ML20111B454

Responds to NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Over Safety- Related Equipment

ML20111B454
Person / Time
Site:	Cooper
Issue date:	05/13/1996
From:	Horn G NEBRASKA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-002, IEB-96-2, NLS960096, NUDOCS 9605140436
Download: ML20111B454 (2)

Text

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, GENERAL OFFICE

• P.O. box 499. COLUMBUS, NEBRASKA 68602@99 Nebraska Public Power District *WWe'l!%" x a .-

G. R. HORN Senior Vice-President, Energy Supply 140s) sas.ssis NLS960096 May 13,1996 U.S. Nuclear Regulatory Commission

' Attention: Document Control Desk Washington, D C. 20555-0001

Subject:

Response to NRC Bulletin 96-02; Movement of Heavy Loads Cooper Nuclear Station, NRC Docket No. 50-298, License No. DPR-46

References:

1) NRC Bulletin 96-02, dated April 11,1996, " Movement of Heavy Loads Over Spent Fuel Pool, Over Fuel in the Reactor Core, or Over Safety-Related Equipment"

2) NUREG 0612, dated July 1980, " Control of Heavy Loads at Nuclear Power Plants"

3) Letter to J. M. Pilant (NPPD) from D. Vassallo (NRC), dated October 31, 1983, " Control of Heavy Loads (Phase 1)"

Gentlemen:

Pursuant to the requirements of 10 CFR 50.54(f), the Nebraska Public Power District (District) hereby submits to the Nuclear Regulatory Commission (NRC)its response to NRC Bulletin 96-

02. As required by the bulletin, the District has reviewed its plans and capabilities to handle heavy loads over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power and currently scheduled to be moved within the next two years from the date of the bulletin. The District has determined that its plans and capabilities to handle these heavy loads are in accordance with the existing regulatory guidelines, and that these activities are within its licensing basis. At this time, no changes to the Cooper Nuclear Station's (CNS's)

Technical Specifications are required.

Because the medes excluded from the scopo of the bulletin (cold shutdown, refueling, and defueled) do not precisely correlate to the plant modes defined in the CNS Technical Specifications, the District has interpreted the scope of the bulletin for CNS as applying to heavy loads being moved during the Run Mode, Startup/ Hot Standby Mode, and Shutdown Mode where the station is not in Cold Shutdown (reactor coolant temperature equal to or less than 212' F and the reactor vessel vented). The attached table describes the movement of heavy loads within the scope of this bulletin anticipated within the next two years.

9605140436 960513 PDR ADOCK 05000298 O PDR dq

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2 U.S. Nuclear Regulatory Commission May 13,1996

-Page 2*of 3

• As discussed in Reference 3, the Reactor Building crane, Intake Structure crano, and Control Building hoist (H-7) are all subject to the guidelines of NUREG-0612 (Reference 2). Other load handling devices have been excluded from the guidance of NUREG-0612 because either no safe shutdown / decay heat removal equipment or irradiated fuel is

- located in proximity of the device, or the load handling device's sole purpose is to provide

, a maintenance function such that a load drop will damage only equipment which is already out of service for maintenance.

• The NRC has accepted our response to Phase I to NUREG 0612 in the Safety Evaluation Report (SER) per Reference 3.

• The District has no plans to lift loads greater than those already analyzed in the Updated Safety Analysis Report (USAR) using the cranes subject to NUREG 0612 guidelines (see attached table).

• The District currently has no plans to move loads in excess of the analyzed limits (e.g.,

dry storage casks such as those used at Oyster Creek) over spent fuel.

Should you have any questions or require any additional information, please contact me.

Sin rely, _

W

. . rn ice President, Energy Supply

/dnm Attachments cc: Senior Project Manager -

USNRC - NRR Project Directorate IV-1 Senior Resident Inspector  ;

USNRC - Cooper Nuclear Station Regional Administrator l USNRC - Region IV NPG Distribution

. , 1 U.S. Nuclear Regulatory Commission l May 13,1996 l

'Page 3 of 3 STATE OF NEBRASKA )

)

PLATTE COUNTY )

G. R. Horn, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State

, of Nebraska; that he is duly authorized to submit this response on behalf of Nebraska Public Power District; and that the statements contained herein are true to the best of his knowledge and b icf.

. ux ln, ~

d . R. Ho'rn Subscribed in my presence and sworn to before me this /3 day of

/I?Ad ,1996.

' J M9NfMdH

>Ye 81r 4 M8 NOTXRY IMBLIC

Attachment to NLS960096 .

Page 1 of 2 Currently Planned Heavy Load Movements at CNS .

Within the Scope ofIEB 96-02 for the Next Two Years Loads to be moved by the Reactor Building Crane (Capacity 100 Tons):

Item No. Heavy Load Movement Approximate Current Movement Applicable Procedure Weight or Schedule Capacity (tons) 1 RPV Specimen Shipping Cask 17 July % Special Procedum 96-053 (GE 2000) 2 New Fuel Receipts 1.4 February 97 CNS Procedure 10.22 (Shipping Container) 3 Fuel Pool Cleanout May 1996 through SORC Approved Special

- TN-RAM Cask 40 June 96 Procedure 142B Cask 34 (to be developed),

- Associated Equipment 14 (max) Special Procedure 96-073 (e.g., Underwater Shear Compactor, (currently under Disposable Liner, Transfer Bell) development) for moving of associated equipment 4 Fuel Pool Coupon Inspection Cask 17 TBD CNS Pmcedure 10.20, (GE 2000) SORC Approved Special Procedure (to be developed) 5 Reactor Vessel Cavity Plug Removal (both activities)

- Outside Seal Circulator Cavity Plug 80 June 96 *, March 97 CNS Procedure 7.4.1

- Center Cavity Plug 92 June 96 *, March 97

• Date based on contingency mid-cycle outage.

Attachment to

-NLS960096 -

Page 2 of 2 Currently Planned Heavy Load Movements at CNS Within the Scope ofIEB 96-02 for the Next Two Years Loads to be moved by the Intake Structure Crane (Capacity 35 Tons):

Item No. Heavy Load Aforement Approximate Current Movement Applicable Procedure Weight or Schedule Capacity (tons) 1 Service Water Pump Rebuilding 6 A -May 96 CNS Procedure 7.1.8 B - Oct 96 C - Jan 97 D - March 97 2 Service Water Pump Closure Plug 6 Per above schedule CNS Procedure 7.1.8

- To be performed around the time of for Service Water SW Pump Rebuilding pump rebuilding

ATTACHMENT LIST OF NRC COMMITMENTS 3 i

. . (

Correspondence No: NLS960096 The following table identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or l planned actions by the District. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE

"^

None i

l l PROCEDURE NUMBER 0.42 l REV7SION NUMBER 1 l PAGE 9 OF 11 l l 1

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