ML20078C930
| ML20078C930 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/20/1995 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078C934 | List: |
| References | |
| NUDOCS 9501270168 | |
| Download: ML20078C930 (9) | |
Text
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E UNITED STATES i
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION i
SALUDA RIVER ELECTRIC COOPERATIVE. INC.
j DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIJ_l AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 127 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated August 25, 1994, as supplemented November 16, 1994., complies with the standards and requireraents of the Atomic Energy Act cf 1954, as amended (the Act), and the Comissien's rules and regulations as 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 Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
9501270168 950120 PDR ADOCK 05000413 P
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2.
Accordingly, the license is hereby m nded by page changes to the j
Technical Specifications as indicated in the attachment to this license lj amendment, and Paragraph 2.C.(2) of Facility Operating License No.
l NPF-35 is hereby amended to read as follows:
l Technical Specifications l
The Technical Specifications contained in Appendix A, as revised i
through Amendment No.127
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are j
hereby incorporated.into this license. Duke Power Company shall operate the facility in accordance with the Technical j
Specifications and the Environmental Protection Plan.
a 3.
This license amendment is effective as of its date of issuance and shall i
be implemented within 30 days from the date of issuance.
1 i
FOR THE NUCLEAR REGULATORY COMISSION l
j erbert N. Berkow, Director Project Directorate II-3 J
Division of Reactor Projects - I/II l
l Office of Nuclear Reactor Regulation i
i
Attachment:
j Technical Specification Changes J
j Date of Issuance: January 20, 1995
a pa"G UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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t DUKE POWER COMPANY
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NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 i
AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 121
]
License No. NPF-52 j
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, i
Unit 2 (the facility) Facility Operating License No. NPF-52 filed i
by the Duke Power Company, acting for itself, North Carolina 1
Municipal Power Agency No. I and Piedmont Municipal Power Agency i
(licensees), dated August 25, 1994, as supplemented November 16, 1
1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's j
rules and regulations as set forth in 10 CFR Chapter I; j
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 1
Comission; 1
l C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; i
D.
The issuance of this amendment will not be inimical to the comon j
defense and security or to the health and safety of the public; i
and i
l E.
The issuance of this amendment is in accordance with 10 CFR Part j
51 of the Comission's regulations and all applicable requirements have been satisfied.
i
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h j
- 4 2.
Accordingly, the license is hereby amended by page changes to the i
Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.
NPF-52 is hereby amended to read as follows:
Technical Specifications
]
The Technical Specifications contained in Appendix A, as revised through Amendment No. 121
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall j
be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COPNISSION
' Herbert N. Berkow, Director
.l Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation I
Attachment:
Technical Specification Changes J
Date of Issuance: January 20, 1995 l
i l
1 l
t
ATTACHMENT TO LICENSE AMENDMENT NO.
127 I
FACILITY OPERATING LICENSE NOS. NPF-35 DOCKET NO. 50-413 Alm TO LICENSE AMENDMENT NO. 121 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paoes 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 i
i
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TABLE 3.3-4 (Continued)
I n
?;
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS N
g FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE h
- 8. Auxiliary Feedwater (Continued) 5d c.
Steam Generator Water Level - Low-Low g
- 1) Unit 1 2 17% of span 2 15.3% of from 0% to span from 0% to c,
increasing linearly to linearly to 2 38.3% of span 2 40.0% of from 30% to 100%
span from 30%
- 2) Unit 2 2 36.8% of 2 35.1% of narrow narrow range range instrrment span span d.
Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
e.
Loss-of-Offsite Power 2 3500 V 2 3242 V l
f.
Trip of All Main Feedwater Pumps N.A.
N.A.
kk Auxiliary Feedwater Suction g.
Pressure-Low kk
- 1) CAPS 5220, 5221, 5222 2 10.5 psig 2 9.5 psig 55
- 2) CAPS 5230, 5231, 5232 2 6.2 psig 2 5.2 psig a.
Unit 1 2 6.2 psig 2 5.2 psig gg b.
Unit 2 2 6.0 psig 2 5.0 psig 9.
Containment Sump Recirculation Ej a.
Automatic Actuation Logic N.A.
N.A.
%.g.
and Actuation Relays
" ~. -
b.
Refueling Water Storage 2 177.15 inches 2 162.4 inches Tank Level-Low Coincident With Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
9 TABLE 3.3-4 (Continued) y ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Hi>
FUNCTIONAL UNII TRIP SETPOINT ALLOWABLE VALUE E
- 10. Loss of Power Z
m a.
4 kV Bus Undervoltage-Loss 2 3500 V 2 3242 V l
of Voltage Eo b.
4 kV Bus Undervoltage-2 3766 V 2 3738 V l
Grid Degraded Voltage ro
- 11. Control Room Area Ventilation Operation a.
Automatic Actuation Logic and Actuation Relays N.A.
N.A.
b.
Loss-of-Offsite Power 2 3500 V 2 3242 V g
y c.
Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
M
- 12. Containment Air Return and Hydrogen Skimmer Operation kk a.
Manual Initiation N.A.
N.A.
oa kk b.
Automatic Actuation Logic N.A.
N.A.
gg and Actuation Relays ff c.
Containment Pressure-s 3 psig s 3.2 psig High-High NZ EE oo l
30 i
TABLE 3.3-4 (Continued)
E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE i
- 13. Annulus Ventilation Operation a.
Manual Initiation N.A.
N.A.
b.
Automatic Actuation Logic N.A.
N.A.
and Actuation Relays m
c.
Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
- 14. Nuclear Service Water Operation a.
Manual Initiation N.A.
N.A.
R b.
Automatic Actuation Logic N.A.
N.A.
and Actuation Relays Y
O c.
Loss-of-Offsite Power 2 3500 V 2 3242 V l
d.
Containment Spray See Item 2. above for all Containment Spray Setpoints and Allowable Values.
kk e.
Phase "B" Isolation See Item 3.b. above for all Phase "B" Isolation Setpoints and Allowable
=3 Values.
k5a f.
Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
.E.E g.
Suction Transfer-Low Pit Level 2El. 554.4 ft.
2El. 552.9 ft.
W
- 15. Emergency Diesel Generator Operation (Diesel Building Ep Ventilation Operation, Nuclear
- 3..
Service Water Operation) ee SO a.
Manual Initiation N.A.
N.A.
4
r TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE I
+
c
Operation (Diesel Building d
Ventilation Operation, Nuclear Service Water Operation) (Continued)
E
+
o b.
Automatic Actuation Logic N.A.
N.A.
and Actuation Relays ro c.
Loss-of-Offsite Power 2 3500 V 2 3242 V l
d.
Safety Injection See Item. I above for all Safety Injection Setpoints and Allowable Values.
- 16. Auxiliary Building Filtered Exhaust Operation a.
Manual Initiation N.A.
N.A.
k b.
Automatic Actuation Logic N.A.
N.A.
and Actuation Relays i
c.
Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.
i
- 17. Diesel Building Ventilation l
Operation a.
Manual Initiation N.A.
N.A.
l b.
Automatic Actuation Logic N.A.
N.A.
S$
and Actuation Relays yy c.
Emergency Diesel Generator See Item 15. above for all Emergency Diesel Generator Operation
- p. g.
Operation Setpoints and Allowable Values.
1 SO i
3 3
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