematically correct L;tr) taV:= i tav = 0.231 in LT B. Compute the starting (i = 1) and ending (i = 2) angles9i in radians for each segmentj. Note that segment j = 1 at 0 radians ( )and the ending angle for the last segment (3,) must be 2ir radians. The section starting and ending angles are then:

el,1:= 0*rad 02 n:= 2. X rad 360 p:= -

j:= 2.. n el&j: (e1j- + L 12.7 2

)

J:= ..n THICKNESS ANGLES ANGLES (inches)

L. (radians) (degrees) *1 2j:= ( j' + T2.7r rad @f,j= 3 2,j el,j.p = _i =

LT J 2,j P = in 0.466 0.582 26.677 22.999 0.187 0-582 0.64 33.32 44.061 0.176 0.64 0.755 36.642 65.124 0.077 0.755 0.813 43.284 86.187 0.088 0.813 1.279 46.606 107.25 0.125 1.279 1.745 73.283 128.312 0.062 1.745 2.21 99.961 149.375 0.011 2.21 2.676 126.638 170.438 0.011 2.676 3.141 153.316 191.5 0.141 3.141 3.456 179.993 ?12.563 0.19 3.456 3.77 197.995 233.626 0.198 3.77 4.084 215.997 254.689 0.213 4.084 4.398 233.999 275.751 0.216 4.398 4.712 252.001 282.031 0.187 4.712 4.77 270.003 290.532 0.196 4.77 5.149 273.325 296.812 0.196 This page added by revision 39.

Page 3 of 10 N2-67-3A1 R39 Prepared , 3 Net Section Evaluation Page pLo Checked -6,* 0443/2 C. Compute the mean radius (Rm5) for each segment: tr.

Rm. := Ro -

J 2 D. Compute net cross section metal area (ANET):

A2 ANET:= E [Rm, trj-(E32, j - e 1, j)] ANET = 11.472 mn j

E. Compute centroid locationsSx and by in the baseline rectangular coordinate system:

x [(Rmf) *trj-(sin(62,j) - sin(0,J))]

sx:= Bx = -1.148 in ANET

-1.[ [Rmnj) tr; (cos1j) - 0D#)13,j))lC by:= By = 0.288 in ANET STEP 13 - DETERMENE MOMENTS OF INERTIA A. Compute the area (x, y) and product (Ixy) moments of inertia in the baseline rectangular coordinate system:

AGj:= 2,j - 0 1,j ACOSj:= cO4E2, j) - C0o0 1,j) ASINj := sin(02,j) - sin(E 1 ,j) sin(2 0 2 , j) - sin(2e 1, j) + 2.8y. (ACosj) + BY2-(AOj)l lx:=I 2 4 Rm. (Rm)2 j . i j J sin(2-.2, j) - sin(2.e 1 , j) 2 Sx.(ASIN)

Iy:= +

2 4 Rmj j

sin(2, j)2 sin(O 1 j) sx.ACOSj - By.ASINj iv:= 1 -37.209 in 4 Rmj (Rmj)2 j

This page added by revision 39.

Page 4 of 10 N2-67-3A1 R39 Prepared edr 6-1-93 Net Section Evaluation Page { Checked B. Compute the maximum and minimum pnncipal moments of inertia (Imax and Lmin):

Ix:+

IY Ix IY+I 2 2mx: + 2 ) IJ Imax = 461.283 m4 Ix + Iy Ix-IY' 2 2 Imin:=- - I +I 2 . 2 ' Imin = 352.084 m STEP L4 - FIND TBE ORIENTATION OF THE PRINCIPAL AXIS A. Compute the angle P in radians of the maimum principal stress axis with respect to the global X Axis. Note that when 2p approaches + or - xJ2, the tangent of2p approaches co. Therefore, in the formula fori below, the minimum value of the quantityAl = Ix - Iy must be restricted from becoming zero to avoid division of by zero.

Al:= ix- Iyl Set Iv = Ix whenAl is small Set l AI < n n0.00001m 4, sx,sy)

Set Al to a small finite nmber wfhenAI is snall Al:= ifAI <0.00001 -n, 1 Ain,I) AI = 79.915 in4 Compute a preliminan angle between the Imax axis and the +X axis

= .5-ta2 )IXY 0= 0.375 rad p = 21.48 deg B. The equation forP above assumes that Ix > ly. When Iy > Ix, the value op3 when cahllated using the above formula changes sign and is measured relative to the 4y axis. Therefore to compute the true angle (D, of the Imax axis with the +X axis, the following logic is applied:

P1 := if(Iy> x,@ + X,) D I = 0.375 rad 01 = 21.48 deg C. The angle 0P2between the Imin axis and the +X axis is determined simply by subtractingz/2 radians:

02:= 01 - 02 = -1.196rad 02 = -68.52 deg 2

D. Adjust 0P and 2 to avoid numencal problem with tan (ct2) - O.

SGN0 l:=2 01-(01) SGND1 =

SGN4b2:= 4DX(1'021)- SGN02 = -1 P 1 := i(tan(41) > 1.59 105,1.57079 SON01, P1J 4) = 21.48 deg 02:= if(Jtan(2) > 1.5810 ,1.57079-SGNO2 ,0 2,, 02 = -68.52 deg This page added by revision 39.

Page 5 of 10 N2-67-3A1 R39 Prepared Ar-ro?

Net Section Evaluation Page Checked _ -4113 STEP L5 - FIND THE DISTANCE FROM THE NEUTRAL AXS TO OUTER FIBER

. Detenmine the intersection of lines parallel to the principal axes passing through the origin with the orthogonal principal axis.

The equations of the principal axis in the x-y coordinate system are:

y =mq x + bq; where q = corresponds to the Imax axis and q = 2 corresponds to the Iminaxis.

Then:

q:= .. 2 mq:= tan(cQ The y axis intercepts of the principal axes are:

bq:= by- mq ox The equation of the orthogonals to the principal axes passing through the origin are:

y = (MqtIX

.1.. -6 -6 mqJ Adjust nt when mq is small to avoid division by zero:mq:= inlmq < 1.-10 ,110 Solving the two equations simultaneously, the intersection coordinates of the principal axes with their orthogonals passing through the origin are:

bq q q XI = .252in XI = -. 896in mq + Imiy YIq:= -l.(mq 1*=Iq Yj =0.641 in Y1 =-0.353 in B. Determine the intersection points (Xl ,Yl)q & (X2,Y2)q of the orthogonals to the principal axis passing through the origin with the circle defined by the pipe outside radius:

XI :=Rocos4' q+ 2) XI -3.158in X 2= 8.026in X2=R&cosfq2) X 2 =3.158 in X 2 =-8.026in (4)2)12 Y 1 :=Ro 4 q+ ) Y1 8.026in Y1 =3.158in q= 2) 1 2 Y2 :Ro q ) Y2 1 8.026 in Y2 2 = 3.15 in q + 2J )

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Page 6 of 10 N2-67-3A1 R39 Prepared 63-1A-.

Net Section Evaluation Page .. 4.i3 Checked a/ZG/

C. Compute the x and y axis components of distance from the neutral axis to the outer fiber:

X - Axis Xp :=Xi -XI Xp (-2.906 ),n - x distance to 1st intercept pairs g q q 8.922 )

XN := X2 XI XN =( 3>, - x distance to 2nd intercept pairs q q q -7.13J)

Y - Axis yp := Yi - YI C7.385 ) - y distance to 1st intercept pairs q q q P 3.511)i YN = Y2 -YI YN = (-8.667 )in - y distance to 2nd intercept pairs q q q -2.806)

D. Compute total distance from neutral axis to mean radius point considering that the mean radius is represented by the average wall thickness (tv):

C1q= (XP) 2 + (YP )2 taV C 1 = 7.821 in C 1, 2 = 9.472 in 2 2 -

C2 q:= (XN) (YN C2 1=9.198in C2,2 = 7547in E. Compute the minimum section modulus about each principal axis:

Clq:= Cq, C2q:= C 2 ZMjN : Imax ZM[NI = 50.149 in3 1 max(Cl).

Imin ZMIN = 37.169 in3 ZN2 =ma(C2) 2 F. Compute the offset of the principal axes with respect to the pipe centerline:

SOFFq = (XIq 2

+ (YIq) 2 SOFF = 0.688 in SOFF2 = 0.963 in This page added by revision 39.

Page 7 of 10 N2-67-31 R39 Prepared. .-. L.03.o Net Section Evaluation Page L 1\\ Checked PART II - SECTION STRESS ANALYSIS The following process computes the net section elastic stresses for a degraded pipe section using the previously computed net section properties to implement the stress calculation procedure developed in reference CEB-CQS-449.

STEP IL- INPUT STRESS DATA FROM PIPING ANALYSIS Sh:= 15000-psi - allowable stressforpipe atmaximumdesigntemperature Sc := 15000-psi - allowable stress for pipe at room temperature SS:= 869 psi - stress from piping equation 8 (normal)

S9U:= 2985-psi - stress from piping equation 9U (upset)

S9F := 5226-psi - stress from piping equation 9F (faulted)

S1 := 421-psi - stress from piping equation 10 (thermal expansion)

SIF 1.0 - stress intensification factor at point in question P:= 160 psi - designpressure STEP IL2 - BACK CALCULATE THE APPLIED BENDING MOMENTS IN THE PIPING ANALYSIS A. Compute nominal section modulus (7,,) and pressure stress (p,)

29 \2 4

1m: t nom I4 o Znom = 72.47 in 3 P (Ro - nomno apr:= 2 apr =2.024x 103psi Ro2 - (Ro - tnomf B. Determine controlling stress intensification factor (SIF'):

SIF':= if(0.75-SIF 5 1.00,1.0,0.75 SIF) SIF' = 1 C. Compute bending moment (ME) for sustained mechanical loads:

M8 spSIP' MS= -8.367 x 10 in lbf D. Compute bending moment (?u) for piping Equation 9U:

M9U:= ( 9 CFpr?2nom MgU=6.96712x 104 in1Ibf SIPS E. Compute bending moment ( 4 F) forpiping Equation 9F:

M9F (S9F r) 7n MgF= 2.321 x 10 iDlbf SIo' This page added by revision 39.

Page 8 of 10 N2-67-3A1 R3 Prepared re d -l.?3 Net Section Evaluation Page 4.+/-S Checked 40 23/S F. Compute bending moment (oM) for piping Equation 10:

4 inlbf (SIF)Znom Mlo = 3.051 x SEP STEP IL3 - DETERMINE PRESSURE INDUCED BENDING MOMENT DUE TO NEUTRAL AXIS OFFSET A. Compute the nominal metal area (AN":

ANOM:= 2.1.tno(Ro-- ANOM= 17 . 12 4 in B. Compute the added pressue area (AP) due to degradation:

Ap:= ANOM - ANET C. Compute the axial pressure force (Fx):

4 lbf Fx:= P.E(Ro - tno0 2 + AP] Fx= 3.556 x l D. Compute the induced bending moment (04):

Mp q := Fx OFF,q MP(.4x Mp °) in.lblbf 3.423 x 10I STEP 114 - DETERMINE A MODIFIED SIF IF COMPONENT SIF IS BASED ON NOMINAL THlCKNESS The location in question is a girth butt weld. Therefore, SIF is not a function of component thickness and:

SIFM:= SIF SIFM:= if(0.75. SIFM 1.0, 1.0, 0.75.SIFM) SIF'M = 1 STEP IL - COMPUTE NET SECTION STRESSES A. Equation 8 stress (aj):

Fx Mp +Mg 1.919x 103 crg :=- + SIFM- c= psi q ANET ZM[Nq 1.769x o,)

B. Equation 9U stress (ag):

Fx MP +M9U (4.977x c9u := + SIFM q cJ9u= psi q AET ZMINq 5.895 x 10 )

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Page 9 of 10 N2-67-34 R39 Prepared X45 o Net Section Evaluation Page r.I Checked C. Equation 9F stress (Y9,):

Fx Mp +MgF 8.215x 103 09F:='- + SFM q C 9F = psi q ANET ZMIN q <1.026x le4)

D. Equation 10 stress (,0):

(608.381 )

0lo = SFMM-q ZMIN a10 = 820.8 3 2 )P' q

E. Equation I Istress ( 1):

Fx SEFV(MPq + Mg) + S1FM M1O ,2528x 103 )

1l  :=- + a11 = psi q ANET ZMI 2.59x 103 )

q STEP LL6 - CHECK ALLOWABLES A. Compute primary stress ratios:

08 SR 8 := -

Sh (0.118)

SR9U = 018 SRU 0.276 )

SR9U := '- q t0.327 )

SR9(0.228 )

2.4. Sh =0.285 )

B. Compute secondary and primary plus secondary stress ratios:

SRI= a lo SRO 0.027 SR 1 5

= 1.25. Sc + 02h3 0.25- Sh QQ3o6 )

SI= 0.067 )

SRII:= ' a1 1.25 Sc + 1.25 Sh SRII = 0.069J C. Find maximum stress ratio.

Primay Stesses:

P1 = m(SRg) P 1 = 0.128 P 2 := max(SRu) P 2 = 0.327 P3 := mX(SR9F) P 3 = 0.285 i := sa .4 rv:=

Pby max(P) Pmax =c0.327 This page added by revision 39.

Page 10 of 10 N2-67-3A1 R39 Prepared.... L-o3-L*

Net Section Evaluation Page P Checked A /7 a Secondary and Primary plus Secondary Stresses:

Ql:= ma(SRIo) Q 2 := ma(SR11)

Q1 = i4Q > Q2' Ql' Q2)

Sm:= max(Q) Sm = 0.069 Worst Case Stress Ratio:

SRmax: = if(Smax > Pmax, Smax, Pmax)

SRmax = 0.327

Conclusion:

Suctural Integerity for the portion of 8" ERCW piping listed above haswith the existing through wall of 1/2'circumferential flaw.

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N2-67-3A1 R39 Prepared ff,,f3>

Evaluation of Through Wall Checked. W ///a Leakage Crack PER 03-008909-000 P. 19 The following calculation is based on the requirements of GL 90-05, Guidance for Performing Ternporary Non-code Repair of ASME Code Class 1, 2 and 3 Piping. This application is for a through wall flaw located on the 8" STD ERCW Train B return piping from the Board Room and Main Control Room A/C coolers, near valve 1-67-5552B. UT examination has idenfied a flaw size of 1" where the wall thickness Is less than tmin. A flaw size of 1 12" (measured flaw size + 2 times transducer size) Is used in this calculation to account for possible Inaccuracies due to Inaccessibility of the flaw location. The Initial lirdtation to appfication of this method Is the flaw size imit of the lesser of 3" or 15% of the pipe circumference, which in this case is 4.0r. Since the bounding flaw size assumed for this evaluation Is less than 3", the method appies.

D.:= 8.625-in t:= 0.322-in Do + (Do t) 4 R = 4.151 in P:= 953.psi DW:= 819 psi TH:= 421-psi SSE:= 5226-psi S:= P+DW+TH+ SSE S= 7419psi twoa tmin:= 0.097-in twoa:= 1.5-in a:= - a= 0.75 in 2

R r = 42.799 tnin c := ac = 0.058 (3.1416-R)

A:= -3.26543 + 1.52784r- 0.072698.r2 + 0.0016011*r3 A= 54.481 B:= 11.36322 - 3.91412.r+ 0.18619.r 2 - 0.004099.r 3 B = -136.453 2 3 C:= -3.18609 + 3.84763-r- 0.18304-r + 0.00403-r C= 142.145 F:= +A-c 5+BRC.5 +c 3.5 F= 1.65 Kl:= 1.4-SF KI = 1.713 x 104psi K2:= (3.1416-a) 0 5 K2= 1.535 in0.5 K:= K1-K2 K = 26299.591 psi in 0 5 Limit:= 35000-psi.in° 5 Since the value of K Is less than the lim-it of 35000 psl(in)O. this lrmit is satisfied and Code requirements for the use of a temporary non-Code repair are met.

This page added by revision 39.

Wt-G?>3-341 pig

/el .1 I

DIGITAL ULTRASONIC TENNESSEE VALLEY CALIBRATION REPORT NUMER:

AUTHORITY DATA SHEET Ro # 2367 PROJECT: SQN UNIT: I CYCLE: 12 CALIBRATION DATE: 6-13-03 PROC.: N-UT- 26 REV:21 TC:03-01 CALIBRATIONBLOCKNO;: Stepwedge TEM: 77'F INSTR WG: KRAUTKRAMER DUE DATE: 5-27-04 SIMULATORBLOCK NO: nla MODELMYE USN-52L M&TE NO.: E18501 TEIRMONflEE S/N: 558273 DUE DATE: 12-09-03 TRANSDUCER MFG: KBA COUPLANT ULTRAGEL II BATCH: 001225 S/N 009KHZ SIZE-:.375 FREQ: 8 M1z EXAM TYPE: SHEAR] LONGO RL[]

CABLE TYPE: RG174 LENGTH: 72 inches ANGLE VERICATION BLOCK TYPE: NA S/N: NA DAC NOMINAL ANGLE: NA l ACTUAL ANGLE: NA INSTRUMEb T SETTINGS

.100 REFLECTOR REFERECE MEMORY if I- _ - I M SCAN DIRECT. NTCH SDE sENsrTvT( NUMBER 80 I 55 dB I

$ _ _ . I ___ I~~~__ . LI CIRC . __nla dB n/a 60

_ r *FEQ: 2-8 MHz *REJECT: 0  %

l ~=-= I =_ I T ANGLE: 0 deg *DAMPING: 1000 ohms 40 DELAY: 0.00 msec- *PUL?ER. SING ZERO: 6.389 msec FILTER- FDC 20 VELOCITY: 2398 msec *REP RATE: IGH 0 I I =I == RANGE: .5 inchs TOF: OPEAK 0 FLANK

• DISPLAYMODE: FULL POWER BATTERY DISPLAY WIDTR .5 inches DUAL: ON 0 OFF TCG: OON 0 OFF REF. REFLECTOR: N/A AMPLITUDE: N/A %

VERIFICATION TMES GAIN: N/A dB METAL PATH: NIg 1)NIA 12)NA 13)NA j INIAL TIME: 11:30 4)NA CALIBRATION TIMES S)NA I 6)NA I 7)NA FINAL TIME: 1310 8)NA I 9)NA.

• PDI QUALIED INSTRUMENT SETINGS:

VERIFY INSTRUNENT SETTINGS AND CALEBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE!

_-LNEAR CHECK SIGNAL 100 90 80 70 60 50 4.0 30 20 VERTICAL SGNAL5 4 20 15 10 GAIN SET -6 dB -12 dB SET +12 SET+6 AITENUATOR AMP 80% 32 TO 48 16 TO 24 20 % 64 TO 96 40% 64TO96 41 20 80 81 COMENTS: WELDS/ITEMS EXAMED:

WO# 03-8910-4noo,_ < 8" ERCW return line fiom B tain electrical

. . w ¢zt t room lo Loco-;te chillers lboard

~.CMsS~ -p ?tl C6p.JsE3 7 7 c,pg'° E.RAA' MR. l REVIEWER. ANI:

LEVEL: .L l LEVEL: ATE:(./A3 PG.: OF I f

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LICENSING TRANSMITTAL TO NRC

SUMMARY

AND CONCURRENCE SHEET THE PURPOSE OF TILlS CONCURRENCE SHEET IS TO ASSURE THE ACCURACY AND COMPLETENESS OF TVA SUBMITTALS TO THE NRC.

DATE DUE June 14.2003 NRC SUBMITTAL PREPARED BY Jim Smith

SUBJECT:

American Societv Of Mechanical Engineers (ASME) Section Xl Inservice Inspection (s) Program -

Relief Reuests ITR Required? (2) YES X NO Applicable DCN: OR OR Jim Smith / 06/13/03 /

Licensing Date ITR Reviewer Date Verification Required? (3) E YES NO Peer Check Required? (4) XX YES __NO OathorAffirmationRequired? YES _; NO If Yes:

New Commitments? YES XX NO l Posting Reqired? YES XX NO Peer Checker Date LICENSING BASIS CHANGE - If this submittal requires a change to the licensing basis, a change has been initiated in accordance with NADP-7. DATE A concurrence signature reflects that the signatory has assured that the submittal is appropriate and consistent with TVA Policy, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared.

NAME ORGANIZATION SIGNATURE DATE D. L. Koehl Plant Manager ___/______

D. V. Goodin SQN Licensing Eng ._

J. D. Smith SQN Licensing &/0 D. L Lundy SQN Engin gr_  % L 6I,r/o3

UCENSING TRANSMITFAL TO NRC SUMIMARY AND CONCURRENCE SHEET THE PURPOSE OF THIS CONCURRENCE SHEET IS TO ASSURE THE ACCURACY AND COMPLETENESS OF TVA SUBMllTALS TO THE NRC.

DATE DUE June 14.2003 NRC SUBMITTAL PREPARED BY Jim Smith

SUBJECT:

American Societv Of Mechanical Engineers (ASME) Section Xl Inservice nspection s) Program -

Relief Requests ITR Required? (2) - YES ZX NO Applicable DCN:

OR Jim Smith / 06/13/03 /

Licensing Date ITR Reviewer Date Verification Required? (3) X YES NO Peer Check Required? (4) X YES _NO Oath orAffirmationRequired? YES E NO If Yes:

New Commitments? YES E NO l Posting Required? YES a NO Peer Checker Date LICENSING BASIS CHANGE - If this submittal requires a change to the licensing basis, a change has been initiated in accordance with NADP-7. DATE A concurrence signature reflects that the signatory has assured that the submittal is appropriate and consistent with TVA Policy, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared.

NAME ORGANIZATION .,<- ,SIGNATURE DATE D. L. Koehl Plant Manager I L A l/4 D. V. Goodin SQN Licensing Eng - I //c/ q J. D. Smith SQN Licensing Supv' V Owl)

D. L. Lundy SQN Enginezili ' / o4 KJ-