ML20087G213
| ML20087G213 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/11/1995 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20087G214 | List: |
| References | |
| NUDOCS 9508160288 | |
| Download: ML20087G213 (5) | |
Text
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g UNITED STATES NUCLEAR REGULATORY COMMIS0!ON 3
E WASHINGTON, o.C. 20866 4 001
/
SOUTH CAROLINA ELECTRIC & GAS COMPANY SQQTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.125 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 March H. 1994, complies with the standards and requirements of the '-
c Energy Act of 1954, as amended (the Act), and the Commiss i., 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:
9508160288 950811 PDR ADOCK 05000295 P
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~.
s (2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 125-, 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 Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 8t/AA Frederick J. Hebdon, Directo Project Directorate 1I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Dde of Issuance: August 11, 1995 l
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1 i
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's ATTACHMENT TO LICENSE AMENDMENT NO.125 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET 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.
Remove Paaes Insert Paaes 3/4 4-34 3/4 4-34 B3/4 5-2 B3/4 5-2 6
4
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REACTOR COOLANT SYSTEM OVERPRESSLRE PROTECTION SYSTEMS LINITING CONDITION FOR OPERATION I
3/4.9.3 At least one of the following overpressure protection systems shall be OPERABLE:
a.
Two RHR relief valves with:
1.
A lift setting of less than or equal to 450 psig, and 2.
The associated RHR relief valve isolation valves open; or b.
The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 2.7 square inches.
APPLICABILITY:
MODE 4 when the temperature of any RCS cold leg is less than or equal to 300*F, MODE 5, and MODE 6 with the reactor vessel head on.
ACTION:
With one RHR relief valve inoperable, restore the inoperable valve a.
to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or depressurize and vent the RCS l
through a greater than or equal to 2.7 square inch vent within the 3
next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With both RHR relief valves inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:
1.
Restore at least one RHR relief valve to OPERABLE status, or 2.
Depressurize and vent the RCS through a greater than or equal to 2.7 square inch vent.
In the event an RHR relief valve or RCS vent is used to mitigate an c.
RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the RHR relief valves or vent on the trans-ient and any corrective action necessary to prevent recurrence.
d.
- The provisions of Specification 3.0.4 are not applicable.
s i
SLM4ER - UNIT 1 3/4 4-34 Amendment No. 26,125-
t EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE charging pump to be inoperable below 300*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single RHR suction relief valve.
l The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:
(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration.
(2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
3/4.5.4 REFUELINC WATER STORAGE TANK The OPERABILITY of the Refueling Water Storage Tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of either a LOCA, a steamline break or inadvertent RCS depressurizatien. The limits of RWST minimum volume and boron concentration ensure 1) that sufficient water is available within containment to permit re-circulation cooling flow to the core, 2) that the reactor will remain subcriti-cal in the cold condition (68 to 212 degrees-F) following a small break LOCA assuming complete mixing of the RWST, RCS, Spray Additive Tank (SAT), contain-ment spray system piping and ECCS water volumes with all control rods inserted exceptthemostreactivecontrolrodassembly(ARI-1),3)thatthereactorwill l
remain subcritical in the cold condition following a large break LOCA (break l
flow area 33.0 sq. ft.) assuming complete mixing of the RWST, RCS, ECCS water and other sources of water that may eventually reside in the sump post-LOCA with all control rods assumed to be out (ARO), 4) long term subcriticality fol-lowing a steamline break assuming ARI-1 and preclude fuel failure.
The maximum allowable value for the RWST boron concentration forms the basis for deter 1 mining the time (Post-LOCA) at which operator action is required to switch over the ECCS to hot leg recirculation in order to avoid precipitation of the soluble boron.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics SUtHER - UNIT 1 B 3/4 5-2 Amendment No. W. $ E 125
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