ML20059D570
| ML20059D570 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/30/1990 |
| 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 | |
| ML20059D573 | List: |
| References | |
| NPF-68-A-034, NPF-81-A-014 NUDOCS 9009070105 | |
| Download: ML20059D570 (9) | |
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UNITED STATES ~
q NUCLEAR REGULATORY COMMISSION'
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. GEORGIA POWER COMPANY L
OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA-CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1-AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 34-License No. NPF-68 t
1.
The Nuclear Regulatory Consission.(the Commission) has found that:
A..
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the f acility), Facility Operating License No. NPF-68. filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority.of Georgia, and City of Dalton.
l Georgia (the licensees). dated May 29,.1990, complies with.the standards and requirements of the Att, mis Energy Act of'1954, as-amended (the Act), and the:Consission's rules and regulations set.
forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and-regulations of the l
Commission; C.
There is reasonable assurance (1) thatLthe activities authorized by this amenanent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted -
n in conoliance with the Consission's regulations set forth in 10 CFR Chapter I;.
9.
The issuance of this license amendment will not be inimical-to the common defense and security or-to tne 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 satisfica.
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O i 2.
Accoroingly, 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 Fecility Operating License No. NPF-68 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. 34, and the Environmental Protection Plan contained in Appendix B,. both of which tre attached hereto, are hereby incorporated into this license. SPC s..all operate the
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facility in accorotnce with the Technicai Specifications and the Environmental Protection Plan.
3.
This license amendnent is effective as of its date of issuance.
FOR THE NUCLEAR EfGULATORY COMMISSION c/f ad s<
David B. Iatthews, Director Project Directorate.II-3 Division of P.eactor Projects -:l/11 Office of Nucitar Reactor Regulation Attachnent:
Technical Specification thanges Date of 1ssuance:
August 30, 1990 l
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.. UNITED STATES o
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NUCLEAR REGULATORY COMMISSION s
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- WASHINGTON. D. C. 20555
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GEORGIA' POWER: COMPANY!
OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CI1Y'0F DALTON GEORGIA V0GTLE ELECTRIC GENERATING PLANT, UNIT 2-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.-
14-License No. NPF s 1.
The Nuclear. Regulatory Comnission (the Commission) has found that:.
A.
The app (lication for amendment to the Vogtle Electric Generating Plant, Unit 2 the' f acility), Facility Operating License Nos NPF-81 filed by ~
the Georgia Power Company, acting for itself, Oglethorpe Power.Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated May 29, 1990,- complies with the standards and requirements of the Atomic: Energy Act of 1954, as amended (the Act), and the-Cornission'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 (1) that the activities authorized by I
this amendment can be. conducted without endangering.the health land j
safety of the public, and (ii) that such activities will be conducted in con:pliance with the Conaission's regulations set forth in 10 CFR Chapter I; D.
The-issuance of this~ license amendment will not be inimical to'the
~
conaon 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 Concission's regulations ar.d all applicable requirements have been satisfico.
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-Accordingly, the license is hereby amended by page changes to.the Technic 61 Specifications as indicated in the attechnent to this license amendment and paragraph 2.C.(2) of Facility Operating License No. hPF-81 is heret,y anended to read as follows:-
I3chni_calSpecificetionsandEnvironmentalProtectionPlan-Tb; Technical Specifications contained in Appendix A, as revised:
through Amendrent No. 14, tnd 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 Environnental Protection Plan.
3.
This license anenament is effective as of its date of. issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
cc6 David B. Matthews, Director Project Directorate 11-3
. Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachtent:
Technical Specification Changes Date of Issuance:
August 30, 1990 9
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i' ATTACHMENT TO LICENSE AMENDMENT NO. 34
' FACILITY OPERATING LICENSE NO. NPF-68 AND LICENSE AMENDMENT NO.'14 FACILITY OPERATING '1 CENSE NO.- NPF-61 DOCKET NOS. 50-424 AND 50-425 Replace'the follwing pages of the Appendix "A" Technical Specifications with the enclosed pages.. The reviseo pages are. identified by Amendment number and contain' vertical lines incicating the; areas of change. Theicorresponding overleaf pages are also provided to maintain document completeness.-
Amended Page Overleaf Page 2-5 2-6 3/4 3-31 3/4 3-32 i
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TABLE 2.2-1 (Continued) n.
<'8 REACTOR TRIP SYSTEM INSTRUMENTATION. TRIP SETPOINTS EE TOTAL SENSOR 5
ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT' ALLOWABLE VALUE E
9.
Pressurizer Pressure-Low
-3.1 0.71 1.67 21960 psig**
21950 psig
.p
.(PI-0455A,B&C, PI-0456 &
PI-0456A, PI-0457 & PI-0457A, g
PI-0458 & PI-0458A) 3 N
10.
Pressurizer Pressure-High 3.1 0.71 1.67
<2385 psig
<2395 psig (PI-0455A,B&C, PI-0456 &
PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-0458A) 11.
Pressurizer Water Level-High 8.0 2.18 1.67
<92% of instrument
<93.9% of instrt.sent (LI-0459A, LI-0460A,'LI-0461) ipan span 12.
Reactor Coolant Flow-Low 2.5
- design flow
- FI-0414 FI-0424 FI-0434 'FI-0444 FI-0415 -FI-0425 FI-0435 FI-0445 FI-0416 FI-0426 FI-0436 FI-0446).
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- 13. Steam Generator Water Level 18.5 17.18 1.67
>18.5% (37.8)***
>17.8% (35.9)***'
l.cw-Low (21.8)***
(18.21)***
of narrow range of narrow range gg (t_00P1 LOOP 2 LOOP 3 LOOP 4 instrument span instrument span eo LI-0517 ii-05?7-LI-0537 LI-0547 EE LI-0518 LI-0528 LI-0538' LI-0548 55 LI-0519 LI-0529 LI-0539 LI-0549 55 LI-0551 LI-0552 'LI-0553-LI-0554)
'E E 14.
Undervoltage - Reactor 6.0 0.58 0
>9600 volts
>9481 volts
. Coolant Pumps 1T70%' bus voltage)
.T69% bus voltage)
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15.
Underfrequency - Reactor.
- 3. 3 '
- 0.50 0
157.3 Hz 157.1 Hz.
gg -
Coolant Pumps.
..[
^ Loop design flow = 95,700 gpm
- Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 10 seconds for lead.and vv 1 second for lag.
CHANNEL' CALIBRATION shall ensure that these time constants are adjusted to these values.
- The value stated inside the. parenthesis is for instruinent that has 'the lower tap. at elevation 333"; the value stated outsida the parenthesis is for instrumentation that.has the lower tap at elevation 438".
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lABLE 2.2-1 (Continued) i REACT 00. TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
~
i rn c.
TOTAL' SENST.d j5 ALLOWANCE ERROR FUNCTIOPAL UNIT (TA)
Z_
(S)
TRIP SETPOINT ALLOWABLE VALUE 16.
- ~
a.
Low Fluid Oil Pressure N.A.
N. A.-
N.A.
1580 psig' 1500 psigL
- o. -
m (PT-6161, PT-6162, PT-6163) b.
Turbine Stop Valve ~ Closure N.A.
N. A.-
N.A.
>96.7% open 196.7% open 17.
Safety Injection Input from ESF N.A.
N.A.
N.A.
N.A.
N.A.
18.
Reactor Trip System Interlocks m
J, a.
Intermediate Range N.A.
N.A.
N.A.
ll x 10 10- amp
-36 x 10 11 amp Neutron Flux, P-6 (NI-00358, NI-00368) i b.
Low Power Reactor Trips
{
Block, P-7
- 1) P-10 input" N.A.
N.A.
N.A.
-<10% of RTP#
<12.3% of ET (NI-004IB&C, NI-0042B&C,.
NI-0043B&C,NI-00448&C) i
. 2). P-13 input N.A.
N.A.
N.A.
<10% RTP# Turbine.
x12.3% RTP# Turbine
- (PI-0505, PI-0506)
Impulse ~ Pressure-Impulse Pressure Equi. talent Equivalent c.
Power Range Neutron
-N.A.
N.A.
N.A.
$48% of RTP#
150.3% of RTP#
Flux,'P-8:.
- (NI-00418&C,NI-0042B&C,
~
NI-0043B&C,NI-0044B&C)
- RTP.= RATED-THERMAL POWER-t W-.z.
n A-.
%h M
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TABLE 3.3-3 (Continued) o Og
' ENGINEERED SAFETY FEATURES ACTUATION' SYSTEM INSTRUMENTATION TRIP SETPOINTS-c.
TOTAL SENSOR 5
ALLOWANCE ERROR d
FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT' ALLOWABLE VALUE 5.
Turbine Trip and Feedwater Isolation p
(Continued)
.U Steam Generator Water 5.1 2.18 1.67
<78.0% (86.0)* <79.9% (87.9)*
c.
Leve'--High-High (P-14)
(14.0)*
(8.62)*
'of instrument of narrow range span.
instrument span.
m (LOOP 1-LOOP 2 LOOP 3 LOOP 4 LI-0517
'LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549 R
LI-0551 LI-0552 LI-0553 LI-0554)
.b d.
Safety. Injection See Functional' Unit 1. above fer all Safety Injection Trip J,
Sotpoints and Allowable Values.
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6.
Auxiliary-Feedwater-a.
Automatic Actuation Logic N.A.
N.A.
N.A.
N.A.
N.A.
and Actuation Relays b.
Steam Generator Water Level--
Low-Low 3$,$
gg (LOOP 1 LOOP 2-LOOP 3 LOOP 4 LI-0517 LI-0527 LI-0537
-LI-0547 LI-0518 LI-0528 ~LI-0538 LI-0548 pp LI-0519 LI-0529 LI-0539 LI-0549 1
LI-0551-LI-0552 LI-0553 LI-0554) 1.
Start Motor-Driven' Pumps 18.5-17.18
'1.67
>18.5% (37.8)*
>17.8% (35.9)*
gg
~(21.8)* -
(18.21)*
Ef narrow
.of narrow range El range instru-'
. instrument span.
ment span...
g 2.
Start Turbine-Driven Pump-18.5 17.18 1.67 218.5%-(37.'8)*
117.8% (3Ts.9)*
(21.8)*
(18.21)*
of narrow of narrow range range instru -
instrument ment span.
span.
- The value stated inside.the p renthesis is for instrumentation that has the' lower tap,at. elevation 333";
,)
the value statea ou b!Je the parenthesis is for instrumentation ~that has the lower tap at elevation 438".
~
_ _._,i
, TABLE 3.3-3 (Continued) o ENGINEERED SnTETY Fc"ATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS g
TOTAL SENSOR ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE 6.
Auxiliary Feedwater (Continued) e-m c.
Safety Injection Start See Functional Unit 1. above for all Safety Injection Trip Motor-Driven Pumps Setpoints and Allowable Values.
d.
Loss of or degraded 4.16 kV ESF Bus Voltage Degraded Degraded 1.
Start Motor-Driven Pumps N.A.
. N. A.
N.A.
>3746 volts with
>3683 volts with 720 s time delay
{20stimedelay.
i Loss Loss P2975 volts with
> B F2 volts with w1 3 <0.8s. time i <0.8s time deTay-deTay w
w" Degraded-Degraded 2.
Turbine Driven Pump
'N.A.
N.A.
N.A.
>3/46 volts with
>3683 volts with 120stimedelay
{20stimedelay loss Loss 5B 75 volts P2912 volts with' with a <0.8s i <0.8s time i
time deTay
-deTay.
l e.
Trip of All Main Feedwater-N.A.
N.A.
N.A.
N.A.
N.A.
Pumps, Start Motor-Driven ~ Pumps -
f.
~ Manual Initiation N.A.
N.A.
N.A.
N.A.
N. A.
7.
. Semi-Automatic Switchover to Containment Emergency Sump i
a.
Automatic Actuation Logic N.A.
N.' A.
N.A.
- N.A.
M.A.
and Actuation' Relays R
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- J.