ML20093D862
| ML20093D862 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/24/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093D863 | List: |
| References | |
| NUDOCS 8410110435 | |
| Download: ML20093D862 (8) | |
Text
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UNITED STATES y,
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NUCLEAR REGULATORY COMMISSION 7.
<j WASHINGTON, D. C. 20555 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLI _N_A PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for smendment to the Virgil C. Sumer Nuclear Station, Unit No.1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated October 21, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this license 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 hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 26, are hereby incorporated into this licen;e.
South Carolina Electric 5 Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, kk kD 0
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4W Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes Date of Issuance: September 24, 1984 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 26 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 identified by Amendment number and contain vertical lines indicating the areas of change. To maintain document completeness, corresponding overleaf pages are also provided.
I Amended Overleaf Page Page 3/4 4-34 3/4 4-33 3/4 4-35 B3/4 4-14 B3/4 4-13 Page 3/4 4-35a is deleted I
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- I PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:
a.
A maximum heatup of 100 F in any one hour period, b.
A maximum cooldown of 200 F in any one hour period, and c.
A maximum auxiliary spray water temperature differential of 625 F.
i APPLICABILITY:
At all times.
1 ACTION:
With the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the fracture toughness properties of the pressurizer; determine that the pressurizer remains acceptable for continued operation or 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 reduce the pressurizer pressure to less than 500 psig within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.9.2 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.
The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during auxiliary spray operation.
SUMMER - UNIT 1 3/4 4-33
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:
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5 1.
A lif t 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:
a.
With one RHR relief valve inoperable, restore the inoperable valve to OPERABLE status within 7 days or depressurize ar.d 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 2.
Depressurize and vent the RCS through a greater than or equal to 2.7 square inch vent.
c.
In the event an RHR relief valve or RCS vent is used to mitigate an 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 ( F 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.
1 SUMMER - UNIT 1 3/4 4-34 Amendment No.
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2 REACTOR'C00LANT SYSTEM h
SURVEILLANCE REQUIREMENTS I
32 4.4.9.3.1 Each RHR relief valve shall be demonstrated OPERABLE by:
a.
Verifying the RHR relief valve isolation valves (8701A, 8701B, 8702A, and 87028) 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.
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 once per 18 months on a rotating basis.
1 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 used for overpressure protection.
- 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 once per 31 days.
SUMMER - UNIT 1 3/4 4-35 Amendment No. 26 i
REACTOR COOLANT SYSTEM BASES PRESSURE / TEMPERATURE LIMITS (Continued) during cooit results in a higher value of K at the 1/4T location for IR finite cooldown rates than for steady-state operation.
Furthermore, if conditions exist such that the increase in K exceeds kit, the calculated IR allowable pressure during cooldown will be greater than the steady-state value.
The above procedures are needed because there is no direct control on temperature at the 1/4T location; therefore, allowable pressures may unknowingly be violated if the rate of cooling is decreased at various intervals along a cooldown ramp.
The use of the composite curve eliminates this problem and assures conservative operation of the system for the entire,cooldown period.
HEATUP Three separate calculations are required to determine the limit curves for finite heatup rates. As is done in the cooldown analysis, allowable pressure-temperature relationships are developed for steady-state conditions as well as finite heatup rate conditions assuming the presence of a 1/4T defect.at the inside of the vessel wall.
The thermal gradients during heatup produce compressive stresses at the inside of the wall that alleviate the tensile stresses produced by internal pressure.
The metal temperature at the crack tip lags the coolant temperature; therefore, the K for the 1/4T crack IR during heatup is lower than the K f r the 1/4T crack during steady-state IR conditions at the same coolant temperature.
During heatup, especially at-the end of the transient, conditions may exist such that the effects of compressive thermal stresses and different K
's for steady-s. tate and finite heatup rates IR do not offset each other and the pressure-temperature curve based on steady-state conditions no longer represents a lower bound of all similar curves for finite heatup rates when the 1/4T flaw is considered.
Therefore, both cases have to be analyzed in order to assure that at any coolant temperature the lower value of the allowable pressure calculated for steady-state and finite heatup rates is obtained.
SUMMER - UNIT 1 B 3/4 4-13
r REACTOR COOLANT SYSTEM BASES PRESSURE / TEMPERATURE LIMITS (Continued)
The second portion of the heatup analysis concerns the calculation of pressure-temperature limitations for the case in which a 1/4T deep outside surface flaw is assumed. Unlike the situation at the vessel inside surface, the thermal gradients established at the outside surface during heatup produce stresses which are tensile in nature and thus tend to reinforce any pressure stresses present. These thermal stresses, of course, are dependent on both the rate of heatup and the time (or coolant temperature) along the heatup ramp.
Furthermore, since the thermal stresses, at the outside are tensile and increase with increasing heatup' rate, a lower bound curve cannot be defined.
Rather, each heatup rate of interest must be analyzed on an individual basis.
Following the generation of pressure-temperature curves for both the steady-state and finite heatup rate situations, the final limit curves are produced as follows.
A composite curve is constructed based on a point-by-point comparison of the steady-state and-finite heatup rate data.
At any given temperature, the allowable pressure is taken to be the lesser of the three values taken from the curves under consideration.
The use of the composite curve is necessary to set conservative heatup limitations because it is possible for conditions to exist such that over the course of the heatup ramp the controlling condition switches from the inside to the outside and the pressure limit must at all times be based on analysis of the most critical criterion.
Finally, the composite curves for the heatup rate data and the cooldown rate data are adjusted for possible errors in the pressure and temperature sensing instruments by the values indicated on the respective curves.
Although the pressurizer operates in temperature ranges above those for which there is reason for concern of non-ductile failure, operating limits are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code requirements.
TheOPERABILITYoftwoRHRSRVsoranRCSventopeningofatleast2.7squarej inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR part 50 when one or more of the RCS cold legs are less than or equal to 300 F.
Either RHRSRV has adequate l
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 a HPSI pump and its injection into a water solid RCS.
SUMMER - UNIT 1 B 3/4 4-14 Amendment No. 26
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