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CAROLINA POWER 6 LIGHT COMPAHY

NUCLEAR P3~ ENGLKERING DEPARTMENTPROCEDURE

MANUAL NO.

Number

071

SUBJECT

3.2

DESIGN CHANGE CONTROL

3.2.1 APPLICABILITY

AllNPED personnel (including APED managed contract personnel) who areinvolved with- changes to approved designs for Q-List equipment, systems,structures or other work being performed to meet the requirements of. SSIN45.2.11-1974.

3.2.2 PURPOSE

To specify the procedures to be used to evaluate an'd control changes toapproved designs involved with equipment, systems, structures or other workrequired to be performed in accordance with ANSI N45.2.11-1974.

3. 2.3 GENERAL

The need or reasons for changes to approved designs may be identified, byNPED personnel or ntheu organizations involved in the review, approval oruse of the design documents.

The extent of the design verification required is a function of the im-portance to safety of'he item under consideration, the complexity of thedesign, the degree'f :tandardization, the state of the art and the simi-larity with previously'roven designs: For minor design changes that do

not involve changing the safety review or design calculations or theoqiginal design documents, verification may not be required.

Design changes may be implemented in the field prior to any requiredrevision of the original design documents, based on interim design change,information released by the Assigned Ind'ividual, provided appropriate ~reviews are conducted before final acceptance as permitted by appropyiatesite procedures and/or interface agreements.

Changes to Design Documents prepared by one organization may be authorizedby another (i.e«E CP6L may authorize a change to an AE prepared designdocument or vice versa) as directed by NPED, provided such changes aredeveloped in accordance with approved design change procedures. Theresponsible NPED Supervisor will assure that the alternate design agencypossesses the necessary. background, knowledge, and capability as requiredby ANSI'45.2.11.

3.2.4 DEFINITIONS

3.2.4.1 Field ChangeRequest

8310130294 830919PDR ADOCK 05000400E PDR

A request for deviation from designdrawings'nd/or

specifications normally initiated bythe'mplementing organization prior toimplementation or a request for permanent ~

Rev. 3 ~ 2 1

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FORM 1503E

CAROLINA POWER 6 LIGHT COMPANY

1 lUCLEAR PLANT ENGINEERING DEPARTtiRK'ROCEDURE

MAMJAL NO.

Number3.2

3.2.4.1 Field ChangeRequest(Cont'd)

3.2,.4.3 Interpretation

3.2.4.2 Design Change-Notice

waiver non-conforming items to be "usedas-is." Field Change Requests may utilize an"FCR Form" or other controlled means oftransmission, such as "Field Memos."

r

A r'equest- or notification to change anestablished design document normally initiated,"

~ by the design agency as. a result of designdevelopment or to implement field changes.'

~ Advisory information provided to assist inimplementation of design documents which doesnot violate the limiting criteria set forthin the plant design documents.

3 ~ 2 o 5 PROCEOURE

Action

3.2.5.1 ResponsibleSupervisor

a. Assigns the responsibility for handlingdesign change to appropriate individualor organization cognizant of design

~ requirements.

b. Provides guidance to initiate theevaluation and development of the designchange.

c. '" Provides guidance on the extent ofdesign verification and specifiesadditional reviews desired. ~

3.2.5. 2 Assigned Indi-vidual(s) orOrganization

Performs engineering evaluation ofidentified problem and/or of proposed„design changes. Interpretations:may be .*resolved between the implementing'.:jorganization and.the NPED approvingauthority without creating design changedocumentation for approval or record.

b. Prepares or revises authorizing documents,as necessary, to effect the change.These may be interim or permanentdesign documents, as appropriate.Interim documentation may be in the formof approved Field Change Requests,Design Change Notices, or other locally

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CAROLINA POWER 6 LIGHT COMP~ÃJCLEAR PLANT ENGINEERING DEPARTAEVZ

PROCEDURE

I

MANUAL NO.

Number '.2

Res onsibilit Action

3.2'.5.2 Assigned Indi-vidual(s).orOrganization

authorized mechanisms as provided forin locally (site) approved procedures.

. Where NPED is performing the designchange activity. and permanent documentsare involved, the applicable portionsof NPED Procedure 3.1 apply.

c. Obtains appropriate verifications/reviews.Design change documentation whichchanges the requirements of designspecification or procurement documentsaffecting safety-related, fire protectionand radwaste QA programs must be reviewedby the appropriate QA organizationprior to implementation.

3.2.5.~ ResponsibleSupervisor

',a.I

Reviews design change documents and- any—--reviews/verifications and resolves anyconcerns.

b. Obtains or provides necessary approvalsfor final release of design changedocuments. Level of approval will becommensurate with approval levels ofNPED Procedure 3.1.

Co Ensures that design change documentsare filed and/or distributed as delineatedby applicable site procedures, interfacedocuments or distribution lists.

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Shearon Harris Nuclear Power PlantDraft SER Open Item No. 354NRC Ouestion 210.65

Pi in Stress Analysis Data, Allowable Flange Moments

The Stress Analysis Data package contains sheets showing moments fromCalculation No. 8050-1 and "Allowable Moment"; presumably in units of ft-lb.The allowable moments of 32285 and 64570 apparently were calculated by Eqs.(12) and (13), NC-3658.3 of the present Section III.Eqs. (12) and (13) can be used only if the flanged joint uses high strengthbolts.

(a) What is the basis for the 99214 allowable moment?

(b) Where does the Specification CAR-SH-M»30, Rev. 16 assure that highstrength bolts are used in the flanged joints?

RESPONSE:

(a) The 99214 allowable moment is based on the Level C Service Limit ofNC-3658.3 of the present Section III.

(b) Specification CAR-SH-M-30, Appendix A, General Requirements, Paragr aph VIcalls for use of ASTM A-193, Grade B7 bolting which per ASME-III codeclassification is a high strength bolting material. In addition, thespecification allows the use of ASTM A-307, Grade B material for pipingCategories 6, 7, and 8 with design pressure 250 psig or less and thedesign temperature 450'r less.

The latter material spec (A-307-Grade B) as indicated by the M-30 spec.,has a limited use. This material was used by Southwest Fabricating onlyfor the nonpressure boundary applications. Refer to the below discussionfor more details.

As a followup to this question, the following comments were made by NRC duringthe meeting on August 16, 1983 in Bethesda, MD:

(1) The CAR-SH-M-30 Specification, Appendix A, Paragraphs VIb states:"——conforming to ANSI B18.2.1 heavy dimensions and per ASTM A-193,Grade B7 may be used." The staff requested to revise this sentence toread "——per ASTM A 193, Grade B7 shall be used."

(2) ASTM A-307, Grade B bolting material identified in the CAR-SH-M-30Specification, Appendix A, General Requirement, Paragraph VI C, is not ahigh strength bolting material.

(3) Provide assurance that only high strength bolts are being furnished bySouthwest Fabricating and by field.

(7876FXTccc)

0'RC Question 210.65 (cont'd)

Regarding comment (1), the M-30 Specification will be revised to incorporatethe NRC comment.

Related to comments (2) and (3), the concerns were reviewed with SouthwestFabricating and the field. Southwest position is reflected in the enclosedletter dated August 17, 1983 (Item 3). The procurement of bolting materialsby field is summarized in the enclosed CP&L letter LS-4995, dated August 19,1983.

(7876FXTccc)

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- SQL/THWEST FABRICATING4 SELDlNG CO INC.

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August 22, IM3 S-EB-748

Kbasco Services, Inc.2 Vor)d Trade Center, 81st Floor.'tev York, N 1¹8Attentfont Nr. Pote FLala

Reference: Shezron Harris nuclear Paver PlantP.O. KY-43503$S.O, 3301 3304 and 4121-4)24

Gent)enent

In response to your telephone request ve offer the !ollovfngt

1. Ql;ESTIONt Pov do you assure that niniwn va)1 thickness fs nain-tafned at ccumtcrbored ends.

hÃS'«ERt @nore counter bores are a revuirenent, the counter beredianeter, vali thfckness and tolerances arc specified on Scuthvest'sdetaL1 sheets. Prfor to fLt up'icr "a)ding the pipe ends are counterb'ored to the specified dfnensfon and thi:kncss is checked vith anfcroneter to verify that the thfckhess satis!fes the spe iffed re-qufrement. Since this check is only to"'erf!y that the thickness isaciequate, actus'hicknesses are n:t recorded.

2. 0:ESTI08: «hat tclerance applies at a ccunter bore vhen Ebasco speci-!Les a ninLun valley

A".(S«ER: «hen Kbasco speci!Lcs a nfnfnun vali, the nininum .hicknessalso applies to counter bored ends.

3. 0"ESTICZt «hat spect! ication bolt f-..g s;as urnished bv Southves

A55~H: scut.": es- furnished the gra"e -f materia) specified bvbasco.;ne nest:reaccent) speci!Lcd fs SA-193 37 studs;.L:h SA-19-H nuts !:r press rc bound~''ofnts. A-30I is t.i gra=e c- only s",c'.-fcd r (ac.(ine bolts or ncnpr(((55 e 0 Jnda 'pp peat i ~ ns ~

~ 528 SMrnan St(eet ~ P(0. Boer 9449 ~ HOuSt n. TesaS 7(261-8449 {'3) 928-3451 ~ TAX Q10 ddt-16CC~ ~ li e /rH (~4~ 4

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Ebasco Services. Inc.August 17, 1963Page Tvo

4. Q:KSTZOY: Did Southvest specify corrosion yll,cvance to the manufac- ,turers of veldolet type fittings~

AiS~R: I do not believe corrosion a'.-Iwances "ere a part of thedata furnished to Southvest. If a corrosion allovance vas specified,Southvest vould i=pose the sa"e requirement on manu!acturers of specialfit ings. The vali thicknesses spe ified bv Ebasco are included in

the'equirementsi~posed on our ouppliers.

I trust this vi'I satisfactoril> arsver your questions. CalL if I can beof further help.

ry truly::ours,

;.n E. narrisro)est Nanager

JQ.ecp

boa ~ 3. ~. G~odvfnR. !Ichnally

'c. H. berkeR. P. I mesS. N. Goodvin

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choax Mr. Tialag

Ia response to your telephone ca% ef.hugest 19, 1983, ve cantbat only Sh-193 b-7 etude and 8W194 Credo 2K heavy hex nntsnasd for permanent baltic in aatety-related systems.

Attached is 0 fikxlge cohnSction filspsction fo?gl lfhioh fs needaD ABKE 1hmge connections 5P-129). To date, eervice watereach are the onIy poxxuncaat, safety-related eyoteao that beteboited.

aiOQre yonhave been

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Nocord Seat Code/Heat lo. @alee),Verify Labricant: Taupe, kppiiaatioa. Specie. Tao tractioaa pert maed.Verify Valve/SpccQQfty ?tens PXet Kzacticm~Verify CrieatotLoa of Valve Stae, Operator, Etc.Abave Seto~Var To+pm Qreach Ca1Qe�ate-

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Pi ing Stre'ss Analysis Data, Loads on Pumps Nozzles

The Stress Analysis Data package contains sheets showing loads fromCalculation No. 8050-1 and allowable resultant forces and moments. However,there is no check of combination of thermal, weight and either OBE or DBE. Itwould seem that pump nozzles could be subjected to a combination of theseloads. Why are no combined load checks made? (See also 0210.47)

RESPONSE:

Allowable nozzles loads are specified in Appendix C of the Piping DesignSpecification CAR-SH-M-71. The allowable loads are specified in terms ofcombinations of loads.

The nozzle load sheet conservatively separates these allowable loads intosmaller values applied to uncombined loads for ease of evaluation. If theselower limits are exceeded, then loads are combined and evaluated against thespecification.

To illustrate, please note from the typical values below that thespecification "Normal" limit is equivalent to the load sheet "Thermal" plus"Weight," the "Upset" limit is equivalent to "Normal" plus "Weight" plus "ORE"and so forth.

'YPICALALLOWABLE NOZZLE LOADS

Design Spec M-71

Maximum 0 eratinTem erature 'F140'nd Above

Nozzle Load Sheet

140'nd Above

Operating Condition Loading Case ResultantForce Moment

Normal

Upset

Emergency

Faulted

500A 625Z

700A 875Z

800A 1000Z

900A 1125Z

Thermal

Weight

Seismic OBE

Seismic DBE

Faulted DBE

400A 500Z

100A 135Z

200A 250Z

300A 375Z

400A 500Z

(7876FXTccc)


Pi in Com uter Output (8050-1), Allowable Stress, f ~ 1.0

The allowable stresses agree with generally accepted Section III allowablesfor Class 3 piping, provided f is equal to unity. Where does theSpecification provide the basis for using f 1.0?

RESPONSE:

The stress range reduction factor of f 1.0 is not indicated in thespecification at this time. However, the next general revision of EbascoSpecification CAR-SH-N-71, Design Specification for Piping, will provide areference to the 'f'actor and will indicate that for all piping systems onShearon Harris Project a factor of f 1.0 should be used.

The use of f ~ 1.0 is )ustified by the fact that the total number of fulltemperature cycles over 40 years during which the various, system are expectedto be in service is less than 7,000 cycles. This applies to any system onShearon Harris Project.

(7876FXTccc)

Shearon Harris Nuclear Power Plante 'I

Draft SER Open Item No. 354NRC Ouestion 210.68

Pi ing Computer Output (8050-1), i-factor for Weldolets

Apparently, the i-f~ctors for Weldolets were calculated by the equation:i ~ 0.9[R/(3.3T)l . This formula is not now and never has been inSection III. Provide the basis for the i-factor used for Weldolets. (Theresponse should be cognizant that tests on full outlet Weldolets are notrepresentative of the reduced outlets involved; and tests with moment appliedto the branch are not representative of moments applied to the run.)

RESPONSE:

The i-factors for Weldolets were calculated based on the. stated equation.This formula, which is not in Section III, was derived by Bonney Forge basedon test data and empirical relationships and subsequently verified by WFI fortheir Pipets. To date, only the ANSI B31.3 Code explicitly lists theequation. The i-factor equation is internally stored in the PIPESTRESS2010computer program and is used whenever the analyst designates a tee connectionas a "WELDOLET." The reference for the equation is documented in thePIPESTRESS2010 Verification Manual.

The test method and empirical relationships developed by Bonney Forge areidentical to those employed in the development of the Section III factors forother tee connections. As is true for all tee connections, the testsperformed on full size connections may not be representative of those forreduced outlets, and tests with moments applied to the branch may not berepresentative of tests with moments applied to the run. Nevertheless, all ofthe connections mentioned above have been tested only for full sizes and onlyfor moments applied to the branch.

Because limited test data has indicated the possibility of a generic concernfor reducing tee connections, a cooperative effort of the cognizant ASMF. andPVRC subcommittees is currently reviewing the situation. The recommendationsof that study should then become the basis for any evaluation of reducing teeconnections.

(7876FXTccc)

Shearon Harris Nuclear Power PlantDraft SER Open Item No. 354NRC Question 210.69

Pi ing Computer Output (8050-1), Loading Combinations

The computer output gives stresses for 11 "Cases." Where does theSpecification CAR-SH-M-30, Rev. 16 give the analyst instructions as to whichCases to run and how to evaluate them? See also 0210.47.

RESPONSE:

Instruction regarding the required Cases and their evaluation is provided inthe Hbasco Piping Design Specification, CAR-SH-M-71. See our reply toQuestion No. 210.59.

Also, please refer to the Attachment for the Thermal Mode Diagram and ThermalData for the Service Hater System. This diagram and the data information arealso part of our Piping Design'pecification, CAR-SH-M-71.

(7876FXTccc)

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Pi ing Computer Output (8050-1), Seismic Input Data

Where does the Specification CAR-SH-M-30, Rev. 16 give instructions on how toselect the specific seismic input data for piping system analyses?Appendix F, "Seismic Consideration for Mechanical Equipment" is included inthe Specification but we have not seen any reference to it in the text of theSpecification. For example, Appendix F is not referenced in 3. of Part I orin 23.01 or 23.03 of Part II. Further, 2. of Appendix F says that "Safe'shutdown earthquake loads for all equipment (except as noted in thespecification) are obtained from the attached Floor Response Spectra Curvesfor Horizontal and Vertical Excitation." The "attached" curves are labeled"Typical . . . Spectra" and, despite what Appendix F says, we assume thatthese are not the spectra used in, for example, Calculation No. 8050-1.

RESPONSE:

<

The instructions regarding the specific seismic input data for piping systemanalyses are given in Ebasco Design Specification for Piping, CAR-SH-M-71.Paragraph 6.lla of this specification states: "All piping covered by thisspecification is classified as Seismic Category I which shall be analyzedutilizing the response spectra curves and computer output sheets provided inAppendix A of this specification and the seismic criteria set. forth in theFSAR."

As a sample, we are enclosing for your information and use, the OBE North-South response spectra which was subsequently enveloped for Calc. No. 8050-1.

(7876FXTccc)

ATTACHMENT

~em(ior~ Zlc,7=

2.00 FLOOR SPECTRA AT El. 261.0 HASS PT 4

aeter J@e~ aaldSJNh

1.80

l F60

1 e40

1 .20

t F00

0.80

(S)

C3

I

CZ

lU

tel

47

O.SO

Oo40

0.200"2.0Ã

1 00

~ ~ VV

2 00

C ~ UV

S.onrnerl~~vJ ~ VUmr ni ~~. ~Lr v

10 ~ 00~ +++) ~ .mi)~ ~ 'l/

gg oglglr f.nr

20 00W~ltr

~+CL~ VV

50.00!)IJ olJU

~ ~ ~ ~

t.00

AUX BLDG UNIT I OBE N-S

FLOOR SPECTRA AT El 236.0 tlRSS PT.S

0.90

l

0.80

0.70 3

0.60

0.50

Ooip

V7

C3

a:

UJ

UJL7

G:

0.30

0.20

0. to0=2.0X

00 2.DO >O.OOb 00FREOiiF«rv tCP5)

20 00 SO.OU

I ~ UV~ W 'V & ~ ~~ \ + ~

~ ~ ~ ~ ~

IJ ~

1.00

AUX BLOB UNIT I OSE N-S

FLOOR SPECTRA A> EL 226 0 BASS PT 6

0.90

. 0»80

0.70

0»60

D.SD

0.40

V7

C3

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UJ

K

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'0.70

0.60

0.50

0.40

0.30,

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1 00 r.nn S.oo 10.00FBI: AlJFN[:Y ( CPS )

20 00 50.00


Piping Support Specification, Applicability of Section IIIThe first sentence of 22.05 in Specification CAR-SH-t4-30, Rev. 16 is: "Allsupports and hanger components shall conform to the requirements R/2 of theANSI Code for Pressure Piping, B31.1, and ASNE Section III, asapplicable, . . ." What are the applicable requirements of Section

III'dentifyby Edition/Addendum date and Section III heading identification;e.g., NC-3674 (1971).

RESPONSE:

The original contract for the design and fabrication of pipe supportingelements involved Section III of the ASME Code to the 1971 Edition withAddenda through Summer of 1973. The rules for component supports andcomponent standard supports (Subsection NF) was still in the preparation stage(Ref: NA-2131.b.l 1971 Edition).

Contractual requirements for design and fabrication of pipe supports was,therefore, referenced to the ANS B31.7 and ANSI B31.1 codes which were ineffect at the aforementioned time. In essence, the definitions and referencesmade in the above question were non-existent at the contracted date.

As a side note, the design fabrication process for the vendors standardproduct is to more recent codes (i.e., Subsection NF 1977 Edition).

Welding where performed by the vendors shop is being performed to proceduresqualified to ASIDE Section IX. Inspection is being performed to a contractdocument which incorporated NF 5000 and AWS Dl.l requirements.

(7876FXTccc)

~

~

1


Piping Support Specification, Supplementary Steel Versus Auxiliary SupportingSteel

Paragraph 22.05 of the Specification CAR-SH-N-30, Rev. 16 states that"supplementary steel" shall be in accordance with AWS Dl.l, etc. Paragraph22.16 states that "auxiliary supporting steel" shall be designed on the basisof the allowable stresses as per the AISC specification, etc. What are thedefinitions of "supplementary steel" and "auxiliary supporting steell"

RESPONSE:

The terms "supplementary steel" and "auxiliary supporting steel" as used incontext of the specification CAR-SH-N-30, are synonymous.

The hanger manufacturer (Bergen-Paterson) does not differentiate betweensupplementary steel and auxiliary supporting steel.

All Bergen-Paterson designs of steel structures for pipe hangers, supports,restraints, anchors, etc., are based on the AISC specification. The AWS Dl.lcode does not offer guidelines for the design of structures.

The chapters in the AWS code dealing with existing structures, new buildings,bridges, and tubular structures are only concerned with the welds, welddetails, base metal and welding allowable stresses, fatigue stresses in welds,workmanship and quality of welds.

Except for a limited number of guidelines on welds given in the AISC codewhich do not conflict with the AWS provisions and are only used in the designof structures there is no overlap of the fields covered by the two codes.

(7876FXTccc)


Pi in@ Support Specification CAR-SH-M-30, Rev. 16 (22.14)

When shear lugs or fabricated lugs are used, how are the stresses due to theseattachments evaluated? See NC3645 (1971) and (1980).

RESPONSE:

The stresses for shear lugs and fabricated lugs are evaluated based on theenclosed procedure. This procedure complies with the requirements of theWelding Research Council Bulletin No. 198. The attached procedure wasincorporated into the pipe hanger fabricator (Bergen-Paterson) welded pipeattachment program and is called BPLUG. This procedure is used for evaluatingrun pipe stresses due to integral lug attachments. Stresses within the runpipe wall due to the integral lug attachment can be found by a review of thatprocedure.

(7876FXTccc)

ATTACHMENT

Subject: STRESSES IN ASME CODE CLASS 2 6 3 AND ANSI B31.1PIPES DUE TO LUG ATTACHMENTSHEARON HARRIS NUCLEAR PROJECTS 1 THRU 4 CRL CO ~

The recommended procedure to be used to account for additional stresses

induced in the pipe wall due to the integral lug attachment is outlined

in subsequent paragraphs of this memorandum.

* mgThe following design requirements must be satisfied in order to use this

procedure:

(1) The attachment configuration shall comply with ASME Code, .Section IIIParagraphs NC/ND 3645 and 4433 and Figure 1 of this procedure.

(2) The attachment material, weld material and pipe material shall have»

essentially the same moduli of elasticity and coefficient of thermal

expansion.

(3)f3

m0.3» p >w 0.5 and p p >

—'.075(4) The attachment (lug) is made on straight pipe at a distance greater or

equal to R t from any other discontinuity such as valve, fittings etc.

Where R ~ Mean radius of pipe in inches andm

~ Mall thickness of pipe in inches.

(5) The axis of the attachment is normal to the surface of the run pipe.

(6) The clear distance between the adjacent attachments in the longitudinal

direction is equal or greater than three times R t .

7 7

(7) The clear arc distance (measured along 'the surface of the run pipe)

between the attachments in the circumferential direction is equal or

greater than R t ~m

'8)

D /t < 100 Where D ~ Outside diameter of pipe in inches.0 0

B EVELOBKNT OF STRESS INTENSIFICATION FACTORS

Paragraph NC/ND 3673 (b) of ASME code states that for components not showri

in Pig. NC/ND 3673.2 (b) al, the stress intensification factor may be taken as:

sC K /2»2F~ aaaa(B 1)

Where C2and K2 are stress indices for Class 1 components. Code Case 1745

outlines a method for computing C, C> and C ~ It further recommends tocuse K ~ 1.3 or 2 depending on geometrical configuration of fielded joint.In order to develop required "i" it is assumed that

K ~ K ~ K . Thus>

c

'LL C

0

aaaaaaaaaaa aa aa a aa aaaKr/2 3

/2aaaaaa a-(B 3) and(B +3

/2 aaa aaaaaaa aaaaaaaaa aaaaaaaaaaaaa(B 4)c

Por K ~ K ~ K ~ 1.3 (See figure 1) and the equationsc

given in code case 1745, the Equations (B.2),(B,3) and (B.4) can be

developed as follows:

~5.093 (y ) R A ~ W l.p-aaaa--aa —-aaa(B 5)

g1.74 p p2 p4.74

~ 0.34 P p1.74 2 4.74~ Jls~ 1 0aaaaaaaaaaa(B 6)

'1.3 (.76) g 'l1P3 67

' 1.0C 2

&.506 g 01.9 g 2~ ~3.40 1.0aa —----—a(B.7)

PC~

(-Where

«-(X cos 8+7 sin8) -- (X sin 8- T cos 8)1 21 1 ~ A 1 10

X «X +log1 pl

Yl Y +1oS ya p2

Load !h 80'

0 0

ThrustI t'.2 '0 0 0.05

Longitudinalmoment

I

Circumferentialmoment . 1 ~ 8 40 -0.75 -0.60

I

C NOMENCLATURE:

r « mean pipe radius (In.)~ Same as Rm

t «nominal pipe-vali thickness (in.)

PX,~lr

L/Lland L2 are defined in Fig. 1

L « lesser of L and ta 2

Lb lesser of L and tL lesser of Ll and L2c

Ld greater of Lland L2

4L1 L2 (in. )

4L, L'2 (3 (in.')4L L2)3 (in )

X «1,3 for "ground" fillet velds per Fig. 1

P «range of operating pressure (psi)0

D «outside diameter of pipe (in,)

C HOHENCLATURE: (cont 'd)

M ~ greater of M / L Ld t (1 + L /Ld)and

g/(0.8 + 0.0S ( d/ ))LI

Q ~ Thrust load in pounds. See Fig. 1

Shear Toads in direction 1 end 2 respectively, in pounds ~ See Fig. 11'

M, M., Q~ Moment loads in in-pounds. See Fig. 1Ct

S, S, S, and S ~ Stresses corresponding to Equations 8, 9, 10 andsl'l''e

I ]I) II/)

t8, t9, tlo, tll «.-

ll respectively. For detailed defini.tions refer

to NC/ND Section of ASME Section IIICode. These

stress values are obtained from "PIPESTRESS2010" output.

~ primes are used to indicate these stresses may be

different for different component conditions even

though applicable ASME code equation number is unchanged.

For example Equation (9) is used for evaluation against

normal, upset,emergency and faulted conditions.

~ Subscripts indicate, "total" stress in pipe wall for

ASME code Equations 8, 9, 10, 10a and ll respectively.~ Stresses in psi due to lug against ASME code

Equation 22~u ~ 22~12may be 82 9 ~ 102 10a, 11 and 12

depending on load combinations and component conditions.

D~ COMPUTATION OF ADDITIONAL STRESSES: ~Computation of additional stresses due to lug attachment is to be performed

in the following manner:

Z~ ~ ~T +L Lj + ~c"aA2 ZLL ZA

Repeat (D-1) for each applicable equations

+ ~1J' ~21 +2LL 2LL Tj4

««««««««««eQ ]of Section E as required

Ee COMPUTATION OF TOTAL STRESSES

Total stresses in the pipe wall at the )uncture of pipe and attachment consistof two parts namely (i) stresses in the pipe wall from the output of PIPESTRESS20>0

"or" equivalent and (ii) stresses in the pipe wall as computed in Paragraph (D) ~

hh«J )'( eh p e /"IO - h e«'l4'P" » h ~ 0 ~ ~ ~

7/d -5a

I ~

Eel NORMAL COMPONENT CONDITION.

t8 18 1-8 loO S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Eelel

t9 19 1-9

t10 e10 1-10

tlOa 10a 1-10a

tll tell l«ll

lo2 She ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ eEe2o2

S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Eolo34

3S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oEele4C

S8

+ S 10 «(ah + S ) ~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Eele5a

Either of Equations E.1.3 "or"E.1.5 must be'atisfied.

Only for high energy lines evaluate,0

S12

S9 10 ( 2 Sh+S )o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ eEel ~ 6*

a

E,2 UPSET COMPONiZT CONDITION:

S t9 «S'9 + F'19

St ~ St +Pttl0 e10 1-10

tll t8 tlo

ge5 Sh ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ eEe2el

S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Eel 2a/ (S< + S )o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ eEe2o3h a

Either of Equations E.2.2 "or" Ee2.3 must be satisfied.

Only for high energy lines evaluate,

S t12 S9

+ S la o Oo8 (lo2 S + S )ee ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Ee2o4 *t 0 h a

Eo3 EMERGENCY COMPONENT CONDITION

Stt gg Stl + Pllt9 ol9 1-9

Eo4 fAULTED COMPONENT CONDITION

S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oEo3ol4,

Sttt ~ Sttt + Ptltt9 ol9 1% 4 2.4 Sho ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oEe4el

Wl ~ ".g- ~

p)4/i ge

E.5 For ANSI $31.1 piping compute stresses .for Equatfons B..1 thru 4 and

B.2 1 and 8.2 2

Departmental positfon in evaluating additional stresses in the pipe

vali due to integral attachment is fn progress ~ Considering the critical

importance of the project schedule, thfs interim procedure is to be used

for subject vork and shall not be construed as department's position.

/CHES

'If

calculated stresses exceeds allovable, contact Ebasco prior to modification.

This stress value is used in postulatfng pipe-break location. Even ffcalculated stresses are vithin the allovable stress limit, Piping Engineer

shall make sure that these stress values are vithin the limits to mafntain

the validity of predetermined break location.

~fs procedure does not provide guide lines for evaluating structural

integrity of lugs, veld connectfng pipe and lugs.

~ '~

Q~Me

lo) Graphic representation of Ll,LR w ML Ol~ Oz ~ ona Mg: Lq and L? are tobe measured along .he surface Of the run pipe. Welds or fdiet radii betweenattachment ond pipe ore not to be included.

rftt(b) Ground old or integrally cost altaChments K>~ t.3.

Fig. g NOMENCLATURE ILLUSTRATION

Shearon Harris Nuclear Power Plant0Draft SER Open Item No. 354NRC Ouestion 210.74

Pi in Su ort S ecification CAR-SH-H-30, Rev. 16,(22.08)

The first sentence reads: "The supporting force required and movement at eachhanger location shall be determined by Seller through methods of calculationreviewed by Purchaser." This appears to be contradictory to other portions ofthe Specification where the Purchaser (Ebasco) apparently calculates theforces and movements at each hanger location. What is the intent of thequoted sentence?

RESPONSE:

As noted in Paragraph 23.01 of the Specification, the Purchaser (Ebasco)provides a computer printout to the Seller which contains forces and movementsfor the restraints on the associated isometric(s). This information is listedfor each stress point, in each of three directions, for all the casesanalyzed. The intent of the first sentence of Paragraph 22.08 is to make itthe Seller's responsibility to determine the total resultant forces andmovements upon which to base his design for each hanger. The method ofcalculation to be used by the Seller is described in the response toOuestion 210.76.

(7876pXTccc)


Piping Sup ort Specification CAR-SH-M-30, Rev. 16 (23.03)

The first two sentences read: "Unless otherwise noted, the seismic analysisis based on the 1/2 Safe Shutdown Earthquake. Unless noted differently in theanalysis, the forces imposed on restraints by the Safe Shutdown Earthquake(SSE) are twice the magnitude of those for the 1/2 SSE." Calculation No.8050-1 provides data for OBE and DBE; e.g., Cases'0 and 200. Under whatcircumstances are, the provisions of the quoted sentences applied?

RESPONSE:

Per Ebasco Design Specification CAR-SH-M-71 for Piping, Nuclear Safety Class 2and 3 and ANSI B31.1 (Non Nuclear Safety/Seismic Category I), Page 6,Paragraph 6.11.C, the Safe Shutdown Earthquake (SSE) is conservatively takento be equal to 2 times the Operating Basis Earthquake (OBE). Thus unlessotherwise noted in the analysis, as is the case where Design Basis Earthquake(DBE) loads are given, the provision of the quoted sentences apply.

(7876PXTccc)


Pi ing Support Bergen-Paterson Hanger Sketches

The form sheet used by Bergen-Paterson appears to be inappropriate; variouslines are marked out and relabeled in an inconsistent and partially illegiblemanner. The first two lines of loads (with one exception) agree withCalculation No. 8050-1, Case 41 or Case 1. Some of the other entries agreewith Calculation No. 8050-1, Cases 10, 200, ll or 12. Our copy of CalculationNo. 8050-1. is identified as Rev. 2, 5/5/81, which is apparently the same asused by Bergen-Paterson. Explain the relationship between the Bergen-Patersonloads and those. given in Calculation No. 8050-1.

Having obtained loads from somewhere, Bergen-Paterson presumably combines themin some manner and applies some criteria to select or design the support.Where does Specification CAR-SH-M-30, Rev. 16 prescribe these loadcombinations and criteria? If not contained in the Specification, describethe loading combinations and criteria used for Shearon-Harris supports ofSection III Class 1, 2, and 3 piping.

RESPONSE:

With each isometric/calculation transmitted from the Purchaser (Ebasco) to theSeller (Bergen-Paterson), there is included a cover letter which contains alisting of the items in the particular transmittal, as well as the applicableanalysis cases and the load combination equations to be used. For CalculationNo. 8050-1, Rev. 2 that letter is EB-B-3894, dated June 8, 1981, a copy ofwhich is attached hereto.

The legends which are pre-printed on the Bergen-Paterson forms are not alldirectly applicable to Shearon Harris. Normally, the loads other than weightand thermal for each equation are listed in the order in which each termappears in the equation per the aforementioned letter. For example, SW H 4754/D, 477 5/D, 479 7/E, 481 6/D and 510 3/D have the loads listed in thismanner when compared to Attachment 3 of EB-B-3894. Please note, the sequencein which the load cases appear in the computer print-out is the same as inAttachment 3 and differs from that on the sketches only with respect to weightand thermal, which are clearly labeled on each sketch. When the sequence ofthe loads differs between the Bergen-Paterson sketch and that of the computerprintout, Bergen-Paterson has labeled them with the symbol given inAttachment 2 of EB-B-3894 for the purpose of clarity. (Refer to SW H 23391/B)

For all Bergen«Paterson sketches, the loads to be used are defined by thecases identified in Attachment 2 of the transmittal letter. These loads arethen combined by Bergen-Paterson, per the equations given in Attachment 3, todetermine the largest absolute sum possible for use in their design of thehanger. These combined loads are indicated in the diagram below the table oneach sketch. The loading criteria is given in EB-B-173, dated July 9, 1976, acopy of which is attached hereto. In addition, Specification CAR-SH-M-30,Part II, Page 26, Paragraph 22.05 invokes ASME Section III and MSS-SP-58.

(7876FXTccc)

NRC Question 210.76 (cont'd)

Finally, in cases where the combined loads per the current revision of acalculation are less than those from a previous revision upon which the hangeris designed, Bergen-Paterson adds the following note in lieu of revising theentire table:

"Loads decreased per revised Iso."

Since in these cases the hangers have been designed by Bergen-Paterson toloads higher than those per the latest calculation, their approach isconservative.

i

(7876FXTccc)

ATTACHMENTS

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S

EB-B- 3894~ bc: H Oslick

Q SsablovskiE GebetM Gagliardi/P FialaI GrossB Teverovsky v/att 8 le.Q Shahh BoehmJ GallagherFile CustodianMech File

.~oa SP

3894File: 5Q-H-2

5Q"M30"C

EBASCO

Mr N J NicolichBergen-Paterson Pipesupport Corp50 Clinton StreetHempstead, NY 11550

Dear Mr Nicolich:

Subject: CAROLINA POWER AND LIGHT COMPANYSHEARON HARRIS NUCLEAR POWER PLANTSTRESS ANALYSIS TRANSMITTALP 0 NY-435035

The stress analysis calculations and isometrics transmitted by this letterare listed in Attachment 1. All of these analyses are released for engineer-ing vork. Attachment 2 lists the analyses performed for each calculation andindicates the analysis abbreviation. The load combinations for the design ofhangers and restraints that apply to each calculation are listed in Attach-ment 3. Force components should be added in accordance vith the criterfwgiven at our meeting of April 23, 1976. See EB-B-164, dated May 12, 1976,for the Minutes of the Meeting. The design criteria for the hangers shallbe as given in Letter EB-B-173, dated July 9, 1976.

Very truly yours,

Z GebetAssistant

Prospect

ManagerBT:mcAttachments: Calc: 8050-1

Isos: lA-216-SW-1,2 and 1A-236-SW-14,15 all Rev 2

cc: L 1 LoflinPlant Manager c/o C R GibsonR M ParsonsJ Harris - SWP

P BlouinB BurkhartL H Martin

ES 8 3894

ATTAQ~ 1

Calo Fo. Iso(s Ro.

8050-1

8050-1

8050-1

&050-1

1A«216-SW-1

IA-216-SV-2

1A-236-SV-14

lA-236-SW-15

o, 7(

EB-B- 3894

Calcula tion 8050-1

hnal sis

Thermal (Case 1)

1G Vert Eff/Test Weight(For ref only)

OBE Seis Response (Case 10)

DBE Response (Case 200)

0.3G XYZ Sec Seis Displ (Casell)'YZ

Seis Displ Bldg (Case 12)

XYZ Seis Conn Displ (Case 18)

Wt

OBE

DBE

SSD

SDB

EB-B- 3894

ATTAC~ 3

Calculet oa

AU, piping shova oa this i.soaeMc is "esseat~wl" aad hsa8ers/rcstrai tsshould be desi~ed in accordance with the load coebinat'oas given belav:

~Eua tioa Load ConhiaetfoaRanger/Rest=aint S~ctursl SteelDesi Criteria .Desi+ Criteria

1. T+ Wt MSS-SP-58 S

2 $ T + Wt + OBE

+ SSD + SDB + SCD MSS-SP-58 SX

3. N/A

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5. N/A

6. T+ MT+ DBE

+ 2 (SSD + SDB + SCD) MSS-SP-58 SX

7. N/A

8. N/A

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In our review of your design specifications for ASME Class 1 piping, weexpressed a concern regarding the minimum wall thickness permitted at girthbutt welds. We would expect this minimum to be controlled for shopfabrication by (Westinghouse) Specification G-678843 and/or G-679187. InSpecification G-678843, Section 6.1.7 states: ". . . providing such grindingdoes not infringe on the required minimum wall thickness of. the piping."

(a) Define what is meant by "required minimum wall thickness of thepiping." For example, is it the wall thickness calculated by Eq. (1) orEq. (3) in NB-3600 (1971)?

(b) If the definition of minimum wall thickness is less than (7/8) of thenominal wall thickness used in stresses analyses, indicate whatmodifications to the Stress Indices are used to account for significantlyless-than-nominal wall thickness at girth butt welds.

(c) Indicate what action is required by your specifications should localizedareas of girth butt welds be inadvertently ground beyond the "requiredminimum wall thickness." Is repair welding always required in suchsituations or is further evaluation without repair welding permitted? Ifso, what criteria are applied to determine when repair welding isnecessary.

RESPONSE:

(a) The Shop Fabrication Specification G-678843 references the PipingSpecification G-678866. This piping specification is provided to thepiping assembly fabricator and is referenced in the purchase order as acontract document. Paragraph 3.1.3 of G-678866 defines the calculatedand nominal wall thickness for the cold leg (27 1/2"), hot leg (29") andcrossover leg (31") piping. Please note that Paragraph 3.1.1 of G-678866states that the calculated wall thickness is derived from ASME CodeSection III, Paragraph NB-3641.1(3).

(b) The table in Paragraph 3.1.3 of G-678866 shows that the minimum wallthicknesses are not less than 7/8 of the nominal wall thicknesses.Therefore, modifications to the stress indices based on wall thicknessesat girth butt welds are not necessary.

(c) If the fabricator violates the calculated minimum wall thicknessspecified in Paragraph 3.1.3 of Equipment Specification G-678866, thevendor is required by the contract to file a deviation notice (DN) whichrequests Westinghouse disposition prior to any action being taken by thevendor. It has been Westinghouse policy not to accept a minimum wallthickness violation at a vendor's plant. Westinghouse dispositions ofthese conditions require weld repair of the area to return it tocompliance with the noted specification with subsequent smooth blendingof the area to the surrounding surfaces.

(7876FXTccc)


In our review of your design report for the reactor coolant loop piping, wefound that only Volume 1, "Structural Analysis of the Reactor Coolant Loop forShearon Harris Nuclear Station, Units 1, 2, 3, 4," was available for reviewand that it was preliminary. We were informed that the complete stress reportwould consist of five volumes.

The following information is required to complete our review. Provide aschedule of when the following information will be available for ou" review:

(a) Complete Stress Report (not necessarily final in representing the as-built) of the Reactor Coolant Loop Piping for Shearon Harris.

(b) If not included in the Stress Report, a tabulation of numerical values ofall Stress Indices used in the analysis.

(c)

(a>

I

If Stress Indices are used that are not obtained from Table NB-3683.2-1(1971) or analogous tables from later Code editions, a description of thetechnical basis for those Stress Indices.

If not included in the Stress Report, details of the fatigue evaluationof that location which gives the highest usage factor. Those details areto include pressure ranges, moment ranges, thermal stress ranges and thenumber of assumed cycles of each.

RESPONSE:

A complete stress report for ASME Class 1 components on Shearon Harris will beavailable by December 1984.

At that time, additional details of the analysis such as usage factors, etc.,will be available for review at the Westinghouse files.

(7876FXTccc)

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