ML19312C413
| ML19312C413 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/28/1976 |
| From: | Parker W DUKE POWER CO. |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEC-76-06, IEC-76-6, NUDOCS 7912130935 | |
| Download: ML19312C413 (3) | |
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Di' E POWER COMPMY Powzs Buturwo 4gg 422 SocTn Catacu Srazzr, CnAaWTTz, N. C. 28242 4
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ViCE P=ES8 0tset TCLEPwC*st: AmE4 704 373 40a3 S.ra= pocovenow 1
December 28, 1976 4
Mr. Norman C. Moseley, Director U. S. Nuclear Regulatory Commission Suite 818 230 Peachtree Street, Northwest Atlanta, Georgia 30303 Re:
IE:ll:NRC IE Circular 76-06 50-269 50-270 50-287
Dear Mr. Moseley:
f Your letter of November 24, 1976 transmitted ole Circular 76-06 dis-cussing problems encountered with stress corrosion cracks in stagnant low pressure stainless steel piping containing boric acid solution and requested that we submit a description of a program for assuring i
i continued integrity of safety-related piping systems which are not i
f requently flushed or which contain non-flowing liquids.
In response to this request, the following program is submitted:
j Oconee Unit 1
(') Class I and 2 piping and components will be examined in accordance with the inservice inspection provision of 10CFR50.55a, with exceptions noted in the Oconee Technical Specifications.
(2) Class 3 piping and components will be examined as indicated in.
Oconee Units 2 and 3 i
The requirements of the ASME Boiler and Pressure Vessel Code,Section XI
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1970 Edition through Winter 1970 Addenda, and Enclosure 1 apply.
Ex-ceptions are identified in the Oconee Technical Specifications.
The above examinations will be performed during the next scheduled refueling outage for each unit and once again within the ten (10) year inspection interval.
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Mr. Norman C. Moseley Page 2 December 28, 1976 Portions of the decay heat removal and core flood lines on Oconee Unit I wcre volumetrically examined during the 1976 inservice inspection and no evidence of cracking was found.
V y truly yours,A N
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William O. Parker, Jr EDB:vr Attachment i
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Inspection Table System Boundaries of Examination inspection *a Extent
- Decay Heat Removal; From connection to RCS to first Vol 25>, of all welds Core Flood; Lew isolation valve Pressure injection From first isolation valve to:
Vol 5% of total welds (1)
Core flood tanks, and (2)
Outside containment isola-tion valves From outside containnent isolation Pressure 15 inspection points s
..es to BWST Test N)
Reactor Building From inside containment check Vol 10% of total welds Spray valves to outside containnent isolation valves From outside containment isolation Pressure 2 inspection points per valves to branch connection Test header to low pressure injection pump suction headers liigh Pressure From connection to RCS to first Vol 25% of all welds injection isolation valve (Pump 2C Dis-charge)
F roia f i rs t isolation valve to Vol 5'/, of total welds outside containment isolation valve From outside containnent isolation Pressure 5 inspection points valte to letdown storage Test tank
^ Pressure retaining welds only will be considered in determining the number of welds to be examined.
involumetric examinations shall be conducted in accordance with the procedures contained in the cuirent inservice inspection Manual for each unit.
Pressure test shall be conducted in accordance with IWA-5000 and IWB-5000 of ASME Code Section XI 1974 Edition, except that the number of inspect w points w,ill be as listed in the
" Extent" column above.
Enc 0es"-e 0
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