ML18018A823

Engineering Procedure 3.2, Design Change Control

ML18018A823
Person / Time
Site:	Harris
Issue date:	08/19/1983
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18018A805	List: ML18018A803 ML18018A808 ML18018A809 ML18018A810 ML18018A811 ML18018A812 ML18018A813 ML18018A814 ML18018A815 ML18018A817 ML18018A818 ML18018A819 ML18018A820 ML18018A821 ML18018A822 ML18018A823 ML20085J680
References
3.2, NUDOCS 8310130294
Download: ML18018A823 (71)

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CAROLINA POWER 6 LIGHT COMPAHY NUCLEAR P3~

ENGLKERING DEPARTMENT PROCEDURE MANUAL NO.

Number 071 SUBJECT 3.2 DESIGN CHANGE CONTROL 3.2.1 APPLICABILITY All NPED personnel (including APED managed contract personnel) who are involved with-changes to approved designs for Q-List equipment,

systems, structures or other work being performed to meet the requirements of. SSI N45.2.11-1974.

3.2.2 PURPOSE To specify the procedures to be used to evaluate an'd control changes to approved designs involved with equipment,

systems, structures or other work required 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, by NPED personnel or ntheu organizations involved in the review, approval or use 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 the

design, 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 the oqiginal design documents, verification may not be required.

Design changes may be implemented in the field prior to any required revision 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 appropyiate site procedures and/or interface agreements.

Changes to Design Documents prepared by one organization may be authorized by another (i.e<<E CP6L may authorize a change to an AE prepared design document or vice versa) as directed by NPED, provided such changes are developed in accordance with approved design change procedures.

The responsible NPED Supervisor will assure that the alternate design agency possesses the necessary.

background, knowledge, and capability as required by ANSI'45.2.11.

3.2.4 DEFINITIONS 3.2.4.1 Field Change Request 8310130294 830919 PDR ADOCK 05000400 E

PDR A request for deviation from design drawings'nd/or specifications normally initiated by the'mplementing organization prior to implementation or a request for permanent

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FORM 1503E CAROLINA POWER 6 LIGHT COMPANY 1 lUCLEAR PLANT ENGINEERING DEPARTtiRK

'ROCEDURE MAMJAL NO.

Number 3.2 3.2.4.1 Field Change Request (Cont'd) 3.2,.4.3 Interpretation 3.2.4.2 Design Change-Notice waiver non-conforming items to be "used as-is."

Field Change Requests may utilize an "FCR Form" or other controlled means of transmission, such as "Field Memos."

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

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

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Advisory information provided to assist in implementation of design documents which does not violate the limiting criteria set forth in the plant design documents.

3 ~ 2 o 5 PROCEOURE Action 3.2.5.1 Responsible Supervisor a.

Assigns the responsibility for handling design change to appropriate individual or organization cognizant of design

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requirements.

b.

Provides guidance to initiate the evaluation and development of the design change.

c. '" Provides guidance on the extent of design verification and specifies additional reviews desired.

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3.2.5. 2 Assigned Indi-vidual(s) or Organization Performs engineering evaluation of identified problem and/or of proposed design changes.

Interpretations:may be resolved between the implementing'.:j organization and.the NPED approving authority without creating design change documentation for approval or record.

b.

Prepares or revises authorizing documents, as necessary, to effect the change.

These may be interim or permanent design documents, as appropriate.

Interim documentation may be in the form of approved Field Change Requests, Design Change Notices, or other locally Rev.

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MANUAL NO.

Number '.2 Res onsibilit Action 3.2'.5.2 Assigned Indi-vidual(s).or Organization authorized mechanisms as provided for in locally (site) approved procedures.

. Where NPED is performing the design change activity. and permanent documents are involved, the applicable portions of NPED Procedure 3.1 apply.

c.

Obtains appropriate verifications/reviews.

Design change documentation which changes the requirements of design specification or procurement documents affecting safety-related, fire protection and radwaste QA programs must be reviewed by the appropriate QA organization prior to implementation.

3.2.5.~

Responsible Supervisor

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I Reviews design change documents and-any--

reviews/verifications and resolves any concerns.

b.

Obtains or provides necessary approvals for final release of design change documents.

Level of approval will be commensurate with approval levels of NPED Procedure 3.1.

Co Ensures that design change documents are filed and/or distributed as delineated by applicable site procedures, interface documents or distribution lists.

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Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Ouestion 210.65 Pi in Stress Analysis Data, Allowable Flange Moments The Stress Analysis Data package contains sheets showing moments from Calculation 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 strength bolts.

(a)

What is the basis for the 99214 allowable moment?

(b)

Where does the Specification CAR-SH-M>>30, Rev.

16 assure that high strength bolts are used in the flanged joints?

RESPONSE

(a)

The 99214 allowable moment is based on the Level C Service Limit of NC-3658.3 of the present Section III.

(b)

Specification CAR-SH-M-30, Appendix A, General Requirements, Paragr aph VI calls for use of ASTM A-193, Grade B7 bolting which per ASME-III code classification is a high strength bolting material.

In addition, the specification allows the use of ASTM A-307, Grade B material for piping Categories 6, 7, and 8 with design pressure 250 psig or less and the design 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 only for the nonpressure boundary applications.

Refer to the below discussion for more details.

As a followup to this question, the following comments were made by NRC during the 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 to read "per ASTM A 193, Grade B7 shall be used."

(2)

ASTM A-307, Grade B bolting material identified in the CAR-SH-M-30 Specification, Appendix A, General Requirement, Paragraph VI C, is not a

high strength bolting material.

(3)

Provide assurance that only high strength bolts are being furnished by Southwest Fabricating and by field.

(7876FXTccc)

0'RC Question 210.65 (cont'd)

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

Related to comments (2) and (3), the concerns were reviewed with Southwest Fabricating and the field.

Southwest position is reflected in the enclosed letter dated August 17, 1983 (Item 3).

The procurement of bolting materials by field is summarized in the enclosed CP&L letter LS-4995, dated August 19, 1983.

(7876FXTccc)

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August 22, IM3 S-EB-748 Kbasco Services, Inc.

2 Vor)d Trade Center, 81st Floor

.'tev York, N 1¹8 Attentfont Nr. Pote FLala

Reference:

Shezron Harris nuclear Paver Plant P.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 bere dianeter, vali thfckness and tolerances arc specified on Scuthvest's detaL1 sheets.

Prfor to fLt up'icr "a)ding the pipe ends are counter b'ored to the specified dfnensfon and thi:kncss is checked vith a nfcroneter to verify that the thfckhess satis!fes the spe iffed re-qufrement.

Since this check is only to"'erf!y that the thickness is aciequate, 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.hickness also 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 bv basco.;ne nest:reaccent) speci!Lcd fs SA-193 37 studs;.L:h SA H nuts !:r press rc bound~ofnts.

A-30I is t.i gra=e c-only s",c'.-

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(ac.(ine bolts or ncnpr(((55 e

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August 17, 1963 Page 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 the data furnished to Southvest.

If a corrosion allovance vas specified, Southvest vould i=pose the sa"e requirement on manu!acturers of special fit ings.

The vali thicknesses spe ified bv Ebasco are included in the'equirements i~posed on our ouppliers.

I trust this vi'I satisfactoril> arsver your questions.

CalL if I can be of further help.

ry truly::ours,

.n E. narris ro)est Nanager JQ.ecp boa

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Tm world Trade Center Sew Torh, Hew York 10048 ChROLIRA PQRR fi LIGHT CCKPJLHf HhRRI8 PROJECT'986-1990 - 1,800 e - dna I ue ~

bOLTIÃQ KCSRXhXa mZOPlmlN AUG ~ 989 EBASGO PROJ. ENG.

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

Attached is 0 fikxlge cohnSction filspsction fo?gl lfhioh fs need aD ABKE 1hmge connections 5P-129).

To date, eervice water each are the onIy poxxuncaat, safety-related eyoteao that bete boited.

aiOQre yon have been to document eid screen been Tours very truly, KN/)am

~httacbnent E, 3h QQ.lett Resident Mechanical Xagineor cc!

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Shearon Harris Nuclear Power Plant Draft SER Open Item No. 354 NRC Ouestion 210.66 Pi ing Stre'ss Analysis Data, Loads on Pumps Nozzles The Stress Analysis Data package contains sheets showing loads from Calculation No.

8050-1 and allowable resultant forces and moments.

However, there is no check of combination of thermal, weight and either OBE or DBE. It would seem that pump nozzles could be subjected to a combination of these loads.

Why are no combined load checks made?

(See also 0210.47)

RESPONSE

Allowable nozzles loads are specified in Appendix C of the Piping Design Specification CAR-SH-M-71.

The allowable loads are specified in terms of combinations of loads.

The nozzle load sheet conservatively separates these allowable loads into smaller values applied to uncombined loads for ease of evaluation.

If these lower limits are

exceeded, then loads are combined and evaluated against the specification.

To illustrate, please note from the typical values below that the specification "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 eratin Tem erature 'F 140'nd Above Nozzle Load Sheet 140'nd Above Operating Condition Loading Case Resultant Force 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)

Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Ouestion 210.67 Pi in Com uter Output (8050-1), Allowable Stress, f ~ 1.0 The allowable stresses agree with generally accepted Section III allowables for Class 3 piping, provided f is equal to unity.

Where does the Specification provide the basis for using f 1.0?

RESPONSE

The stress range reduction factor of f 1.0 is not indicated in the specification at this time.

However, the next general revision of Ebasco Specification CAR-SH-N-71, Design Specification for Piping, will provide a

reference to the 'f'actor and will indicate that for all piping systems on Shearon 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 full temperature cycles over 40 years during which the various, system are expected to be in service is less than 7,000 cycles.

This applies to any system on Shearon Harris Project.

(7876FXTccc)

Shearon Harris Nuclear Power Plant e

'I Draft SER Open Item No.

354 NRC 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 in Section III.

Provide the basis for the i-factor used for Weldolets.

(The response should be cognizant that tests on full outlet Weldolets are not representative of the reduced outlets involved; and tests with moment applied to 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 based on test data and empirical relationships and subsequently verified by WFI for their Pipets.

To date, only the ANSI B31.3 Code explicitly lists the equation.

The i-factor equation is internally stored in the PIPESTRESS2010 computer program and is used whenever the analyst designates a tee connection as a "WELDOLET."

The reference for the equation is documented in the PIPESTRESS2010 Verification Manual.

The test method and empirical relationships developed by Bonney Forge are identical to those employed in the development of the Section III factors for other tee connections.

As is true for all tee connections, the tests performed on full size connections may not be representative of those for reduced outlets, and tests with moments applied to the branch may not be representative of tests with moments applied to the run.

Nevertheless, all of the connections mentioned above have been tested only for full sizes and only for moments applied to the branch.

Because limited test data has indicated the possibility of a generic concern for reducing tee connections, a cooperative effort of the cognizant ASMF. and PVRC subcommittees is currently reviewing the situation.

The recommendations of that study should then become the basis for any evaluation of reducing tee connections.

(7876FXTccc)

Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Question 210.69 Pi ing Computer Output (8050-1), Loading Combinations The computer output gives stresses for 11 "Cases."

Where does the Specification CAR-SH-M-30, Rev.

16 give the analyst instructions as to which Cases to run and how to evaluate them?

See also 0210.47.

RESPONSE

Instruction regarding the required Cases and their evaluation is provided in the Hbasco Piping Design Specification, CAR-SH-M-71.

See our reply to Question No. 210.59.

Also, please refer to the Attachment for the Thermal Mode Diagram and Thermal Data for the Service Hater System.

This diagram and the data information are also part of our Piping Design'pecification, CAR-SH-M-71.

(7876FXTccc)

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Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Ouestion 210.70 Pi ing Computer Output (8050-1),

Seismic Input Data Where does the Specification CAR-SH-M-30, Rev.

16 give instructions on how to select the specific seismic input data for piping system analyses?

Appendix F, "Seismic Consideration for Mechanical Equipment" is included in the Specification but we have not seen any reference to it in the text of the Specification.

For example, Appendix F is not referenced in 3. of Part I or in 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 the specification) are obtained from the attached Floor Response Spectra Curves for Horizontal and Vertical Excitation."

The "attached" curves are labeled "Typical.

. Spectra" and, despite what Appendix F says, we assume that these are not the spectra used in, for example, Calculation No. 8050-1.

RESPONSE

The instructions regarding the specific seismic input data for piping system analyses are given in Ebasco Design Specification for Piping, CAR-SH-M-71.

Paragraph 6.lla of this specification states:

"All piping covered by this specification is classified as Seismic Category I which shall be analyzed utilizing the response spectra curves and computer output sheets provided in Appendix A of this specification and the seismic criteria set. forth in the FSAR."

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 0.20 0"2.0Ã 1

00

~

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~ UV S.on rnerl~~v J

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~ +++) ~.mi)

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~+

CL~

VV 50.00

!)IJ olJU

0)

~

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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 UJ L7 G:

0.30 0.20

0. to 0=2.0X 00 2.DO

>O.OO b 00 FREOiiF<<rv tCP5) 20 00 SO.OU I

~ UV

~

W 'V & ~~~

\\ + ~

~ ~ ~ ~ ~

IJ

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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 CZ UJ K

0>>30 D.2D 0.10 D=2 DI.

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20 00 50.00

Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Ouestion 210.71 Piping Support Specification, Applicability of Section III The first sentence of 22.05 in Specification CAR-SH-t4-30, Rev.

16 is:

"All supports and hanger components shall conform to the requirements R/2 of the ANSI Code for Pressure Piping, B31.1, and ASNE Section III, as applicable, What are the applicable requirements of Section III'dentify by Edition/Addendum date and Section III heading identification; e.g.,

NC-3674 (1971).

RESPONSE

The original contract for the design and fabrication of pipe supporting elements involved Section III of the ASME Code to the 1971 Edition with Addenda through Summer of 1973.

The rules for component supports and component 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 in effect at the aforementioned time.

In essence, the definitions and references made in the above question were non-existent at the contracted date.

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

Welding where performed by the vendors shop is being performed to procedures qualified to ASIDE Section IX.

Inspection is being performed to a contract document which incorporated NF 5000 and AWS Dl.l requirements.

(7876FXTccc)

~

~

1 Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Ouestion 210.72 Piping Support Specification, Supplementary Steel Versus Auxiliary Supporting Steel 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.

Paragraph 22.16 states that "auxiliary supporting steel" shall be designed on the basis of the allowable stresses as per the AISC specification, etc.

What are the definitions of "supplementary steel" and "auxiliary supporting steell"

RESPONSE

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

The hanger manufacturer (Bergen-Paterson) does not differentiate between supplementary 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.l code 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, weld

details, 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 code which do not conflict with the AWS provisions and are only used in the design of structures there is no overlap of the fields covered by the two codes.

(7876FXTccc)

Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Ouestion 210.73 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 these attachments evaluated?

See NC3645 (1971) and (1980).

RESPONSE

The stresses for shear lugs and fabricated lugs are evaluated based on the enclosed procedure.

This procedure complies with the requirements of the Welding Research Council Bulletin No. 198.

The attached procedure was incorporated into the pipe hanger fabricator (Bergen-Paterson) welded pipe attachment program and is called BPLUG.

This procedure is used for evaluating run pipe stresses due to integral lug attachments.

Stresses within the run pipe wall due to the integral lug attachment can be found by a review of that procedure.

(7876FXTccc)

ATTACHMENT

Subject:

STRESSES IN ASME CODE CLASS 2 6 3 AND ANSI B31.1 PIPES DUE TO LUG ATTACHMENT SHEARON 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.

mg The following design requirements must be satisfied in order to use this procedure:

(1)

The attachment configuration shall comply with ASME Code,.Section III Paragraphs 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 and m

~ 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 to c

use 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 aaa Kr/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 equations c

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

p 1.74 2

4.74

~

Jls~

1 0aaaaaaaaaaa(B 6)

'1.3

(.76) g 'l1 P3 67 '

1.0 C

2

&.506 g

0 1.9 g 2~

~3.40 1.0aa ----a(B.7)

PC~

(-

Where

<<-(X cos 8+7 sin8) --

(X sin 8-T cos 8) 1 2

1 1

~

A 1

1 0

X <<X +log 1 pl Yl Y

+1oS ya p2 Load

!h 8

0 0

0 Thrust I

t

'.2 '0 0

0.05 Longitudinal moment I

Circumferential moment

. 1 ~ 8 40

-0.75

-0.60 I

C NOMENCLATURE:

r <<

mean pipe radius (In.) ~ Same as Rm t <<nominal pipe-vali thickness (in.)

P X,~lr L/

Lland L2 are defined in Fig. 1 L

<< lesser of L and t a

2 Lb lesser of L and t L

lesser of Ll and L2 c

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/

))L I

Q ~ Thrust load in pounds.

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

~ See Fig.

1 1'

M, M., Q~ Moment loads in in-pounds.

See Fig. 1 Ct S, S, S, and S

~ Stresses corresponding to Equations 8, 9, 10 and sl'le I ]I) II/)

t8, t9, tlo, tll <<.-

ll respectively.

For detailed defini.tions refer to NC/ND Section of ASME Section III Code.

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"a A2 ZLL ZA Repeat (D-1) for each applicable equations

+ ~1J'

~21

+

2LL 2LL Tj 4

<<<<<<<<<<<<<<<<<<<<eQ ]

of Section E as required Ee COMPUTATION OF TOTAL STRESSES Total stresses in the pipe wall at the )uncture of pipe and attachment consist of 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

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Eolo3 4

3S

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oEele4 C

S 8 + S 10 <<(ah + S ) ~ '

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Eele5 a

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

Only for high energy lines evaluate, 0

S 12 S

9 10

(

2 Sh+S

)o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ eEel ~6*

a E,2 UPSET COMPONiZT CONDITION:

S t9 <<S'9 + F'1 9

St

~ St

+Pt tl0 e10 1-10 tll t8 tlo ge5 Sh ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ eEe2el S

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Eel 2 a

/

(S< + S )o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ eEe2o3 h

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

Only for high energy lines evaluate, S t12 S

9 + S la o

Oo8 (lo2 S

+ S )ee

~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Ee2o4

• t 0 h

a Eo3 EMERGENCY COMPONENT CONDITION Stt gg Stl

+ Pll t9 ol9 1-9 Eo4 fAULTED COMPONENT CONDITION S

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oEo3ol 4,

Sttt

~ Sttt

+ Ptlt t9 ol9 1%

4 2.4 Sho ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oEe4el

Wl

~ ".g-

~

p)4/i g e

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 ff calculated 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 to be measured along.he surface Ofthe run pipe. Welds or fdiet radii between attachment ond pipe ore not to be included.

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

Fig.g NOMENCLATUREILLUSTRATION

Shearon Harris Nuclear Power Plant 0

Draft SER Open Item No.

354 NRC 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 each hanger location shall be determined by Seller through methods of calculation reviewed by Purchaser."

This appears to be contradictory to other portions of the Specification where the Purchaser (Ebasco) apparently calculates the forces and movements at each hanger location.

What is the intent of the quoted 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 movements for the restraints on the associated isometric(s).

This information is listed for each stress point, in each of three directions, for all the cases analyzed.

The intent of the first sentence of Paragraph 22.08 is to make it the Seller's responsibility to determine the total resultant forces and movements upon which to base his design for each hanger.

The method of calculation to be used by the Seller is described in the response to Ouestion 210.76.

(7876pXTccc)

Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Ouestion 210.75 Piping Sup ort Specification CAR-SH-M-30, Rev.

16 (23.03)

The first two sentences read:

"Unless otherwise noted, the seismic analysis is based on the 1/2 Safe Shutdown Earthquake.

Unless noted differently in the

analysis, 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 what circumstances are, the provisions of the quoted sentences applied?

RESPONSE

Per Ebasco Design Specification CAR-SH-M-71 for Piping, Nuclear Safety Class 2

and 3 and ANSI B31.1 (Non Nuclear Safety/Seismic Category I), Page 6, Paragraph 6.11.C, the Safe Shutdown Earthquake (SSE) is conservatively taken to be equal to 2 times the Operating Basis Earthquake (OBE).

Thus unless otherwise noted in the analysis, as is the case where Design Basis Earthquake (DBE) loads are given, the provision of the quoted sentences apply.

(7876PXTccc)

Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Question 210.76 Pi ing Support Bergen-Paterson Hanger Sketches The form sheet used by Bergen-Paterson appears to be inappropriate; various lines are marked out and relabeled in an inconsistent and partially illegible manner.

The first two lines of loads (with one exception) agree with Calculation No. 8050-1, Case 41 or Case 1.

Some of the other entries agree with Calculation No. 8050-1, Cases 10, 200, ll or 12.

Our copy of Calculation No. 8050-1. is identified as Rev. 2, 5/5/81, which is apparently the same as used by Bergen-Paterson.

Explain the relationship between the Bergen-Paterson loads and those. given in Calculation No. 8050-1.

Having obtained loads from somewhere, Bergen-Paterson presumably combines them in some manner and applies some criteria to select or design the support.

Where does Specification CAR-SH-M-30, Rev.

16 prescribe these load combinations and criteria?

If not contained in the Specification, describe the loading combinations and criteria used for Shearon-Harris supports of Section III Class 1, 2, and 3 piping.

RESPONSE

With each isometric/calculation transmitted from the Purchaser (Ebasco) to the Seller (Bergen-Paterson),

there is included a cover letter which contains a

listing of the items in the particular transmittal, as well as the applicable analysis cases and the load combination equations to be used.

For Calculation No. 8050-1, Rev.

2 that letter is EB-B-3894, dated June 8,

1981, a copy of which is attached hereto.

The legends which are pre-printed on the Bergen-Paterson forms are not all directly applicable to Shearon Harris.

Normally, the loads other than weight and thermal for each equation are listed in the order in which each term appears in the equation per the aforementioned letter.

For example, SW H 475 4/D, 477 5/D, 479 7/E, 481 6/D and 510 3/D have the loads listed in this manner when compared to Attachment 3 of EB-B-3894.

Please

note, the sequence in which the load cases appear in the computer print-out is the same as in Attachment 3 and differs from that on the sketches only with respect to weight and thermal, which are clearly labeled on each sketch.

When the sequence of the loads differs between the Bergen-Paterson sketch and that of the computer printout, Bergen-Paterson has labeled them with the symbol given in Attachment 2 of EB-B-3894 for the purpose of clarity.

(Refer to SW H 2339 1/B)

For all Bergen<<Paterson

sketches, the loads to be used are defined by the cases identified in Attachment 2 of the transmittal letter.

These loads are then combined by Bergen-Paterson, per the equations given in Attachment 3, to determine the largest absolute sum possible for use in their design of the hanger.

These combined loads are indicated in the diagram below the table on each sketch.

The loading criteria is given in EB-B-173, dated July 9,

1976, a

copy 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 a calculation are less than those from a previous revision upon which the hanger is designed, Bergen-Paterson adds the following note in lieu of revising the entire table:

"Loads decreased per revised Iso."

Since in these cases the hangers have been designed by Bergen-Paterson to loads higher than those per the latest calculation, their approach is conservative.

i (7876FXTccc)

ATTACHMENTS

~ < ~

S EB-B-3894

~

bc:

H Oslick Q Ssablovski E Gebet M Gagliardi/P Fiala I Gross B Teverovsky v/att 8 le.

Q Shah h Boehm J Gallagher File Custodian Mech File

.~oa SP 3894 File:

5Q-H-2 5Q"M30"C EBASCO Mr N J Nicolich Bergen-Paterson Pipesupport Corp 50 Clinton Street Hempstead, NY 11550

Subject:

CAROLINA POWER AND LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT STRESS ANALYSIS TRANSMITTAL P 0 NY-435035 The stress analysis calculations and isometrics transmitted by this letter are listed in Attachment 1.

All of these analyses are released for engineer-ing vork.

Attachment 2 lists the analyses performed for each calculation and indicates the analysis abbreviation.

The load combinations for the design of hangers and restraints that apply to each calculation are listed in Attach-ment 3.

Force components should be added in accordance vith the criterfw given 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 shall be as given in Letter EB-B-173, dated July 9, 1976.

Very truly yours, Z Gebet Assistant Prospect Manager BT:mc Attachments:

Calc:

8050-1 Isos:

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

cc:

L 1 Loflin Plant Manager c/o C R Gibson R M Parsons J Harris - SWP P Blouin B Burkhart L 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 (Case ll)'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 ts should be desi~ed in accordance with the load coebinat'oas given belav:

~Eua tioa Load Conhiaetfoa Ranger/Rest=aint S~ctursl Steel Desi Criteria

.Desi+ Criteria 1.

T+ Wt MSS-SP-58 S

2 $

T + Wt + OBE

+ SSD + SDB + SCD MSS-SP-58 SX 3.

N/A 4.

N/A 5.

N/A 6.

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+ 2 (SSD + SDB + SCD)

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N/A 8.

N/A

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Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Question 210.77 In our review of your design specifications for ASME Class 1 piping, we expressed a concern regarding the minimum wall thickness permitted at girth butt welds.

We would expect this minimum to be controlled for shop fabrication by (Westinghouse)

Specification G-678843 and/or G-679187.

In Specification G-678843, Section 6.1.7 states:

. providing such grinding does not infringe on the required minimum wall thickness of. the piping."

(a)

Define what is meant by "required minimum wall thickness of the piping."

For example, is it the wall thickness calculated by Eq. (1) or Eq. (3) in NB-3600 (1971)?

(b) If the definition of minimum wall thickness is less than (7/8) of the nominal wall thickness used in stresses

analyses, indicate what modifications to the Stress Indices are used to account for significantly less-than-nominal wall thickness at girth butt welds.

(c)

Indicate what action is required by your specifications should localized areas of girth butt welds be inadvertently ground beyond the "required minimum wall thickness."

Is repair welding always required in such situations or is further evaluation without repair welding permitted?

If so, what criteria are applied to determine when repair welding is necessary.

RESPONSE

(a)

The Shop Fabrication Specification G-678843 references the Piping Specification G-678866.

This piping specification is provided to the piping assembly fabricator and is referenced in the purchase order as a

contract document.

Paragraph 3.1.3 of G-678866 defines the calculated and nominal wall thickness for the cold leg (27 1/2"), hot leg (29") and crossover leg (31") piping.

Please note that Paragraph 3.1.1 of G-678866 states that the calculated wall thickness is derived from ASME Code Section III, Paragraph NB-3641.1(3).

(b)

The table in Paragraph 3.1.3 of G-678866 shows that the minimum wall thicknesses are not less than 7/8 of the nominal wall thicknesses.

Therefore, modifications to the stress indices based on wall thicknesses at girth butt welds are not necessary.

(c) If the fabricator violates the calculated minimum wall thickness specified in Paragraph 3.1.3 of Equipment Specification G-678866, the vendor is required by the contract to file a deviation notice (DN) which requests Westinghouse disposition prior to any action being taken by the vendor.

It has been Westinghouse policy not to accept a minimum wall thickness violation at a vendor's plant.

Westinghouse dispositions of these conditions require weld repair of the area to return it to compliance with the noted specification with subsequent smooth blending of the area to the surrounding surfaces.

(7876FXTccc)

Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Ouestion 210.78 In our review of your design report for the reactor coolant loop piping, we found that only Volume 1, "Structural Analysis of the Reactor Coolant Loop for Shearon Harris Nuclear Station, Units 1, 2, 3, 4," was available for review and that it was preliminary.

We were informed that the complete stress report would consist of five volumes.

The following information is required to complete our review.

Provide a

schedule 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 of all 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 the technical basis for those Stress Indices.

If not included in the Stress Report, details of the fatigue evaluation of that location which gives the highest usage factor.

Those details are to include pressure

ranges, moment ranges, thermal stress ranges and the number of assumed cycles of each.

RESPONSE

A complete stress report for ASME Class 1 components on Shearon Harris will be available 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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