ML20004D721
| ML20004D721 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/02/1981 |
| From: | Parker W DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 NUDOCS 8106090685 | |
| Download: ML20004D721 (3) | |
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June 2, 1981 m..o n
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Mr. Harold R. Denton, Director 4
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U. S. Nuclear Regulatory Commission Washington, D. C.
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Attention: Ms. E. G. Adensam, Chief f
Licensing Branch No. 4 co l
Re: McGuire Nuclear Station Y/
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Docket Nos. 50-369, 50-370 Control of Heavy Loads, NUREG-0612 i
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Dear Mr. Denton:
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)j On December 22, 1980 a letter was sent to all licensees of operating plants and applicants for operating licenses and holders of construction permits requesting a review of the controls for handling heavy loads. Certain interim actiont were specified to be implemented by May 15, 1981. Also, several reports documenting the licensees / applicants' review were requested. The purpose of this letter is
'to. inform you of the present status and future actions regarding this issue.
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The evaluation whichis underway has uncovered the need for flexibility in in-plementing some of the concepts in NUREG 0612, in particular, the safe load path concept. For example, NUREG 0612 states that safe load paths should be l
clearly marked on the flecr. In the Reactor Building, safe load paths painted
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E on the floor would be obscured since the floor is covered when work is in pro-
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j gress. Also, in other plant areas where several different safe load paths exist j
for one crane, load paths can criss-cross each other and lead to confusion t
which could causa mishandling of suspended loads. As an alternative, safe i
" load zones" can be defined. Insfde a particular zone the crane operator would be free to select the optimum path for moving the load. Duke Power Comp &ny con-r cludes that this load zone concept meets the intent of a safe load path and is therefore pursuing this approach.
The following is a brief discussion of the status of implementation for each of i
the five interim actions:
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l-1.
Safe Load Paths - Safe load paths have been defined specifically for the spent fuel cask in the fuel building. Load paths for the reactor i
building polar crane are implicitly defined, particularly for the i
major loads handled by thir crane, i.e., reactor vessel head, reacto
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intercals, and shield blocks. Each of these items has a designated i
l lay-down area and the most direct route is used in moving these items 30
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7 Mr.' Harold R. Denton, Director r
June 2, 1981 i
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f to the designated areas. Due to the design of the McCuire contain-ment, the only potential load drop target of concern is the fuel in the reactor vessel. All other 6quipment is located in the lower containment and thus is not a potential target for a dropped load.
A more detailed evaluatica is in progress to verify this, the re-i suits of which wili be reported later.
In any event, dropped loads in the recctor building are not a safety I
concern for the present. McGuire has not operated, thus there is no
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fission product inventory and essentially no potential public health and safety concerns. Upon completion of-the load path evaluation, l
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o detailed procedures for polar crane operation including safe load paths will be developed. These procedures will be available prior j
to the f'.rst use of the polar crane af ter initial criticality.
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'2.
Procedures - Spec ifin procedures exist for movement of the. spent.
f fuel cask in the fuel building and for the major loads in the re-l actor building as noted in Item 1 above. The existing procedures l
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or the need for additional procedures'will be evaluated. New pro-cedures will be implemented and/ot existing procedures modified prior to the first use of the polar crano after' initial criticality.
Similarly, any procedural modifications in the area of the spent fuel cask handling crane will be Lnplemented, if necessary, prior to placing j
any irradiated fuel in the spent fuel pools.
3 3.
Operator Qualification and Trsining - The guidelines of ANSI B30.2-1976 l
are followed in the qualification, training and conduct of crane operators.
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One minor area has been identified where improvements can be made...The vision screening program at McGuire does not fully meet ANSI B30.2-1976.
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New equipment will be ordered to upgrade the vision screening program.
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4.
Maintenance and Testing of Cranes - Cranes are inspected, tested and
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maintained in accordance with the guidelines of ANSI B30.2-1976.
l 5.- Special Consideration for Load Handling Operators Over the Core - As noted.a Items 1 and 2 above, the primary consideration for safe handling of loads is focused on load handling of heavy components /
equipment in the reactor buildirg. An evaluation is underway with a commitment to revise / write load handling procedures for the polar crane prior to the first use after initial criticality.
i The information requested by June 22,1981 (Six months af ter date of December 22,
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1,980 letter) will not be available at that time. This is due to the extensive l
involvement of McGuire Station personnel in preoperational testing and mainte-nance' activities directed toward startup of Unit 1.
It is anticipated that i
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3-Mr. Harold R. Denton, Director June 2, 1981 Page 3 this information will be submitted by August 5, 1981. A similar delay is likely 6
in submitting the information requested by September 22, 1981; however, any schedule delay fcc submitting this information will be addressed in our August 5 response.
l Very truly yours, William O. Parker, Jr.
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cc:
Ms. M. J. Graham.
Mr. J. P. O'Reilly, Director Resident Inspector - NRC U. S. Nuclear Regulatory Commission McGuire Nuclear Station Region II i
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