ML20004D721

Responds to NRC 801222 Ltr Re Review of Controls for Handling Heavy Loads.Discusses Status of Implementation for Safe Load Paths,Procedures,Operator Qualification & Training,Maint & Testing of Cranes

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)

Text

. . - - - - - ._ . - . _ _

f a

i DUKE Powrn COMPANY l Powra Bunutwo l 422 SouTu Caur x Stasst. CaAnwitz, N. C, sea 4s  ;

L i wlLLI AD4 O. *4 meter, Jm. ,

• CF Patt'Otas? TELt*=Oset Asta 7Ce '

I s,C.= *=ooweto= June 2, 1981 m..o n

, . . o , ..

Mr. Harold R. Denton, Director . , , ,

4'

. Office of Nuclear Regulation . /' i ,+-

-f- j, <

l U. S. Nuclear Regulatory Commission f' g ,

Washington, D. C. 20555 ;r M (t  ;

i' .. a :. 0 s 193 g **

Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4

' i, ,co' N.Is@'*W - f Re: McGuire Nuclear Station Y/  !

<Qih l "

t Docket Nos. 50-369, 50-370 Control of Heavy Loads, NUREG-0612 i

i

Dear Mr. Denton:

l l

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  !

30.s <

l 810 300 06 y m_ . _ . . , ,

7

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,

~

o l

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

t f

f

. . . _ . . , . _ . , . _ . , - . . _ - . . . , , , - - - . ~,, - . . . . . - . . _ _ , . . - _ , _,.._m. , ..

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. '

. f.

GAC:pw d

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

i l

l l l l

i T - - -,-+g .

n - .y- r- - - --9-, g-,- -- y ---y-ge . _