ML20153F990
| ML20153F990 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/02/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20153F973 | List: |
| References | |
| TAC-66895, NUDOCS 8805110110 | |
| Download: ML20153F990 (4) | |
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o UNITED STATES
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NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D. C. 20555
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t AEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF OFORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENLVENT TO FACILITY OPERATING LICENSE Amendment No.153 License No. OPR-57 1.
The Nuclear Reculatory Commission (the Commission) has found that:
A.
The application for amentrent to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Tacility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corcoration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated December ?l, 1987, complies with the standards and requirements of the Atomic Eneroy Act. of 1954, as amended (the Act), and the Commission's rules and regu-lations set forth in 10 CFR Chapter It B.
The facility will operate in confornity with the application, the provisions of the Act, and the rules and regulatiers of the Cornission; 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 ce conducted in compliance with the Commicsion's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendrent 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 1
of the Commission's regulations and all applicable requirements have been satisfied.
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PDR ADOCK 05000321 P
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2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph ?.C.(2) o# Facility Operating License No. DPR-57 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.153, 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.
FOR THE NUCLEAR REGULATORY CCFFISSION David B.
Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 2, 1988 I
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ATTACHMENT T01.ICENSE AMENDMENT NO.153 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the followin? page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identi'ied by amendment number and contains a vertical line indicating the area of change.
Remove Insert Page lage 3.7-14 3.7-14
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tl0lflNG CONDITIONS 10. ' OPERATION SURVElttAOCE REQUIAth(NTS R
4.7 D.I.
10rveillange of Operable yelves (Conunued) b.
At least once per operating cycle the reacto.oolant system instrument line excess flow check valves shall he tested for proper operatior.
c.
At least once per quarter.
l all normally open, power-operated isolation valves (except for the r.ain steam line power-operated isolation valves) shall be fully closed and reopened.
d.
The isolation time of each main steam line isolation valve, shall be determined to be within its limit when tested.
pursuant to Specification 4.6.K.
e.
At least once oer week the main steam 1.ne power-oper-ated isolation valves shall be exercised one at a time by partial closure and sub-sequent reopening.
3.7,0.2.
Operation with Inocerable Valves
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Surveillance of Lines with an Inocerable valve In the event any isolation valve Whenever an isolation valve specified in Table 3.1-1 becomes listed in Table 3.1-1 is inoperable, reactor power operation inoperable the posillon of at may continue *.rovided at least one least one other isolation valve isolation velve in each line having in each line having an inoperable an inoperable valve is in the mode isolation valve shall be verified corresponding to the isolated con-to be in its isolated position dition.
daily.
.1.
Shutdown Reauirements if Specification 3.7.0.1. and 3.7.0.2.
cannot be met, an orderly shutdown shall be initiated and the reactor shall be p; aced in the Cold Shut-down Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
HATCH - UNIT I 3.7-14
/unendment No.153 4
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