ML20059B192

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Forwards SE Re Reanalysis of Fuel Handling Accident Inside Containment.Use of Staff Values,Utilized During Operating License Stage,Would Result in Reduction in Dose by Factor of Two
ML20059B192
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 10/22/1993
From: Shiraki C
Office of Nuclear Reactor Regulation
To: Farrar D
COMMONWEALTH EDISON CO.
Shared Package
ML20059B195 List:
References
TAC-M87738, TAC-M87739, NUDOCS 9310280080
Download: ML20059B192 (3)


Text

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W ASHINGTON, D. C. 20555 October 22, 1993 Docket Nos. 50-295 and 50-304 Mr. D. L. Farrar Manager, Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515

Dear Mr. Farrar:

SUBJECT:

ZION NUCLEAR POWER STATION, UNITS 1 AND 2, REVISED FUEL HANDLING ACCIDENT INSIDE CONTAINMENT (TAC N05. M87738 AND M87739)

By letter dated September 13, 1993, Commonwealth Edison Company (Ceco, the licensee) submitted a reanalysis of the fuel handling accident inside containment (FHAIC).

The reanalysis included a corrected filter efficiency factor for organic iodine and a reduction of the assumed preshutdown power from 104.5% to 100% of rated power (3250 MWt) to offset the increased off-site dose. The reanalysis corrected the filter efficiency factor used in the analysis previously provided by Ceco in its July 10, 1991, submittal in support of Zion's transition to VANTAGE 5 fuel.

Ceco stated in its September 13, 1993, letter that the filter efficiency utilized for organic iodine in the July 10, 1991, submittal was inconsistent with the guidance in Regulatory Guide (RG) 1.25.

In its July 10, 1991 submittal, Ceco assumed a value of 90% for the removal efficiency of the charcoal adsorbers of organic iodine instead of the value of 70% recommended by RG 1.25.

In the Safety Evaluation related to Amendment Nos. 43 and 40 of the Zion Nuclear Power Station, Units 1 and 2, Technical Specifications, the staff stated that the results of a FHAIC were considered " appropriately within the guidelines of 10 CFR Part 100." At that time, the staff stated that

" appropriately within the guidelines of 10 CFR Part 100 has been defined as less than 100 rem thyroid." The staff's current estimate indicates that the operator thyroid doses would be on the order of 110 rem, however, the staff considers this to be a conservative value, based on the use of the licensee's 27000::

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Mr. D. L. Farrar October 22, 1993

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meteorology values instead of the staff's. Use of the staff's values, which were utilized during the operating license stage, would result in a reduction in the dose by a factor of two.

The results of the staff's review are included in the attached SE.

Sincerely, Original signed by:

Clyde Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects III/IV/V i

Office of Nuclear Reactor Regulation

Enclosure:

Safety Evaluation i

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Mr. D. L. Farrar Zion Nuclear Power Station Commonwealth Edison Company Unit Nos. I and 2 CC*

Michael I. Miller, Esquire-Sidley and Austin One First National Plaza Chicago, Illinois 60603 Dr. Cecil Lue-Hing Director of Research and Development Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611 Phillip Steptoe, Esquire Sidley and Austin One First National Plaza l

Chicago, Illinois 60603 Mayor of Zion Zion, Illinois 60099 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 U.S. Nuclear Regulatory Commission Resident Inspectors Office 105 Shiloh Blvd.

Zion, Illinois 60099 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 i

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