ML20063B539
| ML20063B539 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/10/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20063B540 | List: |
| References | |
| TAC 47443, DPR-57-A-089 NUDOCS 8208250504 | |
| Download: ML20063B539 (4) | |
Text
_
[vac w
UNITED STATES
[\\
' \\'i NUCLEAR REGULATORY COMMISSION w AsHINGTON, D. C. 20555 l
%...../
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT. UN T NO.1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.89 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Georgia Power Company, et al., (the A.
licensee) dated December 2,1981, 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;
The facility will operate in confomity with the application, B.
the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized C.
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; The issuance of this amendment will not be inimical to the common D.
defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR'Part E.
51 of the Commission's regulations and all applicable requirements -
have been satisfied.
Accordingly, the license is amended by changes to the Technical Spec 2.
ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License Nc. DPR-57 is
~
hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 89, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8208250504 820810~
PDR ADOCK 05000321 P
ATTACHMENT TO LICENSE AMENDMENT NO. fig FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix "A"-Technical Specifications The revised pages are identified by Amendment with the enclosed pages.
number and contain a vertical line indicating the area of change.
l
-Insert Remove 3.7-26 3,7_gg 3.7-27 3.7-27 i
ge
~
^
Table 3.7-4 (Concluded)
Primary Containment Testable Isolation Valves Penetration Notes valve Desianation Runcer X-220 P33-F006 & F014 (1) *(2) (4) (5) (9)
X-220 T48-F318 & F326 X-220 T48-F332A & F333A X-220 T48-F3328 & F3338 T48-F338 & F339 X'220 X-218A G51-F002 (1) (2) (4) (5) (10)
X-218A G51-0001 (1) (2) (4) (5) (13)
X-218A G51-F0ll (1) (2) (4) (5) (10)
X-218A G51-F012 (1) (2) (4) (5) (10) i i
l l
l l
1 l
3.7-26 Argnda nt No. M, R, 89 j
"-"n-w
O
',\\
Notes For Tables 3.7-2 through 3.7-4 (1)
Test duration for all valves and penetrations listed will generally exceed one hour.
(2)
Test pressures are at least 59 psig for all valv'es,and penetrations except MSIV's which are tested at 28 psig.
(3)
MSIV acceptable leakage limit is 11.5 scfh/ valve of air.
(4)
The total acceptable leakage for all falves and penetrations other than the MSIV's is 0.6 La-(5)
Local leak tests on all testable isolation valves shall be performed each major refueling shutdown but in no case at intervals greater than 2 years.
(6)
Local leak tests on all testable penetrations.shall be performed each major refueling shutdown but in no case at intervals greater than 2 years.
(7)
The personnel air lock shall be tested at intervals not to exceed 6 months.
(8)
The personnel air lock door seals are tested at 10 psig after each opening.
(9)
Identifies isolation valves that are tested by applying pressure between the inboard and outboard isolation valves.
Inboard valve is not tested in the direction required for isolation but will have equivalent or more conservative leakage results.
(10) Identifies isolation valves that are tested by applying pressure between the isolation valve and a manually operated valve such that the isolation valve is tested in the direction required for isolation.
(11) Identifies isolation valves that are tested by applying pressure the isolation valves and other system valves.
Isolation
. tsetween valves not tested in the direction required for isolation will have equivalent or more conservative results.
(12) The RFR system remains water filled post-LOCA.
Isolation valves are tested with water.
(13) Identifies blind flange that is tested by applying pressure between flange and a manually operated valve such.that the flange is the tested in the direction required for isolation.
3.7-27 Amendment No. E,Kr, 89
-