ML18018A825

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Forwards Response to NRC Question 210.59 Re Piping Spec, Loading Combinations & Stress Limits Completing Response to 32 Mechanical Engineering Branch Questions in 830819 & 25 Ltrs for SER Open Item 354
ML18018A825
Person / Time
Site: Harris  Duke Energy icon.png
Issue date: 10/10/1983
From: Mcduffie M
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
LAP-83-461, NUDOCS 8310140126
Download: ML18018A825 (32)


Text

REGULATORY

'ORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR:8310140126 DOC,DATE: 83/10/ip NOTARIZED; NO D

FACIL:.50-400 Shearon Harris Nuclear Power Planti Unit ii Carolina 50"001 Shear on Harris Nuclear Power Pl anti Unit 2i Carolina 05000401 AUTH.NAME AUTHOR AFFILIATION MCDUFF IEi M, A, Car o 1 i na I'ower L Ligh t Co.

RECIPiNAME RECIPIENT AFFILIATION DENTONiH,Ri Office of Nuclear Reactor Regulationi Director

SUBJECT:

Forwards response to NRC Question 210 '9 re piping speci loading combinations 8 stress limits completing response,to 32 Mechanical Engineering Branch questions in 830819 L 25 ltrs for SER Open Item 354

'ISTRIBUTION CODE:

B001S COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Licensing Submittal:

PSAR/FSAR Amdts 8 Related Correspondence NOTES:

RECIPIENT ID CODE/NAME NRR/DL/ADL NRR LB3 LA INTERNAL: ELD/HDS1 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 2A NRR/DHFS/HFEBPO NRR/DHFS/PSRB NRR/DS I/AEB 26 NRA/DSI/CPB 10

~NRR/DS I/ICSB 16 NRR/OSI/PSB NRR/DS'l/RSB 23 RGN2 EXTERNAL: ACRS Pl DMB/DSS (AMDTS)

LPDR 03 NSIC 05 COPIES l.TTR ENCL 1

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1 RECIPIENT ID CODE/NAME NRR LB3 BC BUCKLEYiB 01 IE FILE IE/DEPER/IR8 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DS I/CSB 09 NRR/DS I/METB 12 N

/RAB 22 04 RM/DDAMI /MI8 BNL(AMDTS ONLY)

FEMA~REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1

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TOTAL NUMBER OF COPIES REQUIRED:

LTTR 53 ENCL 46

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CIRQUE, Carolina Power & Light. Company SERIAL:

LAP-83 461 i'u t OCT 1.0.")983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS.

1 AND 2 DOCKET NOS.

50-400 AND 50-401 RESPONSES TO REQUESTS FOR ADDITIONAL INFORMANTION

Dear Mr. Denton:

Carolina Power

& Light Company hereby transmits one original and forty copies of the response to NRC Question No. 210.59.

This completes our responses to the thirty-two (32) Mechanic'al Engineering Branch Questions transmitted by NRC letters dated August 19 and 25, 1983.

Previous "responses were submitted via CPSL letter dated September 19, 1983 (LAP-83-429).

Yours very truly, M. A. McDuffie Senior Vice President Nuclear Generation NEC/pgp (8076NEC)

Enclosure Get Mr. B. C. Buckley (NRC)

Mr.

G. F. Maxwell (NRC-SHNPP)

Mr. J.

P. O'Reilly (NRC-RII)

Mr. Travis Payne (KUDZU)

Mr. Daniel F.

Read (CHANGE/ELP)

Mr. R.

P.

Gruber (NCUC)

Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson Mr. G.

O. Bright (ASLB)

Dr. J.

H. Carpenter (ASLB)

Mr. J. L. Kelley (ASLB) 8310140126 831010 PDR ADOCK 05000000 E

PDR 411 Fayettevltle Street o P. O. Box 1551 o Raleigh, N. C. 27602

l

Shearon Harris Nuclear Power Plant Draft SER Open Item No.

354 NRC Question 210.59 Pi ing Specification Loading Combinations and Stress Limits Where does the Specification CAR-SH-M-30, Rev.

16 dated 4/18/83 define the loading combinations and associated stress limits for:

(a)

Class 1 Piping, and (b) for Class 2 or 3 Piping?

RESPONSE

Ebasco Specification CAR-SH-M-30, General Power Piping, is not a complete design specification.

The loading combinations and associated stress limits for Class 2 and 3 piping are covered by Ebasco Design Specification CAR-SH-M-71.

The M-30 and M-71 specifications are two complimentary design documents which together form a design specification.

We are enclosing, for your information and use, the loading combination tables for all Class 2 and 3 piping systems from the specification (Attachment. 1).

The loading combination tables identify the applicable sys'em operating conditions (normal, upset, emergency or faulted);

these system conditions in conjunction with the design requir'ements of ASME-III, Subsection NC 6 ND referenced in the specification (see copy of the pages 2 6 7, Paragraphs 2.03, 7 and 8 from the M-71 specification; Attachment

2) provide the appropriate stress limits.

Note the loading combinations and associated stress limits for Class 1 piping is not within the scope of specification M-71 (refer to Paragraph 1 of the M-71 specification; ).

Class 1 piping analysis including the fatigue analysis

-is part of Westinghouse's scope of work.

See response to Question 210.78.

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I Ebasco Specification Design Specification for Piping Nuclear Safety

. Classes 2,

3 and ANSI B31.1 (Nonnuclear Safety/Seismic Category I)

Project Identification No. CAR-SH-M-71 1.

SCOPE '(Cant'd)

F 05 (Cont'd)

Feedvater System Auxiliary Feedvater System Main Steam System

  • Chilled Water Return System Fuel Oil System
  • Primary Makeup Water System
  • Fire Protection System
  • Service hir System Screen Wash System
  • Waste Gas
  • Waste Liquid

.06 hny conflict betveen this specification and any of the reference

.": uments vill be brought to the attention of the Project Mechanical-Nuclear

.
-..gineering Supervisor for resolution.

2.

APPLICABLE CODES'TANDARDS 6 DOCUMENTS

.01 Ebasco Specification "General Pover Piping," CAR-SH-M-30, Rev 4.

.02 Ebasco Specification "Heavy Tall Seamless Pipe" CAR-SH-M-30A, Rev 0.

.03 hSYE Boiler and Pressure Vessel Code,Section III, 1973 Summer Addendum.

.04 NRC Regulatory Guide 1.48 - Design Limits and Loading Combinations for Seismic Category I Fluid System Equipment vill be in accordance vith the PSAR commi tment.

05 NRC Regulatory Guide 1.67 - Installation of Overpressure Protection Devices.

.06 Preliminary Safety Analysis Report

.07 Ebasco Piping Line List and Valve and Specialties List

~ 08 hpplicable Vendor Dravings of Components vhich are supplied to the analyst via the Ebasco EMDRAC System.

  • Miscellaneous System Load Combination to be used

fiasco Specification'isignSpecification for ping Nuclear Safety Classes 2,

3 and ANSI B31 1 (Nonnuclear Safety/Seismic Category I)

Prospect Identification No. CAR-SH-M-71 6.

GENERAL DESIGN RE UIRE~TS (Cont'd)

.14 Mind or tornado effects shall'aot be considered.

~ 15 Pipe end loads for containment penetraitons are specified in Ebasco Specification CAR-SH-M-54 (ref

, Paragraph 2.14) and Drawing No. 2165-G064.

.16 Portions of Main Steam and Feedwater Piping which is classified as Nonnuclear Safety/Seismic Category I shall be analyzed as specified in Paragraph 1.B-6.1.5 of PSAR.

Any other piping which is Nonnuclear Safety/

Seismi'c Category I will be analyzed as follows:

a - All NNS Seismic I piping in nonseismic building structure must be supported from a seismic structure such as main steel piping being supported off the RAB wall, not off Turbine Building.

b - NNS nonseismic piping attached to safety class piping can never damage the safety piping regardless of pipe routing or location.

The restraint or anchor must be suitably designed to protect the safety class piping.

(see R.G. 1.29, Paragraph C-3).

These lines are indicated in Line List.

.17 All Safety Class 1 interface piping with Safety Class 2, will be analyzed as indicated in Paragraph 7.01.

Final design varification of this SC-1 piping as-built condition will be done by Vestinghouse.

7.

GENERAL DESIGN RE UIREMENTS FOR SAFETY CLASS 2 PIPING

.01 In accordance with Section NC of the he% Code, the equations therein will govern the analysis of Class 2 piping.

8.

GENERAL DESIGN RE UIRPKNTS FOR SAFETY CLASS 3 PIPING

.Ol Class 3 piping shall be analyzed in accordance with Section ND of the ASME Code.

9.

TESTING CONDITIONS AND PNVLMETERS

~ 01 All piping covercdby this specification will undergo field hydrostatic testing.

The test vill be conducted by using 60 F to 120oF water and the test pressure will be 1.5 times the design pressure (corrected to account for the temperature difference between the test temperature and the aaximum

ATTAQBKNT 3

Kbasco Specification Design Specification for Piping Nuclear Safety Classes 2,

3 and ANSI B31.1 (Nonnuclear

'Safety/Seismic Category I)

Project Identification No. CAR-SH-M-71 1.

SCOPE

~Ol This specification pro~ides, in accordance with Article NA-3250 Provisions of Design Specifications" and related paragraphs of the American Society of Mechanical Engineers, Boiler and Pressuze Vessel

Code,Section III, (hereinafter referred to as ASME Code),

the information required for analyzing Safety Classes 2,

3 and B31.1 piping to meet the requirements of the ASME Code.

.02 The term "Piping" as used in this specification includes straight pipe, piping bends, fittings, flanges, and bolting. It also includes

hangers, supports and other equipment items necessazy to prevent over-stressing the pressure retaining pazts.

Pipe Supports Load Combination for Safety Classes 2,

3 and B31.1

( Main Steam and Feedwater up to the system.of restraints which separates seismic category from nonseismic

-.ategory) are specified in Appendix H. It does not include structures

"".d equipment such as building frames, valves, pumps, pressure vessels and-foundations, as they may affect the system stress analysis.

.03 Station piping, hangers and supports shall be furnished in accordance with Ebasco Purchase Specification CAR-SH-M-30 and CAR-SH-M-30A.

.04 For material and NDE requirements, see Ebasco Specification CAR-SH-M-30 and CAR-SH-M-30A.

.05 Systems covered under this specification are:

Chemical and Volume Control System Sa fe ty In)ec tion System

-Reactor Coolant System

  • Sampling System (Nuclear)
  • Chilled Mater Supply System
  • Demineralized Mate. System
  • Instrument Air System

~ Leak Test System

  • Miscellaneous Drain Syste=
  • Miscellaneous System Load Combination to be used

'