ML20077D453
| ML20077D453 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/15/1983 |
| 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 NUDOCS 8307260526 | |
| Download: ML20077D453 (2) | |
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DUKE POWER GOMPANY P.O. BOX 33180 CIIAHLOTrE. N.C. 28242
- HALH. TUCKER TELEPHONE gly==L July 15, 1983 (704) ara-4sai Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370
Dear Mr. Denton:
This is in response to Elinor G. Adensam's letter of June 10, 1983 containing a draft Technical-Evaluation Report (TER) concerning control of heavy loads.
The draft TER identified unresolved items concerning two of the seven guide-lines in Section 5.1.1 of NUREG-0612. The unresolved items concern (1) visual aids for safe load paths and (2) review of special lifting devices against the guidelines of ANSI N14.6-1978. The following provides additional information concerning those unresolved items:
1 (1) Safe Load Paths -' Safe load paths for the fuel handling area cranes, A108A and'A111A, are identified in procedures. As recommended in the TER, visual aids will be provided to assist the crane operator in ensuring that the designated safe load paths are actually followed. These visual aids will con-
-sist of temporary rop.e barriers, pylons, color-coded floor coverings, or other suitable aids as determined by practical considerations. Procedures to imple-ment 'the use of visual aids will be in effect by September 1,1983.
(2)
Special Lifting Devices - The following special lifting devices are being
. evaluated for compliance with the guidance in ANSI N14.6-1978:
a.
Reactor vessel head lifting rig and load cell b.
Reactor internals lifting rig c.
Reactor Coolant Pump motor lifting rig d.
Control Rod Drive Mechanism (CRDM) missile shield-lifting rig Our evaluation which is in progress indicates that the above devices comply with many of the applicable guidelines in ANSI N14.6-1978; however, information on the stress design factors used in the design of these devices is incomplete. We are pursuing additional information from the manufacturer for items a and b above.
The remaining devices were designed and constructed by Duke Power.
Items c and d were designed using standard engineering practices applicable at that time but the stress margins to yield strength were not determined. We are evaluating these A W)'. F. cdem Eadod 8307260526 830715
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' Harold R..Dento'n July;15, 1983~
Page 2 devices to determine the stress margins.
Programs concerning inspections, testing, and maintenance'of special lifting
- devices are in effect which conform to the applicable guidelines of Section 5 of ANSI N14.6-1978. except the load testing recommended in Section 5.2.1.
For
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items a and b, we'are working with the manufacturer to determine'what load l
testing has been performed. For the remaining items, we plan to perform load I
. tests in accordance with the guidance in the standard.
We' expect to complete the evaluation of special lifting devices for compliance with the guidelines of: ANSI N14.6-1978, including load tests, before the next refueling outcge on Unit.1 (December. 1983). We will provide NRC' staff with the results of the evaluation when completed.
Please advise if there are any questions.
Very truly yours, bsk Hal B.' Tucker REH:j fw cc:
Mr. James P. O'Reilly, Regional Administrator
- U. S.. Nuclear Regulatory Commission Region II 101 Marietta Street NW, Suite 2900 Atlanta, Georgia 30303 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station l
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