ML20138R908
| ML20138R908 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/01/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20138R909 | List: |
| References | |
| NUDOCS 8511190234 | |
| Download: ML20138R908 (5) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
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I WASHINGTON, D. C. 20555 DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 1 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership
/CorporationandSaludaRiverElectricCooperative,Inc.,(licensees) dated October 18, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; j
B.
The facility will operate in confonnity with the application, as l
amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted withc,ut endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I;-
D.
The issuance of this license amendnent will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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-35 is hereby amended to read as follows:
- (2) Technical Specifications and Environmental Protection Plan I
The Technical Specifications contained in Appendix A, as revised r
through Amendnent No.1, and the Environmental Protection Plan contained 8511190234 851101 i
PDR ADOCK 05000413 P
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-2 in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment was effective October 18, 1985.
FOR THE NUCLEAR REGULATORY COMMISSION
$4'h j62.Elinor G. fo Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance:
November 1, 1985 i
ATTACHMENT TO LICENSE AMENDMENT N0.1 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 Replace the following oages of the Appendix "A" Technical Specifications with the enclosed pages. The revised page is identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Amended Overleaf Pg Page 3/4 4-20 3/4 4-19 i
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REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:
a.
The Containment Atmosphere Gaseous Radioactivity Monitoring System, b.
The Containment Floor and Equipment Sump Level and Flow Monitoring 4
Subsystem, and c.
Either the Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem or the Containment Atmosphere Particulate-Radioactivity Monitoring System.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With only two of the above required Leakage Detection Systems OPERABLE, operation may continue for up to 30 days provided grab samples of the contain-ment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required Gaseous or Particulate Radioactivity Monitoring System is inoperable; 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 SHUTDOWN 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 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:
a.
Containment Atmosphere Gaseous and Particulate Monitoring System performance of CHANNEL CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, b.
Containment Floor and Equipment Sump Level and Flow Monitoring Subsystem performance of CHANNEL CALIBRATION at least once per 18 months, and c.
Containment Ventilation Unit Condensate Drain Tank Level Monitoring Subsystem performance of CHANNEL CALIBRATION at least once per 18 months.
k CATAWBA - UNIT 1 3/4 4-19
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 gpm UNIDENTIFIED LEAKAGE, 1 gpm total reactor-to-secondary leakage through all steam generators c.
and 500 gallons per day through any one steam generator, d.
10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, 40 gpm CONTROLLED LEAKAGE at a Reactor Coolant System pressure of e.
2235 1 20 psig, and f.
1 gpm leakage at a Reactor Coolant System pressure of 2235 1 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 in COLD SHUTDOWN within.the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.*
l With any Reactor Coolant System Pressure Isolation Valve leakage c.
greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- Until 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, October 23, 1985, operation in Modes 3 and 4 is permitted with the Reactor Coolant System unidentified leakage rate > 1 gpm but < 5 gpm.
If the unidentified leakage rate is not reduced to < 1 gpm by the above time, the unit will be placed in COLD SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
CATAWBA - UNIT 1 3/4 4-20 Amendment No. 1
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