ML20235K198
| ML20235K198 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/07/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235K201 | List: |
| References | |
| TAC-64778, NUDOCS 8707160200 | |
| Download: ML20235K198 (4) | |
Text
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UNITED STATES g,
y ig NUCLEAR REGULATORY COMM!SSION s
'j WASHINGTON, D. C. 20555
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment $10. 142 License No. DPR-57 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, l
Unit 1 (the facility) Facility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, l
(the licensee) dated Fay 8, 1987, complies with the standards and l
requirements of the Atomic Energy Act of 1954, as amended (the Actl, and the Commission's rules and regulations set forth in 10 CFR i
Chapter I;
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B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 amendment will not be inimical to the comon 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.
8707160200 070707 DR ADOCK 0500 1
1 2.
Accordingly, the license is amended by changes to the Technicc1 Speciff-cations as indicated in the attachment to this license amendment, and i
paragraph 2.C.(2) of Facility Operating License No, DPR 57 is hereby amended to read as follows:
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(2)
Technical Specifications
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The Technical Specifications contained in Appendices A and B, as revised through Amendment No.142, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance, l
FOR THE NUCLEAR REGULATORY COMMISSION
- 1 B. J. Youngblood, Director l
Project Directorate II-3 j
Division of Reactor Projects-I/II
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Attachment:
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Changes to the Technical i
Specifications Date of Issuance: July 7, 1987
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ATTACHMENT TO LICENSE AMENDMENT NO.142 3
l FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
Revised Page i
1 3.4 l i
1 l
I 4
1
4 LIMITING CONDITIONS FOR OPERA 110N SURVEILLANCE REQUIREMENTS 4.4.A.2.
Each Operatino Cycle (Continued) c.
vessel. This test checks the explosive charge, proper opera -
tion of the associated valves and selected pump operability.
The replacement charge to be l
installed will be selected from a manufactured batch which has been tested.
d.
Both loops including both explo-sive valves should be tested in j
the course of two operating cycles.
1 e.
Prior to startup, verify (by analysis) i that the sodium pentaborate enrichment is within prescribed limits.
3.4.B.
Operating with Inoperable B.
Surveillance with Inoperable Components Components If one Standby Liquid Control When a component is found to be i
redundant component is inoperable inoperable, its redundant com-1 l
the reactor may remain in operation ponent shall be demonstrated to for a period not to exceed seven be operable immediately and daily (7) days provided the redundant thereaf ter until the inoperable component is operable.
comporent is repaired. Continuity-of the explosive charge is considered a demonstration of operability.
C.
Sodium pentaborate Solution C.
Sodium pentaborate Solution At all times when the Standby The folicwing tests shall be Liquid Control System is re-performed to verify the avail-quired to be operable tre bility of the liquid control following conditions shall be solution:
met:
1.
Volume 1.
Volume The volume of the liquid Check the standby liquid control solution in the control tank volume at least liquid control tank shall once per day.
be maintained as required in Figure 3.4-1, 2.
Concentration 2.
Concentration The concentration of the Check the concentration of the liquid control tank shall liquid in the standby liquid be maintained as required control tank by chemical in Figure 3.4-1.
analysis:
HATCH - UNIT 1 3.4-2 Amendment No. 142
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