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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i DUKE Powrn COMPANY l Powra Bunutwo l 422 SouTu Caur x Stasst. CaAnwitz, N. C, sea 4s ;
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Mr. Harold R. Denton, Director . , , ,
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Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4
' i, ,co' N.Is@'*W - f Re: McGuire Nuclear Station Y/ !
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t Docket Nos. 50-369, 50-370 Control of Heavy Loads, NUREG-0612 i
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Dear Mr. Denton:
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On December 22, 1980 a letter was sent to all licensees of operating plants and !
)j 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. }
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 [
E on the floor would be obscured since the floor is covered when work is in pro- )
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: l l- 1. Safe Load Paths - Safe load paths have been defined specifically for i 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 -)
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 !
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Mr.' Harold R. Denton, Director r June 2, 1981 i Page 2 [
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 I fission product inventory and essentially no potential public health 'I and safety concerns. Upon completion of-the load path evaluation,
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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. j i '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 i ~
actor building as noted in Item 1 above. The existing procedures l 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. I I 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. [
New equipment will be ordered to upgrade the vision screening program. l 1
- 4. Maintenance and Testing of Cranes - Cranes are inspected, tested and [
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, {
1,980 letter) will not be available at that time. This is due to the extensive involvement of McGuire Station personnel in preoperational testing and mainte- l nance' activities directed toward startup of Unit 1. It is anticipated that i l
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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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