ML20101L550
| ML20101L550 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/18/1984 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NED-84-620, NUDOCS 8501020267 | |
| Download: ML20101L550 (2) | |
Text
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Georg a Power Company 333 P edmont Avenue Attanta. Geor;;:a 303C8 Telephone 404 526 6526 Maarg Address' Post Cnf ce Box 4545 A!Qnta, Georgia 30302 Georgia Power L T. Gucwa the southern eiectrc system Manager Nucrear Eng:neenng and CNet NucWf Eng.neer NED-84-620 December 16, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 CORRECTION TO SUBMITTAL ON INSPECTION OF INCONEL-BUTTERED RECIRCULATION SYSTEM N0ZZLES Gentlemen:
By letter dated July 27, 1984, Georgia Power Company provided you with information concerning the inservice inspection of selected Inconel 182-buttered Recirculation System nozzles during the 1984 maintenance / refueling outage at Hatch Unit 2.
Review of the subject letter by NRC Region II inspector, Mr.
B.
R.
Crowley, has indicated that a contradictory statement exists in Attachment 2 of that letter relative to the inspection of the Recirculation System jet pump instrumentation nozzle safe end-to-penetration seal welds.
The purpose of this letter is to correct the contradictory statement in our July 27, 1984 submittal.
Paragraph 2 of Appendix 2 of our July 27 letter incorrectly stated that the non-relevant indications observed in both "A"
and "B"
Loop safe end-to-penetration seal welds were detected on the ultrasonic instrument screen in a position representing a half vee-path node.
This statement is contradictory to Statement I which along with Statements 2 through 5 in Appendix 2 of the subject letter provides justification for the non-relevant indications as being evaluated as not representing material defects.
Please be advised that the indications were detected on the ultrasonic instrument screen in a position representing a one-and-a-half vee-path node rather than that discussed above and in Appendix 2 of our July 27 submittal.
This corrected statement resolves the contradiction between the original erroneous statement regarding indication screen position and Statement 1 of the justifications cited in Appendix 2 of the subject letter.
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Georgialbwer A Director.of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 December 18, 1984 Page Two Should you have any questions in this regard, please contact this office.
Sincerely yours, f C -Q= 1 -
L. T. Gucwa JAE/mb xc:
J. T. Beckham, Jr.
H. C. Nix, Jr.
J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector 700770