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.

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:

SYSTEM:

8-inch Nominal Pipe Size (NPS), Schedule 40 carbon steel pipe ERCW ASME CODE CLASS:

3 FUNCTION:

CODE REQUIREMENT:

BACKGROUND:

This section of piping returns cooling water to the 1B ERCW discharge header.

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.

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:

ALTERNATIVE REQUIREMENTS:

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.

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' P

A IGNA7TL d

DATE I

/CO4NS6r p&/j~j

____D__iez J

/t, 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 CALC ID TYPE ORG PLANT BRANCH I

Kil IMRD I

RFV I

I '-~~-~-

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

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 DATE I CHECKER SIGNATURE DATE PREPARER PHONE NO.

EDMS ACCESSION NO.

Page 2 of 2 NEDP-2-1 107-09-~~~~~~~

TVA 4032 07-2001 20011 Page ALTERNATE CALCULATION IDENTIFICATION I

L z

w I

39 1

Page 2of 2 NEDP-2-1 0749

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.

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 In the 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:

Checked:

BVX Date:

/#' /:5 Date: -i1 23/L.

Legibility evaluated and accepted for issue.

This applies to all pages.

Signature I

Date This page added by revision 39.

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.

WA 40633 [12-20001 Page 1 of I Page of v

This page replaced by revision 39.

NEDP-2-4 112-04-20001 TVA 40533 12-20001

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 Appendix G Appendix H Evalaion of Temporary Configuration by DCN-M11500 Evaluation of Sampling Une Additon by DCN-Ml 1473 Evaluafion of MIC for Weld 14478-1 R30 XCl 5 0ltq 464 sh*

A PPEN'ax t),p,rEDI K APPED I X p>RM-INWArto~

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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 Page Prepared:

eri tQ5 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

.2 D:= 8.625-in Sh:= 15000-psi Tnom:= 0.322-in d:= D-2 Tnom Design Pressure Outside Diameter of 8" sch 40 Allowable Stress Norninal Pipe Wall Thickness Inside Diameter d= 7.981in Znom:= 0.0982.-

Nominal Section Modulus DT 4 om = 16.813 in

_ D Tuom

,om

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

P-D Tmnh:. 2. (Sh + 0.4 P)

Tmih= 0.046 in This page added by revision 39.

Insed on.3 X TM.

Tmint:=.3 Tnom Tmint = 0.097 in

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

1. Check Equation 8 Stresses based on computer analysis:

stressg:= 869.psi Sustained Stress from TPIPE Post Processor tcd~8:= 0.040.in D - trstg rm8O =

2 Mean Radius rm8 = 4.292 in dinn8:= D tea Znun8:= 0.0982-D Znn8 = 2.305 m i:= 1.000 i75 := 0.75-i ii=.765times i.

i75 = 0.75 sif:= f1> i75,1,i7 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 Eqg:=

2 2

Z-IS D - dmg c

Eag = 14843.053 psi 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 2 of 6 S8:= Sh R;8:=

qg SRg SRg = 0.99

Problem N2-67-3A1 R39 Page t

Prepared:,%

6A-/03 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 i75 := 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 Mcll:=-

i MclI = 7078.449 in. lbf Bending moment due to thermal stresses.

P dminl r Ma sif )

MCI i

-qll := D d

2 +

+-

Eql = 35816.182psi D2 2

.1

~Zmin )

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

Minimum reauired thickness for Ea 11:

SRII := Eql SI SR11 = 0.955 tctll = 0.02in I This page added by revision 39.

Page 3 of 6

Problem N2-67-3A1 R39 Page

, I)

Prepared: t%* 6'/o3-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 tst =0rmgU:=

D -Mean Radius rmgU = 4.271 in 2

djngu:= D - 2 t9U D - dU 3

Zmin9U:= 0.0982-D zmi9uU= 4.712Mn i:= 1.000 i75:= 0.75-i

=.7times i.

i 75= 0.75 sif:= if(1 > i75, 1,i7 5) sif-The SIF used In code equation comparison (.75i or 1.0 which ever is areater) sif= 1 (stress9u). Znom sif Mb9u = 50188.056 i&lbf Bendinc moment due to occasional (OBE) stresses.

P din9U2 MbgU sif Mar sif EqU:=

++

EqgU = 17787.803 psi DE2-_4 n9U2 Zmin9U Zmin9U Eq9u S9U SRgU = 0.988 Equation 9U stresses below allowable of 16440 PsI. Therefore. OK.

Minimum required thickness for Ea 9U:

This page added by revision 39.

Page 4 of 6 testgU = 0.083 in

Problem N2-67-3A1 R39 Page g' Prepared:

4'-1 6/703 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 - dnF 4F 3

Zmn9F = 0.0982-D___

_=

3.434i i:= 1.000 i75:= 0.75i

=.75 times.

i75 = 0.75 sif:= if1 > i75,1,i75) 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 D2 in9F2 Zmin9F Zmin9F Eauation 9F stresses below allowable of 32880 nsi. Therefore, OK.

Minimum required thickness for Eq 9F:

Eq9F SR9F :=

S9F 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 5 of 6 SRgF = 0.985

Problem N2-67-3A1 R39 Page P7 Prepared: AS 6-3-o?

Checked:

6 -/3 I Summary of Tmin Values:

Tmint = 0.097 in L, required for 0.3 x Tnom T-jj required for Hoop Stress testg = 0.04 in testli = 0.02i test9U = 0.083 in test9F = 0.06 in recuired for DW Bendinc Stress recWuired for DW + Thena1 Stress

,required for OBE Bendinq Stress u

required for SSE Bendinc Stress Deterrnine Tmins Based on Actual Piping Stresses Tmin: = if(Tmit> Tmjh, Tmint Tmin Tmm := if(TM > testg, Tmin, test)

Tniin: =

Tmin > etl1, Tmin,testi 1)

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 6 of 6 T inh = 0.046 in

Page 1 of 10 Net Section Evaluation N2-67-3A1 R39 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 tnom:= 0.322-in n:= 20 j:=.. n

- Pipe Outside Radius

- Nominal Pipe Wall Thickness

- Nmber of Constant Thickness Are Segments Used to Model Degradation. The gnd as applied to the piping contains 20 divisions.

Segment Data:

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

L.:=

2.008. in I.500 in 0.250- in 0.500-in 0.250 in 2.008-in 2.008 ir 2.008 in 2.008 in 2.008. in 1.355. in 1.355. in 1.355-in 1.355-in 1.355.in 0.250- in 1.631*in 1.631-in 1.631-in 1.631. in tr.

0.213 in 0.139-in 0.094-in 0.0. in

0. 126-in 0.255 in 0.280. in 0.280-in 0.280. in 0.269 in 0.230 in 0.230- in 0.230-in 0.230- in

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

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

LC := E L i

The total cross section is:

LC = 27.097 in LM := if(trj S 0.0in,L, 0 in)

LMi:= X L j

LMTi = 27.097 in 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 = 27.097 in LT-LC = 0in If LT - Lc is zero the length adjustments are mathematically correct L;tr) taV:=

i LT tav = 0.231 in 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 J:=..n 2j:= (

j' L.

+ T 2.7r rad LT J

ANGLES (radians)

@f,j=

3 2,j 0.466 0.582 0-582 0.64 0.64 0.755 0.755 0.813 0.813 1.279 1.279 1.745 1.745 2.21 2.21 2.676 2.676 3.141 3.141 3.456 3.456 3.77 3.77 4.084 4.084 4.398 4.398 4.712 4.712 4.77 4.77 5.149 This page added by revision 39.

LT:= ELi j

)

360 p:= -

2 ANGLES (degrees) el,j.p =

26.677 33.32 36.642 43.284 46.606 73.283 99.961 126.638 153.316 179.993 197.995 215.997 233.999 252.001 270.003 273.325 THICKNESS (inches)

• 1

_i

=

in 0.187 0.176 0.077 0.088 0.125 0.062 0.011 0.011 0.141 0.19 0.198 0.213 0.216 0.187 0.196 0.196 2,j P =

22.999 44.061 65.124 86.187 107.25 128.312 149.375 170.438 191.5

?12.563 233.626 254.689 275.751 282.031 290.532 296.812 j:= 2.. n el&j: (e1j-

+ L 12.7

Page 3 of 10 Net Section Evaluation N2-67-3A1 R39 Page pLo C. Compute the mean radius (Rm5) for each segment:

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

ANET:= E

[Rm, trj-(E32, j - e 1, j)]

j tr.

Rm. := Ro -

J 2

A 2 ANET = 11.472 mn E. Compute centroid locationsSx and by in the baseline rectangular coordinate system:

x [(Rmf)

• trj-(sin(62,j) - sin(0,J))]

sx:=

ANET

-1.[

[Rmnj) tr; (cos1j)

- 0D#)13,j))lC by:=

ANET Bx = -1.148 in By = 0.288 in 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(E1,j) sin(2 0 2, j) - sin(2e 1, j) 4

+ 2.8y. (ACosj) +

Rm.J BY2-(AOj)l (Rm)2 j i

2

+

sin(2-.2, j) - sin(2.e 1, j) 4 sin(2, j)2 sin(O 1 j) 2 Sx. (ASIN)

Rmj sx.ACOSj - By.ASINj Rmj (Rmj)2 This page added by revision 39.

Prepared 3

Checked

-6,*

0443/2 lx:=I j

2 Iy:=

j iv:=

1 j

-37.209 in4

Page 4 of 10 Net Section Evaluation N2-67-3A1 R39 Page {

Prepared edr 6-1-93 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 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:

D I = 0.375 rad 01 = 21.48 deg C. The angle 0P2 between the Imin axis and the +X axis is determined simply by subtractingz/2 radians:

02:= 01 - 2 02 = -1.196rad 02 = -68.52 deg D. Adjust 0P and 2 to avoid numencal problem with tan (ct2) - O.

SGND1 =

SGN0 2l:= 01-(01)

SGN4b2:= 4DX(1'021)-

SGN02 = -1 P 1 := i(tan(41) > 1.59 105,1.57079 SON01, P1J 02:= if(Jtan(2) > 1.5810,1.57079-SGNO2,0 2,,

This page added by revision 39.

4) = 21.48 deg 02 = -68.52 deg P1 := if(Iy> x,@ + X,)

Al:= ifAI <0.00001 -n, 1

Ain,I)

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 Imin axis.

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 = (Mqt IX

.1..

-6

-6 Adjust nt when mq is small to avoid division by zero:mq:= inlmq < 1.-10,110 mqJ 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)

X2 =3.158 in X2 =-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 Y22 = 3.15 in q

+

2J )

This page added by revision 39.

Page 6 of 10 Net Section Evaluation N2-67-3A1 R39 Page.. 4.i3 Prepared 63-1A-.

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 g

q q

XN := X2 XI q

q q

Y - Axis yp := Yi - YI q

q q

YN = Y2 -YI q

q q

Xp

(-2.906 ),n 8.922 )

XN = ( 3>

-7.13J)

C 7.385 )

P 3.511)i YN = (-8.667 )in

-2.806)

- x distance to 1st intercept pairs

-x distance to 2nd intercept pairs

- y distance to 1st intercept pairs

-y distance to 2nd intercept pairs 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 C2 q:= (XN) 2 (YN 2 C 1 = 7.821 in C2 1=9.198in C 1, 2 = 9.472 in C2,2 = 7547in E. Compute the minimum section modulus about each principal axis:

Clq:= Cq, C2q:= C 2 ZMjN :

Imax 1

max(Cl).

Imin ZN2 =ma(C2)

ZM[NI = 50.149 in3 ZMIN = 37.169 in3 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 Net Section Evaluation N2-67-31 R39 Page L 1\\\\

Prepared..-.

L.03.o 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 41m:

t nom I 4 o P (Ro - nomno apr:=

2 Ro2 - (Ro - tnomf Znom = 72.47 in3 apr =2.024x 103psi 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 sp MS= -8.367 x 10 in lbf SIP' D. Compute bending moment (?u) for piping Equation 9U:

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

(SIF)Znom Mlo = 3.051 x 4 inlbf 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= 17.124 in B. Compute the added pressue area (AP) due to degradation:

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

Fx:= P.E(Ro - tno02 + AP]

Fx= 3.556 x l 4 lbf D. Compute the induced bending moment (04):

Mp := Fx OFF, MP(.4x

°)

lbf q

q Mp in.lb 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 )

This page added by revision 39.

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

Fx Mp +MgF 09F:='-

+ SFM q

q ANET ZMIN q

8.215x 103 C 9F =

psi

<1.026x le4)

D. Equation 10 stress (,0):

0lo = SFMM-q ZMIN q

E. Equation I Istress (

1):

Fx SEFV(MPq + Mg) + S1FM M1O 1l

=-

+

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

08 SR8 := -

Sh SR9U := '- q SR9U = 018 (0.118)

SRU 0.276 )

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 02h3 1.25. Sc + 0.25-Sh QQ3o6 )

SRII:= '

a1 1.25 Sc + 1.25 Sh C. Find maximum stress ratio.

Primay Stesses:

P1 = m(SRg)

P2 := max(SRu)

P3 := mX(SR9F) i := sa

. 4 Pby rv:=

max(P)

This page added by revision 39.

SI=

0.067 )

SRII = 0.069J P1 = 0.128 P2 = 0.327 P3 = 0.285 Pmax =c 0.327 Prepared X45 o

Checked (608.381 )

a10 = 820.83 2)P'

,2528 x 103 )

a11 =

psi 2.59x 103 )

Page 10 of 10 Net Section Evaluation N2-67-3A1 R39 Page P Prepared.... L-o3-L*

Checked A

/7 a Secondary and Primary plus Secondary Stresses:

Ql:= ma(SRIo)

Q2 := 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.

This page added by revision 39.

Prepared ff,,f3>

Checked.

W

///a N2-67-3A1 R39 Evaluation of Through Wall 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 P:= 953.psi t:= 0.322-in DW:= 819 psi Do + (Do t) 4 TH:= 421-psi R = 4.151 in SSE:= 5226-psi S:= P+DW+TH+ SSE twoa:= 1.5-in R

tnin twoa a:=

-2 a= 0.75 in tmin:= 0.097-in r = 42.799 c :=

ac

= 0.058 (3.1416-R) 2 3

A:= -3.26543 + 1.52784r- 0.072698.r + 0.0016011*r B:= 11.36322 - 3.91412.r+ 0.18619.r2 - 0.004099.r 3 2

3 C:= -3.18609 + 3.84763-r- 0.18304-r + 0.00403-r F:=

+A-c 5+BRC.5 +c 3.5 Kl:= 1.4-SF K2:= (3.1416-a)0 5 B = -136.453 C= 142.145 F= 1.65 KI = 1.713 x 104psi K2= 1.535 in0.5 K = 26299.591 psi in0 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.

S= 7419psi A= 54.481 K:= K1-K2

TENNESSEE VALLEY AUTHORITY DIGITAL ULTRASONIC CALIBRATION DATA SHEET I

REPORT NUMER:

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 if I-I M

I I~~~__

I L

r l

~

I

-

=_

I T

I I =I

==

DISPLAY WIDTR.5 inches INSTRUMEb T SETTINGS REFLECTOR REFERECE MEMORY SCAN DIRECT.

NTCH SDE sENsrTvT(

NUMBER I

55 dB I

CIRC

__nla dB n/a

• FEQ:

2-8 MHz

• REJECT: 0 ANGLE:

0 deg

• DAMPING: 1000 ohms DELAY:

0.00 msec-

• PUL?ER. SING ZERO:

6.389 msec FILTER-FDC VELOCITY:

2398 msec

• REP RATE:

IGH RANGE:

.5 inchs TOF: OPEAK 0 FLANK

• DISPLAYMODE: FULL POWER BATTERY DUAL:

ON 0 OFF TCG: OON 0 OFF REF. REFLECTOR: N/A GAIN: N/A dB CALIBRATION TIMES AMPLITUDE: N/A %

METAL PATH: NIg j INIAL TIME:

11:30 FINAL TIME: 1310 VERIFICATION TMES 1)NIA 12)NA 13)NA 4)NA S)NA I 6)NA I 7)NA 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 lo Loco-;te lboard room chillers

~.CMsS~

-p

?tl C6p.JsE3 7 7

c,p g'° E.R AA' MR.

l REVIEWER.

ANI:

LEVEL:

.L l

LEVEL:

ATE:(./A3 PG.:

OF

.100 80 60 40 20 0

W t-G?>3-341 pig

/el.1 I

f

(9 2b nos S

aw (v<)

F~~~~~t

-C 1 6T3 I'

• \\X5 G,,

v% > o

o.

.0

'1W \\

.*o

+0oO i L-S %

.13.,

• f, A

.2O 3

• ZSS U,j.1.

a.

9 cp'I k

w

\\)S)tc-c 1-i W,.16 3:oo

'oo qy o

'. 12o 00o I

v 6

K W; L,

,2.p-D4 I

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

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.

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 Jim Smith NAME

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

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.

ORGANIZATION

,SIGNATURE 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

D. L. Lundy SQN Enginezili

/ o4 KJ-Jim Smith NAME Owl)

DATE