ML20077C448
| ML20077C448 | |
| Person / Time | |
|---|---|
| Site: | Summer  (NPF-12-A-121) |
| Issue date: | 11/29/1994 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077C455 | List: |
| References | |
| NUDOCS 9412050036 | |
| Download: ML20077C448 (6) | |
Text
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$a atcoq'o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION
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- E WASHINGTON, D. C. 20555 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.121 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applica ion for amendment by South Carolina Electric & Gas Company (the licensee), dated July ic. 1994, as supplemented September 2C,1994, complies with tL 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 applicatior_ ' le provisions of the Act, and the rules and regulations of the Commission, 3
1 C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health j
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 1
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 i
51 of the Commission's regulations and all applicable requirements have been satisfied.
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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:
9412050036 941129 i
PDR ADOCK 05000395 p
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.121
, 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 1
Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance and shall be i
implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/1 "s /f)
W illiam H. Ba
,an, Director Project Directorate II-l Division of Reactor Projects - I/Il Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 29, 1994 i
E ATTACHMENT TO LICENSE AMENDMENT NO.121 TO FACILITY OPERATING' LICENSE NO. NPF-12 i
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 8-3 3/4 8-3 3/4 8-4 3/4 8-4 6-16a 6-16a i
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ELECTRICAL POWER SYSTEMS
. SURVEILLANCE REOUIREMENTS (Continued t
4.8.1.1.2 Each EDG shall be demonstrated OPERABLE:
In accordance with the frequency specified in Table 4.8-1 on a a.
STAGGERED TEST BASISby:
1.
Verifying the fuel level in the day tank and fuel storage tank.
2.
Verifying the fuel transfer pump can be started and transfers fuel ffom the storage system to the day tank.
3.
Verifying the diesel generator can start
- and accelerate to synchronous speed (504 rpm) with generator voltage and frequency at 7200 720 volts and 60 1.2 liz.
4.
Verifying the generator is synchronized, gradually loaded
- to an inilicated 4150-4250 kW** and operates for at least 60 minutes.
b.
A t least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to I hour by removing accumulated water from the day tank.
i At least once per 31 days by checking for and removing accumulated c.
water from the fuel oil storage tanks; d.
By sampling new fuel oil in accordance with the applicable ASTM standard prior to addition to storage tanks and:
1.
By verifying in accordance with the tests specified in the applicable ASTM standard prior to addition to the storage tanks that the sample has:
An API Gravity of within 0.3 degrees at 60*F or a a.
specific gravity of within 0.0016 at 60/60*F, wnen compared to the supplier's certificate, or an absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.89, or an API gravity of greater than or equal to 27 degrees but less than or equal to 39 degrees; b.
A kinematic viscosity of 40"C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes (alternativelv, Saybolt viscosity, SUS at 100*F of greater than or equal to 32.6, but not less than or equal to 40.11, if gravity was not determined by comparison with the supplier's certification; This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and as applicable regarding loading recommendations.
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- This band is meant as guidance to avoid routine overloading of the engine.
Loads in excess of this band shall not invalidate the test.
SUMMER - UNIT I 3/48-3 Amendment No. 7it, M, M, 121 1
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1 A flash point equal to or greater than 125'F; and c.
d.
A clear and bright appearance with proper color when tested in accordance with the applicable ASTM standard.
l 2.
By verifying within 30 days of obtaining the sample that the specified prope ties are met when tested in accordance with the applicable ASTM standard.
At least once every 31 days by obtaining a sample of fuel oil in e.
accordance with the applicable ASTM standard, and verifying that total
[
contamination is less than 10 m ;/ liter when checked m accordance with the applicable ASTM stanc ard.
l f.
At least once per 184 days by:
1.
Starting and accelerating the EDG to synchronous speed (504 rpm) with generator voltage and frequency at 7200 720 volts and 60 1.2 Hz within 10 seconds after the start signal. The EDG shall be started for this test by using one of the following signals:
a)
Simulated loss of offsite power by itself.
b)
Simulated loss of offsite power in conjunction with an ESF actuation test signal.
c)
An ESF actuation test signal by itself.
d)
Simulated degraded offsite power by itself.
e)
Manual.
2.
The generator shall be manually synchronized, loaded to an indicated 4150-4250 kW** in less than or equal to 60 seconds, and operate for at least 60 minutes.
g.
At least once every 18 months by:
1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, 2.
Verifying that on rejection of a load of greater than or equal to 729, the voltage and frequency are maintained at 7200 720 volts and frequency at 60 1.2 liz.
3.
Verifying'the generator capability to reject a load of 4250 kW without tripping. The generator voltage shall not exceed 7920 volts during and following the load rejection.
- This band is meant as guidance to avoid routine overloading of the engine.
Loads in excess of this band shall not invalidate the test.
SUMMER - UNIT 1 3/484 Amendment No. 'N, M,121
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ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
- (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient 3.1.3.5 - Shutdown Bank Insertion Limit,3.1.3.6 -
Control Bank Insertion Limit,3.2.1 - Axial Flux Difference,3.2.2 -
Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
b.
WCAP-10216-P-A, Rev.1A," RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", February 1994 (W Proprietary).
(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (FQ Methodology for W(Z) surveillance requirements).)
j c.
WCAP-10266-P A,Rev.2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", March 1987(WProprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements there to shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
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SUMMER - UNIT 1 6-16a Amendment No. M 121
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