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Forwards Addl Info in Response to SER Confirmatory Item 4 Re Design Documentation of ASME Components.Info Responds to NRC Concerns Identified by 850618 Ltr & Mechanical Engineering Branch Questions 210.80,210.81 & 210.82
	ML18019A400
Person / Time
Site:	Harris
Issue date:	09/26/1985
From:	Zimmerman S; CAROLINA POWER & LIGHT CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	NLS-85-338, NUDOCS 8510010302
	Download: ML18019A400 (235)
	v • d • e

>>

REGUL"- INFORMATION DISTRIBUT YSTEM (RIDS)

Al,CEFSTON NBR:851001030?".'OC DATE: 85/09/26 NOTARIZED: NO DOCKET* 0 Harris Nuclear Power Planti Unit ii Carolina

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FACIL'.5Q>>400 Shearon 05000000

'AUTH'At'lE AUTHOR AFFILlATION ZIMMERMANiS,R, Carolina Power L Light Co, RECIP ~ NAME RECIPIENT AFFILIATION DENTONi H ~ R ~ Of f i ce of Nuc ear Reactor Regul 1 at i one Di*

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SUBJECT:

Forwards addi info in= response to SER Conf irmator y Item- 0 r e design documentation of ASME, components. Info responds to NRC concerns identified by 850618 ltr 8 Mechanical Engineering Branch Questions ?10,80i210 ~ 81 L ?10.82, DISTR'IBUTION CODE! 8001D COPIES RECEIVEDgLTR ENCL -

SIZE; ,,Zm TITLE: Licensing Submittal: PSAR/FSAR Amdts 8, Related Correspondence'OTES>-

REC IP IENT" COPIES'TTR RECIPIENT" COPIES'TTR ID CODE/NAME) ENCL'- ID CODE/NAME" ENCL" NRR/DL/AOL 1 0 NRR LB31 BC 1 0 NRR'B3 LA 1 0 BUCKLEYpB 01. 1 1~ / L1 INTERNAL) ACRS 01- 6 AOM/LFMB ELO/HDSi 1 IE, FILE 1 IE/DEPER/EPB 36 1 IE/DQAVT/QAB21 1 NRR ROEgM ~ L 1 NRR/DE/AEAB 1 NRR/DE/CEB 11<< 1 NRR/DE/EHEB 1 NRR/DE/EQB 131 2 NRR/DE/GB 28 2 NRR/OE/MEB 18 1 NRR/DE/MTEB 17 1 NRR/DE/SAB 24 1 NRR/DE/SGEB 25 1 NRR/OHFS/HFEBOO, 1>> NRR/DHFS/LQB 32 1.

NRR/DHFS/PSRB 1 NRR/DL/SSPB 1, NRR/DSI/AEB 26 1 NRR/DS I/ASB 1 NRR/DSI/CPB 10. 1 NRR/DSI/CSB 09 1 NRR/DS I'/ICSB 16 1 NRR/DS I/METB 12 1 NRR/DSI/PSB 19 NRR/D RAB ?2 1.

NRR/DSI/RSB RGN2 23 1

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CSt5E Carolina Power 8 LIght Company SERIAL: NLS-85-338 SEP 2 61985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. I - DOCKET NO.50-000 ASME DESIGN DOCUMENTATION

Dear Mr. Denton:

Carolina Power R Light Company hereby submits additional information in response to the Shearon Harris Nuclear Power Plant (SHNPP) Safety Evaluation Report (SER)

Confirmatory Item No. 0 concerning design documentation of ASME components. The attached information responds specifically to the NRC concerns identified by letter dated 3une 18, 1985 and to Mechanical Engineering Branch Questions 210.80, 210.81, and 210.82.

If you have any further questions on the subject or require additional information, please contact me.

Yours very truly, r

S . Zi merman ager Nuclear Licensing Section SRZ/mf (19013DK)

Attachment CC: Mr. B. C. Buckley (NRC) Mr. Wells Eddlernan Mr. David Terao (NRC-MEB) Mr. 3ohn D. Runkle Mr. G. F. Maxwell (NRC-SHNPP) Dr. Richard D. Wilson Dr. 3. Nelson Grace (NRC-RII) Mr. G. O. Bright (ASLB)

Mr. Travis Payne (KUDZU) Dr. 3. H. Carpenter (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Mr. 3. L. Kelley (ASLB)

Wake County Public Library SSZOOZOSaa 8so926 I I PDR ADOCK 05000+OOi E PDR LI 411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N. C. 27602

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Shearon Harris Nuclear Power Plant SER Confirmator Item No. 0 Provide revised sections of Volumes 1, 3, and 0 of the Westinghouse piping design report describing the use of non-code stress indices and flexibility factors and a commitment to include three additional sections as described in NRC letter of February 12, 1985, in the final design report.

RESPONSE

In response to NRC's letter dated 3une 18, 1985, "Summary of Audit of Class I Piping Design Report Meeting," CPRL and Westinghouse have reviewed the NRC Findings and confirm that the requested additions to the Design Report (WCAP-9990) will be incorporated into the final design report.

The additions to the Design Report will be as follows:

A. (a) Selection of Corrosion/Erosion Allowance "A" in NB-3601.1: Section 3.2.2 "Pressure" of Volume 1 and Section 3.1.2 "Pressure" of Volume 0 will be expanded to cover the selection of corrosion/erosion allowance "A" of NB-3601.1.

(b) Branch Connections, NB-3603: Section 2 "Criteria" of Volume 3, will be expanded to confirm that the branch connections, nozzle opening, meet the requirements of NB-3603.

(c) Attachments, NB-3605: Attachments will be addressed in Section 0.5 "Welded Attachments" of Volume 0.

(d) Purchased Fittin s, NB-3609: Section 0.6 "Class 1 Fittings" of Volume 0 will be expanded to address compliance with NB-3609 "Pressure Design of Other Piping Products".

For the above changes to the final Design Report, reference will be provided for the detailed evaluations files.

B. An Appendix will be added to Volumes 1, 3, and 0 which provides the files for generic calculations, design and as-built analyses applicable to Shearon Harris. A statement will be added confirming that these files are retained for as long as the Design Report.

C. Section 3, "Loading" of Volumes 1 and 0 will be expanded to cross reference the Design Specification loading requirements (D-Spec. 955239) with the analysis and qualification loading conditions.

(1941JDK/Ai) 85100)pgp>

Shearon Harris Nuclear Power Plant N C(C Your response to Q210.59 requ1res additional information. In our review of your piping design specifications, we were furnished the specification identified as CAR-SH-M-30, "General Power Piping, Nuclear Safety Class I, 2, 3, and Non-nuclear Safety Class Piping." Your response to Q210.59 provided in your 9/19/83 letter indicated that the CAR-SH-M-30 specification when supplemented with CAR-SH-M-71 forms a complete design specification for piping and supports. However, the M-71 specification is not applicable to ASME Class I piping and supports. You have provided the Westinghouse Specification 955239 for Class I piping but appear to have no design specification covering Class I supports (non-NSSS).

a) Provide the design specification for Class I piping supports (not in the Westinghouse scope).

b) Provide the complete design specification CAR-SH-M-71 for our review.

c) Revise page 2 of the M-71 specification (paragraphs 2.00 and 2.06) to accurately state that the design limits and loading combinations for Seismic Category I fluid System Equipment will be in accordance w'ith the FSAR commitment (and not the PSAR commitment as currently stated).

RESPONSE

The above NRC question is based on Revision 0 of specification CAR-SH-M-71. These concerns are addressed in Revision I of the specification as follows:

a) The scope of the specification, on page I, paragraph 1.01, has been revised to clearly indicate that the information necessary for the design and analysis of Safety Class I piping and pipe supports not provided'by the NSSS supplier (Westinghouse) is contained in CAR-SH-M-71. Analysis of Safety Class I piping is discussed in paragraphs 8.01 (page 9a) and 8.08 (page 10). Design criteria for all pipe supports is given in Appendix l.

b) A complete copy of specification CAR-SH-M-71, Revision I is attached.

c) Regulatory Guide I.ff8 is now listed in paragraph 3, page Oa with the other applicable NRC documents. The reference to the PSAR has been removed.

(1941 JDK/mf )

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Pro5ect Identification No. CAR-SH-M-71 EBASCO SERVICES INCORPORATED EBASCO SPECIFICATION DESIGN SPECIFIAiTION FOR AI4~NUCLEAR SAFETY CLASSES Rl 1 ~ 2 6 3 AND ANSI B31 1 NONNUCLEAR SAFETY/SEISMIC CATEGORY I AND SEISMICALLY DESIGNED PIPING AND SUPPORTS PURCHASER : EBASCO SERVICES INCORPORATED AGENT OWNER CAROLINA POWER 6 LIGHT COMPANY OPERATING COMPANY: CAROLINA POWER 6 LIGHT COMPANY PRO JECT -. SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.: NOMINAL MW 950 000 kW PER UNITS Rl i

LOCATION: WAKE COUNTY NORTH CAROLINA SELLER:

"THIS DOCUMENT IS DELIVERED IN ACCORDANCE WITH AND IS SUBJECT TO THE PROVISIONS OF SECTION X OF THE CONTRACT BETWEEN. CAROLINA POWER 6 LIGHT COMPANY AND EBASCO SERVICES INCORPORATED DATED SEPTEMBER 1,1970, AMENDED"~

Rl CPSL Pages 'pproval S ec. Status Date Pre ared B : *<< Date Original '3/II/78 N Battiata/ R J Giorgio A11 Nariani G

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Rev. 1 R C Roeei CE-15983 3/7/85 NCPE No. 11504 cZC~ 3/5/85

Ebasco Specification esign Specification for gllSX.Nuclear Safety Classes 2 & 3 and ANSI B31.1 Non-Nuclear Safety/Seismic i Rl tegory I and Seismically Designed Piping and Supports

~gqlllllllggg Project Identification No CAR-SH-M-7I

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I fN+'0 T S~'Ih Cr lO ~ Prof e ssional Engineering Registration Number 8 3K 4 in the State of North Carolina, certify that this design specification is correct and applicable vith respect to the requirements of Article NA-3250 of the ASME Boiler and Pressure Vessel Code Section III.

~ vaa aaavvaa ~ vaaaa aaall EBASCO SPECIFICATION DESIGN SPECIFICATION FOR +NSXNVCLEAR SAFETY CLASSES 1, 2, & 3 and ANSI B31.1 NON-NVCLEAR SAFETY/SEISMIC CATEGORY I and SEISMICALLY DESIGNED PIPING AND SUPPORTS CONTENTS

~Para ra h ~Pa e Scope 1 1 Definitions 2 2 hpplicable Codes, Standards & Documents 3 4 Environmental Conditions 6 Classification of Piping 5 7 Piping and Support Boundaries 6 8 General Design Requirements 7 8 Specific Design Requirements 8 9a Plant Conditions 9 11 System Conditions 10 11 Quality Assurance Requirements 11 12 Insulation Requirements 12 12 hnalysis of Buried Piping 13 14 Pipe Rupture hnalysis 14 17 Seismic Interaction Study 15 18 hllovablc Pipe Stresses 16 20 APPENDICES (DELETED)

Thermal Mode Diagrams (B-1 thru B'.12,B-12a,B-12b,B-13 thru B-42)

C- Nozzle Loading for System Components and Reactor Coolant Loop Piping (C-1) b- Piping Linc List }364 B070 (D-1)

Reactor Coolant System Design Transients (E-l)

Loading Combinations (F-1 thru F-33)

G Containment Building Displacement (G-I thru G-3)

Piping Supports Load Combination (H-l thru 1-6).

Pipe Support Design Criteria (I-l thru I-19)

Personnel Protection For 2" & Smaller Pipes Inside Containment (Up to 400 F) (J-1 'thru J-14)

Eb sco Specification Specification for $9STNuclear Safety Classes 1 3 and ANSI 831.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports Pro5ect Identification No. CAR-SH-M-71 SCOPE

.01 This specification provides, in accordance with Article NA-3250 "Provisions. of Design Specifications" and related paragraphs of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III (hereinafter referred 'to as ASME Code), the infor-mation required for the design and analysis of Safety Classes 2 & 3 Seismic Category I piping hand supports, and the design and analysis of the piping and pipe supports not provided by the NSSS supplier for Safety Class 1 piping. This specification also provides the information required for the design and analysis of 831.1 Seismic Category I and seismically designed piping and supports. "

.02 Station piping shall be furnished in accordance with Ebasco Purchase Specifications CAR-SH-M30 and CAR-SH-M30A. Instrument tubing and supports shall be furnished in accordance with Ebasco Drawings CAR-2166-$ -429, 431,432 and 434>and Site Specifications 059 & 061~

Hangers and supports for said piping shall be furnished in accordance with Ebasco Purchase Specification CAR-SH>>M30B.

The material, testing, handling, storage, cleanliness and shipping requirements for piping, tubing, and supports are given in the respective specifications and drawings referenced above.

.03 Systems covered under this specification ares Chemical and Volume Control System Sampling System (Nuclear)

Safety In)ection System Condensate System Reactor Coolant System Steam Generator Blowdown System Boron Recycle System Chilled Rater Supply System Containment Spray System Demineralized Vater System Component Cooling Mater System Instrument Air System Residual Heat Removal System Leak Test System Spent Puel Pool Cooling 6 Cleanup Miscellaneous Drain System System Service Mater System Leak Detection System

Ebasco Specification Design Specification for ANSZ Nuclear Safety Claasea 1, 2 & 3 and ANSI $ 31.l Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports Project Identification No. CAR-SH-M-11

1. SCOPE (Cont'd)

.03 (Contsd)

Primary Sampling System Reactor Vessel Level Indication System Rl Hydrogen Sampling System Fire Protection System Post Accident Sampling System Feedvater System Nitrogen System Emergency hir System huxiliary Fccdvater System Scrvicc hir System Main Steam System Screen Mash System Chilled Mater Return System Reste Caa System Fuel Oil System Paste Liquid System Primary Makeup Mater System

.04 hny conflict betveen this specification and any of the reference documents shall be brought to the attention of the Project Mechanical )

Rl Engineering Supervisor for resolution.

2e DEFINITIONS The folloving 4efinitiona apply to the terms listed bclov aa used in this apcciiicationg Rl

~pi ~in - Includes straight pipes, tubes, piping and tubing bends ~

fittingas supporters flangea, gaskets, bolting, and vclded integral attachments. It does not include structures and equipment such ae building frames, valves, pumps, pressure vessels ~

foundations, pcnctratione>expansion joints or piping supports; )

~gu orts - Includes sprtng hangers'onstant support, "mechanical and hydraulic anubbera, rigid hangers, anchors, guides, thermal rcetrainte, seismic restraints, supplementary) steel for pipe supports, attachments for hangers, piping covering protection saddles and fasteners for hangers. It does not include pipe vhip restraints vhich do not restrain thc piping in Normal, Upset or Emergency conditions.

Ebasco Specification Design Specification for &>>Nuclear Safety Classes Rl 2 6 3 and hNSI B31.1 Non-Nuclear Safety/Seismic tegory I and Seismically Designed Piping and Supports Pro)ect Identification No. CAR-SH" M-71

2. DEFINITIONS (Cont'd)

Supplement- - hny structural steel framing betveen thc cxi'sting building ar Steel members, that is required primarily to support the piping.

I Standard h support assembly consisting of onc or more units vhich are Support catalog items aad generally mass produced.

Seismic Cate or I - Piping and supports vhich are designed to vithstand the event. of a Safe Shutdovn Earthquake (SSE) vith-out loss of capability to perform their safety functions.

Seismfcall Desi ncd - Piping aad supports vhose contiaued function are not required but vhose failure could reduce the i Rl functioning of those safety related systems/ I components designated to mitigate the consequences of wn accident to an unacceptable safety level are designed and constructed so that an SSE vould not cause such a failure Essential S stems - Those systems needed to shutdovn the reactor and to mitigate the consequences of a design basis accident vithout off-site paver.

High Energy Piping Those systems, or portions of systems, vhose normal S stems operating conditions exceed 200oF or 275 psig.

Moderate Energy Those systems or portions of systems, vhich are maintained above atmospheric pressure, vhose maximum norma) operating conditions are less than, or equal to, 200 F and 275 psig. In addition, those systems, or portions of systems, vhich exceed either or both of the above conditions but only for a period less than tvo percent of the system normal operating time (not including testing), or arc in operation less than one percent of the plant normal operating time (not including testing), are classified as moderate energy piping systems.

Ebasco Spccificatioa Design Specification for Rl6X.Nuc?ear Safety Classes 2 6 3 and ANSI 331.1 Non-Nuclear Safety/Seismic tegory I and Seismically Designed Piping and Supports Pro)ect Identification No, CAR-SR-M 71 30 APPLICABLE CODES STANDARDS DOCUMENTS 6r DRAWINGS hSME American Society of Mechanical Engineers Boiler and Pressure Vessel Coda.

Section III, Divisioa l, Nuclear Pover Plant Components 1971 Edition*, and Addenda thereto dated as follovsa 6/30/71, 12/31/71, 6/30/72'2/31/72'/30/73o

- For Mechanical snubbers, Section III'ubsection NF, 1977 Edition including Summer 1978 hddenda is applicable. For hydraulic

~ nubbcrs, Section III, Subsection NF, 1980 Edition including hddenda thru Minter 1981 is applicable.

Section ZI Rules for Inservice Inspection for Nuclear Povcr Plant Components. 1977 Edition including hddcnda thru Summer-1978 (as ammended by 10CFR 50.55'l/1/79) ~

ANSI - American National Standards Institute Ml.l - Code for Pover Piping, June 15, 1973 Issue including Addendum dated Junc 30, 1973.

N45.2.11- Quality Assurance Program Requirements for Nuclear Pover Plants, 1974.

N18.2 - Nuclear Safety Criteria for the Design of Stationary Pressurized Mater Reactor Plants, 1973 N18.2a Revision and Addendum to Nuclear Safety Criteria for the Design of Stationary Pressurized Mater Reactor Plants, 1975 hISC - American Institute of Steel Construction Spccificatioa for the Design, Fabrication and Erection of Structural Steel Buildings (Seventh Edition, February 1969, including supplements dated 11/1/70, 12/8/71, 6/12/74) ~

MSS - Manufacturers Standardization Society of the Valve and Fittiags Industry.

SP-58 Pipe Hangers and Supports. (1967 Edition)

-4

Ebasco Specification Design Specification for ANSI Nuclear Safety Classes 1, 2 & 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports ro)ect Identification CAR- SH-M-71 3~ APPLIChBLE CODES STANDARDS DOCUMENTS & DRAWINGS (Cont'd)

USNRC United States Nuclear Regulatory Commission.

NRC Regulatory Guide 1.48,- Design Limits and Loading Revision 0 Combinations for Seismic I Category I Fluid System Equipment NRC Regulatory Guide 1.67, Installation of Ovcrpressure dated 10(73 Protection Devices.

NRC Regulatory Guide 1.29,- Seismic Design Revision 3 Classification NRC Regulatory Guide 1.84 Code Case Acceptability.

NRC Regulatory Guide 1.85 Materials Code Case Acceptance ASME Section III, Division 1 NRC Regulatory Guide 1.92,- Combining Modal Responses Revision 1 and Spatial Components In Seismic Response Analysis-Standard Reviev Plan 3.6.1,- Plant Design for Protection Against Postulated Piping Failures In Fluid Systems Outside Containment.

Standard Reviev Plan 3.6.2,- Determination of Rupture Locations and Dynamic Effects Associated vith thc Postulated Rupture of Piping.

Standard Revicv Plan 3.7 3,- Seismic Subsystem Analysis I

Standard Reviev Plan 3.9.3 ASME Code Class 1, 2 6 3 Components, Component Supports, and Core Support Structures.

a 4a

Ebasco Specification Design Specification for ANSI Nuclear Safety Classes 1, 2 & 3 and hNSI b31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports Project Identification CAR-SH-M-71

3. hPPLIChBLE CODES STANDARDS DOCUMENTS & DRAWINGS (Cont'd)

USNRC United States Nuclear Regulatory Commission (Cont'd}

Branch Technical Position Protection hgainst hPCSB 3-1 Postulated Piping Failures in Fluid Systems Outside Containment, March 1975.

Branch Technical Position Postulated Break and MEB 3-1 Leakage Locations in Fluid System Piping Outside Containment, March 1975.

Site Specificationsc 059 Stainless Steel Flareless Compression Fittings and Tube Fittings for Field Welding ASME Section III, Code Class 2.

061 Stainless Steel Tubing hSME Section III Class 2 For PPC.

- 4b-

Ebasco Specification Design Specification for hhSXAuc2ear Safety Classes 1,2 and ANSI B31.1 Son-Nuclear Safety/Seismic Ca y I and Seismically Designed Piping and Supports Pro5ect Identification No. CAR-SH-M-71 30 APPLICABLE CODES STANDARDS DOCUMENTS 6 DRAWINGS (Cont'd)

WRC - Me%ding Research Council Bulletin No. 107 yhugust 1965 AS - American Melding Society Standard - A2.0-68 Standard Vclding Symbols (1968 Edition)

Dl.l - Structural Melding Code - Steel (1975 Edition including provision from 1982 Edition for tubular steel)

Ebasco Specificationss CAR-SH-M30 General Povcr Piping M30A Heavy Mall Seamless Pipe M30B General Pover Piping (Hangers, Supports 6 Anchors)

M31 Heat, Antisveat and Process Heating Insulation, Non-Nuclear Safety Class.

M54 Nuclear Containment Mechanical Penetrationa, Components and Assemblies. I I

Ebaaco Dravingac CAR-2166-B-429 Ebaaco Instrument Installation Details (%') ~

CAR-2166-B-431 Ebaaco Instrument Installation Details (BOP) ~ ,

CAR-2166-B-432 Ebaaco Instrument Liat vith Data and References (BOP) ~

CAR-2166-B-434 Ebasco Instrument Liat vith Data and References (MP) ~

CAR-2165-G-064 Containment Building Liner Penetrationa (Sheet 1).

CAR-2165-G-065 Containment Building Liner Penetrationa (Sheet 2).

CAR-2165-G-107/S01 - field Installation Tolcrancea for Hangers CAR-2165-G-107/802 - Pield Installation Tolerancca for Piping CAR-2168-G-6091 Standard Details Steel Structural Tolcrances hpplicable Vendor Dravinga oi Components vhich are supplied to the analyst via thc Ebaaco EMDRAC System.

ETR - . 1002 .. Design Considerations for the Protection from the Effects of Pipe Rupture, November 1975 Ebasco Valve and Specialties List - 1364 B069

Kbasco Specification Design Specification for AHSXNuclear Safety Classes Rl 1, 2 & 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports Pro)ec t Ident ification CAR-SH-M 71 No.

30 APPLICABLE CODES STANDARDS DOCUMENTS & DRAWINGS (Cont'd)

NSSS Suppliers Equipment Specifications and Vendor Equipment Design and Seismic Reports which are supplied to the analyst via the Ebasco EHDRAC System.

Westinghouse Overpressure Reports - WCAP-7769 Rev. 1 and Overpressure Protection Report for SHNPP (5farch 1980).

4 ENVIRONMENTAL CONDITIONS

.Ol The environmental conditions to be considered for all piping and supports covered by this specification are as folio@ac Containment Buildin Normal LOCA Stm Line Break a - Peak Temperature 80 - 120oF 252oF 379oF 5 - Peak Pressure Atmosphere 36 ' psig 39.1 psig c - Relative Humidity 100'L 100'X d - Radiation 3.5xl06 Rads 'ntegrated dose for 40 years of normal operation.

1.3xlO 7 Rads Dose one year after the design basis accident Steam Tunnel Normal LOCA Stm Line Break

'a - Peak Temperature lll F 340 F b - Peak Pressure Atmosphere 22 psia c - Relative Humidity 20-90Z 100K d Radiation 1.0x103 Rads Integrated dose for 40 years of normal operation.

2.5xlO 4 Rads Dose one year after the design basis accident

Ebasco Specification Design Specification for )5SXNuclear Safety Classes

), 2 & 3 and ANSI $ 31.1 Non-Nuclear Safety(Sefsmic Category I and Seismically Desfgned Piping and Supports Pro]ect Identification

o. CAR-SH-H 71

4. ENVIROAKNTAL CONDITIONS (Cont'd)

F 01 (Cont'd)

Auxiliar Buildfn Normal LOCh Stm Line Break a Temperature 60 - 104'F 130 F b - Pressure hIH c - Relative Humidity 20-90X 100Z d - Radiation 1.0xlO> Rads Integrated dose for 40 years of normal plant operation 2.7xlO 6 Rads Dose one year after the design basis accident Fuel Handlfn Buildin Normal Stm Line Break a - Temperature 60 104 F 120 F b - Pressure c - Relative Humidity 20-90K 100 d - Radiation 1.0xlO 4 Rads Integfated dose for 40 years of normal plant operation 1.0xlO 3 Rads Dose one year after the design basis accident So CLASSIFICATION OF PIPINC 01 The classification of pfping covered Clas ass 1, 2 or 3, or ANSI 131.1 Non-Nuclear by'this specification as S a e t f

Seismically Designed is identified on the Piping Safety(Seismic Category I or Sfmflarly, the classification of tubing is identified Line List, Appendix D.

Classiffcation System fndicated on Dravfngs 2166B-432 by& the I&C 434.

Xbasco Specification for ]tHSINuclear Safety Classes Specification'esign l 3 and ANSI 531.1 Non-Nuclear Safety/Seismic Rl ry I and Seismically Designed Piping and Supports Project Identification No. CAR-SH-M-71 CLASSIFICATION OF PIPING (Cont'd)

.02 Ebasco categories 1,2 and 3 correspond to Safety Classes 1,2 and 3 respectively, and Seismic Category I. These classifications are determined in accordance vith ANSI N18.2 and N18.2a.

Ebasco categories 4,5,6,7 and 8 are non-nuclear safety and only those lines designated Seismic Category I or seismically designed are covered by this specification.

.03 I&C Safety Classes Nl&N2 correspond to Safety Classes 1&2 Seismic Category I. 'Ihese classifications are determined respectively'nd in accordance vith ANSI N18.2 and N18.2a.

7a

Ebasco Specification Design Specification for ANSI Nuclear Safety Classes 1, 2, 6 3 and ANSI $ 31.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports e ofect Identification

o. CAR"SH-M-71 6~ PIPING AND SUPPORT BOUNDARIES

~ 01 The boundaries of thc piping and supports covered by this specification are defined by the descriptions in hppcndix D, Appendix -5, and as follovss a- Thc first circumferential Joint in velded connections and the attaching veld of MPhs, the connecting veld shall be considered part of the piping.

b- Thc face of the first flange in bolted connections, the bolts shall be considered part of the piping.

c>> The first threaded Joint in screved connections.

d- Boundaries for penetrations arc shovn on Draving C 2165-065.

e- Boundary for instrument tubing ends at the last fitting before the instrument.

f. For supports, the connecting veld to an embedded plate or building structural steel shall be considered vithin thc support boundary.

~ 02 The specific dimensional locations and structural characteristics of all boundaries shall bc obtained from the follovings a- Piping <<From general arrangement dravings, flov diagrams, PSIDs, and applicable vendor dravings.

b- Supports - Embedded plate and structural steel dravings.

.03 hllovable forces and moments at all piping boundaries shall comply vith the requirmcnts ef hppendix C. Forces and moments at all support boundaries shall be vcrificd in accordance vith Paragraph 10 of Appendix I.

7~ GENERAL DESIGN RE UIREMENTS

01. Thc design stress combinations vhich act simultaneously during thc various plant and system operating conditions to be considered in the pipe design and analysis are specifically indicated in the Load Combinations, Appendix F

Ebesco Specification Design Specification for ANSI Nuclear Safety Classes 1, 2, & 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports ProJect Identification No. CAR-SH-M-71

7. GENERAL DESIGN RE UIREMENTS (Cont'd)

02. For the systems covered in the Thermal Mode Diagrams, Appendix 5, the temperatures noted for piping shall be used in all pipe design thermal expansion stress analysis in lieu of the temperatures specified in the Piping I.ine List, Appendix D. For all systems not addressed in Appendix B, the maximum operating temperature listed in Appendix D for that piping shall be used in all pipe design thermal .

expansion stress analysis.

.03 Unless othervise designated in the Load Combinations, Appendix F, the design pressure values given in the Piping Line List, Appdneix D, may be used in lieu of the peak pressure (P max) as allowed by ASME Section III, since the peak pressure and earthquake need not be taken to act concurrently.

.04 For tubing subJect to dynamic conditions (i.e., sampling lines), the process line maximum operating pressure/temperature specified in the Piping Line List, Appendix D shall be applied throughout. For tubing subJect to static conditions (i.e, impluse lines) ~ the process line maximum operating temperature as defined above shall be applied up to the three dimensional clamp only and the process line maximum operating pressure specified in the Piping Line List, Appendix D, shall apply throughout.

Ebssco Specification Design Specification for ANSI Nuclear Safety Classes 1, 2, 6 3 and hNSI B31.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports Pro)ect Identification

o. CAR-SH-8-71

7. GENERAL DESIGN RE UIREMENTS (Cont'd)

.05 Stress analysis of piping shall be performed in accordance vith ASME Section III using a stress range reduction factor (f) equal to 1.0.

.06 Pipe cnd loads imposed by the piping on equipment nossles shall not cxcecd the values given in Appendix C, unless higher loads are approved in 'vriting by the equipment supplier.

.07 Equipmcnt veights, center of gravity and locations and displacements of end connections required for thc design and analysis of the piping covcrcd by this spekification shall bc derived from the respective equipment manufacturers'ravings and specifications.

.08 Operating Basis Earthquake (OBE) and Design Basis Earthquake (DBE) loads shall bc developed from the applicable floor response spectra and anchor movements provided by the Ebasco Civil Department. In the absence of DBE spectra, Safe Shutdovn Earthquake (SSE) loads equal to tvice the OBE Loads shall be used for thc DBE loads.

.09 No reduction in allovablc stress limits shall be considered due to environmental conditions.

.10 Piping systems, or portions of systems, having a natural frequency greater than or equal to 33 Hs may be'considered rigid. In cases vherc the natural frequency ie lese than 33 Hs, a flexibility analysis shall be performed. Thc natural frequency thermal displaccmcnts and analytical model, where applicable, for each are to be obtained from the respective equipment Design or Seismic Report.

Vibration loads are not considered in the initial stress analysis.

Excessive vibrations vill be determined during the thermal expansion and vibration monitoring program at thc site. Items of concern vill be addressed by HPES stress analysis ae they are identified.

.12 Pipe end loads for containment pcnetrations are specified in Ebasco Specification CAR-SH-M54, Part 2 ~ Paragraph 4.06, and on Draving 2165-C-064.

.13 Pipe support design criteria ie given in Appendix I.

.14 Piping euppoitcd from flexible platforms shall bc designed utilising thc applicable floor and vali building response spectra.

Ebasco Specification Desfgn Specificatfon for PHSXNuclear Safety Classes

),2 3 and ANSI $ 31.l Non-Nuclear Safety/Sefsmic Cs y I and Sef smically Designed Pf ping and Supports Pro)ect Identfffcatfon No. CAR-SH-M-7)

8. SPECIFIC DESIGN RE UIREMENTS

.01 All Safety Class 1 piping, except that covered in Paragraph 8.09, shall be analyzed by Ebasco in accordance with ASNE Section III, Subsection NC for the purpose of suggesting support types and locations. The NSSS supplier shall use thfs information as a starting peCnt in performing the Class 1 .analysis for this piping. The NSSS supplier is resoonsible for determining the actual support types and locations and corr correspon ng loads. Upon receipt oi the completed Class 1 analysis, the existing Class 1 piping supports shall be evaluated and revised @here necessary.

-9a-

Ebasco Specification Design Specification for DNSXNuclear Safety Classes Rl 1, 2 6 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports oject Identification No. CAR-SH-M-71

8. SPECIFIC DESIGN RE UIREMENTS (Cont'd)

.02 hll Safety Class 2 piping shall be analyzed in accordance vith ASME Section III,.Subsection NC.

.03 All Safety Class 3 piping shall be analyzed in accordance vith hSME Section III, Subsection ND.

.04 hll ANSI B31.1/Seismic Category I piping shall be analyzed in accordance vith ASME Section III, Subyection ND.

.05 hll ANSI B31.1/Seismically Designed piping shall be analyzed in accordance vith ASME Section III, Subsection ND.

~ 06 In the case of non-Seismic Category I piping attached to Seismic Category I piping, the dynamic effects were included in the modeling of the Seismic Category I piping up to the first anchor or system of restraints vhich decouplcs the piping.

.07 (DELEIED)

.08 hll piping and supports exposed to external vind forces shall be evaluated.

vith regard to thc plant safety features t'o isolate the containment and safely shutdovn the plant. Any line vhose loss vill ieopardize these plant safety features shall be analyzed and designed for tornado/hurricane.

~ nd vind loads or protected from same by means such ae shields or :,

barriers. Lines requiring said analysis are identified in the Loading Combinations, Appendix F, 'along vith the applicable loads.

The Design Basis Tornado/Hurricane and Vind Loads (DBT) are not assumed to act concurrently vith a seismic event. Rather the DBT Loads are to bc compared to the seismic loads to determine vhich is greater and therefore, should be used for design purposes. DBT loads are not to be considered for the Faulted Plant Condition unless the piping is required to provide a lbag term core cooling folloving a LOCA.

~ 09 The seal vatcr bypass lines to the reactor coolant pumps are qualified to Safety Class 2 rules and are therefore, to be analyzed by Ebasco in accordance vith ASME Section III, Subsection NC.

.10 The vali thickness/schedule specified in the Piping Line List, Appendix D, includes an allowance for corrosion/erosion as necessary.

Ebasco Specification Design Specification for ANSZNuclear Safety Classes R1 1, 2 & 3 and ANSI 531.1 Non-Nuc!ear Safety/Seismic Category I and Seismically Designed Piping and Supports ro)ect Identification

o. CAR- SH-M-71

9. PLANT CONDITIONS

01. Normal Conditions Any condition in the course of system start-up, operation in the design power range and system sbutdovn, in the absence oi Upset, Emergency or Faulted conditions.

.02 U set Conditions Any deviations from Normal Condition anticipated to occur often enough chat design should include a capability to vithstand thc conditions vithout operational impairment. The Upset Condition includes those transients caused in a system component requiring its iso1ation from the system, transients due to a loss of load or P over and an s stem u set not resulting in a forced outage.

Thc Upset Conditions include the effect of tbe specified earthquake for vhich the l~

system must remain operational or must regain its operational status.

.03 Emer enc Conditions Any deviations from Normal Conditions vbich require shutdown for correction of the conditions or repair of damage in the system. Thc conditions have a lov probability of occurrence but arc included to provide assurance that no gross loss of structural integrity vill result as a concomitant effect of any damage developed in the system. Thc total number oi postualted occurrences for such events shall not cxcecd tvcnty-five (25) for the life of the plant. (RX

.04 Faulted Conditions Those combinations of conditions associated vith extremely lov probability postulated events vhose consequences are such that the integrity and operability of the nuclear energy system may be impaired to the extent vbere considerations of public health and safety arc involved. Such considerations require compliance vith safety criteria as may be specified by )urisdictional authorities. Among thc Faulted Conditions may be a specified, earthquake for vhich safe shutdovn is required..

SYSTEM CONDITIONS System design stress requirements for piping for specified plant conditions are indicated in the load combinations presented in Appendix F. The allow-able stresses for support members are given in Appendix I.

Kbasco Specificatfon n Specification for /f57 Nuclear Safety Classes 3 and ANSI 531. 1 Non-Nuclear Saic ty/Se fsmf c gory I and Seismically Designed Piping and Supports Project Ident iffcation No. CAR-SH-M-71 11 'ALITY ASSURANCE RE UIREMENTS The quality assurance requirements for the design and analysis of piping and supports covered by thfs specification, as defined in Paragraph 1.01, shall comply vith ANSI N45.2.11 'uality Assurance Program Requirements for thc 5esign of Nuclear Pover Plants.

12. INSULATION RE UIREMENTS F 01 The Piping Line List, hppendix D, indicates vhich piping requires insulation. The insulating material for all piping located outside containment shall limit the heat loss during maximum operating temperature conditfons to not morc than 65 STU/HR-SQ FT of outcr surface of insulation. The appropriate insulation thickness for each pipe located outside containment is to be determined from the Piping Line List, hppendix D.

For pipfng 2 inches and smaller located inside containment vith a maximum operating temperature of 400 F or less, no insulation 3Q is required. Personnel protection from this piping is achieved by the installation of a pipe shield around the hot surfaces I vhere personnel are most likely to be, i.e., near access platforms, valkvays ~ etc'he pipe shield system is fabricated from type 304 expanded stainless steel and designed for total and rapid removal and replacement. The positive lockfng buckles for these pipe shields are seismically qualified. Details of this personnil protection are given fn hppendix J, Personnel Protection for 2" and Smaller Pipes Inside Containment (Up to 4PPOF) ~

All other piping inside containment vhich requires insulation shall have reflective type insulation of the thickness specified in Table 12.1, vith thc corresponding veight identified in Table 12.2.

Ebaaco Specification Design Specification for gflSZ Nuc?ear Safety Classes

~ 2 i 3 and ANSI B31.1 Non-Nuclear Safety/Seismic I

tegory and Seismically Designed Piping and Supports Rl Project Identification Ho. CAR-SH-M-71

12. INSULATION (&nt'd)

.02 Insulation fo'r piping systems shall be as follovac a~ REFLECTIVE - For all piping inside of Containment.

b. COMPOSITE For piping subjected to inservice inspection in accordance with ASME Section XI (as identified in Ebasco Specification M-30, Appendix D) outside of Containment

c. CONVENTIONAL - Piping not subject to inaervice inspection outside of Containment.

d. Chilled vater system piping shall be provided vith ~ fiber glass pipe insulation vith an all purpose vapor barrier jacket consisting Rl of vhite paper surface bonded to aluminum foil and reinforced vith a fiber glass yarn. An adhesive vill be needed to seal the jacket.

I.ap shall be reinforced vith FSKL tape or approved equal. The insulation shall have a thermal conductivity of 0.23 BTU/oF-Hr-Ft2/In at 75oF mean temperature.

Based on the above the piping insulation shall be:

i) I inch for pipes up to 1-inch ii) 1 1/2 inch for pipes 1-inch up to 4-inch iii) 2 inch for pipes 6-inch and larger

.03 Details of pipe insulation are covered in Ebaaco Specification M-31.

.04 Insulation requirements for tubing are detailed on drawing CAR-2166-B-431.

-12a-

Ebasco Specification ll Design Specification for QNSc Nuclear Safety Classes ~ ~

1, 2 6 3 and ANSI B31.1 Non-Nuclear Safety/Seismic

~

Category I ~ ~ ~ ~

and Seismically Designed Piping and Supports

~

Rl Project Identification

~ ~

Ho.~ CAR-SH-M-71 l2. INSULATION (Cont'd)

TABLE 12.1

,INSULATIOH THICKNESS (IN.) INSIDE CONTAINMENT MAXIMUM OPERATING TEMPERATURE ( F) 140- 201- 251- 301- 351- 401- 451- 501- 551- 601- 651-200 250 300 350 400 450 500 550 600 650 700 3/4 NONE NONE NONE NONE NONE 0. 975 0. 975 0. 975 0.975 1.475 1.475

l. 0 HONE NONE NONE NONE NONE I 343 1.343 1.343 1.343 1.343 1.343

2. 0 HONE NONE NONE NONE NONE 1. 313 1.313 1.3.3 1.313 1.313 1.313 3.0 I 250

~ 1.250 1 ~ 250 l. 250 1. 250 1.750 1.750 1.750 1+750 2.250 2e250

4. 0 I 250

~ 1. 250 I ~ 250 1.250 I ~ 250 1.750 1. 750 1.750 1,750 2.750 2.750,'.188 6.0 I 188 1.188 I ~ 188 1.688 l. 688 2.188 2, 688 2. 688 2 ~ 688 3. 188 j 8..188 1.188 1.188 1. 688 1. 688 2.188 2 '88 2.688 3.6SB 3.688 3. 688

0. 0 1. 125 1. 125 1.125 1. 625 2. 125 2. 125 2. 625 3, 125 3, 625 4, 125 5. 125.

I 125 I ~ 125 I ~ 125 1. 625 2 ~ 125 2. 125 2 ~ 625 3. 125 3. 625 4. 125 5.125 '.0 4 0 1.500 1.500 1.500 1. 500 2 ~ 000 2 ~ 500 2 ~ 500 3 ~ 500 4y 000 4 500 5, 000 6.0 I 500 1.500 1+500 1,500 2,000 2 500 2.500 3.500 4.000 4.500 5.500 3.0 l. 500 1.500 1.500 I ~ 500 2.000 2.500 2.500 3.500 4,000 4.500 5.500

).0 1+500 1+500 1+500 1.500 2,000 2,500 3.000 3.500 4.000 4.500 5.500;

'..0 1.500 1.500 1.500 I ~ 500 2.000 2.500 F 000 4,000 4.50O 5

~ 0 I 500

~ 1,500 1.500 1 500 2o 000 2 '00 3.000 3. 500 4.noo 5.000 500'.500

'~500

..0 1.500 1.500 1.500 1.500 2,000 2.500 3 ~ 000 3 ~ 500 4.500 5. 000 5. 500, i

3.0 I 500 1,500 1,500 I 500 2.000 2 ~ 500 3.000 3.500 4.500 5.000 6.000 i

),0 1.500 1.500 1.500 I 500 2. 000 2. 500 3, 000 3 ~ 500 4.500 5,000 6.ooo i

?~ 0 I 500 I ~ 500 lo500 . I.500 2 ~ 000 2 ~ 500 3.000 3.500 4 500 5.000 '.000 ~

i ~ 0 1. 500 1.500 1.500 1.500 2. 000 2.500 F 000 3.500 4.500 5.500 6.500

)

?~ 0 I ~ 500 1,500 1.500 1.500 F 000 2,500 3.000 3.500 4.5oo 5.500 6.500

t Eb o Specification Specification for pgcT.Nuclear Safety Classes 1, 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports Pro)ect Identification No. CAR-SH-M-71 TABLE 12.2 INSULATION WEIGHT (LBS PER FT.) INSIDE CONTAINMENT MAXIMUM OPERATING TEMPERATURE ~oF

$ 40- I0$ I5$ 50$ S5$ 40$ 0$ 50$ 55$ 401 451 F00 ISO 500 550 400 450 500 550 400 450 700 II4 $ .5 1.5 $ .5 $ .5 R.!

5.0 $ .7 $ .7 $ .7 5.7 I.4 R. ~

I.O t.S I.S t.S I.S I.S I.S 3.0 S.i I.O I~ 5 ~ 5 0 5 0 5 0 5 5 S 5 4.0 4.0 4.0 I.I 4.0 4.0 4.0 4. ~ 7.5 7.5 S.S 4.5 4.5 I.I t.O t.O 0.0 $ 0.5 $ 0.5 I.O 7.0 7.0 7.0 I.O t.0 10.0 $ 0.5 11.5 $ 5.0 $ 4.0 $ 4.0

$ 0. ~ I.O ~ .0 I. ~ t.5 $$ .0 $ $ .5 $ R.O $ 4.5 $ 5. ~ $ 7.0 it.0 SI.D $ 0.0 $ 0.0 10.0 $ 1.0 $ R.I $ 5.0 $ 4.0 $ 4.0 $ 7.0 it.0 I1.5

$ 4.0 $ 1.5 $ 1.5 $ 1.5 $ 1.5 $ 4. ~ $ 5. ~ $ 5.5 $ 5.0 IO.O I1.0 t3.5

$ 4.0 $ 5.0 $ 3.0 $ 5.0 $ 4.0. $ 5.S $ 4.5 $ 7.5 IO.O t2.0 I4.5 IT.O

$ 0.0 14.I $ 4.I $ 4.I $ 4.0 $ 7. ~ $ 0.0 it.O I$ .5 t4.0 tT.O Rt.5 IO.O $ 5.O $ 5. ~ $ 5.I $ 7.5 it.o it.I Ia.o Ia.o <<. ~ It.O II.O tR.O $ 7.5 $ 7.5 $ 7.5 it.~ tO.I I1.5 I4.0 IS. ~ t1. ~ 51.0 55.5 t4.0 it.O it;0.. it;0 tD.S tR.O Ri.O t4.0 IT.O 50.0 $ 4.5 57.5 t4.0 t0.5 t0.5 IO.S RR.O t$ .5 R4.t ST.S SO.S 55.5 ST.O 40. ~

Se.o IR.O S8.0 tR.O t5.5 IS.O t4.5 It.S It.O 04.0 St.O 44.0 t1.5 t3.5 t5.5 lb.0 IT.O tS.O 51. ~ 54.5 57.5 '41.5 44.0 t5.0 t5.0 t5.0 IT.O te.t tt.S 3.0. 54.5 40.0 4$ .5 4I 5 ea.o ai.o ae.o ee.o 5O.D 51.5 53.0 545 4OS 445 5@0 400

<2.0 $ 3.0 IS.O 53.0 55.0 57.0 5t.h 44.5 51.5 57.5 41.5 13a

Ebasco Specification Design Specification for A/5T Nuclear Safety Classes Rl 1, 2 & 3 and hNSI $ 31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports t

rojcct Identification

o. CAR-SH-M-11

13. hNhLYSIS OF SURXED PIPING

.01 Seismic analysis of Seismic Category I buried piping shall be based upon Nevmark'a method, "Earthquake Response hnalysia of Reactor Structur c urea and Hetenyi s theory, tfSeams on Elastic Foundations". Thc analysis shall include calculation of atrcaecs in thc buried portion of the piping due to loads acting on the nonburied portion of the piping inside the building (interaction effect), superimposed on the stresses duc to various loads acting on the buried portion of the piping. Thc resultant stresses shall be vithin the ~ Ilovable stress criteria of the applicable portion of hSME Section III.

.02 Settlement in the backfill vill not filIalong the piping due to differential depth of cause any significant etressea in the piping.

.03 ht points vhere piping leaves the ground and ia attached to structures, the maximum possible differential movement betveen the ground and the structure shall be determined. The differential movement must be absorbed either by providing sufficient flexibility in the piping from the ground to the structure, or by the uae of flexible joints in the piping.

.04 In instances vhere piping vhich enters atructurca ie supported or anchored vithin the structure and not at the vali penetration, the vali penetration must be aised to provide sufficient room for differential pipe movement.

.05 Thc excavated area under the 30 in. and 8 in. service vater pipe lines, bctvecn the Tank Suilding and Turbine Suilding valle and the rock or natural ground, vae backfilled vith concrete vhich vill have insignificant differential settlement.

06 The fill in the yard area supporting Seismic Category subject to iiquefaction during a seismic event I piping ia not

.07 For the analysis of Seismic Category I pipes buried in fill in the yard the folloving properties are to be usedc Soil Density (pcf) 135 Soil Subgrade Modulus (lb /eq. in/in) 50 Pressure Wave Velocity (fps) 1500 Coefficient of Friction 0.2 Maximum Velocity of Free Field Earthquake Motion (ft/sec.) 0.09 Maximum hcceleration of Free Field Earthquake Motion (ft/sec sq) 3.8 Velocity of Compressional Wave Propagation in Soil (fps) 2300 Velocity of Shear Wave Propagation in Soil (fps) 870

<<14-

Eba'sco Specification Design Specification for. WMNuclear Safety Classes Rl 1, 2 & 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports i ro)ect Identification

o. CAR-SH-M-71

13. ANALYSIS OF BURIED PIPING (Cont'd)

.08 Field tests to determine the moisture content and density of the vere performed on the five types of random fill fill prior to construction in order to develop the construction procedure and also during actual placement. hverage values of the test results are given beloved fill Type ls Brovn clayey silt vith yellov silty claya Dry Density 114 pcf Moisture Content 10 percent Compaction 97 percent maximum standard proctor density Type 2i Brovn clayey (sandy) silt vith pieces of siltstone and some sandstones Dry Density 125 pcf Moisture Content 7 percent jR1 Compaction 98 percent maximum standard proctor density Type 3a Brovn clayey silt vith yellov silty clays Dry Density 117 pcf Moisture Content 13 percent Compaction 99 percent maximum standard proctor density Type 4e Brovn clayey silt vith pieces of siltstone (rock sised up in.)e Dry Density 127 pcf Moisture Content 7.5 percent

.Compaction 98 percent maximum standard proctor density

Ebesco Specification Design Specification for @~Nuclear Safety Classes 1, 2 & 3 and hNSI B31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports ro)ect Identification

o. ChR-SH-M-71

13. hNhLYSIS Oi BURIED PIPING (Cont'd)

F 08 (Cont'd)

Type 5c Brovn siltstone (rock aired up to 21 in.)e Dry Density 136 pcf from test section fill Moisture Content 4.5 percent Ebesco Specification Design Specification for ASS~ Nuclear Safety Classes 1,2, 6 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports rojcct Identification

o. CAR-SH-M-71

14. PIPE RUPTURE ANALYSIS

.01 Thc capability to safely shutdovn the plant and maintain a cold shutdovn condition must not be impaired by the effects oi the postulated pipe breaks. This is accomplished by a combination of design features such as separation, barriers and pipe vhip restraints. After a postulated pipe break event, the consequences are considered to be>

a. Pipe vhip

b. Jet impingement

c. Compartment pressurisation

d. Compartment flooding

c. High temperature/high humidity environment

.02 The criteria used for the protection against dynamic effects associated vith postulated pipe rupture are as follovss

a. Branch Technical Position APCSB 3-1

b. Branch Technical Position MEB 3-1 C. ETR-1002

.03 Main steam and fecdvater piping bctvcen the containment penetration and the pipe rupture restraint system outside containmcnt are not subJect to thc postulation of pipe breaks.

.04 In conducting the pipe rupture analysis, the folloving assumptions arc uscds a~ If thc postulated pipe failure results in an automatic separation of thc turbine generator from the pover grid, or results in an automatic reactor trip, then offsite pover is assumed to bc unavailable.

b. Xf thc postulated pipe fiilure requires safety system response to the event, thc analysis assumes a single active component failure in either the safety systems required to mitigate the consequences of the event or their auxiliary supporting features except as noted in item 14.04d The single active failure is in addition to the postulated pipe failure and any direct consequence of the piping failure.

co Operator action to mitigate the consequences of the postulated pipe failure is analyscd for each specific event. The feasibility of initiating operator actions on a timely basis, as vcll as the accessibility provided to allov the operator actions, is demonstrated.

Ebaeco Specification Design Specification for Ah!SX Nuclear Safety Claeeee 1, 2 6 3 and hNSI 531.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports roject Identification No. ChR-SH-N-71

14. PIPE RUPTURE hNhLYSIS (Cont'd)

d. Mhere the postulated piping failure is assumed to occur in one of tvo or more redundant trains of a dual purpose moderate energy ceecntial system (i.e., one required to operate during normal plant conditions ae veil as to ehutdovn the reactor and mitigate the consequences of the piping failure), single failures of components in the other train or trains of that system only arc not assumed, provided the system ie designed to Seismic Category I standards's povcred from both offeite and oneite sources, and ie constructed, operated and inspected to quality assurance, testing, and ineervice inspection standards appropriate for nuclear safety systems.

e. hn unrestrained vhipping pipe is considcrcd capable of<

i) Rupturing impacted pipes of smaller nominal pipe eiecs, and ii) Developing through-vail leakage cracks in equal or larger nominal pipe eieee vith thinner vali thicknesses.

The energy level in a vhipping pipe ie considered insufficient to rupture an impacted pipe of equal or greater nominal pipe cise and equal or heavier vali thickness.

Jet impingement forces from a given pipe of specified nominal pipe size and vali thickness arc considered capable of<

i) Rupturing targeted pipes of smaller nominal pipe siee and ii) Developing through-vali leakage cracks in pipe of larger nominal pipe cise and thinner vali thickness.

)5 ~ SEISMIC INTERACTION STUDY In NRC Regulatory Guide 1.29, the requirement to survive the effects of the safe shutdown earthquake include systems and components vhose function may not be required for safe shutdovn but vhosc failure may prevent a system important to safety from functioning. To address this requirement, a seismic interaction study vas performed for the Shearon Harris plant. Wc guidelines, methodology, and evaluation criteria used in this study, as it covered under this specification are summarized bclov:

applies to piping and support Step li The first step is the designation of structuree, systems and components ae targets or sources. h target ie defined ae any safety-related structure, system, and component required to safely shutdovn the plant and maintain the plant in a safe shutdovn condition, and certain accident mitigating systems such ae containment isolation, main steam isolation and main feedvater isolation. hll nonsafety related systems, piping and components are designated as sources.

U Ebasco Specification Design Specification for ANSZ.Nuclear Safety Classes Rl 1, 2 & 3 and hNSI 531.1 Non-Nuclear Safety/Seismic Category I and Seismicall e sm ca y D Designed Piping and Supports Project Identification No. CAR" SH-M-71 SEISMIC INTERhCTION STUDY (Cont d)

Step 2e The second step is the identification o interactions involving on of sources and t t Th piping dravings HVhC duct routingg a g o gs, genera arrangements and civil/structural design n a tion, all ertinent s patial consideration study+

Step 3a Step 3 is the evaluatio ation and disposition status of identified interactions. Based upon establi s h e d acceptance critex'ia e interaction ia evaluated and cclassifi ass e d as acceptable or tab ceptable unacce and documented along vith the identification of interaction components sourc ( ) d ( ),

the interaction, and pertinent spatial data.

Step 4a Step 4 is the corrective action taken en too resolve res unacceptable interactions. Thee first rst course of action is to relocate the nonsaiety system or component to an area vhere an a adverse system interaction is not ossibl relocate systems or components due to e ui ment identified detrimental e seismically desi g ned to prevent interaction with a target.

e . Unacceptable bl piping sources are seismi o d i t d "SD" i th Pi i o y portions ses on p of lii e need be seismically designed ines ese ines vill so be noted n the remarks column of the Piping ne I ist.

Line st. Piping Pi in lines 1 or portions of lines designat e d seismfcall y desi gned ned are stress analysed to establi s h d es ign loadin g and locations for supports and restraints.

Ebasco Specification Design Specification for hNSI Nuclear Safety Classes 1, 2, 6 3 and ANSI $ 31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports Pro)ect Identification No. CAR-SH-M-71

,16 'LLOWABLE PIPE STRESS

.01 The allovable stresses for piping covered by this specification, except for the pressurizer safety and relief valves discharge piping under sustained and dynamic loadings during normal operationy are as follows'lant Condition ~Euation S hllovable Normal (8) 1. OSh (10}

(11) Sh h Upset (s) 1.2Sh (10) h (11)

Emergency ( s) 1.8Sh Faulted (s) 2.4Sh Test ( s) 1.35SY chere Sh, Sh, SY and Equations 8 thru'll are defined by hSME Section III, Subsections NC 6 ND.

.02 The allowable stresses for the seismically designed pressuriser safety relief valve discharge piping under sustained and dynamic loadings during normal operation are as follovsa Plant/System Stress 0 eratin Condition Load Combination hllovables Normal 1.0Sh Upset N + SOTU 1.2Sh Upset N + OBE + SOTU l. 8Sh I

Emergency N + SOT 1.8Sh Faulted N + MS/1%PB or DBPB 2.4Sh

+ SSE + SOTF Faulted N + LOCh + SSK + 2.4Sh SOTF vhere, Ebasco Specification Design Specification for ANSI Nuclear Safety Classes 1, 2, 6 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports oject Identification No. CAR-SH-M-71

16. ALLOMABLE PIPE STRESS (Cont'd)

.02 (Cont'd)

N Sustained Loads During Normal Plant Operation SOT System Operating Transient SOTU Relief Valve Discharge Transient (1)

SOTE Safety Valve Discharge Transient (1>>

SOTF Max (SOTU~ SOTE)I or Transition Flov OBE Operating Basis Earthquake SSE Safe Shutdovn Earthquake MS/FMPB Main Steam or Feedvater Pipe Break DBPB Design Basta Pipe Brcak LOCA Loss of Coolant Accident (1) May also include transition flov, if determined that required operating procedures could lead to this condition.

.03 Essential piping is indicated by the designation "E" in the ISI column in the Piping Line List, Appendix D. For this essential piping, the Emergency stress allovablea apply for loading combinations 4 thru 10 given in Appendix F. For all other piping listed in Appendix D and covered by the scope of this specification, the Faulted stress allovablea apply for loading combinations 4 thru 10 given in Appendix F.

Ebasco Specification Design Specification for bVST Nuclear Safety Classes 1, 2 & 3 and ANSI B31.1 Non-Nuclear Safety/Seismic tegory I and Seismically Designed Piping and Supports ro)ect Identification No. CAR- SH-M-71 APPENDIX A (DELETED)

Ebasco Specification Design Specification for 53'uclear Safety Classes 1, 2 6 3 and hNSI 531.1 Non-Nuclear Safety/Seismic tegory I and Seismically Designed Piping and Supports ro)ect Identification No. ChR-SH-M-71 hPPENDIX 5 Thermal Mode Diagrams

0 Ebasco Specificati,on Design Specification for ]+~Nuclear Safety Classes 1,2 & 3 and ANSI b31.1 Son-Nuclear Safety/Seismic C ry I and Seismically Designed Piping and Supports Project Identification No. CAR-SH-M-71 SYSTEMS I

Auxiliary Feedvater Boron Recycle Chemical & Volume Control Chilled Water. Supply & Return Component Cooling Containment Spray Feedvater Fuel Oil Main Steam Reactor Coolant Safety Injection/RHR Spent Fuel Pool Cooling & Cleanup Steam Generator Blowdown Service Water

EbASCO SPECIFICATION DESIGN SPECIFICATION FOR ANSI NUCLEAR SAFETY CIASSES I I 1,2 & AND ANSI bbl, NON-NUCLEAR SAFETY/SEISHIC Rl.

CATEGORY I AND SEISNICALLY DESIGNED PIPING AND SUPPORTS PROJECT IDENTIFICATIOH Ft~ FW NO. CAR SH-N-TI

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~ ahovn unlesa othervise noted.

AMB denotes: Ambient

3) When CBD is not tn use, f~pevatye ES hNB

4) One pump operation. Other pump{a) are prcssurised downstream at discharge check valve(a). 130 P is maximum ailovab?e temp.

5) Dovnstrcas of butterfly TCV'a > of 39 4 55 yields 46 to Chiller Surge Tank.

6) During dilution, flov is straight through. During boration, flov is through branch.

7) Mix)ng 92 vater from Moderatiag HX vith asia CVCS letdovn flov of 115 yields 104 {est.)

8) Mixing 250 vater from Letdova Reheat RK (T.S.) vith 293 main CVCS letdovn flov yields 280 (eat) ~

9) Similar to aote 7, vith 96, yields 106 (eat.).

10) One valve normally open. hll three closed for RHRS Purification and txccaa T.et d ovn.

Chemical Mixing Tank used intermittently for PH control, and for oxygen control during startup from cold position.

This tank is aot necessarily used during Borate mode.

12) Dilution Mode of Reactor Makeup Mater System may also operate Relevant points affected are as follovs:

it this time.

Valves V20 & V19 are open There ia an additional Alternate Dilute Mode, vbere valve V22 ia 110 115 120 also open, alloving vater to flov to chargiag Pump suction header. Io other conditioas are effected.

13) Borate Mode of Reactor Makeup Mater System may also operate at this time.

Relevant points affected arc as follovs:

Valves V23 and V22 are open. SS 8 Q n'n'li0'4) hutomatic Mode of Reactor Makeup Pater System may also operate at this time.

Relevant points affected are as follovs:

Valves V20, V22, V23, are opea. SS )( 9/ U 75 120 95 110

) The highest Qn:Ferpfgyg t5, listed, and cxistaat initiation of this mode.

When normal lctdovn line not available. Flov through excess letdovn line may bc directed to RCDT..During startup, excess letdovn line may be used, vitb flov to RCDT, to supplement main letdovn flov. Conditions for flov to RCDT during pover operation are imilar except vhere noted.

8-12a.

Xbasco Speci ficatfen n Specification for ARSE.Nuclear Safety Classes 3 and ANSI h3].1 Son-Nuclear Safety/Sefsmic C gory I and Sefsxfcally Designed tfping and Supports Pr o)ect identification No. CAR-SH-M-71

'THERMAL MQDES OF OPERATION CVCS 17)Tee.f rctMrcs at these points differ as follovs:

CVCS Purification b c p 3QQ 300 300 f29 429 Heatup 380 380 380 466 466

18) Aux Spray lfne may operate at this time. 130 charging vater vill mfx vfth aain spray bleed bypass line from RCS.

19) For Aux Spray line only (see Note 18).~ for Atl.~ Charging line,dc~pgreql I a. gyes f,s Avb.

20) Charging lfne may b'e used at any tfme at operator preference. Shen fn use, V2 opens, V10 closes, and condftfons are the same as charging line conditions.

Pt CC vill then see RCS conditfons.

Refer to Thermal Modes of Operation for RHRS & SIS for details in this area.

Upstream of valve V7 fs 300. Charging pump header 500.

DoMnstream of suction line check valve to pump auction is 300.

24) To charging lfne check valve IRC,

25) To first fsolat fon valves. Plant Condition Emergency, System Condition-Emergency

26) Plant Condition-Normal; System Condition-Upset

27) Plant Condition-Faulted; System Conditfon-Faulted

28) Plant Condition-Faulted; System Condition-Normal

29) Plant Condition-Normal; 'System Condition-Emergency

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~>~TR i)LINES DESIGNATED Ag A" ARE AT CARP.

R1LINLS DE'%IIIIIATED AS'B; ARE AT hh'F.

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S)THE A8OVE tEMPE RATG6 TALL VS VG ISE USE P FOFIPlt PIANTPPER ATIN6 COHOI'TIONS.

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AH-IC AH-27 AM II 'I) PIPIII& BEYOND THIS POINT I A-SA 1A SA 1A-SA ISTEMPORAR)!

8) AII UMES ARE AIWAYS FULL OF WIITER.

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CO."T. BL1>G. CYLI. 0?ALL DISPLACEMENT DUE TO LOCA DATA: DISPLACEMENTS IN CYLI. WALL AND DONE DUE TO LOCA PRESSURE 45 PSI AND TEMP. RADIAL DIRECTION LONGITUDIN>.L DIRECIIOX+ Elevation Pressure Temp.* Total Pressure Temp+ Total Ft 45.0 PSI 45.0 PSI 216.0 0.000 0.000 0.000 0.000 0.000 0.0 226.0 0.138 0.037 0.175 0.040 0.063 0.103 246.0 0.543 0.219 0.762 0.135 0.105 0.240 276.0 . 0.626 0.220 0.846 0.330 0.201 0.531 286.0 0.654 0.217 0.871 0.405 0.234 0.639 306.0 0.678 . 0.217 0.895 0.566 0.298 0.86: 326.0 0.656 0.217 0.873 0.724 0.363 1.087 356.0 0.612 0.215 0.827 0.948 0.460 1.408 376.0 0.612 0.214 0.826 1.097 0.525 1.622 ADDITIONAL DISP. (POINT TO SPHERE CENTER) 404.0 0.613 0.215 0.828 419.0 0.613 0.215 0.828 435.0 0.613 0.215 0.828

THE TMP. DISPQCEMENTS INDICATED ARE DUE TO NORMAL OPERATING TEMPERATURE (90 OUTSIDE AND 120 INSIDE): THE DISPLACEMENTS DUE TO THE LINER INTERACTION ARE NOT INCORPORATED ~ BUT THESE EFFECTS ARE NOT SIGNIFICANT.

~ THE LONGITtVINALDISPLACVKNTS OP THE INSIDE AND OUTSIDE FACES ARE DIFFERENT: THE DATA LISTED IN THIS TABLE ARE AVERAGE DISPLACEM&TS ~

Reference:

Calculation by M. Patel checked by J. Shen 10/24/77 (C-H Dept.) Ebasco Specification Design Specification for $ }fSZNuclear Safety Classes 1, 2 6 3 and AhSI B31.1 Non Nuc lear Safety/Seismic Rl Category I and Seismic ally Designed Piping and Supports Pro5ec t Iden tification Ko. CAR-SH-M-71

CO:~T. BLDG. CYJ.I ~ MhLLDISP. DUE TO TEST PRESSURE DATA: DISPLACE??ENTS IN VALI. MALL AND DO>K DUE TO TEST PRESSURE 51.75 PSI AND AXllOSPHERIC TENP. (SLOWER) RADIAL DIRECTION **LONGITUDINALDIRECT: Elevation Pressure TEMP.* Total Pressure Temp.* Total Fr. 51.75 PSI. 216.0 0.0 0.0 0.0 0.0 0.0 0.0 226.0 0.159 0.025 0.184 0. 046 0.042 0.088 246.0 0.624 0.132 0.756 0.155 0.070 0.225 276.0 0.720 0.147 0.867 0.380 0.134 0.514 286. 0 0.752 0.146 0.898 0.466 0.156 0.622 306.0 0.780 0.145 0.925 0.651 0.199 0. 85 326.0 0.754 0.145 0.899 0.833 0.242 1. 075 356.0 0.704 0.145 0.849 1.090 0.307 1.397 376.0 0.704 0.145 0.849 1.262 0.350 1.612 ADDITIONAL DISPLACE?'KNT (POINT TO SPHERE CENTER) 404.0 0.705 0.143 0.848 419.0 0.705 0.143 0.848 435.0 0.705 0.143 0.848

THE TPP. DISPLACPAENTS INDICATED ARE DUE TO ATHOSPHERIC TEHP OF 90 F (SAG'tER) ON BOTH SIDES OF MALL.

THE LONGITUDINAL DISPLACEHENTS OF THE INSIDE AND OUTSIDE FACES ARE DIFFERENT: .THE DATA LISTED IN THIS TABLE ARE AVERAGE DISPLACEHEHTS.

Reference:

Calculation by M. Patel checked by J- Shen 10/24/77 (C-H Dept.) Ebasco Spec ification Design Specification for SX, Nuclear Safety Classes 1, 2 h 3 and ANSI B31.1~ Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports Project Identification No.~ CAR-SH-M-71

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)gee'ti~TO '.g tc.>IN No. CAR-SH-M-71
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'-I'T Pe'YiN1 RCCoUe/T gg ."HtlLL AI. VsA ~ I crrl I lIII Rth IIIIIQM ld F F)IP Design Specification for AQSL Nuclear Safety Classes V IC.tP Il~nlllll Rl R FRSTIOIl IITIIIIIIIIJII WEhlf'OIItIIE' AsII5T el.V Fl1/f:Irl ZQ Illg 1,2 & 3 and hNSI 831.1 Non-Nuclear Safety/Seisriic ~l'E9NIII DF IIIPC g-'~EM PI: r~zl Category I snd Seisrrlically Designed Piping and Supports IIIIAr: HtelITQ JII I hel Ip)tIFF 'S S%9I TIJRE Project Identification No. CAR-SH-M-71
Ebasco Specification Design Specification for ANSI.Nuclear Safety Classes 2 & 3 and ANSI B31.1 Non-Nuclear Safety/Seismic ategory I and Seismically Designed Piping and Supports Prospect Identification No. CAR-SH-H-71 APPENDIX I PIPE SUPPORT DESIGN CRITERIA
Ebasco Specification Design Specification for Ah~M Nuclear Safety Classes 1, 2 4 3 and ANSI B31.1 Non-Nuclear Safety/Sefsmic Rl ategory I and Seismically Designed Pfpfng and Supports rogect Identiffcation No. CAR-SH>>M-71 Support/Restratnt (S/R) design shall be based on the follovfng eight (8) equatfons (the components for each equatfon vfll be provided vith the stress analysis transmittals): Equation 1 - Normal Operating Equation 2 Operating Basis Earthquake (OBE) Equation 3 - Hurricane Equation 4 - Pipe or Equipment Accident Equation 5 - Tornado Equation 6 - Design Basis Earthquake (DBF or SSE) Equation 7 Pipe or Equipment Accident Plus Operating Basis Earthquake Equatfon 8 - Pipe or Equipment Accident Plus Design Basfs Earthquake.
~ c s ss Xi-Eba sco Speci ffeat fon Design Specification for hNSXNuc?ear Safety Classea 1, 2 4 3 and ANSI b31.1 Non-Nuclear Safety/Seismic RI ategory I and Sefsmically Desfgned Piping and Supports roject Identification No. CAR-SH-M-71 1~ DESIGÃ EQUATIONS (Cont'8)
Ihe allovable stresses for Ia5or structural components and the supplementary steel are tabulated belov based on section strength S. for structural steel, S fs the required section strength based on the elastic desfgn methods and allovable stresses defined in Part I of the AISC Specificatfon for the Design, i fabrication Erection of Structural Steel for buildings (1969) ~ @hen external loads such as restraint dead veight or thermal expansion are added to the piping loads, the support/restraint must meet these a 11 ovabl as. TAI.K l I uation No. ssent a ystem . on-.ssennrnsysren Flexure 7lexure 1 ~ S le S 1~ S 1 S 1.33S 1.3S 1~ S 1~ S I 7 1 eSS 1~ S le S 1~ S I I I I I 1,5S I 1.3S le S 1 ~ S I I Ibe increase in allovable stresses fn Table fel loving 1 imi tat iona: l.l is subject to the
.01 Compressfve stress fn compression members is limited to 2/3 critical buckling stress eaxfmum in all cases as determined from the follovfng curve.
e CO eO CO Oo FOR CENTRALLY LOADED COLUMNS O BUCKUNG CURVES + I Y lA
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Ebasco Specification Design Specification for AN~Nuclear Safety Classea Rl 1, 2 4 3 and hNSI b31.1 Non-Nuclear Safety/Seismic ategory I and Seismically Designed Piping and Supports Project Identification No, CAR-SH-M-71 F 02 Material yield stress shall not be exceeded.
.03 Loads on bolts are limited to the normal allovable loads in the hISC Specificationi ~ 04 Loads on concrete expansion anchors shall be limited to a 4:1 factor of safety based on ultimate load. Selt drilling concrete type anchors are not used on this project 2 S/R DESIGN LOhDS ~ 01 For stress-analysed linea the folloving load cases shall be used in the design of supports.
ChSE NO ~ TITLE DESIGN E UhTION Sustained Load (Dead Weight) 42 Test Weight (Hydrostatic) 51/52 Fluid Hammer 101 OSE XYZ Inertial Response 103 DSE XYZ Inertial Response 501 Highest Positive Thermal (Normal Plant Condition) 502 Highest Negative Thernal (Normal Plant Condition) 503 Highest Positive Thermal (Normal or Upset Condition) 504 Highest Negative Thermal (Normal or Upset Condition) 505 ~ Highest Positive Thermal (Tea't y 6, 7~ 8 Normal, Upset, Emergency or Faulted Condition) 506 Highest Negative Thermal (Test, 6~ 7, 8 Normal, Upset, Emergency or Faulted Condition)
Ebasco Specification Design Specification for PQQT Nuclear Safety Classes 1, 2 4 3 and ANSI 531.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports ro)ect Identification No. CAR-SH-M-71 S/R DESIGN LOADS (Cont'd) ~ 02 The load cases above are to be combined for Support/restraint design as follovs: Case No. S stem Condition Load Condition Desi n Equation 510 Normal Largest of a. (501+ 41) or b. (502+ 41) 520 Upset (Largest of a. (501+ 41) or b. (502+ 41) or c. (503 + 41) or d. (504 + 41) or e. (41) t
+ OBE (I + D) (largest of a, Fluid Hammer or b Relief Valve Discharge or any other system transients)a ,'R1 530 Emergency Same as Upset (520) plus the larger of combinations
f. (505 + 41) or g. (506 + 41) .
Also use DEE in place of ObE. 540 Faulted Same as Emergency (530) 7, 8 plus LOCh plus Jet Impingement
Fluid Bsmmer/Relief Valve Discharge Loads may be combined vith OSE loads by square root of the sum of the squares (SRSS) method if required The design loads for supports are Case No. 510 - Normal, 520 - Upset, 530 - Emergency, and 540-Faulted. When the computer-analyzed case 510, 520, 530, or 540 is not available, the equivalent load combinatior.
shalg be manually generated. When the case numbers from the stress analysis output are not the same as listed here, the equivalent load cases and load combination shall be used.
Kbacco Specification Decign Specification for WSiLNuclear Safety Classes
~(
Rl 1, 2 4 3 and ANSI b31.1 Non-Nuclear Safety/Seismic ategory I and Seismically Designed Piping and Supports ro ject Identification No. QR-SH-M-71 2~
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.03 For supports on piping systems vithout a stress analysis, the folloving design loads shall be used .Except for plumbing.and drainage lines, vhich are not stress analyzed, these loads are subject to later verification against stress .analysis loads. a, 2" and Under Pipin Lateral and vertical restraints shall be decigned for the loads tabulated belov vhere MT is the dead veight of pipe filled vith vater TAbLE 2o1 LINE SIZE (Ih) 1/2 4 under 3/4 1 1/4 1 '1/2 DESICN LOAD FOR I I LATERAL RESTRAINT I I 1(Lbs) 169 269 420 585 842 1361 I I I DESI CN LOAD FOR ERTI GAL RESTRAINT I 169+MT l2 69+ST I42~T' 585+9'42+9 T l T I 1361 +~T I I I I I I The allovable support design streccec to be used vith these loads shall be those for hormal Operating Condition (Equation 1) as specified in Table I'.l. The maximum cpan length for each pipe size shall be as given in Table 2.4 and 2.S For anchorc on piping syctems vithout a strecc analysis, vhere piping on both cides of the anchor is seicmic, the loads in Table 24 chall be used. TAbLE 2,2 P1PE SIZE Fx, Fy C Fs (lbs) Nx, My C Hs (lbs-in.) (in. ) 3/4 200 1,600 400 3,200 1 1/4 600 4>800 1 1/2 1,000 8>000 1,SOO 16,000
Xbasco Specification Design Specfffcatfon for PIN&I.Nuclear Safety C?asses 2 C 3 and ANSI $ 31.1 Non-Nuclear Safety/Sefsmfc RI tegory I and Seismfcally Designed Pfping and Supports Profect ldentfffcatfon No. CAR"SH-H-71 2 S/R DESIGN LOADS (Gont'd) a: Cont'd Ihe above loads shall be considered as DhE loads, and the corresponding allovable stresses shel) be those for Equation 6 Table lola For anchors, the sfx components of forces and moments shall be applied simultaneously.
b. 2 1/2" and Lar er Pf fn
-Loads to be used for the de sign of supports for 2 1/2" and larger piping shall be as shovn in Table 2.3. Ihese loads are considered to be DbE or Emergency condftfons.
For vertical restraints, the vefght of the piping, and fts contents shall be calculated based on the vefght span method, and shall be added to the magnitude of the 1 ~ terai restraint forces from Table 2 3. Ihe allovable support design stresses to be used vfth the above loads are those of Equation 6 in Table 1 ~ X. Ihe maxfmum span 24 and 2.S ~ length for each ifpe site shall be as given in Table
Ebasco Specification Design Specification for +5LNuc1ear Safety Classes 1, 2 4 3 and ANSI b31.1 Non-Nuclear Safety/Seismic R1 Category I and Seismically Designed Piping and Supports roject Identification No. CAR-SH-M-71 2~ S/R DESIGN LOADS (ContDd)
~ 03 (Coat'd)
b. (Goat ')
COMBIhE& THERMAL 4 SEISMIC ANCHOR>> PIPE PIPE DBE FORCES LBS) MOMENTS
~CH. I ZE--
V2" TLORAL I C+Og+ +F~B Wg2 BE3 40 2 560 1 500 1 500 3, loo 1 2" 00 1 500 1 00 36 900 3% 840 2,200 2 0200 5,000 BO 10 100 40 1 ~340 3,000 9,400 80 1 800 3,000
~1ARI 12,500 40 0~
0 6 lo" 4,200 8,000 8,000 120000 18,000~ 18,000
~$ 35,600 10" 12" 10, 500 18,000 23,000 18,000 ~115,7,400 13 DDD 80 40 8
80 12" 14" le" 16"
~i5i 15 000 23, 000 336000 4,000 236000 47 ~ 000 365, 600 9,ooo ~6, 2670000 613 000 tO FD~ ~.il ~f 40 20" 496,000 20" 5,000 40 24 52,000 l,000 4A DMR .750" 30" 90,000 1500000 15 0,000 1 04330000 Ps" 30" 158,000 1.00" 116 000 h0000 l,ee $ ,000 I ~ ~ FORCES AND MOMENTS ARE CO%'ONENTS zD P yt~ P sD~ H+00 M,C F~, yD H
Ebaaco Specificatfon Design Specification for ANSI Nuclear Safety Classes 1, 2 4 3 and ANSI S31.1 Non-Nuclear Safety/Sefsafc Rl Category I and Seismically Designed Piping and Supports roject Identffication No. CAR-SH-M-71 S/R DESIGN LOADS (Cont'd)
~ 03 (Co'nt'd)
c. Plumbin and Draina e Lfnes Pipe-supports for plumbing and drainage lines shall be designed for the loads for lateral and vertfca1 restraints in Tables 2.4 and 2.5 below.
Friction forces vfll not be applied. Loads tabulated herein are based on Pipe Sch. 40. TABLE 2 4 LOADS FOR VERTICAL SUPPORTS PIPE MAX. AT OF PIPE SE IS HI C Dl FFKRENTIAL TOTAL DE SIGh SIZE SPAh MITH MaTER SEISNC FORCE f SEISMIC FORCE I OAD (Ih,) I (FT) (LSS ) COhDIT ION (LSS ) )OBE88.3G (LSS) I DSE 6G 3/4 7 12 34 4 14 OBE 57 75 114 136 1 1/4 9 OSE 12 26 180 16 222 1 1/2 9 32 OBE 120 10 162 2 10 51 OSE 142 15 208 284 30 2 1/2 11 d7 OBE 320 26 43 I DBE 640 79 490 659
~il'8 3 12 130 4 14 228 OBE d30 1,660 136 2 024 6 17 $35 ~2.000 40000 161 322 20696 4 ~ 857 d 19 950 OBE 38600 285 4,235 0
10 1650 OBE 5 500 495 7,645 I DSE 90 1 9640 12 23 2346 ObE I 14 18 25 22 3053 8202 OSE DBE 082 ATT~ 1291, 22,700 18408 91 1,290
~,ilY 18,~94 12,969
Ebasco Specification Design Speciffcatfon for AHSZ Nuclear Safety Classes 1, 2 4 3 and ANSI b31.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Pfping and Supports o)ect Identiifcatfon '. CAR-SH-M-71 FR1CTION FORCES Frfctfon forces shall be consfdered vhen the pipe can slfde against the support in the unrestrained direction. Friction loads in the unrestrained direction of the pipe shall be added to the design loads or load combinations fn the preceding paragraph 2 vhen the total movement of the pipe fn the unrestrained dfrectfon exceeds 1/16 inches. The frfctfon load fa each unrestrained dfrectfon shall be calculated as follovs: F ~ f1 V1 or f2 Vg vhfchever is greater Vhere: F ~ Frictfon reaction force
~ Coefficient of frfctfon for the surfaces fn sliding contact ~ For steel on steel "fl" shall be 0.6 for loads due to dead vefght and thermal force, "f2" shall be 0.30 for loads due to dead vefght, thermal ~ nd ~ dynamic event such as seismic V1 ~ Dead Vefght and thermal load M2 ~ Dead Veight, thermal load, OBE and occasional loads At points of support vhere excessive frfctfon cannot be tolerated, reduced friction slides may be used. Acceptable slide components are self lubricating bronze slide plates, as manufactured by, or equivalent to, Merriman Bros Inc Lubrite sli'de plates. h design coefficient of 0.15 shall be used'for this application.
Ebssco Specification Design Specification for QNSXNuclear Safety Classea Rl 1, 2 &'3 and ANSI b31.1 Non-Nuclear Safety/Seismic
~
ategory I and Seislnically Designed Piping and Supports Project Identification No.~ CAR-SH-M-71
2. S/R DESICN LOADS (Cont'd)
~ 03 (Cont'4)
c. (Cont'4)
TABLE 2,5 LOADS FOR HORIZONTAL RESTRAINTS PIPE MAX. bGT OF PIPE SEISHIC DIFFERENTIAL TOTAL DESIGN SIZE SPAN t ARITH MATER SEISKC fORCE lSEISlGC FORCEl 'OAD (IN ~ ) l (FT) (LBS) ) CONDITION (LBS) lOBEi.3to (LbS) (LBS) BEBB 6C OBE 22 4 i~3/4 12 OBE 37 82 OBE 60 68 26 1 1/2 32 ~BE 120 16 8~ 136 OBE 125 15 140 2 10 51 DBE 250 30 280 2 1/2 ll 87 OBE DBE 10 26 236 OBE 315 39 354 3 12 130 0M OBE 540 68 608 228 1 214 DBE 1 8080 136 6 17 535 OBE ~1,300 161 322 1 441 2.%22 OBE 2 400 28 8 19 950 0 5, 0 495 10 22 1650 1 7 200 990 ' 8, 190 I OBE , 00 404 12 23 2346 0 B~E ,800 408 11 08
, 00 ~ 816 14 25 ;, 3053 16 27 4301 OB~E 8,890 DBE 15,200 2,581 17 '81
Xbasco Specification Design Specification for ANZ.Nuclear Safety Classes
, 2 4 3 and ANSI B31.1 Non-Nuclear Safety/Seismic Rl ategory I and Sefsmically Designed Piping and Supports Pro)ect Identification No. CAR-SH-M-71 2 S/R DESIGN LOADS (Cont'd) .03 (Cont'd)
c. <Co nt d)
In addition to the loads given fn Tables 2s4 and 2.5, the effect of concentrated loads such as valves obtained by using the folloving factors multiplied by the veights of the concentrated loads shall be added. Vert~Real Su orts Horfxontal Restraints OBE DBE OBE DBE Effect of aoncentrated loads 3.3G 6.6G 2.4G 4 8G
d. PLUMBING LINES IÃ CONTAINMENT BUILDING For plumbing Ifnes fn the Containment Building Unit 1 vhich are supported against the columns, design loads for restraints shall be determined as described herein. These loads shall be used for 105 veils only.
Design loads equals ~ F span+ F dfspl+ F conc+ Valve/Pipe vt Valve/pipe is for vertfcal restraints only. ~e components of the above design loads are gfven in Tables2.6 and 2.l belov. TAKE Z.6 SEISMIC SPAN FORCES (F SPAN) LBS LATERAL VERTICAL BQ B BE 100 200 240 300 250 400 I I> I 1 6 300 600 400 640 I TABLE 2 sl SEISMIC FORES PER PIPE SIZE (LBS) OBE DBE
~7h.X QI 'G ~5gJ lPIPE SIZE IVALVE/PIPE) BLDG REL F DI+P QGT C C BLDG REL ISP 3 I 30 45 30 90 60 63 42 126 84 l 6 80 . 120 I 80 240 ) 160
Ebasco Specification Design Specification for.hN5I.Nuclear Safety Classes 1, 2 i 3 and ANSI $ 31.1 Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports roject Identification No. CAR-SH-M-71 4~ SEISMIC/NON-SKIS>Q C INTERFACE ANCHORS Design loads for seismic/non-seismic interface anchors shall be obtained as follows:
a. For Equation 1, DVs+DM s Or DVs+ DV>>+ THs + THQs Mhere the subscript s denotes the seismic portion and ns the non-seismic portion of the pipe.
DV ~ Dead %eight TH ~ Ihermal Forces b, For Equation 2, D"s + Dgs + T"s + THns + 3OIKs +2OLs + 2SSDs
%here OL ~ Occasional Loads SSD ~ Loads due to Seismic Displacements
c. For Equation 6~
D"'s + Dks + THs + THns + 3DgEs + 2OLs + 2SSDs
d. In addition to the design load criteria given in a. thru c.
above, one of the following criteria must be met for seismic/ non-seismic interface anchors: i - 'lhe interface anchor will be designed to a bending moment moment that causes initial yielding in the pipe, ory ii ;...non-seismic
- Two (2) two~ay restraints shall be designed side of the, interface anchor.
on the
Ebasco Speciffcation Design Speciffcation for AHSLNuclear Safety Classes Rl 1, 2 4 3 and ANSI I31.1 Non-Nuclear Safety/Seiamfc Category I and Seismically Designed Pfping and Supports reject Identfficatfon No. CAR-SH-M-71
5. STANDPQU) SUPPORT COMPONENTS Standard support components to be used must have thefr load capacfty data established by the manufacturers. No additional calculation to qualify the component standard parts is required unless the parts are used outside the scope covered by the load capacity data.
SlJPPI.EMENTARY STEEL Supplementary steel and any structuraI parts that have to be qualified shall be designed in accordance ef th the AISC Specification for the Design, Fabrication and Erection of Structural steelvarious for building. increase in the normal allovable stresses for the design equations shall be in accordance vith paragraph I except that the deflection at the support points due to all load combinations of Equation 1 for shall tnot exceed Normal Operation)or Equation 2 (OBE) frames supporting snubbers 1/32" in each restrained direction, and this deflection shall shall not exceed I/16" for all other frames, including anchors. 7 QE1DED PIPE ATTAClkEhT
~ 01 Velded pipe attachments shall be analysed considering the ~ ttachments as structural members for load transfer, and for additional local stress coneentratfon they impose on the piping. The load combinations and the a]lovable stresses for the design analysts o'f the velded pipe attachments as structural members shall be a's defined in paragraphs 1 and 2. The local stress analysis of ASME Class I piping fs not fn the scope of this document. Hovever, for the purpose of support design only ~ the velded pipe attachments on ASME Class I piping shall be treated in the same manner as those for ASME Class 2 and 3 pipfng sub)act to later design verification of the pfping by ~ Class 1 analysis. for ASME Class 2 and 3 velded pipe attachments, the load combinations to be used in determining additional local stress concentration shall be as follovsf Code Equation S! P + DM Code Equation 9 (Upset): t + DM+ ObE + OL Code Equation 1 (Emergency or Faulted)c P t DM+ DbE+ OL Code Equation 10 (Normal, Upset, Emergency or Faulted)!
TH or TH + SSDe Code Equatfon 11 (Normal Upset, Emergency or Faulted): P + DM + (TH or TH + SSDe) eSSD is Code Eq included fn 9. Code Eq. 10 or 11 only if it has been excluded from
Ebasco Speci ffcatfen Design Specfficatfon fot ~Nuclear Safety Classes 2 4 3 and ANSI 131.1 Non-Nuclear Safety/Sefsmfc Rl gory I and Sefcmically Designed Piping and Supports Project Identification No. CAR-SH-M-71 7 VENDED PIPE ATTACHMENT (Cont'd)
~ 01 (Cont'd) %here Code Equations above are from AS'oiler and Pressure Vessel Code Section III paragraphs NC-3650 and ND-3650, and f ~ Frecsuti and DW, TH, ObE ~ DbE, OL, and SSD have been previously defined. .02 The allowable strecces fot tbe total combined strecces from tbe existing pfpe ctrecces and the addftfonal local pipe streccec shall not exceed the folloving!
Code Equation I! 1.0 Sg Code.Equatfoa 9 (Upset)! 1.2 Sg Code Equation 9 (Emergency ot Faulted)! 1.6 SI, Code Equation 10 (Normal ~ Upcet ~ Emergency or Faulted)! SA 0 Code Equatfon 11 (Normal ~ Upset ~ Emergency or Faulted)! Sh + SA
~ 03 The local strecces fn the piping due to velded pipe attachments shall be determined vbere applicable by the method given fn Veldfng Research Council Bulletin No. 107 (MRC 107) ~ Nere MRC-107 is not applicable, other acceptable methods such ac finite.element analysis or methods vftbin the state of tbe att may be employed. For other'onservative Code Equation 8 or 9, only the primary stresses shall be considered.
For Code Equatfoa 10 or 11 shall
'oth the primary and cecondary stresses be includedi Allowable stresses for velded pipe attachment velds to the piping are the same as those for the pipe itself at the point of attachment Piping equations given in Paragraph 7.02 must be satisfied for the velded pipe attachment velds.
04 The acceptance cifteria fot tbe local strescec due to velded pipe
~ ttacbments are the same fot ASME Sectfon III paragraphs NC-3650 and ND-36SO, ie Code Equations 8, 9 and one of Code Equations 10 and 11 have to be satisfied 8 SPRING CONSTANT Spring constants shall be calculated for all AS)K Clacs 1 pipe cupports and shovn on the detafl drawings ~ Spring constants shall account for the combined stiffnesses of tbe component parts and ctructural framing in each restrained dfrectfon for each support.
Ebasco Specification Design Specification for ANSLNuclear Safety Classes 1,2 4 3 and ANSI b3l.l Ron-Nuclear Safety/Seismic Rl ategory I and Seismically Designed Piping and Supports r object Identification No. CAR-SH-M 71 0 VELD DESIGN CRITERIA The ailovable veld stresses shall be in accordance vith AVS Dl.l, Sectioa 9 - Design of Nev bridges, for open structural shapes and plates, and Section 10 Tubular Structures, for tubular structural sections. Ihe increases in a11ovable veld stresses for various design equations are as given in Table 1>>l except that ir all cases the shiraz stress at the base metal shall not exceed 0.55Fy>> For fillet velds using E70XX electrodes, the allovable veld stresses for Normal conditions are 18.32 XSI for ASIA A36 base metal and 21 L'SI for ASTM A500 Cr b base metal ~ Veld symbols to be shovn on the pipe support details shall be Sn
~ ccordauce vith American Velding Society Standard - A 28-68, Standard Velding Symbols, vith the exceptions listed belov>> The vord "typical" shall not be used vhere it creates ambiguity or confusion>> Ihe all-around symbol shall be used only vhea the all-around veld vithout ~ ny break ia contour caa be made>> Tne folloviag exceptions to AVS StAT ~ard h 2>>0%8 vill be ~ lloved: ~ 01 for skev T-)oint velds vith a dihedral a'ogle betveea 30 and 60 ~
fillet veld symbol shove shall represent a partial penetration groove veld. Veld sixes shall be determined by subtracting 1/4" or 1/8" from the aa-velded groove )oint, as described be1ov Ihe effective throat of this partial penetration groove veld shall be assumed to be 1/4" less than the specif ieo gr oove dep'th for d il edral angles betveea 30 aad 45
~ nd ]/8" less for dihedral angles betveen 45'ad 60 ~ ~ 02 For a 90'-Joint betveea tvo unequal vidth square or rectangular tubular sections, ~ fillet veld symbol may be used on the curved portion of the larger tubular section provided the vioth ratio of the smaller section to the larger is not greater than 0>>8>>
Kbssco Specification Design Specification for Al(S>Nuclear Safety Classes 1, 2 4 3 and ANSI 531.1 Non-Nuclear Safety/Seiseic Category I and Seismically Designed pipiag and Supports pro)ect Identification No. CAR-SH-M-71 10, EMBEDDED PLATE AND STRUCTURAL STEEL VERIFICATION Kmbedded plates Type 1 (fi" x 3/4 strip p?ate) and Type 2 (S" x 1" strip plate) shall be design verified as part of the support design calculation. The allo+able loads for each component for the above tvo (2) types of plates shall be as given in Table 10.1. The term "concentric attachment" means that the veld pattern )oining the structural attachment to the embedded plate is symmetrical about the longitudinal centerline of the embedded plate. Deviation from this symmetrical arrangement shall be vithin the tolerances given on Ebasco Drawing CAR-2168W6091, Zn Table 10.1 , x is the longitudinal direction, x is the transverse direction and y Xs the normal direction of the embedded plate The subscripts xa, ya and sa denote the allovable load for each of the corresponding component acting alone, Ti e total load interactior, shell satisfy the following relations Fx/Fxa+ Fy/Fya+ Fa/Faa+ Mx/)lxa+ fly/klya+ kh/hsa g 1 Rl Rien the interaction above cannot be satisfied, the design should be chatted vhere possiblei Nere the design cannot be cl anged and the interaction check fails, the footprint loads at the point of attache.ent shall be forvarded to Kt.asco Civil Design Kagineeriag for revie~ and disposition. Ia all cases, footprint loads shall be shovn on the support detail dravings for final reviev of embedded plates by Kbasco Civil Design Engineering. Verification of support loads on structural l steel and on embedded plates other than Types and 2 shall be done Civil Design Engineering. by Ebasco '
Ebasco Specification Design Specification for fiNS'r NucIear Safety Classea 1, 2 4 3 and ANSI b31.1 Non-Nuclear Safety(Seisaic Category I and Seismically Designed Piping and Supports Project Identification No. CAR-SH-M-71
10. EMBEDDED PLATE VERIFICATION (Cont'd)
TAbLE 10 1 ALLOl"SLK LOAD (KIP, ZN ) PLATE TYPE FIa Fya Mya N.a I 1 5 i 5 I 5 13o2 13e2 I (With Tolerance) I I 2 (CON CEliTRI C 46+6 20,0 24 +7 62o3 302i8 57.7 ATTACQZliT) I 40+4 12ol 247 55+0 302i8 49+5 (With Tolerance)
Ebssco Specification Design Speciifcetion for RHK Nuclear Safety Classes Rl l, 2 4 3 and ANSI 131.1 Non-Nuclear Safety(Sefsaic I and Seismfcally Designed Piping and Supports Category ro)ect Identiftcatioa CAR-SB-M 71 IN-SERVICE INSPECTION In service inspection requirementsfor ASME Section III Class l 6 2 piping shall be in accordance vith Specifications I-30 and M30A. Support design shall provide access for the required in-service as indicated in Figure ll.l. FIGURE 11.1 CIRCUMFERENTIAL hELD CLEARANCE CRITERIA le CREATER OF CREATER OF 2T+4" 2T+4" i'll OR 6" OR 6" K1N1KUK K IN IKUH CREATER OF 2T+4" OR gate IOTXS: '1) Tntcrfcrencc such as pfpe hanger, pfpe vbip rcstrafnt, vali penetration, etc') rt spools of ~ trafght pipe rust bc provided betvecn fittings less than in dfs=ctcr. Also, no tvo velds in strafght pfpe should be closer together than the dfstance shova.
0 Kb o Specification D Specification for 4NSX Nuclear Safety Classes 1, 3 and ANSI $ 31. l Non-Nuclear Safety/Seismic Rl Category I and Seismically Designed Piping and Supports Project Identification No. CAR-SH-M-71 APPENDIX J Personnel Protection For 2" & Smaller Pipes Inside Containment (Up to 400 F)
Speci fication D Specification for AN~Nuclear Safety Classes 1, 3 and hNSI h31.1 Non-Nuclear Safety/Seismic R1 Category I and Seismically Designed Piping and Supports Project Identification So. ChR-SH-M-71 The folloving criteria is to be applied to determine piping inside containment to be fitted vith personnel protections Only piping vhich is 2" or smaller and vithout insulation need be considered. 20 Maximum operating temperature of 140 F to 400 F. Per hPPENDIX D, Piping Line List, pipes up to 140 F do not require insulation, and therefore do not require personnel protection devices. 30 Only piping vithin 7'-6" vertically and 3'-2" horisontally of areas vhere personnel are most likely to be (access platforms, valkvays, etc) need be considered. ased on the above criteria, the piping listed in this hppendix requires personnel 'protection to the extent indicated herein. The corresponding veight of the personnel protection for each case can be determined from the folloving tables WEIGHT OF PERSONNEL PROTECTION
, PIPE SIZE (in WEIGHT PER FOOT (lbs) 1/2 1.5 3/4 1. 55 1 1.6 1 1/2 1.7 2 1.8
Ebasco Specification Design Specification for AMSZ.Nuclear Safety Classaa 1 3 and ANSI 531.1 Son-Nuclear Safety/Seismic ry I and Seismically Designed Piping and Supports Project Identification
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Xbasco Specification Design Specification for 4$ 5+Nuc1ear Safety Classes 3 and ANSI B31.1 Non-Nuclear. Safety/Seismic Rl Ci y I and Seismically Designed Piping and Supports Pro)ect Identification No. CAR-SH-M-71 Correlation to Valve Ta Number V 1-SF-B 205A 6 B18 SB V 9-SF-B 31SN V 2-SF@ 1%A & B2SB V 10"SF-B11SN & B16SN 0 3-S%-i ISA & V2SB V 11-SF-V4SN V 4-SF-B 3SA & B4SB V 12-SF-B32SA 6 B33SB V 5-SF-B 9SA & B10SB V 13-SF-B22SA 6 B21SB V 6-SF-B 19SA 6 B15SB V 14-SF-B17SA V 7-SF-B 28SA & B24SB V 15"SF-B34SA 6 B35SB V 8-SF-B 29SA 6 B30SB V 16-SF-82kSA 6 B25SB NOTES Modes correspond to the folloving: Node 1-Both trains operating Mode 2-One train operating. Temperature given applies only to that train operating. Second train is assumed to be ambient. Mode 3-Both trains are assumed out oi service allcaring the pool to boil. Subsequently, one train is started. Temperature given applies onl to the train vhich is operating. This condition is not nostulated to occur
~~~coincident vith the SSE.~~
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2. The system is arranged such that the trains may be cross tied. This means that, one train operating "can be taken as pump" A" feeding heat exchanger "B" or vice versa.

3. Temperature indicated is for both Ãev and Spent Fuel Pools alligned to the pumps. If only the Spent Fuel Pool is alligned, this temperature is ambient.

4. The Purification System vill be isolated in this mode due to temperature limitations of the Demineraliaer.
~~Valve is open or closed depending on vhich pools are in use.~~
~~6. Valve(s) is (are) open for filling operations only. The~~
~~.temperature in this case vould'e taken to be "ambient" and System Operating Mode "Normal.~~
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'1 Ebasco Specification Design Specification for ASI Nuclear Safety Classes Rl 1, 2 6 3 and ANSI $ 31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports Pro]ect Identification No. CAR-SH-M-71 Allowable loads for nozzles interfacing with piping covered by this specification shall be obtained from the applicable vendor specification or drawing provided, through the Ebasco EMDRAC System, or the applicable Ebasco specification or drawing. In the absence of Vendor Information, the allowable nozzle loads shall be determined as shown below: 0 Maximum 0 eration Tem erature F 0 eratin Condition 140 and above below 140 F Normal 500 A 625 Z 300 A 375 A Upset 700 h 875 Z 400 A 500 Z 800 'A 1000 Z 460 Z 565 Z Emergency Faulted 900 A 1125 Z 500 A 625 Z Self limiting thermal loads 400 Z 500 Z 200 A 250 Z included in all above cases wheres h ~ Metal area of connecting pipe (in. 2 ) Z ~ Section modulus of connecting pipe (in. 3 ) F ~ Total resultant force acting in any direction (ibs) M ~ Total resultant moment acting in any driection (ft-lbs) Notes F and M are assumed to act concurrently
Kbasco Specification Design Specification for ~~ Nuclear Safety Classes 1, 2 6 3 and hNSI b31.1 Non-Nuclear Safety/Seismic Category I and Seismically Designed Piping and Supports Project Identification No. CAR-SH-M-71 hPPENDIX D Piping Line List
Ebasco Specification Design Specification for RH53 Nuclear Safety Classes 1, 2 6 3 and hNSI 531.1 Non-Nuclear Safety/Seismic ategory I and Seismically Designed Piping and Supports Project Identification No. CAR-SH-M-71 hPPENDIX D Piping Line Liat 1364 - S070
Ebasco Specification Design Specification for gl/5X Nuclear Safety Classes 1, 2 & 3 and hNSI B31.1 Non-Nuclear Safety/Seismic tegory I and Seismically Designed Piping and Supports roject Identification No. CAR-SH-M-71 hPPENDIX E Reactor Coolant System Designs Transients
Ebasco Specification Design Specification for gg5+Nuclear Safety Classes
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~~'ESIGN ~~~~
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pa++~ (pgmaQ J J Fhllt~ (aeratL) m i'bssco Specfffeatfon Desfgn Speeifi<<atfon l,l g 3 and for CHSXÃuelear Safety Classes b3!.1 Non-Su>>lear Safatylgefsnf>> Hme1% EP48qE~y RA G~pdy3hf- ~i'kKTEO ~ 14HE55d<<MT'. RP+5 ASSI bl Category I and Seisnieally Designed piping and Supports DEB6iN STRE.SS Celmw~~g ~o>x prefect ldentificatiotl SYSTEM bo. CAS Sb-ff-)I RJEL Foot. GooUN4)cfststvp JHKLBRL
Shearon Harris Nuclear Power Plant ~ ~~CICi \ .8l The staff review of your response to Q2I0.64 finds that we need additional information regarding how assurance is obtained that Code requirements in NB/NC/ND-3600 are met. Your response states, "In the case of pipe wall thickness determination, Ebasco Design Criteria MNE-65 for pipe line sizing applies, and a standardized worksheet (MNE-WS-16) is employed to document this calculation." Provide several, examples of the above worksheets for various ASME Class I, 2, and 3 piping applicable to Shearon Harris for our review.
~~RESPONSE~~
Attached are three examples of pipe wall sizing using the standardized worksheet, MNE-WS-16, for each classification of ASME Section III piping. In addition to the worksheets, other pertinent portions of the piping wall thickness calculations have been included in order to assist you in reviewing them. Items included in the calculations which do not pertain to determining the wall thickness of the example pipe lines have been so noted. The example calculations provided are part of the following calculations: Pipe Calc I IO - ASME Section III Class I - Reactor Coolant System Pipe Calc 80 ASME Section III Class 2 Fire Protection System Pipe Calc 65 ASME Section III Class 3 - Component Cooling Water System (1941 JDK/mf )
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~ AI.LOWABLfSTRf55, P5I I %9oo D ~ OUTSIDE DIAMETF.R OF PIPE, IN f0050 It. 70D C o aLLOwAHCE FOR MINIMUM STRUCTURAL STABILITY O,o)S y ~ COEF F ICIEHT m MINIMUM PIPE WALL THICKNESS, IH. (See NOTE2) 1~2. 00 n ~ HOMINAL WALL THICKNKSS, IN. (Stt NOTE3)
FIRST STANDARD SCHEDULK THICKNESS EOUAL TO OR GREATER THAN 0.7(8 l. IZ> SCHEDULE (CORRESPONOIHG TO s) SCHEDULE SELECTED IiCH(6O gC< 160 IICN IW SCtl g E IO o IHSIOE DIAMETER OF PIPK, IH. (Ste NOTE 1) C ALLOwaHCE FOR MINIMUMSTRUCTURaL STAbILITY Y COEFFICIENT m o MINfMUMPIPK WALL THICKNESS, IN 9 (See NOTE 2) n HOMINAL WALL THICKNESS, IH. (See NOYE3) s FIRST STANDARD SCHEDULK THICKNESS EQUAL TOOR GREATER THAN n SCHf DULK (CORRESPONDING TO s) SCHKOULE SELECTED Use either of the following equations fo determine fm: 8ASED ON OUTSIDE DIAMETER 8ASED ON INSIDE DIAMETER (Set NOTE 1) PxD C
~~~PID 2 EcA ~201 90 2 (SE+ Py) 2 (SE + Py- P)~~
~~C Allowonce for minimum structural stability~~
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00 w 50 0.065oo (or 1/2 to 3.1/2 inch nominal pipe sist 0.000 for d Inch nominol pipe sist ond I ~ reer HW TC ~+F'LE &6@8.: SEBB Mosimum allowobl ~ stress in motorial dve to internal pressur ~ ond loint ef(icioncy, ot the design temperature, psi. 8 00 .03d for pipe ordered to specified machined I.D. with topered backing ring ond ostrvded pipe specified by I.O. with topered boclcing ring. 00 .000 for the above pipe with flat beciing ring or other typos of pipe with ony Design Guide M 4 backing ring. y w A coofficIent hoving values as le(lower IYeeNOyf4) TEMP. F 900 AND BELOW 950 1000 1050 1100 1150 AND ABDVE Ftrritic Steels OA 08 0.2 D.r 0.2 0,7 Avstenitic Steel ~ OA OA OA OA OA5 0.7 NOTE 1 o (fse moslmIEn possebfe inside dI'omtttr with eff its toftIoIIces on well thIcintss onct ovtsIEtt Itlomtftrs, tsctpt for pipe erdtred to specified mochIIItd I O. ond esrrudtd pipe specified by I O. where nore d, porogIce5h 4 o( Design Cvlde MNEAS governs NDTE 2 ~ Tht pipe wolf thlcintss rtavlrtd tor a given pIt E curt rtmperorure ceIwtI'rien Increases es pipe sist Incrtoses. NOTE 3 - For stwIIftss plpt vst 'O d)g I ltr ony slat of piers plpt, tdd 0.010 inches te the colcvfored m re obtain 50 ~ NOTE d Tht value ot y moy be Inrtrpeftred)5ttwton 50 F velvet shown*ovr. For nonftnevs moterlels EsId cost iron use y t 0.* GENERAL NOTESE Set (ytslgn GvlJt MNE 65 Pipe Line Sls'ng for specific lnformatlono CLtbNY CA IZ ~ ( /I/A'ne/? 4ldH'7 t"o. STATION STANDARDIZED WORK SHEET otoi009 ~A~P~M'~/ dl C EP a=A fbd'Arci Phf PIP E WALL THICKNESS AND SCHEDULE DETERMINATION AD CND5NEED
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SYSTD f >. 1 ST RKVISION 18 (02/29/1984 ) 653 REACTOR COOLAN'I CAROLINA POWER 5 LIGHT CO REPu4T UNIT <<1 SHEARON HARRIS NUCLEAR POWER PLANT UNIT <<1 SYSTEM RC IDENT IF ICATION PIPE WALL MAXIMUM PRES SYS STRESS THICi<NE SS OPERATINQ DESIGN STO. HYDR INS- ANALYSIS C S NOMINAL OR SCHEO. IDKNTITY, PIPE COOE- OR TEST ULA- R . A Y SIZE CHANL 8 ~ $ $ $ 5$ ~ $ ~ ~ ~ 5 ~ ~ b ~ ~ PRES TEMP PRES TEIIP ANSI PRES 5 TION SEIS THER E 7 SPEC O.D IAL (F) P (F) RATG PSIG I GRP. -MIC.-MAL RK MARIC5 V
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~~1 RC 29 1SN, ASME Ill 2485 641 2485 650 106 B I-H YES LOOP EG 1 REACTOR COOLANT HOT L FURNISHED BY MESTINGHOUSK 29~~
$ 10 WITH 2.33 MIN WALL 1 RC31 2SN ASMK Ill 2485 588 2485 650 3108 C I-H YES LOOP 1 REACTOR CDOLANT CROSS OVER LEG FURNISHEO BY MESTINGHOUSE 31 "IO VlTH 2.18 MIN WALL 1 RC 27 1/2 35N ASMK 111 2485 589 2185 550 3106 C I-H YES LOOP 1 REACTOR COOLANT COLO 1 LEG FURNISHEO BY WESTINGHOUSE 27 .5 IO WITH 2.21 MIN MALL 1 RC 29 45N ASME 111 2185 644 2485 650 3106 B I-H YES LOOP 2 REACTOR COOLANT HOT L EG F URNI SHED BY ME ST INGHDUS E 29 "IO MITH 2.33 MIN WALL 1 RC 31 ASME 111 2485 588 2185 550 3106 C I-H YKS LOOP 2 REACTOR COOLANT CROSS OVER LEG FURNI SHED BY WEST INGHOUSK 31 $ 1D WITH 2.18 MIN WALL el 1 RC 27 1/2 BSB ASME 111 2185 589 21b5 850 3108 C I-H YES LOOP 2 REACTOR COOLANT COLO 1 LEG FURNISHED BY 'WESTINGHOUSE 2 7.5 10 WITH 2.21 MIN MALL 1 RC 29 ASME 111 2485 841 2485 550 I-H YES LOOP 3 RKACTOR COOLANT HOT L 1 EG FURNISHEO BY WESTINGHOUSE 29 IO WITH 2.33 MIN WALL 1 RC 31 ASME 111 2185 588 2485 850 3108 C I-H YES LOOP 3 REACTOR COOLAN'f CROSS OVER LEG FURNfSHED BY VESTfNGHPUSE 31 $ ID WITH 2.48 MIN MALL RC 27 1/2 95N ASME 111 21b5 589 2485 550 3108 C I-H YES LOOP 3 REACTOR COOLAN1'OLD 1 LEG FURNISHEO BY WESTINGHOUSE 2 ii4-AkY' ' 10SA SCH 150 ASME 111 55- 1 A-375-304 2185 611 1500 3108 8 I -H YKS 5$ f V 2 1 HOT LEG INLETTO SIS H I 8 LO HO RECIRC 21'.OOP ~t <uv~ii ~lu (es~ ~8<44>D Of ~wzwsw pa%i g T 00 O
SYSTKM RC LINK LIST REVISION 18 (02/29/1984) PAGE 654 RKACTOR COOLANT CAROLINA PONER 8 LIGHT CO REPORT UNIT 41 SHEARON HARRIS NUCLEAR PO'NER PLANT UNIT 41 SYSTEM RC IDENTIFICATION PIPE NALL MAXIMUM PRKS SYS STRESS THICKNESS OPERATINQ O'ESIGN STD. HYDR INS- ANALYSIS S NOMINAL OR SCHED. IDENTITY PIPK CODE- OR TEST I ULA R Y SIZE CHAN/ 8 sssrdrsss artsd<<st ~ sssd ~ s ~ s PRES TEMP PRKS TEMP ANSI PRES S TION SEIS THER K S (IN) LINE NO SPEC 0.0 CLASS MATERIA!. PSIG (F) PSIG (F) RATG PSIG GRP. -MIC -MAL REMARKS V
~S ~S ~S ~S $$$$$~ ~S $$~$$$~$$ ~s ~$$$~$$$ ~s ~$~$$$$ ~s ~ s ~$~s sr r ares s ~s ~ s ssrs ~s sr ~ r ~ s ssr ~ rss ~ s ~ $ ~ sss ~ sssrss ~s ~ ssr ss RC 3/4 I ISA SCH 160 ASIIE 111 SS-I 2485 644 2485 650 5500 3108 8 I-H YES LOOP I HOT LEG TO PI 405 ANO 00 2 A-378-304 PT 403 1 VALVE 2 RC V 1SA 13 RC 12 12SA SCH 140 ASME 55-2 2485 644 24S5 650 1500 3108 I-H YES LOOP 5 HOT LEG OUTLET TO RHR 00 -376 3 SY T RC 13SN SCH 160 ASME 111 S 24 5 644 LOO 5 T LEG UTLKT RC I A-376-304 RTD RC 14SN SCH 160 ASMK 'Ill SS- I 2485 844 2485 850 1500 3108 8 I-H YES LOOP I HOT LEG OUTLKT TO RCS 00 I A-376-304 RTD RC 15SN SCH t80 ASMK 111 SS-1 2485 844 2485 850 5500 3108 I-H YES LOOP I HOT LKG OUTLET TO RCS 00 A-378-304 RTD RC 2 ISSH SCH 180 ASME III 55-5 A-378-304 2485 RI ~ )~15~5 1ooo 3 100 I-H YES LOOP RTD I HOT LEG OUTLKT TO RCS 00 BUTT MELD ENDS VALVK I RC V, 2SN 13 VALVE 1 RC V 109SN 13 ygkht 2 Rc 3/4 17SN SCH 160 ASME 2
lll SS-I A-376-304 2485 5$ 8 2485 850 1500 3108 C I-H YKS LOOP I CROSSOVER LEG TO FLON 00 TRANSMITTER 4 56 I VALVE 2 RC V 3SN 13 2 RC 3/4 ISSN SCH 580 AS15E 2 Ill SS I A-378 304 2485 58S 2485 650 1500 3108 C I-H YKS LOOP I CROSSOVER LEG TO FLON 00 TRANSIII TIER 4 55 I VALVE 2 RC V 45N. 53 Os 2 RC 3/4 19SN SCH 160 ASMK 2 lll SS-I A-37b-304 2485 5$ 8 24S5 850 1500 3508 C I-H YES 5.OOP I CROSSOVER LEG TO FLON 00-TRANSMITTER 414 1 VALVE 2 RC V 13 2 RC 3/4 20SN SCH 180 ASMK lll SS-5 A-378-304 2485 5$ 8 2485 650 1500 3106 C I-H YES LOOP 1 CROSSOVER LEG FROM FL 00 SSN ~ '4 2 ON TRANSMIFTKR RETURN I VALVE 2 RC V 65N 13 I)g~l RC 2150 SCH 150 5535 I lll 55 'I A-378-304 2155 olol2ioo 5~5 1500 3105 I-H VKS 5.00P I CROSSOVER LEG INLET T 00 0 RCS RTO I VALVE I RC V 5055N 13
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SYST)M LINE DEIIGNATION NO. '5CC 9 'IITAONCG5 0'I LI II% L'I 0 P ~ DKSICN PRESSURE. PSIG T ~ DESIGN TEMPERATURE, F (ES PIPE SPECIFICATION IL GRADE E ~ ALLOwaBLE STRESS, PSI D ~ OUTSIDE DIAMETER OF PIPE, IN. C ~ ALLOwaNCK FOR MINIMUM STRUCTURAL STABILITY y COKF FICIEHT m ~ MINIMUM PIPE WALL THICKNESS, IH, (Sre HOTE 21 C), C)Q n ~ NOMINAL WALL THICKNKSS, IH. (Ser NOTE 3J FIRST STANDARD SCHEDULE THICKNESS KQUAI. TO OR CREAT ER THAN SCHEDUI.E (CORRESPONDING TO s ) SCHEDUlE SELECTED ID ~ INSIDE DI AMET E R OF PIPE, IN. (See HOTE 1) C W ALI.OWANCE FOR MINIMUMSTRUCTURAL ST ABII.ITY y ~ COK p FICIEHT m A MINIMUMPIPE Wat. L THICKHK5S, IN . (Sre NOTE 21 n NOMINAl WALL THICKNESS, IN, (Srr NOTE 3) s ~ FIRST STANDARD SCHEDULE THICKNESS EQUAL TO OR CREATER THAN SCHEDULE (CORRESPOHDING TO s) SCHEDULK SELECTED se either of the following equations to determine tm: BASED OH OUTSIDE DIAMETER BASED ON INSIDE DIAMETER (Sre NOTE 1) P<D C
~~~ PvIDe2SE ~ 2 PC +B 2 (SE v Py) 2 (SE+ Py P)~~
C 00 Allowonce (or minimum sttuctvrol stobil0ty 00 0.065" for )/2 to 3.)/2 inch nominol pipe sise BE i 0.000 (or inch nominol pipe siss ond lorger SETE Mosimum ollowobl ~ stress in moteriol due to intemol pressure ond jo0nt ~ f(iciency, ot the design temprroture, psi. B 00 .038 lor pipe ordered to speci(ied mochined I.D, with tapered bocbfng ring ond ertruded pipe specified by I.D. with topered beeline ring. 00 .000 for the above pipe with fist becoming ting or othet types of pipe with ony Design Guide M-d boching ring. y EB A coef(icient hoving volues os (ollows: (See NOTE@) TEMP. F 900 AND 0 ELOW 95D 100D 1050 1100 1150 AliD ABOVE Ferritic Steels DA 08 09 B.T O.T 0.7 Austenitic Steels OA OA OA O,d 0,$ 0.7 NOTE 1 Use rreci5990099 possibfe insidr di'oVNerrr with oil its references en Evoff thfclnrts oildovrsfdr C'Iomrrrrs, ercept for pipe ordered to specified mochinrd.I.D. ond rstrvdrd pipe tprcif.rd by I.D. Bvhrrr note 8, porrgioph 4, of Design Guide MHE45 governs. fvOTE 2 The pipe woff th cl rss rEI iredf<<o g'n p ~ cs<<e rr pr et<<e condition I c roses os pipe rise increosrs. NOTE 3 ~ F<<srrr91(rss pipe vsr ~gg 1 for ony sire of pter ~ pipe, odd 0.010 inches to the cofcvfored m te obtain tn NOTE d ~ Thr vefve of "y moy be'jnrrrpoforrd brrwrrrl 50 F vefvrs sho90n obove. For nonferrous motrriofs ond cost iron vc ~ y ~ O.i. GENERAL HOTES. Srr Drsigri Gvi'dr AINE d5 PI'pe Lfnr Siring w for specific infonnotion CI IKNT Qf)Est@is HP Ir'< ver@- < I 'LCiH s C~yqp(EB S~i 3 ot= g sl gN STANDARDIZED WORK SHEET aosKcT 5 g. 0.~% &A(Lated sit3c L~ 7+ 's~ ((ti.AH% PIP E WALL THICKNESS AND SCHEDULE DETERMlNATION ii00 N c5NCC Kg*geo sKavrcKs tttcoapoaaTKD
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d5-f SE ~ AL LOtr ABL E ST R ESS, PSI M OUTSIDE DIAMETER OF PIPE, IN. C ~ ALLOtrAMCE FOR MINIMUM STRUCTURAI. STABILITY y COEFFICIENT m M kiIHIMUM PIPE WAI.I. THICKNESS, IH. (See NOTE 2) E),O~ 0 n ~ NOMINAL WAI.L THICKNESS, IN. (See NOTE 3J O,z37
~~~ ~ FIRST STANDARD SCHEDUI.E THICKHESS EQUAI. TO OR GREATER THAM SCK E DUL E (COR R ESPOMDING T 0 s 1 SCHEDULE SELECTED ID ~ INSIDE DIAMETER OF PIPE, IH. (See HOTE 1)~~
C ALLO AMCE FOR MINIMUMSTRIICTURAL STABILITY y 0 COEFFICIENT m ~ MINIMUMPIPE WAI.I. THICKNESS, IH ~ (See HOTE 0) tn M NOMINAL WALL THICKNESS, IN. (See NOTE 3) s ~ FIRST STAMDARD SCHEDUI.E THICKNESS EQUAl TOOR GREATER THAM SCHEDULE (CORRESPOMDIHG TO s) SCHEDULE SELECTED se either of the following eqvotions to determine m: BASED ON OUTSIDE DIAMETER BASED ON INSIDE DIAMETER (See HOTE )J I Pi D C PTRID+2S C+ 2 P S 2 (SE v Py) 2 (SE + Py- P) C 50 Allowonce (or minimum atrvctvrol stobility EE 0.065" for 1/2 to 3 1/2 inch nominol pipe site EE 0.000 for 4 inch nominol pspe siss ond lorger
~~- SEER Mosimum ollowobl ~ stress in moterlol due to internol pressure ond joint effic(ency, ot the design temperorure, psi.~~
8 05.038 for pipe ordered to specified machined 1.D. with topered boc'king ring ond ertrvded pipe specified by I.D. with top'ared backing ring. BR .000 for the obove pspe with flot bocking ring or other types o( pipe with ony Design Guide M-IS boc'king ring. y BB A coefficient having wolves aa follower (See NOMe) TEMP. F 900 AMO BELOR 950 <000 '1050 1100 '150 AMO ABOVE Ferritic Steel ~ .OA 08 OT O.T O.T 0.7 Avstenitic Steels D.d OA 0.d 0.4 0.5 0.7 NOTE ) Use moEimLETT petaib)e <nside dlomefer with oil lrs rolenBdces on well rhicbneta o<<dolrralde d<'ometeFS, ~ ECept (or pipe ordered to specified mochined J.D. ond estrvded p:pe specified by J.D. where nore (L p<<og<<rph 4, ol Design Gv<'de MMES tfovems FDTE 2 The pipe well thickness 909tu(red for 0 give<9 p<ettvre remperotuF ~ cond<t<on increases os pipe s(te increoses.
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tECTE 3 ~ For seer<(ess p<pe vse ony ~ Ise el plo< ~ pipe, odd 0.0)0 inches to the co(cu(ored tm re obroin 50. NOTE 4 ~ The volve ef y moy be into<pe(ored betwee<R 50 F volves shown obove. For nonferrous moteriols ond cost (<on use y ~ 0.4. GENERAL, NOTES. See Des<gn Gv(de MNE.dS Pipe Line Sising << for specif<c in%%drmot(on. Q&~OL<WP. 9c..eyt. < 1 kC-H'B (-~O~P(s S~i S ot=g STS )M STANDARDIZED WORK SHEET PIP E WALL THICKHESS AHD 'AR<ART ~5% ALB N <AAILILIB TAUT Lvve rR A.l< sic<5'I4T SCHEDULE DETERMINAT)OH A P Pit OY CO c'z.~-f9 OATC OATC c SAScO sett Ytcc5 ttEcortportATco MECHANlCAL-NUCLEAR ENGIHEERlHG WORK SHEET MHE-WS 16 9 ~ v ~ cev ssoer zrd. 8/ + rd zy t))
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SYSTEM LIHE DESIGNATION HO. ~CE PL~4<H%.'D L Kt IOE U'5 5 I P ~ DESIGN PRESSURE, PSIG T ~ DESIGN TEMPERATURE. F i IPE SPECIFICATIQN d GRADE CS -I A/0C" 5I3 E ALLOwaBLE STRESS, PSI D OUTSIDE DIAMETER QF plpE, IH. C ~ ALLOwaNCE FOR MINtMUM STRUCTURAL ST ABILITY y COEF F ICIENT m MINIMUM PIPE WALL THICKNESS, IH. (Ser NOTE 2] 0, C7+ n ~ HOMINAL WALL THICKNESS, IN. (Sre NOTE 3l FIRST STANDARD SCHEDULE THICKNESS EQUAL TO OR GREATER THAN SCHEDULE (CORRESPONDING TO to 1 9 SCHEDULE SELECTED ID ~ INSIDE DIAMETER OF PIPE, IN. (Srr NOTE l) C ALLOWANCE FOR MINIMUMSTRUCTURAL STABILITY y COE F FI CI EHT
~~- MINIMUMPIPE WALL THICKNESS, IH. ISre NOTE I tn ~ HOMINAL WALL THICKNESS, IN. (See NOTE 3) s ~ FIRST STAHQARD SCHEDULE THICKNESS EQUAL TO OR GREATER THAN SCHEDULE (CORRESPONDING TO s)~~
SCHEDULE SELECTED se either of the following equotions to determine m: BASED ON OUTSIDE DIAMETER BASED OH INSIDE DIAMETER (Sre NOTE II
~~~v PVE D ~ PN ID~ 2SE ~ 2 PC 0~~
2 (SE v Py) 2 (SE+ Py- Pl C 50 Allowance (or minimum structurol stobility 00 0.065" (or 1/2 to 3 1/2 inch nominol pipe eisa 00 0.000 (or 1 inch nominal pipe sis ~ ond larger SELv Mosimum ollowobl ~ stress in'oteriol due to internol pressur ~ ond joint ~ fficiency, ot the design temperoturr, psl. B n .038 (or pipe ordered to sprcified machined I.D. with topered backing ring ond ertrudrd pipe specified by I.D. with topeled backing ring. 00 .000 (or the obove pipe with (lot boching ring or other types ol pipe with ony Design Guide M.4 boclaing ring.
~~-y A coefficient hoving volues as follaws: (SeoNOTE4]~~
TEMP. F 900 *NO BELOW 950 1000 1050 1100 1150 BNO ABOVE Ferritic Steels OA 08 0.7 0.7 0.7 0,7 Austenitic Steels OA OA OA OA 0.5 0.7 NOTE l v Vtr mrsim5099 pOSShble inshde diameter with oil its tolrhanC ~ S On wOII thiclnrts ond outside Ciomerrrsh ~ SCEPt lor pipe orclrred to speci(1'rd mochh'nrd I D. olid rstrhhdrd p pr speci(1'rd by I D. where norr 0, poroghct5h W, o( Design Cuh'dr AIH&$$ 0 governs NOTE 2 ~ Thr p'pr <<oll th clnrss rrEtuirrd for o gi ~ press re tr prroture condition increases os pipe siss increases, thrOTE 3 v NOTE k F<<srlsvhlrss phpr usr Qtr i for ony siss ol piete pipe, odd 0.0IO inches to thr calcu(otrd m re obtain tn ~ Thr volur el "y moy-be intrrr7o(etrd between SO F voIurs shown*eve. For non(mous met<<iols ond cost iron use y s 04. QM -I. Oap tr'. CENERAL NOTES. Srr Drshg59 Cuidr MNE.65 Pipe Line Siring
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In%%drmatlon. S~a S ot- Q STANDARDIZED wORK SHEET PIP E WALL THICKNESS AND SCHEDULE DETERMINATION SN c5 NECN OATK ~ KIASCO SKRVtCKS ttrCORI ORATKO HKCKKD MECHANICAL-NUCLEAR ENGINEERING OaTK WORK SHEET MHE.WS 16 APPROVKD OATK Osurcevlses5 if'/lg. zs) p /(s $ z7
TEM ~ F LIST REVI SION 17 ( 12/01/1983 ) Pn 459 FIRE PROTECTION CAROLINA PO'WER d LIGHT CO REPORT ) UNI T N I SHEARON HARRIS NUCLEAR POWER PLANT UNIT 2$ 1 SYSIEM FP IDENT IF I CAT ION PIPE WALL MAXI MUM PRES SYS STRESS THICKNESS OPERA'TING DESIGN STO. HYDR INS- ANALYSIS C 5 NOMINAL OR SCHEO. IDENTITY PIPE CODE- OR TEST I ULA- R A Y SIZE CHANL d ~ sasd ~ ~ as ~ aasds ~ Sa aa ~ Rdsssa PRES TEMP PRE5 TEIIP ANSI PRES 5 TION SEIS THER E T 5 (IN) LINE NO SPEC 0.0 CLASS MATERIAL PSIG (F ) PSIG (F ) RATG PSIG I GRP. -MIC -MAL R E M A R K 5 V 6AF.C. ~ ~ ~ ~ ~ ~~ ~~ ~ S ~ S ~ $ $ ~ $ ~ as ~ sss ~ ~ ~ ss ~ $ ~ ~ ~ $ $ RRRS ~ ~ s ~ s ~ ss RS ~ S ~ ~ ~ ~ ST ~ ~ ~ ~ Ssa ~ $ $ ~ ASAR ~ s s ~ ~ s R a s s R ~ s ~ R R R s s s R R s R 6 '6 R R ~ R O,2 FP 6 I l626 SCH 40 ASME 111 CS- 1 160 105 175 125 150 219 I YES FP TO CONTMI'LDG SPRINKLER 00 2 A- 106-GRB SYS 1 VALVE 2 FP V aSSn 13 1 VALVE 2 FP V 46SN I5 80-P 2 Fr 1195M SCH 40 ASME 111 C5-1 160 105 175 125 150 219 I YES FP TO CONTMT BLDG 00 2 A 106-GRB VALVE 2 FP V 445A 13 1 VALVE 2 FP V 48SN 13 2FP 1 1205N SCH 80 ASME 111 C5-1 160 105 175 125 150 219 I YES FP TEST CONN 00 2 A-106-GRB 80 1 VALVE 2 FP V 475N 13 2 FP 1215N SCH 80 ASME 111 C5-1 160 105 175 125 150 2 'I 9 I YES FP TEST CONN 00 2 A-106-GRB SFP 3 122 SCH 40 831. 1 C5-2 160 105 175 125 150 2 10 50 NO HOR TO SPRINKLER SYS IN 8op 8FP 3 123 SCH 40 831. A-53 C5-2 GRB 160 105 175 125 150 210 CONTMT BLDG 1 SD NO MOR TO SPRINKLER SYS IN A-53 GRB CONTMT BLOC 80-P 8 FP 6 124 SCH 40 831. 1 C5-2 160 105 175 125 150 210 SO NO HOR TO SPRINKLER SYS IN A-53 GRB CONTMT BLDG VALVE 8 FP V 249 go-'FS FP 3 125 SCH 40 831. 1 C5-2 160 105 175 125 150 210 SD NO HOR TO SPRINKLER SYS IN A-53 GRB CONTMT BLDG 8FP 4 126 SCH 40 831. 1 C5-2 '160. 105 175 125 150 265 SD NO FP RISER IN CONTMT BLDG A-53 GRB COL 19,POST SSE STANDPIPE 1 VALVE 8 FP V 50 ~ l3 8FP 4 127 SCH 40 831. 1 C5-2 A-53 GRB 160 105 175 125 150 265 SD NO 'FP RISER IN CONTMT BLDG COL 12.POST SSE STANDPIPE ll VALVE 8 FP V 51 13 8FP 4 128 . SCH 40 831. 1 C5-2 A-53 GRB 160 105 175 125 150 265 50 NO FP- RISER IN CONIMT BLDG COL 4,POST SSE STANDPIPE ll VALVE 8 FP V 52 ~ ~ 1 VALVE 8 FP V 250 13 Ob dot Ape'~'~<V~ go mg<~p~ vlowdevgm~~ o
(8'" 5YST EM lOOlr) 0 c LINE DESIGNATION NO. P ~ Df SIGH PRESSURE ~ PSIG iSO AS'S-DESIGN TEMPfRATURE, F PIP f SPECIFICATIOH b GRADE I
~~-/f7(. 5cj)8 5~~
ALLOWABLE STRf$ $ PSI /S ooo OUTSIDE DIQrlfT f R OF PIPE, IH. I5',oo" C ~ ALLOWAHCE FOR MINIMUM STRUCTURAL STABILITY y COEF FICIENT m v MINIMUM PIP f WALL THICKNESS, IN. (See NOTE 2) n ~ HOMINAL WALL THICKNESS, IN. (See HOTE3) tov FIRST STANDARD SCHEDUI E THICKNESS EQUAI TO OR GREATER THAH SCHEDULf (CORRESPONDING TO ta) SCHEDULE SELECTED l~ ~ INSIDE DIAMETE R OF PIPE, IH. (See NOTE )) C ~ ALLOWANCE FOR MINIMUMSTRUCTURAL STABILITY y - COEFFICIENT.
~~~ MINIMUMPIPE wALL THICKNESS, IH ~ (See NOTE 21 n ~ NOMIHAL WALL THI CKHESS, IN, (See NOTE 3)~~
FIRST STANDARD SCHEDULE THICKNESS EOUAL TO OR GRf ATER THAN t SCHEDULE (CORRE SPOHDIHG TO a) SCHEDULE SELECTED se either of the following equations to determine m: 8ASED ON OUTSIDE DIAMETER 8ASED ON INSIDE DIAMETER ($ ~ NOTE )I Px 0 + PII ID+ 2$ E ~ 2 P 2 (SE ~ Py) 2 ISE + Py- P) CED Allowance for minimum structural stability BB 0.065" for 'I/2 to 3 1/2 inch naminol pipe siss BB 0.000 for d inch nominal pipe also ond larger SEBI Maximum ollowobl ~ stress in materi ol due to internal preasur ~ ond joint ~ fficlencyr ot the desfgn temperature, psi, 8 .038 for pipe ordered to speciRod machined I.D. with topered backing riny ond extrvded pipe specified BB by I.D. with tapered backing ~ iny. Bo .000 for the above pipe with flat backing ~ iny or other types of pipe with ony Design Guide M 6 backing ring. y BB A coof(icient having voluea aa follower (See NOTE d) TEIAP. F 900 AND 8ELOW 950 1DDO 155D 11DD 1155 IIIO ABOVE Ferritic Steels OA 0.5 0.7 D.r 0.7 0.7 Austenitic Steels OA OA OA OA Od 0.7 NOTE ) Use marfmcrrc possible insicfe Ciamerer with all It! rofenBnces on wall thfcirIess and outside cfiamerers, except for pipe err(ared to speciRed machined I.O. one( extrvcfed pr'pe speal(ied by l,O, where note B, parcrgrca5h i, o( Oesiyrc Gvr'da MHE4$ governs. NOTE 2 ~ The pipe waif rhIC iness trctBr'red (ar o y fvec9 Pres svre remparorvre concfr'rien increases oa pipe Sire inC reases. NOTE 3 - For seamless pipe vse ~;fcr ~ ony sire of pfore pipe, odd 0.0)0 inches te the calculated m ro abroin n. NOTE d ~ The volvo ol y moy be inrerpafared between 50 F valves shown above. For non(anovs mareriols crcd cost fran cze y ~ 0.4. GENERAL NOTESO See OasI'gn Guide MHE 6$ Pipe Line Sisiny ~ far speci(fc information. v T QACOLL HP tr'c5v>LTT- < LLC Iw~l CD ~pox STATION STANDARDIZED WORK SHEET QOJKC'T 5 (L46 BAIZE.I5 bS)3 C I-~ 7 ~ill. QiAP3V PIP E WALL THICKNESS AND SCHEDULE DET ERMINATION ct DATC g CSASCO SKttVICKS IICCOllPORATKD \ CHCCKCD
~ II Irsxa DATE l- ~r MECHANICAL-NUCLEAR ENGINEERING s EBaot195at9 g/Q, I p 2. g 7WORK SHEET MH EDWSv)6
EBASCO SERVICES INCORPORATED pavE 5HE EV OrZP CHKP. IY pavE pr5 Hp G ktK 33 ~ caiE~V ~CLOLl i> PP w 4 0 4 l l GA 7 C<l Lt hW E 5QQ ggog ll+Q.P.(h bLUC-l CAR. rO~~W >m i Ga/CCi (a f '0>> ap.', ~ H>q Wg<l.THAN+ ~AS C<LCuiaiOa f'OC. COm/CnPn7 5 -/in"
~~~ ~~~
~~PbR.Pc St .~~
~~'TH%'O>t <4< F ~l'5 ~l CQl Q~oQ lS 'Ta V~~l~y WlK kl Ml NON WAl I. t%le VNL&% l4f +ullTent& T/ e~<T < l~'N gl.L. 4W 4i< C-L=, WO C. SOS Wc q l-lHK.~~
R,Cc PC Q.Ch4C.% . I) SSWSC.C WeaaiwiC.CV<OO Wa-SA- tq-3~ Re. IC, Z) l.lug uSC ~e l> r q - lg ~O aCV. 55 C 3j HuK WS- l4 D<PP Wall. ~CgV~5, C SCAN Oui'g~lEWiuarioe e 1
~~~~%'R PlPll5Cs ~PL. fall%( B'3l ) 'I<7l YH5LQ 5'l l'l3 ~~~
IJAV~ PLPle4C ChTa u' %,5. NO. LO RRV. SaJMC I, tR>'t ) C) A<Be 5tezc~H ~ 11'll to Mau 5 )175 LQ 5/dt's f<<eoeh L;ne ed'h.s gys-/equi ChE'Pcdcxv( Corrosi'on Ql/g~q<ce ('s'recTdei- Phon 81(p SPeC; fice( +PI)og ence. T$ eie f'~re, +he I'cg/( dh c4ners jJ cydeI, gape &r e~ch I.ae
~~'5ESIMS~~
EBASCO SERVICES INCORPORA7ED SHEET OF ~3 CHKD. bY .)LC DATE I Te ~) f OFS HO. pf PT. NO. CLIENT ~Re< L QA. V O u-'%9- 4 LC Qf'~'ttPAt4 8 / d.c i Sub>ECT NL H ~A l-4 TIL 'MGA ~L~ ~T<<< WP- 4%Q 6
~~].-g 4 /S' tv ~ (gg ~g y ~ g~p 4)~~
~~G. OPh' a =(+>>ossa') Li&%~~
~~<\4',p -t (Lief <LCT) zs Zid. 8) zX z7~~
0 ~ iw 9 e.~~ SvSTEM C C LINE DESIGNATION NO. P DESIGN PRESSURE, PSIG S'0 DESIGN T EMP E RATURE, F Ps5-PIPE SPF CIFICATIOH S GRADE - I.- 0'68
~
SE ~ ALLOwASLE STRESS. PSI ls ooo D OUTSIDE DIAMETER OF PIPE, IN. C ~ ALI OWAHCE FOR MINIMUM STRUCTURAL STABILITY y COEFFICIENT m 9 MINIMUM PIPE WALL THICKHESS, IN. (Set NOTE 2) n ~ HDMIHAI, WALL THICKNESS, IH. (See NOTE 3)
~~g. 9'2?~~
~~~ FIRST STANDARD SCHEDULE THICKHESS EDUAL TO OR GREATER THAN SCHEDUL E (CORRESPONDING TO ~ )~~
SCHEDULE SELECTED Sc/ g ID ~ IHSIDE DIAMETER OF PIPE, IN. (See NOTE l) C ~ ALLOwANCE FOR MINIMUMSTRUCTURAL STASILITY y ~ COEFFICIEHT ' MINIMUMPIPE wkLt. THICKNESS, IH ~ fSee NOTE 2) tn Y NOMINAL WALL THICKNESS, IN. (Set NOTE 3) FIRST STANDARD SCHEDULE THICKNESS EOUAI. TO OR GREATER THAN SCHEDULE (CORRESPONDING TO s) SCHEDULE SELECTED Sch /0 Use either of the follow>'ng eqIIotiona to determine tm: BASED OH OUTSIDE DIAMETER BASED ON INSIDE DIAMETER (Ste NOTE II P5 D 0 P 55 IO0 2 SEC w 2 PC 2 (SE w Py) 2(SEc Py P) Cw Allowance for minimum strvcturol stability 88 0.065" for 1/2 to 3.1/2 inch nominal pipe also 88 0.000 lor 1 inch nominal pipe cise ond lorger
~~- SEe Mosimum ollowobl ~ stress in motorial due to inttmol pressure ond Ioint ~ fficiency, ot the design temperature, psi.~~
B w .038 for pipe ordered to specified machined I.D. with tapered backing ring ond estrvdtd pipe specified by I.D. with toptrtd boching ring. 80 .000 for the obove pipe with flot backing ring or other types of pipe with ony Design Guide M.1 backing ring.
~~- y 88 A coefficient having volute os follawat (See NOTE@)~~
TEMP. F 90D AND 80LDW 950 1000 '1050 1100 115D AND ADDYD Ferritic Steels 0.1 0.5 0.9 D.i D.i 0.7 Avslenitic Steels OA1 OA . OA1 0.1 0;5 0.7 NOTE l Qst mesimum possible inside direneter with oil It ~ tefenmces on well thrclIness oncl outside diameters, tecept fer pipe ordered te sptcified mechi'ned I.b. ond tstrudtd pi'pt specified by I.D. where nett d, poiogieph 4. of Design Guide MHEAS governs. NOTE 2 ~ The pipe well thicbntss rteuIred f>> o yiven pressure temperature condition Increases os pipt sist Increases. NOTE 3 For sersrifess pipe~st ~jTfor ony sist of piers pipe, odd 0.010 Inches te tht cercvlartd m re obroin n NOTE 4 ~ The value ef "y moy'be inrtipeiered between SO F veiuts shown obcwe. For nenfeneus moreriois rsid cost Iron ust y ~ 0.4. GENERAL HOTESD Ste Design Guide MH&5 Pipt Line Sisiny for sf>>el(is Inlbnnotien.
~~.7 Q~C.(HO pouutTT- e t KC Hi C<tqP(s 5TATIOH PROJECT CHECKED 5 9-cs&~~
~~400 LhAKyl ~13e II IIICS 18 t.~ WwC~ QiAt4T~~
~C OATE Pf- STANDARDIZED WORK SHEET PIPE WALL THICKNESS AND SCHEDULE DETERMINATION ESA5CO SERVICES INCORPORATEO MECHANICAL-NUCLEAR ENGINEERING s P09889959e95 (5)8/d 96I/I g~ORK 5 z7 SHEE'T MN EAW 5.16
EBASCO Sr R V'1~<~ iHCORPORATED I <"'v " aevi~~ STREET I oF Olfl(6. SYA~ DATE'~~ OFS HO OE>T. ICONS CLIEIIT CA.'Rail VK V C u-'rP- <L4 W < N 4 v taoiacv ~ ~ Rh Q4.[ R 0 < tFAA2- V A 'P <AH a sueieav QLN wkly< Tll uGA WLCA ~T<<W W( l (4 6 ( ~~ = PDo aQscw ~y) yg C) (t 62.S)
~~+~ Z (Izooo + tb>x c7.<)~~
27
SYSTEM 9 ( kg/ LINE DESIGNATION HO'. .o.'(5a (" P DESIGN PRESSURE. P SIC DESIGN TEMPERATURE, F 2ao cs -i PIPE SPECIFICATION 4 GRADE )KI-/0&&RB SE ALLOWABLE STRESS, PSI /5 L3OO 0 OUTSIDE DILMETER OF PIPE, IH. C ALLOwAHCE FOR MINIMUM STRUCTURAL STABILITY COEFFICIENT y 20',ZW m MINIMUM PIPE WALL THICKNESS, IH. (See NOTE 2) HOMINAL WALI. THICKNESS, IH. (See NOTE 3) s w FIRST STANDARD SCHEDULE THICKNESS EQUAL TO OR GREATER THAN SCHEDUL E (CORRESPONDING TO s ) SCHEDULE SELECTED S7O ID ~ IHSIDE Di AMET E R OF PIPE, IN. (See NOTE 1) C ~ ALLOWANCE FOR MINIMUMSTRUCTURAL STABILITY COE F F I CI EHT m ~ MIHIMUM PIPE WALL THICKNESS> IH ~ (See NOTE 2) n ~ HOMINAL WALL THICKNESS, IN. (See NOTE 3) FIRST STANDARD SCHEDULE THICKNESS EOUAL TO OR GREATER THAN SCHEDULE (CORRESPONDING TO') Use either of the following equations to determine m: BASED ON OUTSIDE DIAMETER BASED ON IHSIDE DIAMETER ($ 00 NOTE il 2 (SE e D Py)
~~+ C PSKID+2SE o 2 PC 2(SEe Py P) i B e~~
~~C Allowance for minimum structurol stobility SE 0.065" for 1/2 to 3.'I/2 inch nominol pipe siso Rl 0.000 for 6 inch nominol pipe siss ond larger~~
~~- SEWE Masimum ollorobi ~ stress in moterial due to internol pressure ond ioint efficiency, ot the design ternperoture, psi.~~
B .038 for pipe ordered to specified machined ).D. with topered backing ring and ertruded pipe specified RE by I.D. with topered baching ring. w .000 for the obova pits ~ with f lot boc)sing ring or other types of pipe with ony Design Gvide M-4 backing ring. TEMP. F Ferritic Steel ~ Austenitic Steel~ 900 AHO OELOW OA OA 900 O.S OA
'.7 y RE A coefficient having volues as follower (See NOTE@) >000 OA 1050 0.7 OA 1100 0.7 0.5 1150 AND ABOVE NOTE I ~ Use mosll>99ESS passible inside dlcvr>erer with oil its toleronces on waif rhicinets and ourside dio>Haters> ercopr lar pipe ordered 0.7 0.7 ~ e specified mach>ned l>D> ond esfrvded pipe Epeclfiesl lry l.D. where note d> poragrcph d> of Design Gvide MNE45 governs.
O NOTE 2 ~ The pipe wall thicirsess required for o given presture rel>>Perature ce>>d rien increases os pipe else increoses. NOTE 3 For secET>fess pipe vse ~d >v (for ony siss or plate pipe, add 0.0lg inches to the colcvlatod m re obroin tn ~ NOTE i The volvo of "y moy be interpolated between 50 F valves shown above. For nonferrous mater>'als ond cost i>on vse y E 0.4. GENERAL NOTESE See Design Guide MNE 65 Pipe Line Slslng ~ for specific Information. C. T MOCi~p. P4vut~. ~ uC t'ai t"-i>pa STANDARDIZED wORK SHEET ',---; O.EEn( +4,Q.Q~ gt)e El> IOEEe I IETER8. ~uS OATC A 'PWAHV PIP E WALL THICKNESS AND SCHEDULE DETERMINATION EBAsco sKhvrccs tttcohpohATf D i0 ~ . r MECHANICAL-NUCLEAR ENGINEERING CHECKCD OATC WORK SHEET MH E+WSe)6 s paar>9>vrl
EBASCO SERVICES IHCORPORA"i'FD bY 0 a TK ~+ 5HEET OF CHKO. bY 'ATE OFS NO a9'E>T. HO
~~~Row \ ted&. V u-'~~~
~~4 <\< IA'7 c-~ H At@ Qc'h ~t ' PgogEcT 5ubiECT S H,LN mkL4 'Tlt~~
~~~ 0 L~Q V~~w~~~
~~VGS WL << ~Y<b< WQ P'L~Q \ i 'LUG v'mn m=~~m C. ) (Q ~~ = PDa zQsc+ pf)~~
~~/KO ~ C = 2(is ~go irt.-(.~))~~
0 "gg y G'.,37'
TEM CC Pj PC gS E LIST REVI SU'I 16 (9/15/1983) AGE 115 COMPONENT ilDLING WATER CAROL POWER d LIGHT CO REI UNI I 4 I SHEARON HARRIS NUCLEAR PO'WER PLANT UNI T > I SYSI cM cc'DFNTIF ICATION PIPE WALL MAX I MUM PRES SYS THICKNESS OPERA I ING DESIGN 5 ID. HYDR C 5 NOMINAL OR SCHEO. IDENTITY PIPE CODE OR TFST R A Y SIZE CHANL 8 s ~ aadsa ~ s ~ sasds ~ as asasdssa ~ PRES TEMP PRES TEMP ANSI PRES at E T 5 (IN) LINE NO SPEC 0.0 CLASS MATERIAL PSIG (F ) PSIG (F ) RA'fG PSIG Cc fc<]oe~oq REMARKS V
~~& $$ ~ '~~
sass ~ saass ~ s ~ $ $ $ $ ~ ~ ~ s $ $ ~ asssssa $$$$$$~~~ s ~s ~ s ~a ' sass a ~ $ $ a'ass ~ s ~ s aas sssssa ~ ss'asa' asassss as 3 CC 18 2SA STD ASME III CS- I 108 116 150 200 150 188 RTN HDR IO CC PMP IA-SA SUCT 07
~ t 3 A-106 GRB ION .I VALVE 3 CC 8 ISA 13.
I VALVE 3 CC 8 SSA 13 I VALVE 3 CC 5 ISA 13 3 CC 18 3SA STD ASME III CS- I 108 I 16 150 200 150 188 CC PMP IA-SA OISCH TO CC tlX 00 3 A-106 GRB IA-SA I VALVE 3 CC 8 2SA 13 I VALVE 3 CC 8 3SA 13 I VALVE 3 CC V 162SA 13 3 CC 18 ~ 4SA STO ASME III CS- I 108 105 150 200 150 188 CC HX IA-SA OUTLET 00 3 A-106 GRB 1 VALVE 3 CC 8 4SA 13 I VALVE 3 CC 8 19SA 13 3 CC 18 558 STO ASME III CS- 1 A- 106 GRB 108 I 16 150 200 150 188 RTN HOR TO CC PMP 18-58 SUCT 07 3 ION I VALVE 3 CC 8 658 13 I VALVE 3 CC 8 I ISB 13 VALVE 3 CC 5 358 13 3 CC 18 6SB 5TO ASME III CS- I A-106 108 1 1 6 150 200 150 188 CC PMP IB-SB OISCH TO CC HX 00 3 GRB IB-SB VALVE 3 CC 8 1258 13 I VALVE 3 CC 8 17SB 13 I VALVE 3 CC V 16458 13 3 CC 1S 758 STO ASME III CS- I 4-106 108 105 'I 50 200 150 I 8S CC HX IB-SB OUTLET 00 3 GRB I VALVE 3 CC 8 ISSB 13 I VALVE 3 CC 8 2058 13 3 CC 8 IOSN SCH 40 ASME III CS-I 108 105 150 200 150 188 CCW HOR TO RCP 00 3 A 'I06 GRB 3 CC 20 11SN STO ASME III CS A-106 GRB 108 114 150 200 150 188 HOR TO HX'5 3 3 CC 12 12SA STO A 3 E II A-106 GRB 8 120 150 200 I 0 I g R 1 HX tA-SA INLET 00 I VALVE 3 CC V 166SA 13 3 CC 12 13SA STO ASME 3 III CS- I A-106 GRB 108 145 150 200 150 188 D Q Q RH HX IA-SA OUtl.ET 00 VAI.VE 3 CC 8 2 ISA 13 VALVE 3 CC V 165SA 13
Shearon Harris Nuclear Power Plant , NRC(R i 2 .R The staff has reviewed your response to Q210.77 and finds it acceptable. However, your response does not necessarily follow from the Westinghouse design specifications. The problem is that Piping Specification G-678866 is a pipe material specification and does not control fabrication. The staff believes that the appropriate place to control the fabrication of a girth butt weld is in the fabrication specification (i.e., specification G-678803). Thus, the staff recommends that the specification G-678803 paragraph 5.3 on Butt Welds, be r4.vised by adding a subparagraph 5.3.5 which would reference the minimum wall requirements in Specification G-678866. For Example:
~~"5.3.5 The minimum wall thickness at girth butt welds shall not be less than the minimum wall thickness specified in 3.1.3 of Specification G-678866."~~
Provide a commitment to revise your specification as suggested above or provide the basis for assuring that the above requirements have been properly incorporated into the Shearon Harris facility.
~~RESPONSE~~
According to Item MEBQ210.82, the NRC recommended that the shop fabrication specification G-678803 be revised "in paragraph 5.3 by adding a reference to paragraph 3.1.3 of Piping Specification G-678866. This action is being requested in order to insure that the minimum wall thickness at girth welds made by the piping assembly fabricator is controlled. The NRC recommends this change made or that Westinghouse provide the basis for assuring that these requirements have been properly incorporated into the Shearon Harris facility. Westinghouse notes that revising the shop fabrication specification (G-678803) to incorporate the above request is impractical for SHNPP since the purchase order with the vendor (Southwest Fabricating 2 Welding Co.) is closed and the hot and cold leg piping was delivered to the site in 1976 and the crossover leg piping was delivered to the site in 1981. However, in accordance with the proposed alternate section, Westinghouse can provide assurance that the subject piping meets the requirements for minimum wall thickness in the area of the girth welds as well as the entire piping assembly. The basis is as follows: Paragraph 2.0 in Specification G-678803 for Shop Fabrication states "The following specifications, standards, or codes plus addenda form a part of this specification."
2) Paragraph 2:1.2 in Specification G-678803 specifically lists Piping Equipment Specification G-678866 as an applicable document.

3) The vendor's (Southwest Fabricating & Welding Company) fabrication drawing show the following in Note 22 for the different piping assemblies as follows:
Hot Leg Piping Drawings - 29" min. design thickness = 2.27" Cold Leg Piping Drawings 27 I/2" min. design thickness = 2.15" Crossover Leg Piping Drawings - 31" min. design thickness - 2.02" (1941 JDK/mf )
0) The vendor drawings are consistent with the minimum wall thickness requirements as stated in Paragraph 3.1.3 of G-678866. These drawings were submitted to Westinghouse for review and approval.

5) The "as-built" revisions of these drawings have the "as-measured" wall thicknesses listed in a table at the top of each drawing. These revisions are sent to Westinghouse for review and approval prior to shipment of the piping assemblies.

6) Each piping assembly has a nameplate attached that provides information as to girth weld location and the measured wall thicknesses at these locations.

7) Westinghouse QA insures that the vendor's inspection data is valid.
Based on the above, CPRL concludes that the specifications invoked and fabrication/ inspection methods employed were adequate to insure that the piping assemblies delivered to the Shearon Harris Unit l Site meet the minimum wall thickness requirements. (1941JOK/mf)
A C I 4 1
~~'I}}~~

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