ML20102C216
| ML20102C216 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/22/1985 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR TAC-47127, NUDOCS 8503050385 | |
| Download: ML20102C216 (2) | |
Text
r-DUKE POWER Gone.*sy P.O. HOX 33180 CHARLOTTE, N.C. 28242 HALD.1UCKER rmenon n's8** = ***T (70-4) 373-4NM NUCLEAB:PRODLTTION February 22, 1985 Mr. Harold R. Denton, Director Off Lee of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
' Attention:
Ms. E. G. Adensam, Chief Licensing Branch D. 4
Subject:
McGuire Nuclear Station Docket Nos. 50-369 and 50-370 NUREG-0612, "Cor. trol of Heavy Loads at Nuclear Power Plants"
Dear Mr. Denton:
My letter dated August 17, 1984 responding to Mr. D. G. Eisenhut'r (NRC/0NRR) letter of December 22., 1980 included an assessment of the reactor coolant pump mctor lifting rig and the control rod drive mechanism (CRDM} missile shield lif ting rig for compl-Lance with the requirements of ANSI N14.6-1978 (as supplemented by NUREG-0612, Section 5.1.1. (4)). This assessment was performed to determine compliance with general load-handling Guideline No. 4 (Special Lifting Devices) of NUREG-0612 Section 5.1.1.
Our assessment of ANSI N14.6-L978 Section 5.3.1 indicated that annual load testing per Section 5.3.1 Part (1) for these lifting devices is omitted in accordance with Section 5.3.1 part (2) of ANSI N14.6-1978; and that Dimensional testing, visual inspection, and nondes tructive testing of mijer load-carrying welds and critical areas is performed in accordance with Section 5.5 as permitted by Section 5.3.1 part (2).
It should be noted that this dimensional, vistal, and nondestructive testing is performed prior to use (as opposed to annually) in view of ALARA considerations,aad since the rigs are only used during outages there is no reason to inspect them annually during power operation in which they wouldn't te used.
Thin matter has previvusly been discussed in a Telecon between mem._rs of your staff (Mr. Darl Hood, et. al) and Mr. P. 3. Nardoci et. al. (DPC) on February 21, 1985, during which this addit 1>nal information was requested. It is considered that this resolves all outstanding concerns with Duke's response to Mr. Eisenhut's December 22, L980 letter.
Very truly yours,
&W Hal B. Tucker PBN/mjf 8503050385 850222 0
PDR ADOCK 05000369 f
G PDR
- o b
Mr. Harold R. Denton, Director February 22, 1985
- Page cc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Darl Hood Division of Project Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. W. T. Orders Senior Resident Inspector McGuire Nuclear Station Mr. Amarjit Singh Auxiliary Systems Branch Division of Systems Integration Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
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