ML18012A310
| ML18012A310 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/24/1996 |
| From: | Imbro E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18012A311 | List: |
| References | |
| NPF-63-A-065 NUDOCS 9607300213 | |
| Download: ML18012A310 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205550001 CAROLINA POWER
& LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON ARRIS NUCLEAR POWER PLANT UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-63 2.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power
& Light Company, (the licensee),
dated March 20,
- 1996, 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and'afety 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:
96073002i3 960724 PDR ADOCK 05000400 P
<<I 3.
(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.
65, are hereby incorporated into this license.
Carolina Power 5 Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental 'Protection Plan.
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 24, 1996 Eugene V. Imbro, Director Project Directorate II-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
65 FACILITY OPERATING LICENSE NO.
NPF-63 OOCKET 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 V1 3/4 3-56 B 3/4 3-4 Insert Pa es V1 3/4 3-56 B 3/4 3-4
t
orso x
~
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION TABLE 3.3-6 TABLE 4.3-3 TABLE 3.3-7 TABLE 4.3-4 TABLE 3.3-8 TABLE 4.3-5 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS (Deleted)
Seismic Instrumentation SEISMIC MONITORING INSTRUMENTATION PAGE 3/4 3-51
. 3/4 3-54
. 3/4 3-56 I
. 3/4 3-57
. 3/4 3-58 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
. 3/4 3-59 Meteorological Instrumentation METEOROLOGICAL MONITORING INSTRUMENTATION 3/4 3-60 3/4 3-61 METEOROLOGICAL MONITORING INSTRUMENTATION SURVE ILLANCE REQUIREMENTS
. 3/4 3-62 TABLE 3.3-9 TABLE 4.3-6 TABLE 3.3-10 TABLE 4.3-7 TABLE 3.3-11 TABLE 3.3-13 TABLE 4.3-9 3/4.3.4 Remote Shutdown System REMOTE SHUTDOWN SYSTEM REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Accident Monitoring Instrumentation.. '.
ACCIDENT MONITORING INSTRUMENTATION.
ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (DELETED)
Metal Impact Honitoring System (DELETED)
Explosive Gas Monitoring Instrumentation EXPLOSIVE GAS MONITORING INSTRUMENTATION.
EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED 3/4 3-63 3/4 3-64 3/4 3-65 3/4 3-66 3/4 3-68 3/4 3-70 3/4 3-73 3/4 3-74 3/4 3-75 3/4 3-82 3/4 3-83 3/4 3-86 3/4 3-89 i
SHEARON HARRIS - UNIT 1 vi Amendment No. 66
I
INSTRUNENTATION MOVABLE INCORE OETECTORS
- DELETED SHEARON HARRIS - UNIT 1 3/4 3-56 Amendment No. 65
INSTRUMENTATION~
BASES 3/4.3.3.2 MOVABLE INCORE DETECTORS - DELETED 3/4.3.3.3 SEISMIC INSTRUMENTAT N
The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features'important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix A of 10 CFR Part 100.
The instrumentation is consistent with the recommendations of Regulatory Guide 1. 12, "Instrumentation for Earthquakes."
April 19)4.
3/4.3.3.4 METEOROLOGICAL INSTRUM NTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data are available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23
'Onsite Meteorological Programs."
February 1972.
3/4.3.3.5 REMOTE SHUTDOWN SYSTEM The OPERABILITY of the Remote Shutdcae System ensures that sufficient capability is available to permit safe shutdown of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50.
The OPERABILITY of the Remote Shutdown System ensures that a fire will not preclude achieving safe shutdown.
The Remote Shutdown System instrumentation.
controls and power circuits and transfer switches necessary to eliminate effects of the fire and allow operation of instrumentation.
control and power circuits required to achieve and maintain a safe shutdown condition are independent of areas where a fire could damage systems normally used to shut down the reactor.
SHEARON HARRIS - UNIT 1 B 3/4 3-4 Amendment No.
65