3F0284-01, Supplemental Application to Amend License DPR-72,consisting of Tech Spec Change Request 96 Re Intake Canal Dimensions. Requests Amend Be Issued Prior to June 1985 Canal Survey

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Supplemental Application to Amend License DPR-72,consisting of Tech Spec Change Request 96 Re Intake Canal Dimensions. Requests Amend Be Issued Prior to June 1985 Canal Survey
ML20080C553
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/03/1984
From: Westafer G
FLORIDA POWER CORP.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML20080C555 List:
References
3F0284-01, 3F284-1, NUDOCS 8402080134
Download: ML20080C553 (2)


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, o . . e, n ~wr February 3,1984 3F0284-01 Mr. John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20535

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request No. 96 Intake Canal Dimensions

Dear Sir:

On May 26,1982, Florida Power Corporation submitted Technical Specification Change Request No. 96 to the Commission for approval. This change request more clearly defined the acceptable requirements to assure minimuin emergency cooling water flow availability from the intake canal.

On January 31, 1983, the Commission informed Florida Power Corporation of an apparent error in Section 2.4.2.3 of the FSAR dealing with blowout during a Probable Maxirr.um Hurricane. Section 2.4.2.3 indicates that hurricane blowout will cause a low water level of 79 feet (plant datum) in the Gulf. Assuming a blowout of one foot per mile, the water level in the canal appears to decrease to 71 feet. The comparison of this water level to the surveys provided on January 4, 1983, indicates most of the canal would be dry. Therefore, the Commission requested Florida Power to:

" Provide a detailed analysis of the water surface profile along the approximate 8 mile length of the Intake Canal during the postulated Probable Maximum Hurricane setdown or blowout condition. This analysis should also include the effects of the water surface profile on the flow requirements to Units 1,2 and 3 during this event as well as the minimum cross-sectional flow area required at various positions along the canal."

8402080134 g40203 DR ADOCK 05000302 PDR iM GEN ER AL OFFICE 3201 Thirty fourth Street South e P.O. Box 14042, St. Petersburg, Florida 33733 e 813-866-5151

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February 3,1984 3F0284-01 Page 2 This letter transmits the requested detailed analysis. At Probable Maximum Hurricane setdown or blowout conditions, Unita 1, 2 and 3 will be shutdown. At that time,' only the Nuclear Services water supply pump (s) will be operating, therefore, this pump (s) should be the only one(s) affecting the water surface profile. -A graph of the water surface profile along the intake canal during these conditions is shown on page 28 of 39 in the attached report. This figure, in conjunction with the attached analysis, demonstrates that, under Probable Maximum Hurricane setdown or blowout conditions, the minimum water level at the Unit 3 intake structure will be at an elevation of 79 feet. The Nuclear Services water supply pump (s)is designed to deliver the maximum required cooling flow of 34,900 gpm with a canal water level of 73.7 feet at the intake end. The extremely large intake canal flow area precludes the possibility of any vessel or natural phenomena water flow (24,000 obstructing)the canal to the extent that the minimum required cooling gpm cannot pass.

Based upon Units 1, 2 and 3 being shutdown and conservative assumptions, it is concluded that during the Probable Maximum Hurricane setdown or blowout conditions, the Nuclear Service water supply pump (s) will be able to satisfactorily operate to maintain the reactor in a safe condition.

The next scheduled canal survey is June 1985. It is requested that the License Amendment be scheduled to be issued in advance of that date.

Sincerely, G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management PGH/feb Attachment cc: Mr. 3. P. O'Reilly Regional Administrator, Region 11 Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, GA 30303

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