ML20033A946
| ML20033A946 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/17/1981 |
| From: | Cross W FLORIDA POWER CORP. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20033A947 | List: |
| References | |
| NUDOCS 8111300198 | |
| Download: ML20033A946 (5) | |
Text
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November 17, 1981 File: 3-0-3-e D}'ih'/@f
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Office of Nuclear Reactor Regulation J
9 U.S. Nuclear Regulatory Commission gd Aip Washington, D.C. 20555
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Subject:
Crystal River Unit 3 Docket No. 50-302 e
Operating License No. DPR-72 Technical Specification Change Request No. 83 Increase in Reactor Coolant System Controlled Leakage Rate
Dear Sir:
Enclosed are three (3) originals and forty (40) copies of Technical Specification Change Request No. 83, requesting an amendment to Appendix A of Operating License No.
DPR-72. As part of this request, proposed replacement pages for Appendix A are enclosed.
This change would increase the Controlled Leakage rate, as shown in Technical Specification 3.4.6.2.e, from 10 GPM to 12 GPM.
Florida Power Corporation considers Change Request No. 83 to be a Class til amendment per 10CFR170.22 as it involves a single safety issue.
The license fee in the amount of four thousand dollars ($4,000) and a signed copy of the Certificate of Service for Technical Specification Change Request No. 83 to the Chief Executive of Citrus County, Florida, are enclosed.
Very truly yours, D
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William A. Cross Manager g
Nuclear Licensing WAC:mm Enclosures eii1300198 B11117.
General Office 32o1 Tnaty-fourm street souin. P O Box 14o42. st Petersburg. Florca 33733 813-866-5151
STATE OF FLORIDA COUNTY OF PINELLAS W. A. CROSS states that he is the Manager, Nuclear Licensing, Nuclear Support Services, of 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.
Wr i d G W. A. Cross Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 17th day of November 1981.
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Notary [J)ublic Notary Public, State of Florida at Large, My Commission Expires: May 29,1984 i
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF
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DOCKET NO. 50-302 FLORIDA POWER CORPORATION
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CERTIFICATE OF SERVICE W. A. Cross deposes and says that the following has been served on the Chief Executive of Citrus County, Florida, by deposit in the United States mail, addressed as follows:
- Chairman, i
Board of County Commissioners of Citrus County Citrus County Courthouse Inverness, FL 32650 One (1) original copy of Technical Specification Change Request No. 83 requesting i
amendment to Appendix A of Operating License No. DPR-72.
FLORIDA POWER CORPORATIC'4 t &
$$W W. A. Croes
- Manager, Nuclear Licensing SWORN TO AND SUBSCRIBED BEFORE ME THIS THIS 17TH DAY OF NOVDBER, 1981.
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W Notary)Public Notary Public State of Florida at Large My Commission Expires: May 29,1984 (NOTARIAL SEAL)
9 9
9 TSCRN 83 INCREASE IN REACTOP. COOLANT SYSTEM CONTROLLED LEAKAGE RATE
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TECHNICAL SPECIFICATION CHANGE REQUEST NO. 83 Replace page 3/4 4-15 of Appendix A with revised page 3/4 4-15.
i Proposed Change This change would increase the CONTROLLED LEAKAGE rate, as shown in Technical Specification 3.4.6.2.e, from 10 GPM to 12 GPM.
Reason for Proposed Change Certain changes have been made to the flow staging coils of the reactor co61 ant pump shaft seals in the interest of improved reliability.
One result of these i
changes is an increase in the leakage flow from the pump seals through the con-i trolled bleed off line to the injection water supply system. The-leakage increases from 1 GPM to 1.5 GPM for each of 4 reactor coolant pumps for a total increase of 2 GPM.
Safety Analysis of Proposed Change As previously stated, the changes to the reactor coolant pump shaft seals were made in the interest of improved reliability. Also, since the leakage is a controlled bleed off to the injection water supply system, the safety of the plant will not be adversely affected. This change does not involve any unreviewed safety itams.
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