ML20059E109
| ML20059E109 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/14/1993 |
| From: | Milano P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059D943 | List: |
| References | |
| NUDOCS 9311030101 | |
| Download: ML20059E109 (3) | |
Text
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION CAROLINA POWER & LIGHT COMPANY DOCKET NOS. 50-325 AND 50-324 HOTICE OF ISSUANCE OF AMENDMENT TO I
FACILITY OPERATING LICENSE The U.S. Nuclear Regulatory Commission (Commission) has issued Amendment Nos. 166 and 197 to Facility Operating License Nos. DPR-71 and DPR-62, respectively, issued to Carolina Power & Light Company (the licensee) that revised the Technical Specifications for operation of the Brunswick Steam Electric Plant, Units 1 and 2, located in Brunswick County, North' Carolina.
Amendment No. 166 for Unit 1 is effective as of the date of issuance, and I
Amendment No.197 for Unit 2 will be effective upon completion of Refueling Outage No. 10.
The amendments revise the Technical Specifications to allow the replacement of existing Riley, GEMAC and Fenwal steam leak detection equipment with General Electric Company NUMAC leak detection equipment.
The proposed s
amendment also revises surveillance requirements for steam leak detection instrumentation associated with the reactor core isolation cooling system, the high pressarc coolant injection system, and the reactor water cleanup system.
The specific changes include:
(1)
Delete the channel check surveillance test for the reactor water cleanup system isolation high differential flow function.
(2)
Extend and standardize the channel functional test and channel calibration surveillance frequencies for the reactor water cleanup, high pressure coolant injection, and reactor core 9311030101 931014 PDR ADOCK 05000324 p
PDR-
4 isolation cooling system isolation ambient and differential i
temperature functions.
(3)
Increase the reactor water cleanup system isolation differential flow time delay trip setpoint and allowable value from "less than or equa1 to 45 seconds" to "less than or equal to 30 minutes."
(4)
Increase the reactor water cleanup system isolation differential flow trip setpoint and allowable value from "less than or equal to 53 gal / min" to "less than or equal to 73 gal / min."
(5)
Delete the instrument response time requirement for the high pressure coolant injection system isolation steam line tunnel temperature - high function.
(6)
Delete the instrument response time requirement for the reactor water cleanup system isolation area temperature - high and area ventilation differential temperature - high functions.
(7)
Delete the instrument response time requirement for the reactor water cleanup system isolation differential flow - high function.
(8)
Revise the description of the reactor water cleanup isolation differential flow delay trip function to reflect elimination of the time delay relays per the new system configuration.
(9)
Add a new reactor water cleanup system isolation area temperature function for piping outside of the reactor water cleanup room.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in i
10 CFR Chapter I, which are set forth in the license amendment.
t
Notice of Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER on November 24, 1992 (57 FR 55287).
No request for a hearing or petition for leave to intervene was filed following this notice.
The Commission has prepared an Environmental Assessment related to the action and has determined not to prepare an environmental impact statement.
Based upon the environmental assessment, the Commission has concluded that the issuance of this amendment will not have a significant effect on the quality of the human environment (58 FR 45535).
For further details with respect to the action see (1) the application for amendment dated September 14, 1992, as supplemented January 13, January 25, February 8, May 11, June 18, July 26, and September 21, 1993; (2)
Amendment No. 166 to License No. DPR-71 and Amendment No. 197 to License No.
DPR-62; (3) the Commission's related Safety Evaluation and Environmental Assessment. All of these items are available' for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street NW.,
Washington, DC 20555, and at the local public document room located at the University of North Carolina at Wilmington, William Madison Randall Library, 601 S. College Road, Wilmington, North Carolina 28403-3297.
Dated at Rockville, Maryland, this 14th day of October 1993.
FOR THE NUCLEAR REGULATORY COMMISSION
<{}d)he i
J Patrick D. Milano, Project Manager I
Project Directorate - II/I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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