ML20136H108

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Forwards SER Re 850718 Requests for Relief from Inservice Insp Requirements.Change in Insp Program Acceptable Based on Listed Condition.Summary Tabulation Encl
ML20136H108
Person / Time
Site: Hatch 
Issue date: 11/07/1985
From: Harold Denton
Office of Nuclear Reactor Regulation
To: Beckham J
GEORGIA POWER CO.
Shared Package
ML20136H113 List:
References
TAC-59304, TAC-64164, NUDOCS 8511250035
Download: ML20136H108 (3)


Text

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November 7,1985 Docket No. 50-321

- DISTRIBUTION

.. Docket File-.

JPartlow NRC POR ~

ACRS-10 L PDR RIngram Mr. J. T. Beckham, Jr.

ORB #4 Rdg GRivenbark Vice President - Nuclear Generation HThompson Gray File Georgia Power Company 0 ELD P. O. Box 4545 EJordan Atlanta, Georgia 30307 BGrimes

Dear Mr. Beckham:

10 CFR 50.55a(g) requires that applicable ASME Code components of a boiling water-cooled nuclear power facility meet the requirements set forth in Section XI, Rules for Inservice Inspection of Nuclear Power Plant components, of the ASME Boiler and Pressure Vessel Code. Each facility is required to have an inspection program plan which is updated every ten years to meet the requirements of the latest approved applicable edition and addenda of Section XI.

By [[letter::05000321/LER-1984-025, :on 841215,linear through-wall Crack Approx 2 3/4 Inches Long Discovered in Weld 1T48-2CPI-18-P1D-6. Caused by Thermally Induced Stress.Crack Ground Out,Weld Repaired & Addl Welds Inspected|letter dated July 18, 1985]], Georgia Power Company (GPC) stated its intention to complete the examinations for the Hatch Unit 1 first ten-year inspection interval, basing the examinations on a program written to the 1980 Edition of the ASME Code Section XI with Addenda through Winter 1980. The [[letter::05000321/LER-1984-025, :on 841215,linear through-wall Crack Approx 2 3/4 Inches Long Discovered in Weld 1T48-2CPI-18-P1D-6. Caused by Thermally Induced Stress.Crack Ground Out,Weld Repaired & Addl Welds Inspected|July 18, 1985 letter]] also requested relief for Hatch Unit 1 from certain of these Section XI Code requirements. The first ten-year inspection interval for Unit I will be concluded on December 31, 1985.

The rationale for the Hatch Unit 1 end-of-the-interval update is to have both Hatch units examined to the same Code Edition. The Hatch Unit 2 first ten-year inservice inspection program had been previously updated to the 1980 Edition and Addenda through Winter 1980 of Section XI Code. Previous inservice inspections for Unit I were completed under a program written in conformance with the 1974 Edition of the ASME Section XI Code with Addenda through Summer 1975. The change in the inspection program for completion of the first ten-year interval is acceptable, provided that all components required to be inspected in this interval based on the 1974 Edition of Section XI Code are inspected by the end of the first interval.

As indicated in the enclosed Safety Evaluation (SE), we have concluded that some of the relief requests should be granted, some conditionally granted and others denied. We have also concluded that relief is not required for some of the items requested. The enclosed SE provides the details of our review, and Attachment I to the SE provides a summary tabulation of our conclusions concerning each request.

We have determined pursuant to 10 CFR Part 50.55a(g)(6)(i), that the granting of this relief is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest.

In making this determination, we have given due consideration to the burden that could result if these requirements were imposed on your facility.

Ob11250035 851107 PDR ADOCK 05000321 0

PDR

1 Mr. Beckham We note that we have also discussed the concept of having concurrent ten-year inspection intervals and updating the inservice inspection programs for both units to the same ASME Code Edition with GPC representatives. We agree with this concept, and we are now evaluating GPC's updated second ten-year interval inservice inspection program for Units 1 and 2 (submitteo June 25, 1985) which will implement this concept.

Sincerely, ggaed13 g,W M Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosure:

Safety Evaluation cc w/ enclosure:

See next page 3

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Mr. J. T. Beckham, Jr.

Edwin I. Hatch Nuclear Plant, Georgia Power Company Units Nos. I and 2 cc:

G. F. Trowbridge, Esq.

Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, D.C.

20036 Mr. L. T. Gucwa Engineering Department Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302

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Mr. H. C. Nix, Jr., General Manager Edwin I. Hatch Nuclear Plant Georgia Power Company P. O. Box 442 Baxley, Georgia 31513 4

Mr. Louis B. Long Southern Company Services Inc.

P. O. Box 2625 Birmingham, Alabama 35202 Resident Inspector U.S. Nuclear Regulatory Comission Route 1, P. O. Box 279 Baxley, Georgia 31513 Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street Suite 3100 Atlanta, Georiga 30303 Mr. Charles H. Badger Office of Planning and Budget Room 610 270 Washington Street, S.W.

Atlanta, Georgia 30334 Mr. J. Leonard Ledbetter,' Comissioner Department of Natural Resources 270 Washington Street, N.W.

Atlanta, Georgia 30334 Chairman Appling County Comissioners County Courthouse Baxley, Georgia 31513

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