ML18012A166
| ML18012A166 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/11/1996 |
| From: | Imbro E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18012A167 | List: |
| References | |
| NPF-63-A-063 NUDOCS 9603150119 | |
| Download: ML18012A166 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMlSSlON WASHINGTON, D.C. 2055&0001 CAROLINA POWER 8
LIGHT COMPANY et al.
OOCKET NO. 50- 00 S
EARO ARRIS NUCL AR PO R PLANT UNIT 1
ENON NT TO FAC TY OP RATING CENSE Amendment No.
63 License No. NPF-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power 5 Light Company, (the licensee),
dated February 16,
- 1996, complies with the stand'ards 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 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:
.P Oii9 9b03ii POR AD PDR ebosiSOOiCiqg 90b500300%400
3.
(2) c ecif cations and Environme tal. Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix 8, both of which are attached
- hereto, as revised through Amendment No. 63, 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.
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:
March 11, 1996 Eugene V. Imbro, Director Project Directorate II-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
C M
TTO C
S A
M TN0.63 AC ITY OPERATING LIC NS NO.
~TN Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Re ove es 3/4 3-41 3/4 3-42 e t Pa es 3/4 3-41 3/4 3-42*
- overleaf page - no changes
TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE CHECK CALIBRATION TEST TEST I-EEET TEST TEST TEST
~IS OE OEOEO CHANNEL FUNCTIONAL UNIT 1.
Safety Injection (Reactor Trip. Feedwater Isolation, Control Room Isolation.
Start Diesel Generators, Containment Ventilation Isolation, Phase A
Containment Isolation, Start Auxiliary Feedwater System Motor-Driven Pumps'tart Containment Fan Coolers, Start Emergency Service Water
- Pumps, Start Emergency Service Water Booster Pumps) a.
Manual Initiation N.A.
N.A.
N.A.
N.A.
N.A.
- R N.A.
N.A.
M(1)
NA NA 1
2 3
4 M(1)
Q(3) 1, 2. 3.
4
- b. Automatic Actuation N.A.
Logic and Actuation Relays
- c. Containment S
Pressure--High-1
- d. Pressurizer S
Pressure--Low N.A.
N.A.
1, 2, 3, 4
N.A.
N.A.
1, 2, 3
N.A.
N.A.
1, 2.
3 N.A.
N.A.
N.A.
e.
Steam Line Pressure--Low Note:
- R = The B SSPS input from the Main Control Board Panel C Manual Safety Injection Switch is to be tested before reactor startup from Refueling Outage No. 7. or when the plant is in Mode 5 for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
whichever occurs first.
TABLE 4.3-2 (Continued}
ENGINEEREO SAFETY FEATURES ACTUATION SYSTEH INSTRUHENTATION SURVEILLANCE RE UIREHENTS CHANNEL FUNCTIONAL UNIT
- 2. Containment Spray TRIP ANALOG ACTUATING CHANNEL DEVICE CHANNEL CHANNEL OPERATIONAL OPERAT IONAL ACTUATION CHECK CALIBRATION TEST TEST LOGIC TEST HODES HASTER SLAVE FOR WHICH RELAY RELAY SURVEILLANCE iM TEH Rtlt t a.
Hanual Initiation
- b. Automatic Actuation Logic and Actuation Relays
- c. Containment Pressure--
High-3
- 3. Containment Isolation a.
Phase "A" Isolation N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
R N. A.
N. A.
N. A.
H(1)
N.A.
N.A.
N.A.
H(1) q 1, 2, 3, 4
1, 2, 3, 4
N.A.
N.A.
1,2; 3
- 1) Hanual Initiation
- 2) Automatic Actuation Logic and Actuation Be)ays
- 3) Safety Injection b.
Phase "B" Isolation N. A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
H(1)
N.A.
N.A 1, 2, 3, 4
H(1) 0(3) 1, 2, 3
4 See Item l. above for all Safety Injection Surveillance Requirements.
- 1) Hanual Containment Spray Initiation
- 2) Automatic Actuation Logic Actuation Relays N. A.
N.A.
N.A.
N. A.
H(l)
H(1) q See Item 2.a.
above for Hanual Containment Spray Surveillance Requirements.
1, 2, 3, 4