ML20036C217
| ML20036C217 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/07/1993 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20036C218 | List: |
| References | |
| NPF-68-A-065, NPF-81-A-044 NUDOCS 9306150300 | |
| Download: ML20036C217 (7) | |
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d - [,s noI%,, 'l UNITED STATES ~ NUCLEAR REGULATORY COMMISSION o y WASHINGTON, D. C. 20555 y\\ /- } GEORGIA POWER COMPANY-OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA l CITY OF DALTON. GEORGIA j V0GTLE ELECTRIC GENERATING PLANT. UNIT l' 1 AMENDMENT TO FACILITY OPERATING LICENSE i Amendment No. 65 License No. NPF-CC i 1. The Nuclear Regulatory Commission (the Commission) has found that: j l A. The application for amendment to the Vogtle Electric Generating.. Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 l filed by the Georgia Power Company, acting for itself, 0glethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of. Dalton, Georgia (the licensees), dated -January 22,-1993, complies with the standards and requirements of the Atomic Energy-Act of 1954, as amended (the Act), and the Commission's rules and j 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;~ l 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 j E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements j have been satisfied. -{ q i i 9306150300 930607-l DR ADOCK 0500 4
Y l 1 ; t 2. Accordingly, the license is hereby amended by page changes to the I t 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 Specifications and Environmental Protection Plan I The Technical Specifications contained in Appendix A, as revised through Amendment No. 65, 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 of issuance. FOR THE NUCLEAR REGULATORY COMMISSION l 'l / David B. Matthews, Director-Project Directorate II-3 i Division of Reactor Projects - I/II 1 Office.of Nuclear Reactor Regulation
Attachment:
I Technical Specification Changes Date of Issuance: June 7, 1993 s
--_~an / 'o UNITE 3 STATES ~,, [ NUCLEAR REGULATORY COMMISSION 7, g g-p WASHINGTON, D. C. 20S55 \\...../ GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 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 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 January 22, 1993, 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 (1) 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.
w i 3-q.; i 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 Specifications and Environmental Protection ' Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 44, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby. incorporated e 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 of issuance. i FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: June 7, 1993 k J t
mi ATTACHMENT TO LICENSE AMENDMENT N0.65 FACILITY OPERATING LICENSE NO. NPF-68 i D'0CKET N0. 50-424 AND TO LICENSE AMENDMENT N0. 44 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 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 Paaes 2-5 2-5 3/4 3-31 3/4 3-31 t
TAGLE 2.2-1 (Continued) g REACTOR TRIP SYSTEM INSTRtBENTATION TRIP SETPOINTS [ 70TAL Sell 500 ALLOWANCE ERROR F181CTIONAL 80117 (TA) 2 (5) TRIP SETPOINT ALLOWAOLEVALW d 9. Pressurizer Pressure-Lew 3.1 0.71 1.67 11960 psig** ->l950 psig (PI-M55A,04C, PI-M56 & PI-M56A,PI-94504)PI-M57 & PI-0457A, w PI-M 50 & e-
- 10. Pressurfrer Pressere-Ntgh 3.1 0.71 1.67
-<2385 psig <2395 psig (PI-M55A,0BC, PI-M56 & PI-M56A PI-M57 & PI-M57A, PI-9450$PI-M50A)
- 11. Pressurizer tester Level-Migh 8.0 2.18 1.67
<93 of instrument <93.M of lastrisment (LI-04594,LI-04604,LI-0461) span span 12. Seacter Caelant F1ent Lew 2.5 1.87 0.60 >905 of loop >09.4% of loo (LOOP 1 LOOP 2 LOOP 3 LOOP 4 Besign flow" 3esign flow
- p FI-M14 FI-M24 FI-0434 FI-0444 FI-M15.FI-M25 FI-0435 FI-0445, m
J. FI-0416 FI-0426 FI-0436 FI-0446)
- 13. Steam Generater Water Level Low-21.8 17.6 1.67
>37.8% >35.9% Law of narrow range of narrow range (LOOP 1 LOOP 2 LOOP 3 L00P4 ' instrument span instrument span i LI-9517 LI-9527 LI-9537 LI-9547 LI-9510 LI-9520 LI-0530 LI-9540 f LI-9519 LI-9529 LI-9539 LI-9549 LI-9551 LI-9552 LI-9553 LI-0554) =
- 14. tidervoltage - Seacter Coolant 6.0 0.50 0
>9600 volts > Met volts Pigs-(70Ebusweltage) {6 M bus voltage) E.I
- 15. tiderfteguancy - Seacter Coolant 3.3 0.50 0
157.3 Nr 157.1ftr 2$ Puers = teep assign flew = 93.600 p m -ET
- Time constants stilfred in the leet-lag centre 11er for Presseriter Pressure-Leer are 10 seconds for lead and 33 1 second for lag. Cf1AINIEL CALIBRATION shall ensure that these time constants are adjusted to these values.
M
6 TABLE-3.3-3 (Continued) o-ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRIMENTATION TRIP SETPOINTS c. TOTAL SENSOR ALLOWANCE ERROR d FUNCTIONAL UNIT (TA) Z (5) TRIP SETPOINT ALLOWA8LE VALUE-5. Turbine Trip and Feedwater Isolation E' (Continued) c. Steam Generator Water 14.0 10.47 1.67 < 86.0% <87.9% l Level--High-High (P-14) of instrument of narrow range span. Instrument span. to (LOOP 1 LOOP 2 LOOP 3 LOOP 4 LI-0517 LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549 g LI-0551 LI-0552 LI-0553 LI-0554) d. Safety Injection See Functional Unit 1. above for all Safety Injection Trip wa Satpoints and Allowable Values. 6. Aux 111ery Feedwater a. . Automatic Actuation Logic M.A. N.A. M.A. N.A. N.A. and Actuation Relays b. Steam Generator Water Level-- Low-Low . k k.' = (LOOP 1 LOOP 2 LOOP 3 LOOP 4 -LI-0517-LI-0527 LI-0537 LI-0547
- * <+
LI-0518 LI-0528 LI-0538- 'LI-0548. gg LI-9519-LI-0529 LI-0539 LI-0549 g, LI-0551 LI-0552 LI-0553 LI-0554) 7 1. Start Motor-Driven Pumps 21.8 17.6 1.67 237.8% 135.9% 'l gg of narrow of narrow range. s,, s., range instru-Instrument span. <+ <+ ment span. Og 2. Start Turbine-Driven Pump 21.8 17.6 -1.67 .137.8%- 135.9% [ of narrow af narrow' range range fnstru. Instrument ment span.- span. . -. -.. -. -.. -}}