ML20149G173
| ML20149G173 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/22/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20149G176 | List: |
| References | |
| NPF-68-A-076, NPF-81-A-055 NUDOCS 9410030168 | |
| Download: ML20149G173 (7) | |
Text
.
,no 4 UNITED STATES y
3 j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2066H201
\\...../
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT I t
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
76 License No. NPF-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated June 24, 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 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 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 set forth in 10 CFR Chapter I; 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.
9410030168 940922 PDR ADOCK 05000424 P
PDR 3
h
. 2.
Accordingly, the license is hereby amended by page 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-68 is hereby amended to read as follows:
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 76, and the Environmental Protection Plan contained in i
Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC 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 be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMNISSION 1
l
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/-
' H rbert N. Berkow, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: September 22, 1994 I
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p,0 Cf C UNITED STATES E
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20555-0001
,o GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC CENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating License No. NPF-81 i
filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated June 24, 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 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 Commission; 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 Commission's regulations set forth in 10 CFR Chapter I; 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 Comission's regulations and all applicable requirements have been satisfied.
l l
. 2.
Accordingly, the license is hereby amended by page 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-81 is hereby amended to read as follows:
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 55, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC 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 be implemented within 30 days from the date of issuance.
FOR TH NUCLEAR REGULATORY COMISSION er ert N. Berkow, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: September 22,-1994
ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AlfQ TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 s
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.
i Remove Paaes Insert Paaes 2.5 2.5 2.6 2.6 O
I L
' if
g, TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS c:
TOTAL SENSOR 5
ALLOWANCE ERROR C
FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE N
9.
Pressurizer Pressure-Low 3.1 0.71' 1.67 21960 psig**
21950 psig (PI-0455A,B&C, PI-0456 &
(1.04)
(1.17) m PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-0458A) 10.
Pressurizer Pressure-High 3.1 0.71' l.67*
$2385 psig s2395 psig t
(PI-0455A,8&C, PI-0456 &
(1.04)
(1.17)
PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-0458A) 11.
Pressurizer Water Level-High 8.0 2.18 1.67 592% of instrument s93.9% of instrument (LI-0459A, LI-0460A, LI-0461) span span 12.
Reactor Coolant Flow-Low 2.5 1.87 0.60 290% of loop 289.4% of loop l
(LOOP 1 LOOP 2 LOOP 3 LOOP 4 design flow
- design flow
- N FI-0414 FI-0424 FI-0434 FI-0444 E
FI-0415 FI-0425 FI-0435 FI-0445 i
FI-0416 FI-0426 FI-0436 FI-0446)
- 13. Steam Generator Water Level low-21.8 17.6 1.67 237.8% of narrow 235.9% of narrow Low range instrument range instrument (LOOP 1 LOOP 2 LOOP 3 LOOP 4 span span LI-0517 LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 gg LI-0519 LI-0529 LI-0539 LI-0549 gg LI-0551 LI-0552 LI-0553 LI-0554) ao SS
- 14. Undervoltage - Reactor Coolant 6.0 0.58 0
19600 volts 29481 volts 55 Pumps (70% bus voltage)
(69% bus voltage) 55
$5
~
- Loop design flow - 93,600 gpm EE
- Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 10 seconds for lead and 11 1 second for lag. CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.
((
- The instrumentation used shall be bounded by either pair of values for Z and S.
TABLE 2.2-1 (Continued) j g
REACTOR TRIP SYSTEN INSTRUNENTATION TRIP SETPOINTS l
d TOTAL SENSOR ALLOWANCE ERROR FUNCTIONAL UNIT fTA)
Z fS)
TRIP SETPOINT ALLOWABLE VALUE
- 15. Underfrequency - Reactor Coolant 3.3 0.50 0
257.3 Hz 257.1 Hz d
Pumps
[
16.
Turbine Trip a.
Low Fluid Oil Pressure N.A.
N.A.
N.A.
2580 psig 2500 psig (PT-6161, PT-6162, PT-6163) b.
Turbine Stop Valve Closure N.A.
N.A.
N.A.
296.7% open 296.7% open 17.
Safety Injection Input from ESF N.A.
N.A.
N.A.
N.A.
N.A.
I 18.
Reactor Trip System Interlocks a.
Intemediate Range N.A.
N.A.
N.A.
21 x 10'" amp 26 x 10'" amp Neutron Flux, P-6 (NI-0035B,NI-0036B) b.
Low Power Reactor Trips Block, P-7
- 1) P-10 input N.A.
N.A.
N.A.
s10% of RTPf s12.3% of RTPf (NI-0041B&C,NI-0042B&C, NI-0043B&C,NI-0044B&C)
- 2) P-13 input N.A.
N.A.
N.A.
s10% RTPf Turbine s12.3% RTPi Turbine yy (PI-0505,PI-0506)
Impulse Pressure Impulse Pressure gg Equivalent Equivalent E%
gg c.
Power Range Neutron N.A.
N.A.
N.A.
s48% of RTP#
$50.3% of RTPi Flux, P-8 gg(NI-0041B&C, NI-0042B&C, MI-0043B&C,N1-0044B&C) inM
$5
- RTP - RATED THERNAL POWER A3 SO
- -