ML20034F897
| ML20034F897 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/25/1993 |
| From: | Jeffrey Mitchell Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034F898 | List: |
| References | |
| NUDOCS 9303050160 | |
| Download: ML20034F897 (8) | |
Text
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[pa at cy'o, UNITED STATES E~
'i NUCLEAR REGULATORY COMMISSION w
g
- E WASHINGTON, D. C. 20555
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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by South Carolina Electric & Gas Company (the licensee), dated February 4,1991, as supplemented November 13, 1992, and February 10, 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 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; 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.
2.
Accordingly, the license is amended by 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-12 is hereby amended to read as follows:
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930305016o 930225 PDR ADOCK 05000395 P
PDR (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 109, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the j
Environmental Protection Plan.
i 3.
This amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
1 FOR THE NUCLEAR REGULATORY COMMISSION
! LJl
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Jocelyn A. Mitchell, Acting Director i
Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 25, 1993 i
ATTACHMENT TO LICENSE AMENDMENT NO.109 TO FAClllTY OPERATING LICENSE NO. NPF-12 J0CKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are indicated by marginal lines.
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Remove Pages Insert Paoes 3/4 7-1 3/4 7-1 3/4 7-2 3/4 7-2 3/4 7-3 3/4 7-3 B 3/4 7-1 B 3/4 7-1 B 3/4 7-2 8 3/4 7-2
3/4.7 PLANT SYSTEMS i
l 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-2.
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APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With 3 reactor coolant loops and associated steam generators in 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 OPERABLE status or the Power Range Neutron Flux High Trip Setpoint 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 SHUTD0liN 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.
l SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements
- other than those required by Specification 4.0.5.
- All valves tested must have "as-left" lift setpoints that are within 11% of the Lift Setting value listed in Table 3.7-2.
SUMMER - UNIT 1 3/4 7-1 Amendment No. 109
'.l TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH IHOPERABLE STEAM LINE SAFETY VALVES DURING 3 LOOP OPERATION Maximum Number of Inoperable Maximum Allowable Power Range Safety Valves on Any Neutron Flux High Setpoint Operating Steam Generator (Percent of RATED THERMAL POWER) 1 87 2
65 3
43 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP S/G A S/G B S/G C Lift Setting
- Orifice Size XVS-2806A XVS-2806F XVS-2806K 1176 psig 11%
4.515 In dia/16 sq in XVS-2806B XVS-2806G XVS-2806L 1190 psig 13%
4.515 In dia/16 sq in XVS-2806C XVS-2806H XVS-2806M 1205 psig 13%
4.515 In dia/16 sq in XVS-2806D XVS-2806I XVS-2806N 1220 psig 3%
4.515 In dia/16 sq in XVS-2806E XVS-2806J XVS-2806P 1235 psig 3%
4.515 In dia/16 sq in
- The Lift Setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
SUMMER - UNIT 1 3/4 7-2 Amendment No. 109
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SUMMER - UNIT 1 3/4 7-3 Amendment No. 109
3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% (1305 psig) of its design pressure of 1185 psig during the most severe anticipated system operational transient.
The maximum relieving capacity is associated with a turbine trip ' rom 100% RATED THERMAL POWER coincident with an assumed loss of condenser hed sink (i.e., no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accord-ance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. The total relieving capacity for all valves on all of the steam lines is 13.76 x 106 lbs/hr which is 110 percent of the total secondary steam flow of 12.2 x 106 lbs/hr at 100% RATED THERMAL POWER. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1.
l STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary 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 bases:
For 3 loop operation (X) - (Y)(V)
SP =
X X 109 Where:
SP = Reduced reactor trip setpoint in percent of RATED THERMAL POWER.
V = Maximum number of inoperable safety valves per steam line.
109 = Power Range Neutron Flux-High Trip Setpoint for 3 loop operation.
X = Total relieving capacity of all safety valves per steam line in lbs/ hour.
Y = Maximum relieving capacity of any one safety valve in lbs/ hour.
SUMMER - UNIl 1 B 3/4 7-1 Amendment No. 109
i PLANT SYSTEMS BASES 3/4.7.1.2 EMERGENCY FEEDWATER SYSTEM The OPERABILITY of the emergency feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating conditions in the event of a total loss of off-site power.
j The emergency feedwater system is capable of delivering a total feedwater flow of 380 gpm at a pressure of 1211 psig to the entrance of at least two steam generators while allowing for (1) any spillage through the design worst-case break of the emergency feedwater line, (2) the design worst-case single failure, and (3) recirculation flow. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350*F at which point the Residual Heat Removal System may be placed into operation.
3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> with steam discharge to the atmosphere con-l current with total loss of offsite power. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube lec< in the steam generator of the affected steam line. These values are consistent with the assumptions used in the accident analyses.
SulHER - UNIT 1 B 3/4 7-2 Amendment No.109