ML20087J748

Application to Amend License DPR-72,consisting of Suppl 1 to Tech Spec Change Request 112,to Provide Greater Assurance That Operation W/Flooded Aspirating Ports Strictly Prohibited.Certificate of Svc Encl

ML20087J748
Person / Time
Site:	Crystal River
Issue date:	03/20/1984
From:	Westafer G FLORIDA POWER CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20087J749	List: ML20087J748 ML20087J753
References
3F0384-12, 3F384-12, NUDOCS 8403230062
Download: ML20087J748 (4)

Text

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m w..e. _r March 20,1984 3F0384-12 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request No.112, Supplement i Steam Generator Operating Level

Dear Mr. Denton:

Enclosed are three (3) originals and forty (40) copies of Request No. 112, Supple ment 1, requesting amendment to Appendix A of Operating License No. DPR-

72. As part of this request, the proposed pages are enclosed.

This supplement is provided at the request of your staff (NRC) to provide greater assurance that operation with " flooded" aspirating ports is strictly prohibited. Our original submittal took credit for the fact that such operation would thermal-hydraulically cause an immediate reduction in superheat which would, in turn, reduce the acceptable operating level via the restrictions proposed in the change.

Furthermore, Florida Power Corporation planned to impose rdministrative limits similar to those proposed herein. Nevertheless we concur that this " clarification" will still allow sufficient flexibility and will obviate the need for a detailed mechanical analysis evaluating the potential of flooding the tube annulus region with cooler feedwater.

Also, at your staff's request, Florida Power Corporation reviewed - ith responsible Babcock and Wilcox staff the potential for this request aave sely affecting mechanical stress levels in the Steam Generator. This subject, in general, is discussed in Section 4.3.4 of the Crystal River Unit 3 Fina! Safety Analysis Report (FSAR). The following points were considered.

a) The Steam Generator inventory, and hence aval!able coolant, is maintained it or below FSAR assumptions. Therefore, the Steam Generator cooldown resulting from a Main Steam Line Break is unaffected.

8403230062 e40320 POR ADOCK 05000302 PDR ly%\

GEM ' W1 Thirty-fourth Street South e P.O. Box 14042, St. Peter:borg, Florda 33733 e 813-066-5151

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j March 20,1984 3F0384-12 Page 2 b) The Steam Generator downcomer is at or near saturation enditions immediately below the aspirating port regardless of downcomer (i.e.

Operating Range) level. Therefore approval of this change is not likely to induce any substantially different thermal gradients on the Generator shell.

Based on the above, FPC does not consider this change to involve any significant effect on the present stress level in the Steam Generators.

, We further request that this change, as supplemented, be pursued on an exigent or emergency basis since we are now experiencing minor power reductions due to the 4

current Steam Generator level restrictions. We have established an approximately 2 degrees F delta T across the reactor coolant system to balance Steam Generator levels and are now limited to approximately 98% Full Power.

Sincerely,

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G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management PGH/ddl Enclosures cc: Mr. J.P. O'Reilly Regional Administrator, Region 11 Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 i Atlanta,GA 30303 I

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STATE OF FLORIDA COUNTY OF PINtiLLAS i

G.R. Westafer states that he is the Manager, Nuclear Operations Licensing and Fuel Management for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

G.R. Westafer /

Manager, Nuclear Operations Licensing and Fuel Management Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 20th day of March,1984.

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Notary Public Notary Pubile, State of Florida at Large, My Commission Expires: November 19, 1986

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t UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF )

) DOCKET No. 50-302 FLORIDA POWER CORPORATION )

CERTIFICATE OF SERVICE G.R. Westafer deposes and says that the following has been served on the Designated State Representative and the Chief Executive of Citrus County, Florida, by deposit in the United States mail, addressed as follows:

Chairman, Administrator Board of County Commissioners Radiological Health Services of Citrus County Department of Health and Citrus County Courthouse Rehabilitative Services inverness, FL 32650 1323 Winewood Blvd.

Tallahassee, FL 32301 Three (3) copies of Technical Specification Change Request No.112, Supplement 1, requesting amendment to Appendix A of Operating Licensing No. DPR-72.

FLORIDA POWER CORPORATION "G.R. W6stafer /

Manager Nuclear Operations Licensing and Fuel Management SWORN TO AND SUBSCRIBED BEFORE ME THIS 20th day of March,1984.

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Notary Public Notary Public, State of Flo da at Large My Commission Expires: November 19,1986 (NOTARIAL SEAL) l o.

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