ML20214P778

Forwards Request for Addl Info to Facilitate Review of 860521 Application to Store Consolidated Spent Fuel.Response Requested within 30 Days of Receipt of Ltr

ML20214P778
Person / Time
Site:	Millstone
Issue date:	09/22/1986
From:	Jaffe D Office of Nuclear Reactor Regulation
To:	Opeka J NORTHEAST NUCLEAR ENERGY CO.
References
TAC-61658, NUDOCS 8609240055
Download: ML20214P778 (2)

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Docket No. 50-336 O

Mr. John F. Opeka, Senior Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270

Dear Mr. Opeka:

We are in the process of reviewing.your May 21, 1986 application regarding storage of consolidated spent fuel at Millstone Unit 2.

In order that we may continue our review, we request that you respond to the enclosed questions within 30 days following receipt of this letter. The enclosed questions supplement our requests for additional information dated July 25, 1986, August 21, 1986 and August 27, 1986.

This request for additional information affects fewer than 10 respondents, therefore, OMB clearance is not required under P.L.96-511.

Sincerely, ff!

David H. Jaffe, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page Distribution:

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y REQUEST FOR ADDITIONAL INFORMATION MILLSTONE 2 - STORAGE OF CONSOLIDATED FUEL IN= SPENT FUEL POOL Your submittal dated May 21, 1986 would permit storage of consolidated fuel in the present spent fuel pool.

Please respond to the following questions related to your proposal.

1.

Because many fuel pin movements will have been involved in the reconstituted fuel assembly, it is likely that activated crud will be released from some fuel pins.and adhere to some other pins.

Show how an increase in dose rates from such crud will be precluded when consolidated assemblies are returned to storage in the spent fuel pool.

2.

Describe the methodology that will be used to preclude' spent fuel pool water from becoming highly contaminated if pin ruptures occur (e.g.,

close capture cleanup system with filters appropriately shielded), and the method used for identifying pins that are most likely to rupture.

3.

Provide all data (mathematical models, parameters, codes and techniques used) that was used in the calculational model devised to determine the increase in dose rates in the spent fuel pool area due to a buildup of radionuclides in the pool water (Pg. 5-4, Attachment 1).

4.

Provide a table showing the expected tritium exposures due to the increased fuel storage capacity as the design maximum spent fuel pool water temperature increases from 120*F to 131*F (Pg. 5-5; Attachment 1).

5.

Your proposal (Pg.1-5) shows a total of 1277 storage locations including 10 spare cells and 217 cells reserved for a full core offload.

What is proposed for the remaining 69 locations?

,