ML20078C365
| ML20078C365 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/20/1995 |
| 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 | |
| ML20078C366 | List: |
| References | |
| NPF-68-A-082, NPF-81-A-060 NUDOCS 9501260281 | |
| Download: ML20078C365 (9) | |
Text
e s>'A FECO
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k UNITED STATES j
,j NUCLEAR REGULATORY COMMISSION '
's WASHINGTON, D.C. 20556-4001
%**,./
GEORGIA POWER COMPANY i
OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPEB8 TING LICENSE Amendment No. 82 License No. NPF-68 I.
The Nuclear Regulatory Comission (the Comission) 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 March 31, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 tt' Act, and the rules and regulations of the Comission,
C.
There is re&sonable 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 Comission'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.
9501260281 950120 PDR ADOCK 05000424 l
P PDR
. 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 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 82
, 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 THE NUCLEAR REGULATORY COMISSION erbert 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: January 20, 1995
O pa cro ft UNITED STATES y-2 8
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2056M001
,o 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. 60 License No. NPF-81 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facili'y; 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 March 31, 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 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.
4 r=
l o 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. 60
, 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.
l FOR THE NUCLEAR REGULATORY COMMISSION He bert N. Ber ow, Director 1
i Project Directorate II-3 l
Division of Reactor Projects - I/II j
j Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: January 20, 1995 1
l l
i l
8TTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 8lE TO LICENSE AMENDMENT NO. 60 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 re?'1ed pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paggi 3/4 7-1* and 3/4 7-2 3/4 7-1* and 3/4 7-2 B 3/4 7-1 B 3/4 7-1 and B 3/4 7-la l
- Overleaf page containing no change.
O 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valve associated with each steam generator shall be OPERABLE with lift settings; as specified in Table 3.7-2.
l APPLICABILITY: MODES 1. 2, and 3.
ACTION:
a.
With four reactor coolant loops and associated steam generators in l
operation and with one or more main steam line Code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed, provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to i
OPERABLE status or the Power Range Neutron Flux High Trip Setpoint I
(NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-00448&C) is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.7.1.1 No additional requirements other than those required by Specification 4.0.5.
l
- All valves tested must have "as-left" lift setpoints that are within il%
of the lift setting values in Table 3.7-2.
V0GTLE UNITS 1 & 2 3/4 7-1
4 I
TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH 1 EPERABLE STEAM LINE SAFETY VALVES MAXIMUM NUMBER OF INOPERABLE MAXIMUM ALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER)
I 71 2
51 3
31 f
V0GTLE UNITS - 1 & 2 3/4 7-2 Amendment No. 82 (Unit 1)
Amendment No. 60 (Unit 2)
4 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE
?
3/4.7.1.1 SAFETY VALVES i
The OPERABILITY of the main steam line Code safety valves ensures that j
the Secondary System pressure will be limited to'within 110% (1304 psig) of its design pressure of 1185 psig.juring the most severe anticipated system j
operational transient. The maximum relieving capacity is associated with a j
Turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of j
condenser heat sink (i.e., no steam bypass to the condenser).
1 The specified valve lift settings and relieving capacities are in I
accordance with the requirements of Section III of the ASME Boiler and Pressure j
Code, 1974 Edition. The safety valves are tested in accordance with the requirements of Section XI of the ASME Code. The life setting allowable values i
are consistent with the safety analysis.
In the event a safety valve lifts
]
outside of the tolerances specified in Table 3.7-2, the Section XI provisions i
of adjusting the setpoint and testing additional valves applies. When tested, j
the as-left setting will be within 11% of the specified set pressure. The i
total relieving capacity for all valves on all of the steam lines is 18,607,220 lbs/h which is 117% of the total secondary steam flow of 15.92x10' lbs/h at 100% RATED THERMAL POWER. A minimum of two OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the i.
allowable THERMAL POWER restriction in Table 3.7-1.
1 STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction l
in Secondary Coolant System steam flow and THERMAL POWER required by the reduced Reactor trip settings of the Power Range Neutron Flux channels. The Reactor Trip Setpoint reductions are derived on the following basis:
I For four loop operation i
Hie - (100/Q)
,tu where:
Hie -
Safety Analysis power range high neutron flux setpoint, percent Q
Nominal NSSS power rating of the plant (including reactor coolant j
pump heat), MWt i
K Conversion factor, 947.82 Et.uf.1).
=
j Mt j
w, Minimum total steam flow rate capability of the operable MSSVs on any
=
i one steam generator at the highest MSSV opening pressure including i
tolerance and accumulation, as appropriate, in 1b/s.
For example, if l
the maximum number of inoperable MSSVs on any one steam generator is
]
one, then w, should be a summation of the capacity of the operable 4
k V0GTLE UNITS - 1 & 2 B 3/4 7-1 Amendment No. 82 (Unit 1)
Amendment No. 60 (Unit 2) i 4..
PLANT SYSTEMS BASES MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV.
If the maximum number of inoperable MSSVs per steam generator is three then w should be a summation of the capacity of the operable MSSVs 'at the highest operable MSSV operating pressure, excluding the three highest capacity MSSVs.
h,,
Heat of vaporization for steam at the highest MSSV opening pressure including tolerance and accumulation, as appropriate, Btu /lba.
N Number of loops in the plant.
The values calculated must be reduced to account for instrument and channel uncertainties (typically 9 percent power). Therefore, the maximum plant operating power level would then be lower than the reactor protection system setpoint by an appropriate operating margin.
V0GTLE UNITS 1 & 2 B 3/4 7-1a Amendment No. 82 (Unit 1)
Amendment No. 60 (Unit 2)