ML20134C148

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Forwards RAI to Complete Review of Licensee 960715 Submittal Re Proposed Exemption to Criticality Monitoring Requirements of 10CFR70.24(a) for Storage of Incore Detectors & Unirradiated Nuclear Fuel
ML20134C148
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 01/29/1997
From: Donohew J
NRC (Affiliation Not Assigned)
To: Hagan J
ENTERGY OPERATIONS, INC.
References
TAC-M96177, NUDOCS 9701310265
Download: ML20134C148 (4)


Text

1 Mr. Joseph J. Hagan January 29. 1997 Vice President, Operations GGNS Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO A PROPOSED EXEMPTION TO THE CRITICALITY MONITORING REQUIREMENTS IN 10 CFR 70.24(a)

(TAC NO. M96177)

Dear Mr. Hagan:

The staff is continuing its review of your submittal dated July 15, 1996, on a proposed exemption to the criticality monitoring requirements of 10 CFR 70.24(a) for storage of incore detectors and unirradiated nuclear fuel.

To permit us to continue our review on the current schedule we require that the information requasted in the enclosure to this letter be provided within 45 days of your receipt of this letter. The information requested in the enclosure was discussed with your staff during my visit to the site during the week of January 27, 1997, to expedite the submittal of the information needed by the staff.

Sincerel j

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Ja k N. Donohew, Senior Project-Manager NRC File CENTER COPY ero3ect Directorate iv-1 l

Division of Reactor Projects'III/IV Office of Nuclear Reactor Regulation s

Docket No. 50-416 S

Enclosure:

Request for Additional Information cc w/ enc 1:

See next page j

DISTRIBUTION:

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UNITED STATES g

g NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 20666-0001

'+9 *****,o January 29, 1997 4

Mr. Joseph J. Hagan Vice President, Operations GGNS Entergy Operations, Inc.

P. O. Box 756 Port Gibson, HS 39150

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO A PROPOSED EXEMPTION TO THE CRITICALITY MONITORING REQUIREMENTS IN 10 CFR 70.24(a)

(TAC NO. M96177)

Dear Mr. Hagan:

The staff is continuing its review of your submittal dated July 15, 1996, on a proposed exemption to the criticality monitoring requirements of 10 CFR 70.24(a) for storage of incore detectors and unirradiated nuclear fuel.

To permit us to continue our review on the current schedule we require that the information requested in the enclosure to this letter be provided within 45 days of your receipt of this letter. The information requested in the enclosure was discussed with your staff during my visit to the site during the week of January 27, 1997, to expedite the submittal of the information needed by the staff.

Sincerely, ban h

Jack N. Donohew e ior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-416

Enclosure:

Request for Additional Information cc w/ encl:

See next page

1 f

4 Mr. Joseph J. Hagan Entergy Operations, Inc.

Grand Gulf Nuclear Station cc:

Executive Vice President General Manager, GGNS

& Chief Operating Officer Entergy Operations, Inc.

i Entergy Operations, Inc.

P. O. Box 756 i

P. O. Box 31995 Port Gibson, MS 39150 j

Jackson, MS 39286-1995 Attorney General Wise, Carter, Child & Caraway Department of Justice i

P. O. Box 651 State of Louisiana i

Jackson, MS 39205 P. O. Box 94005 j

Baton Rouge, LA 70804-9005 Winston & Strawn 1400 L Street, N.W. - 12th Floor State Health Officer i

Washington, DC 20005-3502 State Board of Health P. O. Box 1700 l

Director Jackson, MS 39205 Division of Solid Waste Management i

Mississippi Department of Natural Office of the Governor i

Resources State of Mississippi P. O. Box 10385 Jackson, MS 39201 Jackson, MS 39209 Attorney General l

President, Asst. Attorney General j

Claiborne County Board of Supervisors State of Mississippi Port Gibson, MS 39150 P. O. Box 22947 Jackson, MS 39225 i

{

Regional Administrator, Region IV j

U.S. Nuclear Regulatory Commission Vice President, Operations Support i

611 Ryan Plaza Drive, Suite 1000 Entergy Operations, Inc.

i Arlington, TX 76011 P.O. Box 31995 i

Jackson, MS 39286-1995 Senior Resident Inspector l

U. S. Nuclear Regulatory Commission Director, Nuclear Safety Route 2, Box 399 and Regulatory Affairs Port Gibson, MS 39150 Entergy Operations, Inc.

i P.O. Box 756 l

Manager of Operations Port Gibson, MS 39150

}

Bechtel Power Corporation P.O. Box 2166 Houston, TX 77252-2166 i

i

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1

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4

]

4 REQUEST FOR ADDITIONAL INFORMATION PROPOSED EXEMPTION TO CRITICALITY MONITORING REQUIREMENTS IN 70.24(a)

ENTERGY OPERATIONS. INC.. ET. AL.

i GRAND GULF NUCLEAR STATION. UNIT 1 1

DOCKET NO. 50-416 i

l The following questions are based on the licensee's proposed exemption to 10 CFR 70.24(a) in its submittal of July 15, 1996.

j 1.

Provide a list of the areas at Grand Gulf, Unit I which contain criticality monitors that conform to 10 CFR 70.24(a), the activit.es conducted in these areas with special nuclear material (SNM), and the amount of SNM that could be in these areas. Describe the controls, if any, which limit the SNM in these areas.

2.

Describe the procedural controls and/or physical constraints which exist to preclude inadvertent removal of unirradiated fuel from Nuclear Regulatory Commission (NRC)-approved packaging in areas where criticality i

monitors are not provided.

i i

3.

Discuss the maximum U-235 fuel enrichment (or k-infinity) of fuel analyzed for storage in the fresh fuel racks at Grand Gulf, Unit 1, and the effects of accidental flooding or low-density optimum moderation conditions on potential criticality in storage. Discuss the maximum j

enrichment which is accounted for in the NRC-approved packaging.

4.

Discuss the administrative controls mentioned in Section 9.1.1.3.1 of the i

Updated Final Safety Analysis Report that are used to prohibit the introduction of sources of optimum moderation to the stored fresh fuel.

5.

Discuss how this exemption would remain valid if a future fuel enrichment increase was contemplated for Grand Gulf Unit 1.

The Technical Specifications for Unit I do not limit the enrichment of the fuel at the l

site, i

6.

Discuss that radiation monitoring remains available to meet the requirements of GDC 63 for fuel storage areas.

l 4

i ENCLOSURE