ML20151W518

Provides Clarification to Licensee Re Request for Exemption from 10CFR72.234(c) to Authorize pre-certification Fabrication Activities on Licensee Cask Systems to Support Maint of Full Core Discharge Capability at Ei Hatch Plants

ML20151W518
Person / Time
Site:	Hatch, 07201008
Issue date:	09/04/1998
From:	Tjersland G HOLTEC INTERNATIONAL
To:	Kane W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9809160011
Download: ML20151W518 (3)

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Holtec Center,555 l.incoln Drive West, Marlton, NJ 08053 INTERNATIONAL

{ (( Telephone (609) 797-0900 k l 1

1 BY FAX AND PRIORITY MAIL September 4,1998 Mr. William F. Kane Director, Spent Fuel Project Oflice Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852

Subject:

Clarification on Holtec Jnternational's Request for Exemption from 10CFR72.234(c)

References:

1. USNRC Docket Nos. 72-1008 and 72-1014 (TAC Nos. L22019 and L22221)

2. Holtec International Letter, G. T. Tjerstand to William F. Kane, NRC, dated August 3,1998 1

3. NRC Letter, M. Delligatti to G.T. Tjersland, Holtec, dated July 27,1998

Dear Mr. Kane:

Pursuant to our conversations with Messrs. Eric Leeds and Mark Delligatti of your staff, the ,

purpose of this letter is to clarify, and further justify, our Reference 2 request for an exemption l from 10CFR72.234(c) to authorize pre-certification fabrication activities on the HI-STAR 100 and HI-STORM 100 cask systems to support maintenance of full core discharge capability at l Southern Nuclear's Plant Hatch (Docket Nos. 50-321 and 50-366).

As discussed in the previous request (Reference 2), Southern Nuclear intends to load four cask systems at Plant Hatch in the Spring of 2000 to allow receipt of new fuel prior to the Unit 1 Cycle 19 outage scheduled for August 2000. Holtec is contracted to supply these cask systems.

It is Southern Nuclear's plan to load the HI-STORM 100 metal / concrete storage systems.

O, However, based on the HI-STORM 100 licensing schedule (Reference 3), it may be necessary for Holtec to supply, and for Southern Nuclear to load, HI-STAR 100 metal cask systems instead.

In order to keep the preferred option open (i.e., loading HI-STORM 100 Systems), the Reference 2 letter requested an exemption to 10CFR72.234(c) to fabricate four (4) MPC-68 canisters; four

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(4) HI-STAR 100 overpacks; four (4) HI-STORM 100 overpacks; and one (1) HI-TRAC transfer cask (for use with the HI-STORM 100 System).

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Holtec Center,555 Lincoln Drive West, Marlton, NJ 08053 p g Telephone (609) 797-0900 v lL l L Fax (609) 797-0909 l lNTERNATIONAL i

$ Mr. William F. Kane l

U.S. Nuclear Regulatory Commission i

September 4,1998 Page 2 of 3 Realizing that the HI-STORM 100 System application is early in the review process, Holtec l requests that the NRC grant an immediate exemption to allow material procurement activities for all components of both systems to commence, but only authorize fabrication of the HI-STAR l 100 overpacks and MPC-68 canisters. Due to the shorter fabrication period for the HI-TRAC transfer cask and HI-STORM 100 overpacks, we will separately request authorization to

! fabricate these components following issuance of the first round Request for Additional Information (RAI) currently scheduled for November 30,1998 (Reference 3).

Based on the justification above, Holtec requests that the following exemptiens be issued:

• An exemption to allow material procurement activities for four (4) MPC-68 canisters; four (4) HI-STAR 100 overpacks; four (4) HI-STORM 100 overpacks; and one (1) HI-TRAC transfer cask to begin by September 30,1998.

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• An exemption to authorize fabrication of four (4) MPC-68 canisters and four (4) HI-STAR 100 overpacks by February 15,1999.

After issuance of the First Round RAls, Holtec International will submit an additional request for an exemption prior to the statt of fabrication activities on the four (4) HI-STORM 100 overpacks and one (1) Hi-TRAC transfer cask. In order to support Southern Nuclear's schedule, the exemption to authorize fabrication of the HI-STAR System is required by Febmary 15,1999.

Note that a total of only four systems will be supplied to and loaded by Southern Nuclear in the l first loading campaign. The above approach will best meet the needs of Southern Nuclear to allow loading of four cask systems in early 2000. Preferably these will be HI-STORM 100 Systems due to the lower expected operational doses during loading and storage as a result of the additional shielding materials incorporated in the H1-STORM 100 overpack design.

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Holtec Center,555 Lincoln Drive West, Marlton, NJ 08053

. l Telephone (609) 797-0900 L [ {

L Fax (609) 797-0909 INTERNATIONAL Mr. William F. Kane U.S. Nuclear Regulatory Commission September 4,1998 Page 3 0f 3 If you have any questions please contact us.

Sincerely y n,a. /h. Gan.y T hasue Gary T. Tjersland Director ofLicensing and Product Development Document I.D. 5014233 Distribution (NRCh Mr. Eric Leeds Mr. Mark Delligatti Client Distribution:

Project Utility Holtec Proje_cj Mr. David Bland Southern Nuclear Operating Company 71188 Mr. J. Nathan Leech Comed 50438 Mr. Bruce Patton Pacific Gas & Electric Co. 71178 Dr. Max DeLong Private Fuel Storage, LLC 70651 Mr. Rodney Pickard American Electric Power 70851 Mr. Ken Phy New York Power Authority 80518 Mr. David Larkin Washington Public Power Supply System Mr. Eric Meils Wisconsin Electric Power Company Mr. Paul Plante Maine Yankee Atomic Power Company Mr. Stan Miller Vermont Yankee Corporation Mr. Jim Clark Southern California Edison - SONGS Mr. Ray Kellar Entergy Operations - Arkansas Nuclear One Mr. Joe Andrescavage GPU Nuclear- Oyster Creek Nuclear Station l

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