ML20202F295

Forwards Page 1.3-2 of Updated Fsar,Documenting Use of Rev 2 to NCIG-01 Re Visual Welding Acceptance Criteria for Structural Welding at Nuclear Power Plants.Util Implemented Guidelines for Visual Structural Weld Insps on 860701

ML20202F295
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	07/03/1986
From:	Leblond P COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
1842K, NUDOCS 8607150130
Download: ML20202F295 (2)

Text

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__~ Commonwealth Edison Z. _ < 72 Wr.st Adams Street, Chicago, Illinois

'~' Address Reply to: Post Office Box 767 Chicago, Illinois 60690- 0767 July 3, 1986 Mr. Harold R. Denton, Director office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Zion Nuclear Power Station Units 1 and 2 Visual Weld Acceptance Criteria for Structural Welding (NCIG-01, Rev. 2)

NRC Docket Nos. 50-295 and 50-304 References (a): June 26, 1985 letter from J. P. Knight to D. E. Dutton.

(b): June 30, 1986 letter from D. L. Farrar D. L. Farrar to H. R. Denton.

Dear Mr. Denton:

Reference (a) documented the NPC's approval of NCIG-01, Revision 2, Visual Welding Acceptance Criteria for Structural Welding at Nuclear Power Plants. This document was prepared by the Nuclear Construction Issues Group. Commonwealth Edison Company has implemented this guideline for visual structural weld inspections at Zion Station on July 1, 1986.

Reference (b) transmitted the annual FSAR updates for Dresden, Quad Cities, and Zion Stations. Page 1.3-2 of Zion's Updated PSAR documents the use of NCIG-01, Rev. 2 as discussed above. A copy of this page is attached.

If any questions arise regarding this matter, please direct them to this office.

Very truly yours, l f k$

P. C. LeBlond Nuclear Licensing Administrator 1m cc: Resident Inspector - Zion J. A. Norris - NRR 1840K o h 8607o3 o500o295 PDR A06l l l

.r e

-Qualit.y standards of material selection, design, fabrication, and inspection governing the above features conform to the applicable provisions of recognized codes and ' good nuclear construction practice. Visual structural weld inspections in accordance with guidelines prepared by the Nuclear Construction Issues Group, NCIG-01 Rev. 2 (5/7/85), titled " Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants," will be implemented and used effective July 1, 1986. The concrete structure of the reactor containment conforms to the applicable portions of ACI-318-63.

Further elaboration on quality standards of the reactor containment is given in Chapter 5. Vessels comply with the ASME Boiler and Pressure Vessel Code under the specific classification dictated by their use, or other appropriate Codes. The principles of this Code, or equivalent guidelines, are employed where the Code is not strictly applicable but where the safety function calls for an equivalent assurance of quality. In the same manner, piping conforms to the requirements of the USA Standard Code for Pressure Piping (ASA B31.1-1955) and Nuclear Code Cases N-7 and N-10. Valves within the reactor coolant pressure boundary and those that are safety related were procured to approved equipment specifications from vendors having approved quality assurance programs. The specifications required the valves to be designed to USAS 8.16.5; a few were designed to meet NSS SP-66 and ASME III, 1968 editio'n. These specifications do not require the manufacturer's inspection.

In the normal course of valve vendor quality control, periodic dimensional checks on a campling or spot check basis are made. When errors in thickness were found, the output from the foundries have been checked and repairs have been made as necessary. In addiion to the above, those valves 2-1/2 inches and up are generally subjected to volumetric inspection by ultrasonic or radiographic means (or by both), and are lastly hydrostatically tested.

In the case of valves furnished under the NSSS contract, Westinghouse conducts periodic vendor inspections to verify that the vendor is indeed complying with the approved program and procedures. Edison has audited Westinghouse to confirm this action sequence.

For valves purchased by Edison, audits and inspections of various vendors have been conducted by Edison to verify that the vendors are complying with the approved programs and procedures.

All of the above actions are performed in accordance with the Edison Quality Assurance Program.

No reliance has been placed on the ASME survey and inspection system for equipment. The majority of the Seismic Class I equipment was purchased before the ASME system was instituted.

Particular emphasis is placed on the assurance of quality of the reactor vessel to outain material whose properties are uniformly within tolerances appropriate to the application of the design a methods of the Code. The fatigue usage factor is less than that at )

which propagation of material defects would occur. Design margin and i material surveillance assure that the vessel will be operated well 1.3-2 0086T Revision 1 0066A June 20, 1986 1