ML20008F830
| ML20008F830 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/07/1981 |
| 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 | |
| ML20008F831 | List: |
| References | |
| TAC 43820, DPR-57-A-084 NUDOCS 8105120119 | |
| Download: ML20008F830 (5) | |
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'j NUCLEAR REGULATORY COMMISSION E
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s GEORGIA POWER COMPANY OGLETHORPE POWER C_0RP0 RATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO.50-32T EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.1 APENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-57
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1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated April 28, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will opera'te in confonnity with the application, the provisions of the Act, and the rules and regulations of the
.l Commission; i
.j 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 i
conducted in compliance with the Commission's regulations;
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D.
The issuance of this 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 requirernents have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-571s i
hereby amended to read as follows:
(2) Technical Soecifications i
The Technical Specifications contained in Appendices A and B, as revised thrcugh Amendment No. 84, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hp '
t oh F. Stolz, Chief rating Reactors Branch #4 Divi,sion of Licensing At tachment:
Changes to the Technical Specifications Date of Issuance: May 7, 1981 O
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ATTACliMENT TO LICENSE AMENDMENT _ NO. _81 FACILITY OPERATING LICENSE NO. OPR-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 a vertical line indicating the area of change. The ovarleaf page is provided to maintain document completeness.
Remove Insert 3.6-11 3.6-11 I
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Table 4.6-1 In-Service Inspection Program INSPECTICS DURING TENTATIVE INSPEC-CATE-EXAMINATION EXAMINATION FIRST 5-YEAR TION DURING noRY ADEA C HOD INTERVAL 10-YEAR INTERVAL REACTOR VESSEL AND CLOSURE HEAD A
Longitudinal Voltmetric None 5% of the length of and circumfer-each circurferential sntial shell welds weld; 10% of the in core region length of each longitudinal weld B
Longitudine.1 Volumetric None 5% of the length of and circumfer-each circumferential ential welds in veld; 10% of the the vessel shell length of each and meridional longitudinal weld and circumfer-ential welds in vessel heads (other th'an those of Category A and C)
C Vessel-to-Volumetric 1/3 of the vessel-Cumulative 100% of flange and head-to-flange and 1/3 the vessel-to-flange to-flange circum-of the head-to-weld and of the head-ferential welds circelerential to-flange veld weld D
Primary nozzle-Volumetric Inspecf.!cn of five Inspection of all to-vessel welds noz:le-to-shell nozzle-to-shell and nozzle-to-weld and inner welds and inner vessel inside nozzle radii radius sections radiused section E-2 Vessel penetra-Visual 10% of the control Cumulative 25% of tions, including rod drive mechanism the control rod control rod drive and instru=entation drive mechanism and mechanism pene-penetrations will be of the instrumenta-trations and con-visually inspected tion penetrations trol rod housing for leakage will be visually mechanis= pressure inspected for beundary welds leakage F
Primary noz:les Visual and The dissimilar veld A13 of the dissimilar to safe. end surface and on five no::les metal welds on the welds volueetric vessel no::les will be examined
$1C sure studs Volumetric Cumulative 50%
Cumulative 100%
and nuts and Visual Amendment No. S$
3.6-11
Table 4.6-1 in-Service Inspection Program (Continued) e INSPECTION DURING TENTATIVE INSPEC-CATE-EXAMLNATION EXAMINATION FIRST 5-YEAR tim TRING CORY AREA METHOD INTERVAL 10-YEAR INTERVAL FIACTOR VESSEL AND CLOSURE HEAD G-1 Ligaments be-Volumetric 1/3 of the vessel-Cumulative 100% of.
tween threaded co-flange bolt the vessel flange stud holes ligaments will be bolt ligamenta examined G-1 Closure washers, Visual Cumulative 50%
Cumulative 100%
bushings H
Integrally Volumetric None 10% of the total valded vessel veld length external supports
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I-1 Closure head Volumetric None The closure he'ad is l
cladding not clad. During the 10-year period, at least 6 points will be measured for thickness to deter-mine the corrosion race.
I-1 Vessel clad-Visual None 100% of selected l
ing areas at or near
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end of interval N
Interior sur-Vis t=1 A critical examina-The inspections l
faces and tion vill be made of made at the 4th interaals and the interior surface refueling cycle l
integrally made available by will be repeated welded inter-normal refueling at the 7th and 10th nal supports operations at the 1st refueling cycle refueling cycle.
This will be repeated at the 4th refueling l
cycle with the amount of the inspection be-ing dependent upon re-suits of the 1st in-spection and that made on other boiling-water systa=s 3.6-12
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