ML20205Q721
| ML20205Q721 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 04/16/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205Q724 | List: |
| References | |
| NUDOCS 9904220037 | |
| Download: ML20205Q721 (7) | |
Text
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20066 4 001
%...../
STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.106 License No. NPF-76 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by STP Nuclear Operating Company
- acting on behalf of itself and for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
and City of Austin, Texas (COA) (the licensees), dated January 26,1999, 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, as amended, 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 license 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.
- STP Nuclear Operating Company is authorized to act for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9904220037 990416 i
PDR ADOCK 05000498 P
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! 2.
Accordingly, the license is amended by changes to the Technical Specifications as l
indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as follows:
2.
Technical Soecifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No.106, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
W Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 16, 1999 i
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION i
t WASHINGTON, D.C. 3086H001 l
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STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 93 License No. NPF-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by STP Nuclear Operating Company
- acting on behalf of itself and for Houston Lighting & Power Company (HL&P), the City Public Service Board cf San Antonio (CPS), Central Power and Light Company (CPL),
and City of Austin, Texas (COA) (the licensees), dated January 26,1999, complies with the standard and requirements of the Atomic Energy Act of 1954, as amended (the Act), ano (ne Commission's rules and regulations 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 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 license 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.
- STP Nuclear Operating Company is authorized to act for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
c
' 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 80 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
93, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Ch Robert A. Gramm, Chief, Section 1 Project Directorate IV 8 Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: Apr11 16, 1999 l
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l ATTACHMENTTO LICENSE AMENDMENT NOS 106 AND 93 l
FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-498 AND 50-499 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.
Remove Insert 3/4 4-39 3/4 4-39 3/4 4-40*
3/4 4-40*
- Overleaf page - no change
c REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.10 The structuralintegrity of ASME Code Class 1,2, and 3 components shall be maintained in accordance with Specification 4.4.10.
APPLICABILITY: All MODES.
ACTION:
a.
With the structuralintegrity of any ASME Code Class 1 component (s) not l
conforming to the above requirements, restore the structuralintegrity of the affected component (s) to within its limit or isolate the aflected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.
b.
With the structuralintegrity of any ASME Code Class 2 component (s) not conforming to the abcve requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F.
c.
With the structuralintegrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structuralintegrity of the affected component (s) to within its limit or isolate the affected component (s) from service.
SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be ultrasonically examined over the volume from the inner bore of the flywheel to the circle of one half the outer radius once every 10 years and shall comply with regulatory positions C.4.b (3), (4), and (5) of Regulatory Guide 1.14, Revision 1, August 1975.
SOUTH TEXAS - UNITS 1 & 2 3/4 4-39 Unit 1 - Amendment No.106 t
Unit 2 - Amendment No. 93
I REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR VESSEL HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.11 Two reactor vessel head vent paths each consisting of two vent valves and a control valve powered from emergency busses shall be OPERABLE and closed.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.
With one of the above reactor vessel head vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve actuators of all the vent valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days, or, be in 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 two reactor vessel head vent paths inoperable, maintain the inoperable vent paths closed with power removed from the valve actua-tors of all the vent valves in the inoperable vent paths, and restore at least one of the vent paths 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 i
be in 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 />.
SURVEILLANCE REOUIREMENTS 4.4.11 Each reactor vessel head vent path shall be demonstrated OPERABLE at least once per 18 months by:
a.
Verifying all manual isolation valves in each vent path are locked in the open position, b.
Cycling each vent valve through at least one complete cycle of full travel from the control room, and c.
Verifying flow through the reactor vessel head vent paths during venting.
SOUTH TEXAS - UNITS 1 & 2 3/4 4-40
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