ML20126D479

Requests Info Re Criticality Analyses of Plant Spent Fuel Pool

ML20126D479
Person / Time
Site:	Millstone
Issue date:	12/16/1992
From:	Marucci M CO-OPERATIVE CITIZEN'S MONITORING NETWORK, INC. (CCMN
To:	NORTHEAST UTILITIES SERVICE CO., NRC
References
CON-#492-13479 92-665-02-OLA, 92-665-2-OLA, OLA, NUDOCS 9212280008
Download: ML20126D479 (3)

Text

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. iii.1 December 16, 1992 i:s i.E and Northeast Utilities, Inc.

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Box 270 Hartford, CT. 06101 Docket no. 50-336, FOL No.DPR-65,(ASLBP No. 92-665-02-OLA)

(Spent Fuel Pool Re-design)

Request for Information Pertaining to the criticality Analyses of Millstone II Spent Fuel Pool, Regions A, B,

C:

Numeration of requests is continued from Letter dated December 5,

1992.

1 8

a.

Provide all EPRI and other Industry reports that have been or are currently being used or are under consideration by the industry or the NRC in the development and implementation of programs that are intended to maintain suberitical conditions in the storage of spent and new fuel under "high-density" conditions.

We define "high density" conditions to exist in the stcrage area when, based solely on planned or actual distances between new or spent assemblies or consolidated waste cans, Keff can be greater than.95 l

b.

Specify where it is not immediately apparent from the particular spent fuel subcriticality maintenance

program, what special fuel loading patterns, locations, or other practices are or have been used, or are under consideration that may cause an otherwise unexpected variance in the exposure of the neutron absorbing materials.

9.

For those programs utilized to assess the criticality of the Millstone II spent fuel pbol, we ask that you provide all-algorithms that were utilized, describe what runs were done, give the input and output, and describe how these programs are benchmarked.

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10. How much to the overall reactivity of the spent fuel pool; does each of the following contribute:

a.

each of the currently stored spent fuel consolidated

cans, b.

a typical proposed consolidated can, c.

each of-the assemblies that has been in'the reactor'for one, two and three-fuel-cycles, respectively,

d. all other currently stored materials-in the1 pool.

Specify if reactivity contribution is measured or calculated, and provide both where available.

11. Provide accident records of.all previous criticality accidents, beginning in 1945, for both commercial and weapons industries.

Include descriptions and complete records.

'12.

Provide any and all studies done by anyone~in NRC or Indostry of what happens or can be expected to happen when a spent, fuel pool goes critical.

13. Provide any and all plans devised or under consideration' by NU or the NRC for the disposal or storage of-Millstone'II spent fuel generated in the past and to be generated with resumed operations for:

a.

The current licensed operational plant life.

b. the expected extended plant life with its new steam-generators, c.

the current redesign limit of the spent fuel' pool, with and without fuel consolidation.

d.

the next decade, e.

the period of time prior to the currently-anticipated startup date of a federal repository-for this waste.

14. Provide any and all plans under the; redesign for continuing or ceasing NU's stated corporate and engineering practice of having full-core offload capacity in its spent fuel pool.

15. Since the issuance of the current redesign amendment, how many refuelings can occur before'the Millstone'II spent-fuel pool

~

is:

a. without aesignated space for an emergency full-core offload?.

b. without space for spent-fuel unconsolidated assemblies?

16. Under what conditions can Region B be utilized for storage of anything other than new fuel without first obtaining a so license amendment?

. Sincerely,.

Mw N/L D%t.

Mary' Ellen Marucci Coordinator, CCMN-o

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I certify that copies of the foregoing CCMN REQUESTS FOR NU AND URC CRITICALITY INFORMATION have been served by first class U.S.

Mail on all the following persons.

Office of Commission Appe1 late U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Administrative Judges Ivan Smith, Chairman Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.

20555 John T. Hull, Esq.

Ann P. Hodsdon, Esq.

Office of the General Counsel U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Secretary of the Commission Docketing & Service Branch U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Richard M. Kacich Director, Nuclear Licensing Northeast Utilities P.O. Box 270 Hartford, CT 06101 Nicholas S. Reynolds, Esq.

John A. MacEvoy, Esq.

Winston & Strawn 1400 L Street. N.W.

Washington, DC 20005 7Erm b

(wd Dated at CT this Coordinator, CdMN,Inc.

18th day of December 1992

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