ML20213E082
| ML20213E082 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/12/1982 |
| From: | Johnston W Office of Nuclear Reactor Regulation |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0492, CON-WNP-492, RTR-REGGD-01.065, RTR-REGGD-1.065 NUDOCS 8203220485 | |
| Download: ML20213E082 (4) | |
Text
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DISTRIBUTION:
MAR 1 e 198.7 S
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9 MSR 1 i iSC2u Docket No. 50-397
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'!p MEMORANDUM FOR: Robert L. Tedesco, Assistant Director /
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Division of Licensing FROM:
William V. Johnston, Assistant Director for Materials & Qualifications Engineering Division of Engineering SU3 JECT:
FINAL SER FOR WPF3-2, SECTION 5.3.1.1 Plant Name: Washington Public Power Supply System, Nuclear Project No. 2 Suppliers: General Electric / Burns S Roe Licensing Stage: OL Docket Number: 50-397 Reviewer:
D. E. Smith Responsible Dranch and Project Manager: LB#2, R. Auluck Description of Task:
Final Safety Evaluation Report Date Reviewed: 2/8/82 Review Status: Compl ete The Materials Application Section, flaterials Engineering Branch, Division of Engineering has completed its review of Section 5.3.1.1 of the FSAP.,
This review was conducted in accordance with the applicable sections of the July 1981 edition of the " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," (SRP, NUREG-0800).
The results of this review are contained in this Safety Evaluation Report (SER). The acceptance criteria used were in accordance with the SRP, or as described in the text.
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'Md William V. Johnston, Assistabt Director for Materials & Qualifications Engineering Division of Engineering Attactnent:
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l' ATTACHMENT WASHINGTON PUBLIC POWER SUPPLY SYSTEM WASHINGTON NUCLEAR PROJECT NO. 2 1
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SAFETY EVALUATION REPORT I
j MATERIALS APPLICATION SECTION j
5.3.1.1 Reactor Vessel Material Specifications, Welding and Fabrication I
i The staff concludes that the reactor vessel materials are acceptable i
j and meet the requirements of General Design Criteria 1, 4, 14, 30, 31, and 32 of Appendix A of 10 CFR Part 50; the material test,ing and monitoring requirements of Appendices B, G, and H of 10 CFR Pa rt 50; and the requirements of 150.55a of 10 CFR Part 50.
This conclusion is based on the following:
The materials used for construction of the reactor vessel and its l
appurtenances have been identified by specification and found to 1
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be in conformance with Section III of the ASl1E Code.
Compliance
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with the above Code provisions for material specifications satisfies the quality standards requirements of GDC 1r GDC 30, and 550.55a.
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When welding components of ferritic steelse Code controls are 1
supplemented by conformance with the recommendations of Regulatory Guide 1.50, " Control of Preheat Temperature for Welding of Low-Alloy Steet." These controls provide reasonable assurance that cracking of components made from low alloy steels wiLL not occur during i
fabrication and minimize the potential for subsequent cracking.
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These controls also satisfy the quality standards requirements of GDC 1r GDC 30, and 550.55a.
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. When welding components of austenitic stainless steels, Code controls are supplemented by conformance with most of the recommendations of Regulatory Guide 1.31, " Cont rol of Ferrite Content in Stainless Steel Weld Metal." Where the applicant proposed an' alternate apprcach to the Regulatory positions in the guides, they were acceptable to the staff. The controls used provide reasonable assurance that the welds will not contain micro cracks. These controls also satisfy the quality standards requirement of GDC 1r GDC 30, and 550.55a and the requirements of GDC 14 regarding fabrication to prevent RCPB rapid propagating f ailure.
The controls (during all stages of welding) to avoid contamination and sensitization that could cause stress corrosion cracking in austenitic stainless steels conform with the reconmendations of regulatory guides as follows:
The controls to avoid contamination and sensitization of a.
austenitic stainless steel are in conformance with nost of the reconnendations of Regulatory Guide 1.44, " Control of the Use of Sensitized Stainless Steel." Where the applicant proposed an alternate approach to the Regulatory positions in the guides, they were acceptable to the staf f.
The controls used provide assurance that welded components will not be contaminated nor sensitized prior to and during the welding procets. These controls satisfy the quality standards requirement of GDC 1r GDC 30's and 550.55a and the GDC 4 requirement relative to material compatibility.
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The controls regarding onsite cleaning and cleanliness control of austenitic sta,intess steel are in conforcance with the recommendations of Regulatory Guide 1.37, " Quality Assurance o
Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plantsi" because the controls used provide assurance that austenitic stainless steel components will be properly cleaned onsite. The controls satisfy Appendix B of 10 CFR Part 50 regarding controls for onsite cleaning of materials and components.
Fracture toughness of the reactor vessel and its appurtances is addressed in Section 5.3.1.
Integrity of the reactor vessel studs and fasteners is assured by conformance with the reccmmendations of Regulatory Guide 1.65,
" Materials and Inspections for Reactor Vessel Closure Studs."
Conpliance with these' recommendations satisfies the quality standards requirements of GDC 1r GDC 30, and 550.55a; the prevention of f racture of the RCPB requirement of CDC 31; and the requirements of Appendix G,10 CFR Part 50 as detailed in the provisions of the ASME Coder Sectiens II and III.
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