ML18011A494
| ML18011A494 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/12/1994 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18011A496 | List: |
| References | |
| NPF-63-A-048 NUDOCS 9407150135 | |
| Download: ML18011A494 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISStON WASHINGTON, D.C. 205554001 CAROLINA POWER 8
LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
48 License No. NPF-63 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power 5 Light Company, (the licensee),
dated March 25,
- 1994, 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 facility will operate 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; 2.
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.
Accordingly, 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:
9407150135 940712 PDR ADQCK 05000400 P
0 r
(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.
48
, are hereby incorporated into this license.
Carolina Power
& 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 12, 1994 David B. Matthews, Director Project Directorate II-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation.
ATTACHMENT TO LICENSE AMENDMENT NO.
48 FACILITY OPERATING LICENSE NO.
NPF-63 DOCKET NO. 50-400 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Pa es 3/4 8-39 Insert Pa es 3/4 8-39
p v
O.
ELECTRICAL POWER SYSTEMS ELECTRICAL E UIPMENT PROTECTIVE DEVICES MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION 3.8.4.2 The thermal overload protection of each valve, specified in the Technical Specification Equipment List Program, plant procedure PLP-106, requiring bypass protection, shall be bypassed only under accident conditions by an OPERABLE bypass device.
I APPLICABILITY: Whenever the motor-operated valve is required to be OPERABLE.
ACTION:
With the thermal overload protection for one or more of the above required valves not capable of being bypassed under conditi'ons for which it is designed'o be bypassed, restore the inoperable device or provide a means to bypass the.
thermal overload within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or declare the affected valve(s).inoperable and apply the appropriate ACTION Statement(s) of. the affected system(s).
SURVEILLANCE REQUIREMENTS 4.8.4.2 The thermal overload protection for the above-r'equired-valves shall be verified to be bypassed only under accident conditions by an OPERABLE integral bypass device by the performance of a TRIP ACTUATION DEVICE OPERATIONAL TEST of the bypass circuitry:
a.
At least once per 18 months for those thermal overloads which are normally in force during plant operation and are bypassed only under accident conditions; and b.
Following maintenance on the thermal overload bypass relays and circuitry.
SHEARON HARRIS - UNIT 1 3/4 8-39 Amendment No.
~S.48
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