ML20063C907

Forwards Ssar Markups Addressing Confirmatory Item F14.3.3-1 Pertaining to ACRS Comments on Piping Design Acceptance Criteria

ML20063C907
Person / Time
Site:	05200001
Issue date:	01/25/1994
From:	Fox J GENERAL ELECTRIC CO.
To:	Poslusny C Office of Nuclear Reactor Regulation
References
NUDOCS 9402070239
Download: ML20063C907 (6)

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• January 25, 1994 Docket No STN 52-001 i

r Chet Poslusny, Senior Project Manager l Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Subject:

Submittal Supporting Accelerated ABWR Schedule - Response to Confirmatory Item F 14.3.3 1

Dear Chet:

Enclosed are SSAR markups addressing Confirmatory item F14.3.31 pertaining to ACRS comments on the piping design acceptance criteria. ,

-1 Please provide copies of this transmittal to Dave Terao and Tom Boyce. I i

Sincerely, 1

Jack Fox Advanced Reactor Programs cc: Alan Beard (GE)

Norman Fletcher (DOE) j Joe Quirk (GE)  !

Maryann lierzog (GE)

Tony James (GE) e.

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Table 1.91 Summary of ABWR Standard Plant COL License information (Continued) -

item No. Subject Subsection l 3.30 Audits of Design Specifications and Design Reports 3.9.7.4 l 3.31 ASME Class 1,2, and 3 Piping System Clearance 3.9.7.5 Requirements 3.32  ![ $ ".ecen;SSn ^ nd :!:i 6 ^S"E C! :: ',2 crd 3 23.'S 9p';ng S , =.T a l 3.33 Pipe Support Baseplate and Anchor Bolt Design 3.9.7.7 l 3,34 Pipe-Mounted Equipment Allowable Loads 3.9.7.8 l 3.35 Benchmark Requirements for Computer Codes Used to 3.9.7.9 Perform Piping Dynamic Analysis l 3.36 ASME Class 1,2, and 3 Piping System Design 3.9.7.10 Requirements for Thermal Stratification of Fluids l 3.37 Equipment Qualification 3.10.5.1 l 3.38 Dynamic Qualification Report 3.10.5.2

_l 3.39 Qualification by Experience 3.10.5.3 3.40 Environmental Qualification Document (EOD) 3.11.6.1 l

3A1 Environmental Qualification Records 3.11.6.2 l

l 3.42 Surveillance, Maintenance, and Experience Information 3.11.6.3 3.43 Radiation Environment Conditions 31.3.3.1 l

4.1 Thermal Hydraulic Stability 4.3.5.1 4.2 Power / Flow Operating Map 4.4.7.1 4.3 Thermal Limits 4.4.7.2 4.4 CRD inspection Program 4.5.3.1 5.1 Conversion of Indicators 5.2.6.1 5.2 Plant Specific ISI/ PSI 5.2.6.2 5.3 Reactor Vessel Water Level Instrumentation 5.2.6.3 5.4 Fracture Toughness Data 5.3.4.1 5.5 Materials and Surveillance Capsule 5.3.4.2-5.6 Plant Specific Pressure-Temperature Information '5.3.4.3 5.7 Testing of Mainstsam isolation Valves 5.4.15.1 l

j. 5.8 Analyses of 8-hour RCIC Capacity 5.4.15.2 5.9 - ACIWA F ow Reduction 5.4.15.3 l

6.1 Protection Coatings and Organic Materials 6.1.3.1 6.2 Alternate Hydrogen Control 6.2.7.1 l-195 COL License information - Amendment 33

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3.9.3 ASME Code Class 1,2, and 3 Components, Component Supports, and Core Support Structures 3.9.3.1 Loading Combinations, Design Transients, and Stress Limits ,

i This section delineates the criteria for selection and definition of design limits and  ;

loading combinations associated with normal operation, postulated accidents, and specified seismic and other Reactor Building vibration (RBV) events for the design of safety-related ASME Code components (except containment components, which are i discussed in Section 3.8).

This section discusses the ASME Class 1,2, and 3 equipment and associated pressure-retaining parts and identifies the applicable loadings, calculation methods, calculated stresses, and allowable stresses. A discussion of major equipment is included on a {

component-by-component basis to provide examples. Design transients and dynamic loading for ASME Class 1,2, and 3 equipment are covered in Subsection 3.9.1.1. 1 Seismic-related loads and dynamic analyses are discussed in Section'3.7. The j suppression pool-related RBVloads are described in Appendix 3B. Table 3.9-2 presents 1 the combinations of dynamic events to be considered for the design and analysis of all j ABWR ASME Code Class 1,2, and 3 components, component supports, core support .

structures and equipment. Specific loading combinations considered for evaluation of q each specific equipment are derived from Table 3.9-2 and are contained in the design specifications and/or design reports of the respective equipment. (See )

Subsection 3.9.7.4, 3.9.7.5[3.9.7.) and 3.9.7.8 for COL license information 4 requirements.) Q Piping loads due to the thennal expansion of the piping and thermal anchor movements at supports are included in the piping load combinations. All operating .

modes are evaluated and the maximum moment ranges are included in the fatigue evaluation. Piping systems with maximum opemting temperatures ofless than or equal to 65 C are not required to be analyzed for thermal expansion loading.

Low-pressure piping systems that interface with the reactor coolant pressure boundary will be designed with either a schedule 40 pipe wall thickness, or a pipe wall thickness calculated for a pressure equal to 0.4 times the reactor coolant system pressure. See Appendix SM for additionalinformation on intersystem LOCA.

Thermal stratification of fluids in a piping system is one of the specific operating conditions included in the loads and load combinations contained in the piping design specifications and design reports. It is known that stratification can occur in the feedwater piping during plant startup and when the plant.is in hot standby conditions following scram (Subsection 3.9.2.1.3) . If, during design or startup, evidence of thermal '

stratification is detected in any other piping system, then stratification will be evaluated.

Ifit cannot be shown that the stresses in the pipe are low and that movement due to Mechanical Synems and Components - Amendment 23 3 S 27

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3.9.3.1.17 ASME CIass 2 and 3 Pumps The Class 2 and 3 pumps (all pumps not previously discussed) are designed and evaluated in accordance with ASME Code Section III. The stress analysis of these pumps is perforrrA using clastic methods. See Subsection 3.9.3.2 for additional information on pump operability.

3.9.3.1.18 ASME Class 1,2 and 3 Valves The Class 1,2, and 3 valves (all valves not previously discussed) are constructed in accordance with ASME Code Section III. j All valves and their extended structures are designed to withstand the accelerations due j 1

to seismic and other RBV loads. The artsched piping is supported so that these accelerations are not exceeded. The stress analpis of these valves is performed using clastic methods. See Subsection 3.9.3.2 for additional information on valve operability. l 3.9.3.1.19 ASME Class 1,2 and 3 Piping The Class I,2 and 3 piping (all piping not previously discussed) is constructed in i accordance with ASME Code Section III. For Clas<,1 piping, stresses are calculated on an clastic basis and evaluated in accordance with NP 3600 of ASME Code Section III. i For Class 2 and 3 piping, stresses are calculated on an elastic basis and evaluated in accordance with NC/ND-3600 of the Code.  !

> 3.9..?.I.20 AS~ BUILT STMSS BOORS FOR ASME CL./}SS 2lj . aml3 Piyinf 3.9.3.2 Pump and Valve Operebility Assurance [$cMd67Q Spfems Active mechanical (with or without electrical operation) equipment are Seismic Category I and each is designed to perform a mechanical motion for its safety-related function during the life of the plant under postulated plant conditions. Equipment with  ;

i faulted condition functional requirements include active pumps and valves in fluid systems such as the RHR System, ECCS, and MS system.

This subsection discusses operability assurance of active ASME Code Section III pumps and valves, induding motor, turbine or operator that is a part of the pump or valve (Subsection 3.9.2.2). The COL applicant must ensure that specific emironmental pammeters are properly defined and enveloped in the methodology for its specific plant and implemented in its equipment qualification omgram.

Safety-related valves and pumps are qualified by testing and analysis and by satisfying the stress and deformation criteria at the criticallocations within the pumps and valves.

Operability is assured by meeting the requirements of the programs defined in Subsection 3.9.2.2, design and qualiScation requirements Subsection 3.9.6, Sections 3.10 and 3.11, and the following subsections.

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(2) Provide a study to determine the optimal frequency of the periodic verification of the continuing MOV capability for design basis conditions l (Subsections 3.9.6.2.1, 3.9.6.2.2, and 3.9.6.2.3).

(3) Address the concerns and issues identified in Generic Letter 89-10; specifically the method of assessment of the loads, the method ofsizing the actuators, and the setting of the torque and limit switches (Subsection 3.9.6.2.2).

The COL applicant will indude the design qualiScation test, inspection and analysis l criteria in Subsections 3.9.6.1,3.9.6.2.1,3.9.6.2.2 and 3.9.6.2.3 in the development of the respective safety-related pump and valve design specifications.

3.9.7.4 Audit of Design Specification and Design Reports COL applicants will make available to the NRC staff design specification and design repons required by AShE Code for vessels, pumps, valves and piping systems for the purpose of audit (Subsection 3.9.3.1).

The COL applicant shall ensure that the piping system design is consistent with the construction practices,induding inspection and examination methods, of the AShE Code edition and addenda as endorsed in 10CFR50.55a in effect at the time of I application. i The COL applicant shall identify AShE Code editions and addenda other than those listed in Tables 1.8-21 and 3.2-3, that will be used to design AShE Code Class 1,2 and 3 pressure retaining components and supports. The applicable portions of the AShE Code editions and addenda shall be identifigd to the NRC staff for review and approval with the COL application (Subsection 3.9.3.1). ]

3.9.7.5 ASME Class 1,2 and 3 Piping System Clearance Requirements AShE Class 1,2 and 3 piping sptems shall be designed to provide dearance from j stnictures, systems, and components where necessary for the accomplishment of the l g structure, system, or component's safety function as specified in the representative

[30 structure or system design description. The COL applicant shall verify that the maximum calculated piping system deflections under service conditions do not exceed the minimum dearance between the piping system and nearby structures, systems, or components. The COL applicant shall document in the certified design stress report

=%that the clearance re uirements have been met (Subsection 3.9.3.1).

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-3.0.7.6- As-Built P.::: :!!!:t! n ^.na'yek for ASME Class 1,2 and 3 Piping Systems m For AShE Class 1,2 and 3 piping systems, the COL :pplier.t tha!! recenc!!7the as-bu piping systemlwith the asdesigned p' ping system 7Thc COL app!!: nt "'I pdenndn j 61% .h WO as-built inspection of the pipe routing, location and orientation, the location, size, r- _

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( clearances and orientation of piping supports, and the location and weight of pipe mounted equipment (This inspection will be performed by reviewing the as-built

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drawings containing verification stamps, and by performing a visual inspection of the irrtalled piping system. The piping configuration and component location, size, and k onentation shall be within the tolerances specified in the certified as-built piping stress report. The tolerances to be used for reconciliation of the as-built piping system with

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the as-designed piping system are provided in Reference 3.9-10. A reconciliation f analysis using the as-built and asdesigned information shall be performed. The certified as-built Stress Report shall document the results of the as-built reconciliation analysis;(Subsection &9AL)r8 -

3.9.T.k pu.a 3.9.7.7 Pipe Support Baseplate and Anchor Bolt Design  ;

COL applicants shall providejustification for the use of safety factors for concrete anchor bolts other than those specified in Subsection 3.9.3.4. Thisjustification shall be submitted to the NRC staff for review and approval prior to the installation of the concrete anchor bolts.

COL applicants shall account for pipe support base plate flexibility in the calculatior, of concrete anchor bolt loads in accordance with Subsection 3.9.3.4.

3.9.7.8 Pipe-Mounted Equipment Allowable Loads The COL applicant shallinspect the piping design reports and document that the pipe applied loads on attached equipment; such as valves, pumps, tanks and heat exchangers, are less than the equipment vendor's specified allow.:,ble loads (Subsection 3.9.3.1) 3.9.7.9 Benchmark Requirements for Computer Codes Used to Perform Piping Dynamic Analysis The COL applicant shall benchmark their computer code used for piping system dynamic analysis against the NRC Benchmark Problems for ABWR, defined in Reference 3.9-11. The results of the COL applicant's piping dynamic analysis shall be compared with the results of the Benchmark Problems provided in Reference 3.911 The piping results to be compared and evaluated and the acceptance criteria or range l of acceptable values are specified in Reference 3.9-11. Any deviations from these values a well asjustification for such deviations shall be documented and submitted by the COL applicant to the NRC staff for review and approval before initiating the final certified piping analysis (Subsection 3.9.1.2).

3.9.7.10 ASME Class 1,2 and 3 Piping System Design Requirements for Thermal Stratification of Fluids COL applicants shall design for thermal stratification of fluids in piping systems in accordance with Subsection 3.9.3.1.

3.9-64 Mechanical Systems and Components - Amendment 33