ML20005B229

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Speech Entitled Licensing & Regulatory Aspects of Independent Spent Fuel Storage Installations, to Be Presented at ANS 811129-1204 Meeting in San Francisco,Ca
ML20005B229
Person / Time
Issue date: 12/04/1981
From: Roberts J
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
References
NUDOCS 8107060506
Download: ML20005B229 (5)


Text

.

e A Speech to be

. presented by John P. Roberts, NMSS U.S. Nuclear Regulatory Commission to the American Nuclear Society at its

-1981 Winter Meeting, to be held in San Francisco, California l

November 29 - December 4, 1981 j

" Licensing and Regulatory Aspects of Independent Spent Fuel Storage Installations" i

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a Storage of nuclear reactor soent fuel outside of reactor basins has been practiced in the United States for' decades in both wet and dry storage facilities. However, with the exception of the General Electric Company's Morris Operation, such storage has generally either not been subject to NRC licensing or has been in conjunction with reprocessing activity..The potential need for commercial power reactor spent fuel storage capacity in addition to that provided by reactor basins (because of delays in and, subsequently, deferment of spent fuel reprocessing) was first fonnally recognized by the Nuclear Regulatory Comission (NRC) in 1975.I At that time Commission instructed its staff to prepare a generic environmental impact statement (GEIS) on handling and storage of light water power reactor spent fuel (published as NUREG-0505, August 1979)2 The conclusions of thi: GEIS included recognition of the need for such away-from-reactor storage capacity and support for the development of a specific rule for licensing of such storage. That rule,10 CFR Part 72, " Licensing Requirements for.the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation," was issued in final fonn by the NRC on November 12, 19803 The rule covers the licensing of spent fuel storage, using wet or dry storage technology, at independent spent fuel storage installations (ISFSI's) located either on reactor sites or on separate sites. Associated regulatory guides supporting Part 72 have been published.

While part 72 was under development, it appeared that federal spent fue!

storage policy would result in a few, large, centralized ISFSI's. These were expected to be operated by the Department of Energy (DOE) and licensed by NRC. This policy has been revised and utilities will have to make their i

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own arrangements for additional spent fuel storage capacity. With the exception of the General Electric Company's Morris Operation (for which storage is now licensed under 10 CFR Part 70, " Domestic Licensing of.

Special Nuclear Material"), which has applied for license renewal under the new Part 72, it appears likely that new ISFSI's will be built, for the most part, at reactor sites. Also, there is increasing interest in

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dry storage technologies, the development of which DOE continues to support.

The NRC has received' letters of intent to submit this year Topical Reports on two dry storage cask designs for safety review. The successful completion of such review would result in a letter of approval allowing

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referencing of a Topical Report or portions thereof in a Safety Analysis Report (SAR) submitted as part of a site specific Part 72 license application for spent fuel storage.

A site specific license application under Part 72 for spent fuel storage in an ISFSI involves not only a safety review of the SAR submitted but also an environmental review of the applicant's Environmental Report.

For a proposed at reactor site ISFSI, previous submittals under the reactor Part 50 licensing action for the facility and site may be referenced by the applicant (Section 72.12. " Elimination of Repetition" specifically covers referenc~ing of material previously filed with the

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NRC). Sharing of structures, systems and components may occur with an r


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3 ISFSI and reactor which occupy the same site. This action will be examined both in the Part 72 review as applicable and, separately, from a reactor safety standpoint and the need, if any, for. amendment to-the reactor Part 50 operating license.

This summary has given a brief outline of spent fuel storage developments, the issuance by NRC of a new rule to cover storage of spent fuel in ISFSI, the recent federal policy change with respect to spent fuel storage and NRC reviews of topical reports and license applications.

In the presentation of _this paper we sha'11 discuss in greater detail the licensing of spent fuel storage under Part 72 with emphasis on, as above, at reactor site i

ISFSI's and shall indicate the status of safety reviews of topical reports for dry storage casks.

I Federal Register, Vol. 40, No.180, p. 42801, General Services Administration, Washington,D.C.(1975).

2" Final Generic Environmental Impact Statement on Handling and Storage of Spent Light Water Power Reactor Fuel" (NUREG-0575), U.S. Nuclear Regulatory Commission (1979).

3 ederal Register, Vol. 45, No. 220, p. 74693, General Services Administration, F

Washington, D.C. (1980).

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SUMMARY

COVER SHEET CONTRIBUTED PAPER INVITED PAPER i

k ORIGINAL AND THREE COPIES REQUIRED h Me. Vs Ti m.

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AUTHOR (S,. (List authors in the proper order and exactly as they are to be published. PLACE"AN,ASTE

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I AFTER EACH AUTHOR WHO IS AN ANS MEMBER; AN "S" AFTE:t STUDENT I

1.

John P. Roberts

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AFFILIATION (S): (List corresponding author's affiliation and complete mailing address.)

1.

U.S. Nuclear Regulatory Comission, Mail Stop 396-SS, Washington, D.C.

20555 2.

3.

1 Indicate number of author to whom correspondence should be addressed

. and complete page 4.

To whom should the page charge be billed?

US Nuclear Regulatory Commission Billing address: c/o John P. Roberts, Mail Stop 396-SS, Washington, D.C.

20555 Preferred: Attach purchase order with appropriate purchase order number to original copy of the summary.

3 0

0 Number o.. Pages Tables Figures Word Count-Text 310 + (No. of figures plus tables) x 150.D _ + (No. oflines of equations x 10) 0 870 Total Originalline drawings or glossy black-and-white prints of each figure must be attached to original.

FOR CONTRIBUTED

SUMMARY

Reactor Operations Division Idennfy ANS Division or Technical Group having cognizance of your subject U

In which subject category (carecory number from p. 3) do you feel this summary belongs?

5 Alternative Category Number:

Has the substance of this summary been presented or published previously (including U.S. DOE or equivalent reports)?

(O Give details YES Has the paper been submitted for publication in a technicel journal?

h Give details YES Have you presented related papers?

"geg gd og gp nggg gtions h

NO Give details !a"ited presentatier, M!S 1979 "anual "ccting.

3 Has this summary been approved for publication by your institution or company?

h NO Give de: ails FOR INVITED

SUMMARY

Reactor Operations Division Which ANS Division or Technical Group invited you?

15.3 Person who invited'you Dr. Raymond H. Shum Session No.

A COMPLETED

SUMMARY

COVER SHEET, TOGETHER WITH THE INFORMATION REQUESTED 8

ON PAGE 4. MUST BE ATTACHED TO EACH OF THE FOUR SETS OF THE

SUMMARY

. Please have copies made to complete your four sets.

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