ML17054D571

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Forwards Request for Info in Form of Replacement or Addl Pages to 850612 Application Re Receipt,Possession,Insp & Storage of Fresh Fuel Assemblies.Review of Application Will Continue Upon Receipt of Info
ML17054D571
Person / Time
Site: 07002948
Issue date: 07/29/1985
From: Horn M
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Zllnick A
NIAGARA MOHAWK POWER CORP.
References
NUDOCS 8508080292
Download: ML17054D571 (6)


Text

FCUP:MH 70-2948 Niagara Mohawk Power Corporation ATTN:

Mr. A. S. Zllnick Manage of Nuclear Operations 300 Erie Boulevard West Syraruse.

New York 13202 Gentlemen:

We have completed our initial review of your June 12, 1985, application for the receipt, possession.

inspection, and storage of fresh fuel assemblies required f'oI" the operation of Nine Mile Point Nuclear Station.

We find that additional, information should be included in replacement pages (or additional pages as necessary) to your application.

Our review of your application will be continued upon receipt, of the. requested information.

Please contact us if you have any questions (301-427-4510).

Si nce rely, Original Signed 8y:

Merri Horn Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS

Enclosure:

As stated cc:

Don Hill Conner 5 >letterhahn, P.C.

Distribution Docket 78-2948 8 Docket-410 NMSS R/F FCUP R/F

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REQUEST FOR ADDITIONAL INFORMATION NINE MILE. POINT, UNIT 2 1..

Page 1, Section 1.1 State the inner dimension, thickness, and height of the fuel assembly channel and the. construction of material.

Will the fuel assemblies be channeled before stor age?

2.

Page 2, Secti on 1.1 Page 2 of your application gives the maximum pin enrichment of the new fuel as 2.191 w/o U-235, however,

Table, 1 states the. maximum pin enrichment to be 3.00 w/o U-235, please clarify.

3.

Page 2., Section 1.1 State the total quantity of U-235 requested in your license application;.

4.

Page 3, Section 1.2.

State the maximum number of fuel assemblies that will be covered by each steel cover plate in the New Fuel Vault..

State the maximum number of fuel assemblies that will be uncovered at any one time in the new fuel vault.

5.

Page 5

Demonstrate the maximum number of assemblies in the New Fuel Vault that will remain uncovered at one time cannot be made critical independent of the degree of water (or mist) moderation.

6.

Page 5, Section 1.2 Provide the composition of boraflex, include percent by weight of the various constituents (Boron, Carbon, Impurities), minimum B-10 content, and the Boraflex density (g/cm ).

7.

Describe'the quality assurance program to assure. that the boraflex composition, plate fabrication, and installation meet design specifications.

Describe the quality assurance program to assure that the boraflex is securely captured into the stainless steel wall of the specified storage cell in accordance with storage rack design.

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8.

Identify the position responsible for developing and implementing procedures involving the control and handling of fuel assemblies.

9.

Identify the position responsible for developing the health physics procedures.

10.

Identify the position/committee responsible for the review and approval of the fuel handling and safety-related procedures.

ll.

Describe the fire alarm and control system.

12.

Provide the minimum qualifications for the positions responsible for nuclear criticality safety and fuel handling.

13.

Page 5, Section 1.2 Explain the statement "The spent fuel rack density (storage density) is 100 percent."

14.

Pages 16, 21 Confirm that the Station Shift Supervisor (pl6) and the Station Shift Supervisor Nuclear (p21) are the same position or provide the minimum qualifications and job descriptions for both positions.

15.

Page 10, Section 2.1 Confirm that all equipment used will be calibrated prior to use.

16.

Page 17, Section 2.2 Confirm that all personnel involved in fuel handling activities will receive prior training related to the safety of their operations, which will include emergency procedures and accident conditions.

17.

Page 6, Section 2.1 Document that all personnel involved with radiation control activities will receive training in use of equipment and procedures for dealing with radiological problems or job-related accidents.

18.

Confirm that all personnel will receive training pursuant to 10 CFR 19.12.

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