ML20128B455

Responds to 850312 Request for Clarification on Relief NRC Granted on Item B 3.10 of Table IWB-2500-1 of Section XI of ASME Boiler & Pressure Vessel Code as Applied to nozzle-to- Vessel Welds.Request Granted Due to Amount of Vol Examined

ML20128B455
Person / Time
Site:	Fort Calhoun
Issue date:	06/19/1985
From:	Butcher E Office of Nuclear Reactor Regulation
To:	Andrews R OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 8507030233
Download: ML20128B455 (3)

Text

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June 19, 1985 DISTRIBUTION:

Docket No. 50-285 DOCKu FILE ACRS +10 NRC POR Gray File Local POR ORB #3 Rdg Mr. R. L. Andrews HThompson Division Manager - Nuclear Production OELD Omaha Public Power District EJordan 1623 Harney Street BGrimes Omaha, Nebraska 68102 JPartlow EGTourigny

Dear Mr. Andrews:

PKreutzer By letter dated April 6, 1984, we granted relief relating to ASME Code Class 1, 2, and 3 inservice examination requirements that the Omaha Public Power District determined to be impractical to perform during it's second ten year interval.

By letter dated March 12, 1985, you requested a clarification on the relief we granted to item B 3.10 of Table IWB-2500-1 of Section XI of the ASME Boiler and Pressure Vessel Code as applied to the nozzle-to-vessel welds. Item 83.10 required 100% volumetric examination of the nozzle-to-vessel weld in the earlier edition of code applicable for the first 10 year interval. Relief from this requirement was granted because a sufficient amount of the volume would be examined to provide a high degree of assurance that inservice flaws did not exist or would be detected in the vessel-to-nozzle weld.

Your March 12, 1985 letter indicated that there is no difficulty in achieving 100% weld volume coverage of the nozzle-to-vessel weld when performed from the inner diameter and the examination is deferred to the end of the interval. In addition, the 1980 edition of the code, which is now applicable for the second ten year interval at Fort Calhoun, allows for either internal or external exami-nation and the examination can be deferred until the end of the interval. On this basis we agree with you that an outer diameter examination is not required nor is the exemption necessary since you are now applying the 1980 edition of the code.

Your March 12, 1985 letter also requested that we clarify this matter in our final safety evaluation. Since our final safety evaluation will address only inservice testing of pumps and valves, we elected to address it separately herein.

Sincerely, 0507030233 MM h hPDR 05 Edward J. Butcher, Acting Chief fR Operating Reactors Branch #3 Division of Licensing cc: See next page

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l June 19, 1985 DISTRIBUTION:

Docket No. 50-285 DOCKET FILE ACRS +10 NRC PDR Gray File Local PDR ORB #3 Rdg Mr. R. L. Andrews HThompson Division Manager - Nuclear Production OELD Omaha Public Power District EJordan 1623 Harney Street BGrimes Omaha,-Nebraska 68102 JPartlow EGTourigny

Dear Mr. Andrews:

PKreutzer By letter dated March 12, 1985, Omaha Public Power District requested a clarification on the relief request to item B 3.10 of Table IWB-2500-1 of Section XI of the ASME Boiler and Pressure Vessel Code as applied to the nozzle-to-vessel welds. Item B3.10 required 100% volumetric examination of the nozzle-to-vessel weld in the earlier edition of code applicable for the first 10 year interval. Relief from this requirement was granted because a sufficient amount of the volume would be examined to provide a high degree of assurance that inservice flaws did not exist or would be detected in the vessel-to-nozzle weld.

In the letter dated March 12, 1985, you indicated that there is no difficulty in achieving 100% weld volume coverage of the nozzle-to-vessel weld when per-formed from the inner diameter and the examination is deferred to the end of the interval. In addition, the 1980 edition of the code, which is now applicable fcr the second ten year interval at Fort Calhoun, allows for either internal or external examination and the examination can be deferred until the end of the interval. On this basis we agree with you that an outer diameter examination perscribed in reference 5 of your letter is not required nor is the exemption necessary since you are now applying the 1980 edition of the code.

This issue is concerned with ISI and therefore we have elected to address it as a separate matter since our final SE will deal with only IST.

Sincerely, Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing cc: See next page ORB #3:DL EJButcher

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Mr. R. L. Andrews Omaha Public Power District Ft. Calhoun Station, Unit No. 1 Harry H. Voigt, Esq.

LeBoeuf, Lamb, LeiDy & MacRae 1333 New Hampshire Avenue, NW Washington, DC 20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68023 Metropolitan Planning Agency ATTN: Dagnia Prieditis 7000 West Center Road '

Omaha, Nebraska 68107 Mr. Larry Yandell U.S. NRC Resident Inspector Post Office Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations C-E Power Systems 7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator USNRC, Region IV Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 l

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