ML18016A883
| ML18016A883 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/01/1999 |
| From: | Peterson S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18016A884 | List: |
| References | |
| NPF-63-A-087 NUDOCS 9904070198 | |
| Download: ML18016A883 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINAPOWER 8 LIGHTCOMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No.
87 License No. NPF-63 The Nuclear Regulatory Commission (the Commission) has found that:
A.. The application for amendment by Carolina Power & Light Company, (the licensee), dated December 16, 1997, as supplemented by letters dated August 31, and December 7, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities'authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Accordi'ngly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-63 is hereby amended to read as follows:
9904070i98 99040i PDR ADQCK 05000400 PDR
(2)
Technical S ecifications and'Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No.. 87, are hereby incorporated into this license.
Carolina Power 8 Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Attachm'ent:
Changes to the Technical Specifications Date of Issuance:
April 1, 1999
ATTACHMENTTO LICENSE AMENDMENTNO.
87 FACILITYOPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised area is indicated by a marginal line.
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PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM SURVEILLANCE RE(UIREMENTS (Continued) 2.
Demonstrating that the steam turbine
- driven pump satisfies performance requirements by either:
NOTE:
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
3.
a)
Veri'fying the pump develops a differential pressure that (when temperature
- compensated to 70'F) is greater than or equal to 1167 psid at a recirculation flow of greater than or equal to 81 gpm (40.5 KPPH) when the secondary steam supply pressure is greater than 210 psig, or b)
Verifying the pump develops a differential pressure that (when temperature
- compensated to 70'F) is greater than or equal to 1400 psid at a flow rate of greater than or equal to 430 gpm (215 KPPH) when the secondary steam supply pressure is greater than 280 psig.
Verifying by flow or position check that each valve (manual, power operated, or automatic) in the flow path that is not
- locked, sealed, or otherwise secured in position is in its correct position; and b.
4.
Verifying that the isolation valves in the suction line from the CST are locked open.
At least once per 18 months by:
Verifying that each motor-driven auxiliary feedwater pump starts automatically, as designed, upon receipt of a test signal and that the respective pressure control 'valve for each motor-driven pump and each flow control valve with an auto-open feature respond as required; Verifying that the turbine-driven auxiliary feedwater pump starts automatically, as designed, upon receipt of a test signal.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3; and 3.
Verifying that the motor-operated auxiliary feedwater isolation valves and flow control valves close as required
, upon receipt of an appropriate test signal for steamline differential pressure high coincident with main steam isolation.
SHEARON HARRIS - UNIT 1
3/4 7-5 Amendment No.
87
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