ML18139B887

Responds to 820421 Request for Addl Info Re Clarification of 820325 Response Re Regenerative Heat Exchangers & Welds on RHR Sys

ML18139B887
Person / Time
Site:	Surry
Issue date:	05/25/1982
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S Office of Nuclear Reactor Regulation
References
263, NUDOCS 8206020399
Download: ML18139B887 (4)

Text

e VIRGINIA ELECTRIC AND POWER COMPANY '

RICHMOND., VIRGINIA 23261 R.B.LEASBURO VxcE PRESIDENT NUCLEAR OPERATIONS May 25, 1982 Mr. Harold R. Denton, Director Serial No. 263 Office of Nuclear Reactor Regulation NO/RMT:acm Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch #1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen:

This letter is in response to your request for information dated April 21, 1982 concerning clarification of our previous response dated March 25, 1982.

The enclosure to this letter provides the additional information requested.

~r~t~~urs, R.H. Leasburg cc: Mr. James P. O'Reilly Regional Administrator Region II

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e e Enclosure RESPONSE TO FURTHER REQUEST FOR ADDITIONAL INFORMATION SURRY UNITS ONE AND TWO Question 1 and 2 Please disregard the request for relief of examinations on the regenerative heat exchangers as required by code Category B-B for Unit 2 and Category C-A for Unit 1.

Question 3 As both Surry unit piping systems were constructed to B31.l 1967, no preservice work was performed on Class 2 systems prior to unit startup.

Therefore, the as-built construction of each, weld cannot be determined for inspectability until the NDE examination is performed for Inservice Inspection.

Class 2 circumferential butt welds under Item C2.l that cannot be volumetrically examined 100% as required by Section V T-532 would be determined on a case basis. Supplemental surface inspections would then be performed.

The listings that were provided with both Surry 1 and 2 Relief Request were welds that had been previously inspected for meeting other augmented examination requirements and were known to be inaccessible for performing a 100% volumetric examination of the weld and RAZ due to geometric configuration.

Question 3b Attached are the .sketches showing clarification of welds on the RHR system for items (vi) and (vii) under note II in the unit 1 Relief Submittal.

Question 3c As both Surry units 1 and 2 approach the end of the first 10 year Inspection interval the Inservice Inspection Programs are in the process of being revised and updated under the terms of 10 CFR 50.55a (g) (4) (IV).

With using the 1980 edition thru and including the 1980 winter addenda of Section XI, the volumetric examination requirement in piping is specified in figure IWC-2500-7. The ability to inspect the specified weld volume can be achieved from inspecting from one side of the weld using established techniques. Whereas the 1974 edition thru and including the summer 1975 addenda requires 100% of the weld and RAZ to be volumetrically examined.

Also, there is no provision for exempting piping with O. 500" wall thickness for volumetric examinations where a surface examination is required as is allowed with the 1980 thru winter 1980 addenda of Section XI.

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