ML13310B525

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Rev 0 to Project Design Criteria 15691-583, Walkdown Criteria for Evaluation of Safety-Related Small Bore Piping & Tubing
ML13310B525
Person / Time
Site: San Onofre 
Issue date: 05/10/1984
From:
Southern California Edison Co
To:
Shared Package
ML13310B524 List:
References
15691-583, NUDOCS 8406140192
Download: ML13310B525 (26)
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Text

RETURN TO SERVICE DESIGN CRITERIA FOR SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND TUBING SAFETY RELATED JOB NO. 15691-583 BECHTEL POWER CORPORATION NORWALK, CALIFORNIA W.P. # 82-163 9406'1401'92'-840609-'

PDR ADOCK 05000206 PDR 0

5-10-84 Incorporated SCE Comments and Issued to SCE for Approval B 2-16-84 Issue for SCE Review A

2-16-84 Issued for BPC Review REV NO.

DATE REVISIONSEG PE C-EF A

NO.'CGS (P0E 0CHIEF CA PF-5941 (14000) 12/8.

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF TITLE SAFETY RELATED SMALL BORE PIPING AND TUBING m 0.15691-583 RK,0 TUBING

-No.

REv.

PROJECT DESIGN CRITERIA

,PAGE or CONTENTS Page

1.

GENERAL DESIGN CRITERIA 1

1.1 General 1

1.2 Scope 1

1.3 Design Criteria 1

1.3.1 Seismic 1

1.3.2 Other 2

1.4 Classification of Structures, Systems and Components 2

1.4.1 Quality Class 2

1.4.2 Safety Class 2

1.4.3 Quality Group 2

1.4.4 Seismic Category 2

1.4.5 Design Codes and Standards 2

1.5 Environmental Design Criteria 3

1.5.1 Normal 3

1.5.2 Post-Accident Environment 3

1.6 Design Life 3

1.7 NRC Regulatory Documents 4

1.7.1 Code of Federal Regulations 4

1.7.2 Regulatory Guides 4

1.8 State and Local Regulations 4

1.8.1 Occupational Safety and Health Administration (OSHA) 4 Regulations 1.8.2 California Administrative Code 4

1.8.3 SONGS 1 Documentation 4

1.9 References 5

2.

MECHANICAL DESIGN CRITERIA 5

3.

ELECTRICAL DESIGN CRITERIA 5

4.

CIVIL/STRUCTURAL DESIGN CRITERIA 5

5.

CONTROL SYSTEM DESIGN 5

6.

NUCLEAR DESIGN CRITERIA 5

7.

PLANT DESIGN CRITERIA

,5

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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RV.

PROJECT DESIGN CRITERIA PAGE OF TABLES Page 1.2-1 Safety Related Small Bore Piping and Tubing to be 6

Walked Down 1.3-1 Recommended Span Length for Carbon Steel and Stainless 20 Steel Small Bore Piping 1.3-2 Recommended Span Length for Copper and Stainless Steel 21 Tubing 1.4-1 Classification of Piping Systems and Pipe Supports 22 0 0

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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16-3 PROJECT DESIGN CRITERIA I1 PAGE 23

1.

GENERAL DESIGN CRITERIA 1.1 GENERAL The December 22, 1983 report on Return to Service (RTS) (Ref. 1) identi fied the need to assure that the existing small bore piping and tubing support configuration at SONGS 1 meet the industry practice.

This criteria will demonstrate the capability to achieve and maintain a hot standby condition in the event of a postulated Design Basis Earthquake (DBE).

1.2 SCOPE A field walkdown of 2" and smaller safety related piping and tubing as listed in Table 1.2-1 will be conducted to identify any possible anomalies in the design or installations.

These piping systems will be evaluated to verify that:

(1)

The existing deadweight spans do not exceed the recommended span lengths as specified in Tables 1.3-1 and 1.3-2.

The span length is based on straight run of piping which produces approximately 2500 psi longitudinal deadweight stress.

Appropriate span reduc tions shall be used where concentrated masses (i.e., valves, couplings, etc.)

or multiple bends exist in the piping run.

(ii)

Where valves have extended operators, proper attention should be given to the possible stiffening or support of the operator.

(iii) Where branch lines connect to a header that was not specifically analyzed along with the branch, header thermal and seismic movements shall be taken into consideration in the support of the branch line.

(iv)

In cases where piping has a long run with little or no lateral support, a check shall be made to ensure that excess deflection of the piping will not cause damage to the piping or other equipment.

(v)

Pipe clamp nuts and locknuts are properly installed.

This will be a visual check.

1.3 DESIGN CRITERIA 1.3.1 SEISMIC There is sufficient historical and experimental evidence to demonstrate that small diameter piping systems have inherent structural capability to withstand

SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1, TITLE WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

TUBING NO.

.cv, PROJECT DESIGN CRITERIA PAGE 2

or 23 large earthquake motions when designed to normal industry standards. This criteria will ensure that industry standards are met.

1.3.2 OTHER N/A 1.4 CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS 1.4.1 QUALITY CLASS Quality class is as defined in Subsection 1.4.1 of Volume 1 of the Seismic Upgrade General Design Criteria Manual.

Table 1.4-1 defines the appli cable quality class of the components associated with this modification.

1.4.2 SAFETY CLASS Safety class is as defined in Subsection 1.4.2 of Volume 1 of the Seismic Upgrade General Design Criteria Manual.

Table 1.4-1 defines the appli cable safety class of the components associated with this modification.

1.4.3 QUALITY GROUP Quality group is as defined in Subsection 1.4.3 of Volume 1 of the Seismic Upgrade General Design Criteria Manual.

Table 1.4-1 defines the appli cable quality group of the components associated with this modification.

1.4.4 SEISMIC CATEGORY Seismic category is as defined in Subsection 1.4.4 of Volume 1 of the Seismic Upgrade General Design Criteria Manual.

Table 1.4-1 defines the applicable seismic category of the components associated with this modification.

1.4.5 DESIGN CODES AND STANDARDS The following codes and standards will be utilized for the design and/or analysis if required as a result of the walkdown.

6*.

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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REV, PROJECT DESIGN CRITERIA PAGE OF o

AISC Specification for the Design, Fabrication and Erection of Structural Steel for Buildings, Eighth Edition.

o American Iron and Steel Institute, Specification for the Design of Light Gage Cold-Formed Steel Structural Members, 1980 Edition with Commentary.

o ASTM Material Specifications o

AWS B.3.0-41, Standard Qualification Procedure o

AWS D1.1-81, Structural Welding Code o

AWS D12.1, Recommended Practice for Welding Reinforcing Steel, Metal Inserts and Connections in Reinforced Concrete Connections o

ANSI B31.1, Power Piping Code, 1980 Edition, with Addenda through winter 1980 o

MSS-SP-58-1975, Pipe Hangers and Supports - Material and Design o

ASME B & PV Code Section III, Subsection NC, 1980 Edition with Addenda through Winter 1980 1.5 ENVIRONMENTAL DESIGN CRITERIA 1.5.1 NORMAL N/A 1.5.2 POST-ACCIDENT ENVIRONMENT N/A 1.6 DESIGN LIFE The design life of the components associated with this evaluation is 35 years.

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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nev PROJECT DESIGN CRITERIA 4

23 PAGE OF 1.7 NRC REGULATORY DOCUMENTS 1.7.1 CODE OF FEDERAL REGULATIONS Title 10, Chapter I, Code of Federal Regulations.

Specifically the following Parts:

Part 20 Standards for Protection Against Radiation (10 CFR 20)

Part 21 Reporting of Defects and Noncompliance (10 CFR 21)

Part 50 Domestic Licensing of Production and Utilization Facilities including Appendices (10 CFR 50)

Part 73 Physical Protection of Plants and Materials (10 CFR 73) 1.7.2 REGULATORY GUIDES For walkdown, Regulatory Guides are not applicable.

For any new design or analysis, the NRC Regulatory Guides identified in section 1.7.2 of the Seismic Upgrade General Design Criteria shall be complied with to the extent applicable based on the scope of work.

1.8 STATE AND LOCAL REGULATIONS 1.8.1 OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION (OSHA) REGULATIONS California State Department of Industrial Relations, Division of Industrial Safety, Safety Orders.

1.8.2 CALIFORNIA ADMINISTRATIVE CODE Title 8 - Industrial Relations (effective as of September 1, 1975) 1.8.3 SONGS 1 DOCUMENTATION A. SONGS 1 FSA including all Amendments B. SONGS 1 Provisional Operating License including Technical Specifications C. SONGS 1 Project Quality Program Manual 0

0 L

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF TITLE SAFETY RELATED SMALL BORE PIPING AND TUBING no.15691-583 0

PROJECT DESIGN CRITERIA 5

23 PAGE OF D. SONGS 1 Project Procedures Manual E.

SONGS 1 Field Construction and Quality Control Manual 1,9 REFERENCES

- 1.

J. D. Duffin to A. R. Guerrero Report dated December 22, 1983, BPC/SCE-83-2041, Subject BPC Input to RTS NRC Submitted

2.

San Onofre Nuclear Generating Station, Unit 1, Project Design Criteria Manual, Vol.

1, Seismic Upgrade General Design Criteria, Rev. 1, dated May 2, 1984

3.

Letter from M. Medford (SCE) to D. M. Crutchfield (NRC) dated December 23, 1983

4.

SCE Design Calculation DC-1636, Rev. 0, dated May 9,

1984, "Recommended Span Length."
2.

MECHANICAL DESIGN CRITERIA N/A

3.

ELECTRICAL DESIGN CRITERIA N/A

4.

CIVIL/STRUCTURAL DESIGN CRITERIA N/A

5.

CONTROL SYSTEM DESIGN CRITERIA N/A

6.

NUCLEAR DESIGN CRITERIA N/A

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF TITLE SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

TUBING Ho.

REV, PROJECT DESIGN CRITERIA 6

23 PAGE 0F

7.

PLANT DESIGN CRITERIA See Sections 1.2 and 1.3.

II IL

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1

-5V8 PROJECT DESIGN CRITERIA 7

23 PAGE oF TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING AND TUBING TO BE WALKED DOWN CHEMICAL FEED SYSTEM Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's P1-CF-01 1110-1/2"-EG1 228622 568777 1111-1/2"-EG1 228716 1112-1/2"-EG1 228717

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I TITLE WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND P

5691-583 TUBING o

15691 iv, 0

PROJECT DESIGN CRITERIA PAGE 8

OF 23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN CHEMICAL AND VOLUME CONTROL SYSTEM Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's P1-CV-02 2067-2"-2501R 334476 568767 2068-2"-2501R 334477 2071-2"-2501R 334478 334479 334486 P1-CV-07 2005-2"-2502R 714493 568767 2006-2"-2502R 334614 P1-CV-08 2011-2"-2502R 714497 568767 2012-2"-2502R 334614 P1-CV-09 2008-2"-2502R 334614 568767 2009-2"-2502R 714504

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

TUBING Po.

REV.

PROJECT DESIGN CRITERIA PACE_9 oE 23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN CHEMICAL AND VOLUME CONTROL SYSTEM (continued)

Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's Pl-CV-17 2013-1/2"-151R 228713 568767 2072-1/2"-151R 334793 2032-1"-HP2 2035-1"-HP2 2013-1"-151R 2013-2"-151R Pl-CV-19 2002-3/4"-2501R 334918 568767 2002-2"-2502R 714490 P1-CV-20 2054-1"-151R 334635 568767 2063-1"-151N P1-CV-301 1486-3/8"-BH 228905 568767 3202-3/4"-HM2 714447 714448 P1-CV-302 2104-3/8"-151R 228907 568767 2014-3/8"-151R 16D L

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I TITLE WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 1

TUBIN NO.15691-5830 TUBING No.

REV.

PROJECT DESIGN CRITERIA PAGE 10 OF 23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN CHEMICAL AND VOLUME CONTROL SYSTEM (continued)

Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's P1-CV-303 2002-3/8"-2502R 228904 568767 2003-3/8"-2501R 228908 2002-3/8"-2501R 228909 2024-3/8"-2505R 2535-1/2"-BH 2024-1/2"-BH 2024-3/4"-2502R P1-CV-304 2060-1/2"-151N 228910 568767 P1-CV-305 2105-3/8"-2502R 228911 568767 2110-3/8"-2502R 2105-3/4"-2502R 2110-3/8"-2502R P1-CV-306 2005-3/8"-2502R 228912 568767 2008-3/8"-2502R 2011-3/8"-2502R 2005-3/4"-2502R 2008-3/4"-2502R 2011-3/4"-2502R P1-CV-307 2015-1/2"-151 228913 568767 2015-1"-HP2 228914 2084-1"-HP2 2084-1"-151R P1-CV-300 2088-2"-HP2 334640 568767

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF TITLE SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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REV, PROJECT DESIGN CRITERIA 11 23 PAGE OF TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN CHEMICAL AND VOLUME CONTROL SYSTEM (continued)

Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's CV-151 2091-2"-2501R 334484 568769 CV-152 2008-3/4"-2501R 334460 568767 2008-2"-2501R 334461 2008-2"-2502R 334462 334463 334464 CV-153 2005-3/4"-2501R 714493 568767 2004-2"-2501R 334528 2005-2"-2502R CV-154 2090-2"-2502R 334483 568769 CV-156 2011-1"-2501R 334465 568767 2011-2"-2502R 334466 714497 334467 344468 CV-157 2092-2"-2502R 334485 568769

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I TITLE WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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REV PROJECT DESIGN CRITERIA PAGE 12 23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN CHEMICAL AND VOLUME CONTROL SYSTEM (continued)

Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's CV-160 2007-3/4"-2501R 334457 568767 2017-3/4"-2501R 334558 2055-3/4"-2501R 334459 334473 334474 334475 CV-161 2014-2"-151R 334472 568767 714448 334486 CV-162 2020-2"-2501R 334469 568767 2020-2"-151R 334470 CV-163 2018-2"-151R 334471 568767 3203-2"-HM3 714448 CV-164 2113-3/8"-153R 334644 568767 CV-165 2112-3/8"-153R 334643 568767 CV-166 2111-3/8"-153R 3346642 568767 2111-3/4"-151R

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I TITLE WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

TUBING No.

RE, PROJECT DESIGN CRITERIA PAGE 13 OF 23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN FEEDWATER AND CONDENSATE SYSTEM Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's P1-AF-06 387-1"-GG 228940 5173168 30000-1"-GG 228941 385-1"-GG 228841 399-1"-GG P1-AF-03 8114-1-1/2"-JN 228941 5173168 P1-AF-04 8113-1-1/2"-JN 228940 5173168

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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REV, PROJECT DESIGN CRITERIA

_PAGE 14 f

23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN SAFETY INJECTION SYSTEM Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's SI-159 6009-2"-1501R 334517 568769 6010-2"-1501R 334518

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I TITLE WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

TUBING F40.

159158 V.

PROJECT DESIGN CRITERIA 15 23 PAGE 07 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN REACTOR CYCLE SAMPLING SYSTEM Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's RS-167 5004-3/8"-2505R 714477 568770 5026-3/8"-2505R 456454 5004-3/4"-2501R 334508 5026-3/4"-2501R RS-169 5029-3/8"-2505R 334513 568770 5032-3/8"-2505R 714463 5029-3/8"-2501R 5032-3/4"-2501R

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I TITLE WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

TUBING No.

any.

PROJECT DESIGN CRITERIA

.PACE 16 o

23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN REACTOR COOLANT SYSTEM Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's P1-RC-51 1409-3/4"-151R 714445 568766 1409-3/4"-HM2 568784 P1-RC-350 1409-3/8"-BH 714445 568766 1409-1/2"-BH 453519 568784 1409-3/4"-151R 1409-3/4"-HH 1409-3/4"-HM2 RC-109 5022-3/8"-2501R 334481 568767 5022-3/4"-2501R 334482 5008-2"-2501R RC-110 5037-2"-2501R 334515 586766 RC-111 5014-3/4"-2501R 334509 586766 RC-112 5016-2"-2501R 334509 586766 0

SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND TUBIN NO.

15691-583 0

TUBING POO.

REV, PROJECT DESIGN CRITERIA PAGE 17 23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN REACTOR COOLANT SYSTEM (continued)

Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's RC-113 5003-2"-2501R 334507 568766 5040-2"-HP 334522 7037-2"-HP2 RC-114 5033-3/4"-2501R FS-2501 568766 FS-2502 RC-115 5000-3/4"-2501R FS-2601 568766 RC-116 5007-3/4"-2501R FS-3001 568766 RC-117 5012-3/4"-2501R FS-3002 568766 RC-118 5001-3/4"-2501R FS-3003 568766 RC-119 8314-3/4"-2501R FS-301 568766 8302-3/4"-2501R FS-302 RC-120 8314-3/4"-2501R FS-301 568766 8302-3/4"-2501R FS-302 RC-133 8324-1/2"-BH4 FS-4101 568766 8323-1/2"-BH2 FS-4102 8322-1/2"-BH4 FS-4103

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF TL SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

TUBING

40.

RV, PROJECT DESIGN CRITERIA

,PAGE 18 or 23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN REACTOR COOLANT SYSTEM (continued)

Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's RC-134 8325-1/2"-BH4 FS-4201 568766 8327-1/2"-BH4 FS-4202 8326-1/2"-BH4 FS-4203 FS-4204 RC-135 850-1/2"-BH4 FS-4301 568766 8374-1/2"-BH4 FS-4302 8329-1/2"-BH4 FS-4303 FS-4304 FS-4305 RC-137 8416-3/4"-BH3 FS-4501 568766 RC-138 8420-3/4"-BH3 FS-4601 568766 RC-139 8424-3/4"-BH3 FS-4701 568766

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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REV PROJECT DESIGN CRITERIA 19 23 PAGE or TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN STEAM SYSTEM Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's P1-MS-05 342-2"-EG 334429 568779 PI-MS-06 343-2"-EG 334430 568779 450334 P1-MS-07 341-2"-EG 334428 568779 Pl-MS-360 69-1/2"-EG 228923 5159570 69A-1/2"-EG 228924 69B-1/2"-EG Pl-MS-361 71-1/2"-EG 228923 5159570 85-1/2"-EG 228924 86-1/2"-EG 228951 0

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

TUBING REo.

EVy PROJECT DESIGN CRITERIA

_c_

P 20 23 TABLE 1.2-1 SAFETY-RELATED SMALL BORE PIPING TO BE WALKED DOWN NITROGEN SYSTEM Reference Drawings Stress Problem Isometric Number Lines Drawings P & ID's P1-SA-06 13327-1/4"-GN1 228957 568784 13333-1/4"-GN1 228958 13339-1/4"-GN1 228959 13326-3/4"-GN1 228960 13332-3/4"-GN1 13338-3/4"-GN1 PI-SA-11 1409-3/4"-HM2 5131239 568766 2532-3/4"-HM2 457215 P1-SA-03 8101-1/2"-BH 453520 568784 8101-3/4"-iN 5181970 8101-3/4"-HH 8101-1"-HH 11205-1/4"-BH 11207-1/4"-BH Pl-SA-04 8102-1/2"-BH 453520 568784 8102-3/4"-IN 5181970 8102-3/4"-HH 8102-1"-HR 11206-1/4"-BH 11208-1/4"-BH P1-SA-08 14002-3/8"-HN 453610 568784 14002-1/2"-BH 14002-3/4"-HH

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I WALKDOWN CRITERIA FOR EVALUATION OF TITLE SAFETY RELATED SMALL BORE PIPING AND 15691-583 0

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REV, PROJECT DESIGN CRITERIA 21 23 PAGE OF TABLE 1.3-1 RECOMMENDED SPAN LENGTH FOR CARBON STEEL AND STAINLESS STEEL SMALL BORE PIPING (REF. 4) (1,2)

Deadweight Support (Feet)

Nominal Pipe Size Air, Gas (Inches) or Steam Water 3/8 8

7 1/2 9

8 3/4 10 9

1 12 10 1-1/2 14 12 2

16 14

1. Tabulated span length for piping from 3/8"NPS to 2" NPS is valid for pipe schedules 40, 80, and 160.
2. The span length is based on a maximum longitudinal net dead weight equal to 2500 psi.

SAN ONOFRE NUCLEAR GENERATING STATION UNIT I TITLE WALKDOWN CRITERIA FOR EVALUATION OF SAFETY RELATED SMALL BORE PIPING AND 0

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__PAGE 22 or 23 TABLE 1.3-2 RECOMMENDED SPAN LENGTH FOR COPPER AND STAINLESS STEEL TUBING (REF.

4) (1,2)

Nominal Pipe Size Deadweight Support Material (inches)

(Feet) 3/8 6.0 1/2 6.5 B88 Copper 3/4 7.0 1

8.0 3/8 6.0 Stainless Steel 1/2 6.5

1. Tabulated span length is valid for tubing with the wall thickness equal to 0.049" to 0.065".
2. The span length is based on a maximum longitudinal net dead weight equal to 2500 psi.

I..

PF-8438.1 1140001 7/st TABLE 1.4-1 CLASSIFICATION OF PIPING AND PIPE SUPPORTS(a)

Structure Quality Safety Quality

(

Seismic M

z System/Component Class Class Group Principal Design Codes Category Location 0

Catgor Loctio O

1. Piping System SR 1,2,3 A-C ANSI B31.1 Material, A

IC/OC r

M Fabrication, Instal-oz lation and Testing r

2.

Pipe Supports for SR 1,2,3 NA AISC Design;(b)(d)

A IC/OC "SR" System ANSI B31.1 Material, Fabrication, Instal-T Z

lation and Testing w z (a)

For Classifications of Piping System and Components refer to Seismic Upgrade General Design Criteria Manual Section 1.4, BPC Job 14000.

'V (b)

Refer to Seismic Upgrade General Design Criteria Manual Section 7, Plant Design z

(Reference 2).

C)ZC o0 (c)

Applies to modifications if required as a result of walkdown.

(d)

On a case by case basis, pipe supports may be cop oered functionally capable if the calculated maximum stress does not exceed 30%*atove the yield stress specified o

by the codes (

Reference:

February 8, 1984 letter from Harold Denton to K. Baskin,

Subject:

Proposed Restart Plan for San Onofre Nuclear Generating Station, Unit No. 1.

See enclosure, Safety Evaluation Report, Item 41), page 6).

00 t'C3

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