ML20217E061

Forwards RAI Re Exemption from Requirements of 10CFR70.24, Criticality Accident Requirements. Exemption Re Criticality Monitoring of Areas in Which Special Nulcear Matl Handled,Used or Stored

ML20217E061
Person / Time
Site:	Fort Calhoun
Issue date:	09/26/1997
From:	Wharton L NRC (Affiliation Not Assigned)
To:	Gambhir S OMAHA PUBLIC POWER DISTRICT
References
TAC-M99544, NUDOCS 9710060282
Download: ML20217E061 (4)

Text

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September 26, 1997 Mr, S. K. Gambhir- ~ ~

Division Hanager -- Engineering & Operations Support-Omaha Public Power District Fort.Calhoun Station FC-2-4 Adm.

Post Office Box 399 >

Hwy. 75 - North of Fort'Calhoun Fort Calhoun, Nebraska 68023-0399

SUBJECT:

FORT CALHOUN STATION. UNIf NO. 1 - REQUEST FOR ADDITIONAL INFORMATION ON 10 CFR 70.24 EXEMPTION (TAC NO. M99544)

Dear Mr. Gambhir:

By letter dated August 29, 1997, the Omaha Public Power District requested an-exemption from the requirements of 10 CFR 70.24. " Criticality Accident Requirements." The exemption relates to criticality monitoring of areas in which special nuclear material is handled, used, or stored.

The staff has reviewed your submittal and determined that the additional information listed in the enclosure is necessary for the staff to complete its review.

Please respond to the enclosed questions within 30 days of receipt of this letter. .

Sincerely.

ORIGINAL SIGNED BY L. Raynard Wharton, Project Manager Project Directorate IV-2 Division of Reactor Projects - III/IV Office of Nuclear. Reactor Regulation Docket No. 50-285

Enclosure:

Request for Additional Information cc w/ encl: See next page DISTRIBUTION:

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%,***** September 26, 1997 Mr. S. K. Gambhir Division Manager - Engineering & Operations Support Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 399 Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399

SUBJECT:

FORT CALHOUN STATION, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION ON 10 CFR 70.24 EXEMPTION (TAC NO. M99544)

Dear Mr. Gambhir:

By letter dated August 29. 1997, the Omaha Public Power District requested an exemption from the requirements of 10 CFR 70.24. " Criticality Accident Requirements." The exemption relates to criticality monitoring of areas in which special nuclear material is handled, used, or stored.

The staff has reviewed your submittal and determined that the additional information listed in the enclosure is necessary for the staff to complete its review.

Please respond to the enclosed questions within 30 days of receipt of this letter.

Sincerely, b dh L. Raynard Wharton Project Manager Project Directorate IV-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

Request for Additional Information cc w/ encl: See next page

, Mr. S. K. Gambhir t cc w/ enc 1:-

Winston & Strawn- --

-ATTN: Perry D. Robinson. Esq.

1400 L Street. N.W.

Washington, DC 20005-3502 Mr. Jack Jensen. Chairman -

Washington County Board ofSupervisors Blair, debraska 68008 Mr. Wayne Walker, Resident Inspector U.S. Nuclear Regulatory Connission Post Office Box 309 Fort Calhoun. Nebraska 68023 Regional Administrator, Region IV-U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive. Suite 1000 Arlington, Texas 76011 '

Ms. Cheryl Rodgers. LLRW Program Manager Environmental Protection Section Nebraska Department of Health 301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska' 68509-5007 Mr.- James W. Chase. Manager Fort Calhoun Station Post Office Box 399 Fort Calhoun. Nebraska 68023 Mr. James W. Tills Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box'399 Hwy. 75 - North of Fort Calhoun Fort Calhoun. Nebraska 68023-0399

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O-REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT N0. 1 DOCKET NO. 50-285 Since Fort Calhoun Station fuel handling procedures allow two fuel assemblies to be in the inspection stands at the same time please address the following:

a.- Can flooding or other moderation due to fire fighting equipment (hoses or sprinklers) occur during fuel inspection?

b. If so, what procedures are in place to preclude accidental c.riticality (k-eff greater than 0.95)?

c. How is sufficient physical separation of assemblies during inspection guaranteed?

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