ML20117F010
| ML20117F010 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/10/1996 |
| From: | Imbro E NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20117F013 | List: |
| References | |
| NUDOCS 9605170050 | |
| Download: ML20117F010 (13) | |
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~' 4 UNITED STATES l-l j
NUCLEAR REGULATORY COMMISSION o
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SOUTH CAROLINA ELECTRIC & GAS COMPANY i
SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMER NUCLEAR STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 134 i
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 December 8,1995 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 Cbumission; 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 l
amendment; and paragraph 2.C.(2) of Facility Operating License No.
NPF-12 is hereby amended to read as follows:
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. (2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.134 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 COMISSION EY Ya Eugene V. Imbro, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 10,1996
"M i ATTACHMENT TO LICENSE AMENDMENT NO.134 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 III III 3/4 1-7 3/4 1-7 3/4 1-9 3/4 1-9 3/4 1-10 3/4 1-10 3/4 4-34 3/4 4-34 3/4 4-35 3/4 4-35 i
3/4 5-5 3/4 5-5 1
B3/4 1-3 B3/4 1-3 j
B3/4 4-2 B3/4 4-2 l
B3/4 4-14a B3/4 4-14a I
i INDEX 1
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - Modes i and 2.............................
3/41-1 Shutdown Margin-Modes 3,4 and 5 3/41-3 Moderator Temperature Coefficient...........................
3/4 1-4 Minimum Temperature for Criticality.........................
3/41-6 3/4.1.2 BORATION SYSTEMS Flow Path - Shutdown 3/41-7 Flow Paths - Operating......................................
3/41-8 Deleted 3/41-9 Deleted 3/4 1-10 Borated Water Source - Shutdown.............................
3/4 1-11 Borated Water Sources - Operating............................
3/4 1-12 3/4.1.3 MOVABLE CONTROL ASSEMBLIES G roup H eigh t...............................................
3/4 1-14 Position Indication Systems - Operating.......................
3/4 1-17 Position Indication System - Shutdown........................
3/4 1-18 Rod Drop Time..............................................
3/4 1-19 Shutdown Rod Insertion Limit................................
3/4 1-20 Control Rod Insertion Limits.................................
3/4 1-21 l
SUMMER - UNIT 1 III Amendment No. M 2
J REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATH - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source:
a.
A flow path from the boric acid tanks via either a boric acid transfer pump or a gravity feed connection and a charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.5a is OPERABLE, or b.
The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.5b is OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.1.1 Atleast one of the above r uired flow paths shall be demonstrated OPERABLE atleastonceper31 days verifying that each valve (manual, power operated, or automatic) in the flow pa that is not locked, sealed, or otherwise secured in position, is in its correct position.
4.1.2.1.2 Demonstrate operability of the required charging pump per Surveillance 4.5.2.f.
SUMMER-UNIT 1 3/41-7 Amendment No.134
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' Amendment No.134 l
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'i THIS PAGE DELETED SUMMER-UNIT 1 3/4 1-10
' Amendment No. 134
4 REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 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 ofless 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 through a greater than or equal to 2.7 square inch vent within the 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 i
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.
In the event that two or more charging pumps are capable ofinjecting r
into the RCS, immediately initiate action to ensure a maximum of one charging pump is capable ofinjecting into the RCS*.
e.
The provisions of Specification 3.0.4 are not applicable.
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- Two charging pumps may be capable ofinjecting into the RCS while swapping pumps, s15 minutes.
SUMMER-UNIT 1 3/4 4-34 Amendment No. 26,125.134
4 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each RHR relief valve shall be demonstrated OPERABLE by:
Verifying the RHR relief valve isolation valves (8701 A, 8701B, a.
8702A, and 8702B) are open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the RHR relief valve is being used for overpressure protection.
i' b.
Testing pursuant to Specification 4.0.5.
c.
Verification of the RHR relief valve setpoint of at least one RHR relief valve, at least onco per 18 months on a rotating basis.
4.4.9.3.2 The RCS vent shall be verified to be open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- when the vent is being usec for overpressure protection.
4.4.9.3.3 At least two charging pumps shall be verified incapable ofinjecting into the RCS atleast once per 31 days, except when the reactor vessel head is removed, by verifymg that tne motor circuit breakers are secured in the open position.
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- Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, verify these valves open at least j
'once per 31 days.
SUMMER-UNIT 1 3/4 4-35 Amendment No
.>6. ! 34
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M EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
A visualinspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debns and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
At least once per 18 months, during shutdown, by:
e.
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection actuation and i
containment sump recirculation test signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a safety injection actuation test signal:
a)
Centrifugalchargingpump l
b)
Residualheat removalpump t
f.
By verifying each ECCS pump's developed head at the test flow point for that pump is, greater than or equal to the required developed head in accordance with Specification 4.0.5.
g.
By verifying the correct position of each mechanical position stop for the following ECCS t irottle valves:
l.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems l
are required to be OPERABLE.
2.
Atleast once per 18 months.
HPSI System Valve Number i
a.
8996A b.
8996B c.
89960 d.
8994A e.
8994B f.
8994C J.
8989A
.1.
8989B i.
89890 8991A s.
8991B 1.
8991C i
SUMMER - UNIT 1 3/45-5 Amendment No. 75,134 L
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REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued)
MARGIN from expected operating conditions of1.77% delta k/k or as required by Figure 3.1-3 after xenon aecay and cooldown to 200*F. The maximum expected boration capability r uirement occurs from full power equilibrium xenon condi-tions and is satisfied 13269 gallons of 7000 ppm borated water from the boric acid storage tanks or 98631 gallons of 2300 ppm borated water from the refuel-ing water storage tank.
With the RCS temperature below 200*F, one injection system is acceptable without sin e failure consideration on the basis of the stable reactivity condition o he reactor and the additional restrictions prohibiting CORE i
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ALTERATIONS and positive reactivity changes in the event the smgle injection system becomes inoperable.
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The boron capability required below 200*F is sufficient to provide the required SHUTDOWN MARGIN of1 percent delta k/k or as required by Figure 3.1-3 after xenon decay and cooldown from 200*F to 140*F. This condition is satisfied by either 2000 gallons of 7000 ppm borated water from the boric acid storage tanks or 23266 gallons of 2300 ppm borated water from the refueling water storage i
tank,.
The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.
The OPERABILITY of one boron injection system during REFUELING ensures l
that this system is available for reactivity control while in MODE 6.
l 3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power t
distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is main-tained, and (3) limit the potential effects of rod misalignment on associated accident analyses. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
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q SUMMER - UNIT 1 B 3/41-3
' Amendment No. 67,75,134
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REACTOR COOLANT SYSTEM BASES 3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Eac 1 safety valve is designed to relieve 420,000 lbs per hour of saturated steam at the valve set point p..us 3% accumulation. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown. In the event that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS over-pressurization.
l During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig.
The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss ofload assuming no reactor trip until the first Reactor Protective System trip set point is reached (i.e., no credit is taken for a direct reactor trip on the loss ofload) and also assuming no operation of the power operating relief valves or steam dump valves.
i Demonstration of the safety valves' lift settings will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.
3/4.4.3 PRESSURIZER
. The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady state envelo'>e of operation assumed in the SAR. The limit is consistent with the initial SA 1 assumptions.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant System pressure and establish natural circulation.
3/4.4.4 RELIEF VALVES (PORVs)
The pressurizer power operated relief valves (PORVs) and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump. The PORVs and block valves may be used to depressurize the RCS when normal pressurizer spray is unavailable. Operation of the air operated PORVs minimizes the undesirable opening of the springloaded pressurizer code safety valves. Each PORV has a remotely controlled motor-o >erated block valve to provide a positive shutoff capability should a relief valve become inoperable. The series arrangement of the PORV and its associated block valve permit surveillance while at power.
3 SUMMER-UNIT 1 B 3/4 4-2 Amendment No. 94,129, W l
BASES Although the pressurizer operates in temperature ranges above those for i
which there is reason for concern of non-ductile failure, operating limits are provided to assure compatibility of operation with the fatigue analysis per-formed in accordance with the ASME Code requirements.
The OPERABILITY of two RHRSRVs or an RCS vent opening of at least 2.7 square inches ensures that the RCS will be protected from aressure tran-sients which could exceed the limits of Appendix G to 10 CFR ? art 50 when one or more of the RCS cold legs are less than or equal to 300*F. Either RHRSRV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 50*F above the RCS cold leg temperatures or (2) the start of an HPSI pump and its injection into a water solid RCS.
The limitation for a maximum of one chargi,ng pump to be capable of injecting into the RCS, and the Surveillance Requirement to verify at least two charging pumps are demonstrated to be INOPERABLE at least once per l
31 days, whiae the RCS is below 300*F, provides assurance that a mass addition transient can be mitigated by a single RHR suction relief valve.
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SUMMER -UNIT 1 B 3/4 4-14a Amendment No. 53, 1 M
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