ML20215M373
| ML20215M373 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/22/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | James O'Reilly GEORGIA POWER CO. |
| Shared Package | |
| ML20215M377 | List: |
| References | |
| TAC-64164, NUDOCS 8706260376 | |
| Download: ML20215M373 (3) | |
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UNITED STATES 8'
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WASHING TON, D. C. 20555 4,
,o g2 Junggy Docket No.: 50-321 Mr.-James P. O'Reilly Senior Vice President - Nuclear Operations Georgia Power Company P.O.- Box 4545 Atlanta, Georgia 30302
Dear Mr. O'Reilly:
Subject:
Granting of Relief - Edwin I. Hatch Nuclear Plant, Unit 1 (TAC 64164) 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 met 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 C %pany (GPC) stated its l
intention to complete the examinations for the Hatch Unit 1 first ten-year inspection interval, concluded on December 31, 1985, basing the examinations i
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 j
for Hatch Unit 1 from certain of these Section XI Code requirements. The NRC staff reviewed the relief requests contained in GPC's [[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]] and, on November 7,1985, sent you a response granting some of the requests, granting some conditionally, and denying others. Among these requests, Relief Request 4.1.2 pertained to buried piping in the plant service water system which had not been designed to accommodate the testing as later required by Paragraph IAW-5244 of the 1980 Edition of the ASME Code. Our November 7,
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1985, letter granted this request.
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On November 14, 1986, Georgia Power Company submitted a revised Relief Request I
4.1.2, requesting similar relief for the demineralized water, core spray and any other buried ASME class 3 piping systems which had not been designed to accommodate the testing required by Paragraph IAW-5244,Section XI, of the 1980 Edition of the ASME Code. The NRC staff has examined this revised request and has concluded, as discussed in the enclosed Safety Evaluation, that the Code
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required examinations are impractical to perform on these piping systems, but that the system functional testing will provide assurance of the structural integrity of the piping systens.
$$0$00h !
G L.
-- ---- --- ----- ------o
Mr. O'Reilly I Accordingly, relief is granted during the first 10-year interval only from performing the Code-required system pressure tests for Class 3 buried piping sections of the following systems:
a.
Plant service water from valve pit at the intake structure to the Diesel Generator Building and the Reactor Building.
l b.
RHR service water from the valve pit at the intake structure to the Reactor Building.
l c.
RCIC pump suction from IE51-F009 to IE51-F010.
i d.
HPIC pump suction from IE41-F010 to IE41-F004.
l We have determined pursuant to 10 CFR Part 50.55a(g)(6)(i), that the granting l
of this relief is authorized by law and will not endanger life or property or i
the common defense and security and is otherwise in the public interest.
In making this determination, we have given due coni,ideration to the burden that could result if these requirements were imposed on your facility.
1 Sincerely,
.l l
t B.J. Youngblood, Director l
Project Directorate II-3
{
Division of Reactor Projects I/II J
Enclosure:
Safety Evaluation cc w/ encl: See next page j
1 DISTRIBUTION:
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LCrocker 0GC-Bethesda l
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C Mr. James-P. 0'Reilly' Edwin_I. Hatch Nuclear Plant,
. Georgia Power Corapany Units Nos. I and 2'
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.cc:
~ G. F. Trowbridge,- Esq.
Shaw, Pittman, Potts and Trowbridge L1800 M Street, N.W.
Washington,.D.C. 20036 Mr. L..T.'Gucwa Engineering Department-Georgia Power Company -
P.-0. Box 4545
.o Atlanta, Georgia ' 30302 Mr. H. C. Nix, Jr., General' Manager Edwin I. Hatch Nuclear Plant Georgia Power Company P. O. Box 442
.j Baxley, Georgia 31513 l
Mr. Louis B. Long i
Southern Company Services, Inc.
P. 0.' Box 2625 Birmingham, Alabama 35202 Resident' Inspector U.S. Nuclear Regulatory Commission Route 1, P.'0. Box 279 Baxley, Georgia - 31513 l
Regional Administrator, Region II U.S. Nuclear Regulatory Comission, 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 s
Department of Natural Resources 270 Washington Street, N.W.
Atlanta, Georgia 30334 Chairman Appling-County Comissioners County Courthouse Baxley, Georgia-31513 u