ML20199J861
| ML20199J861 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/26/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20199J867 | List: |
| References | |
| DPR-57-A-128, TAC 59308 NUDOCS 8607080453 | |
| Download: ML20199J861 (6) | |
Text
k UNITED STATES
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p, NUCLEAR REGULATORY COMMISSION C
j WASHINGTON, D. C. 20S55
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GEORGIA POWER CCMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET N0. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 128 License No. DPR-57 1.
The Nuclear Regulatory Comission (iiie Comission) iras found that:
c A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated July 26, 1985, complies with the standards
.l and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth q
in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the i
Comission; y
t C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and i
safety of the public, and (ii) that such activities will bd conducted in compliance with the Comission's regulations; 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 53 of the Comission's regulations and all applicable requirements have been satisfied.
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. DPR-57 is hereby amended to read as follows:
8607080453 860626 DR ADOCK 05000321 PDR r
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.128, 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 COMMISSION Daniel R. Mull r, irector BWR Project Directorate.#2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of 2:suence:
June 26, 1986 j
ATTACHMENT TO LICENSE AMENDMENT N0 128 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET N0. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment numbers and contain vertical lines indicating the area of change.
Remove Insert 5.0-2 5.0-2 5.0-3 6-20 6-20 l
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3.
Fuel Storage Fuel in the Spent Fuel Pool shall have a maximum fuel loading of 15.2 grams of Uranium-235 per axial centimeter.
J 5.0.F.
Seismic Design
,l The reactor building and all engineered safeguard systems are designed for
,j the design basis earthquake with a horizontal ground acceleration of 0.15 g.
1]
The operating basis earthquake has a horizontal ground acceleration of a
0.08 g.
A i
G.
Component Cyclic or Transient Limit i
The Reacor Pressure Vessel is designed for and shall be maintained within the cyclic or transient liaf.to of Table 5.0.G-1.
i j
H.
References 1.
FSAR Section 4.2, Reactor Vessel and Appurtenances Mechanical Design 2.
FSAR Section 5.2, Primary containment System 3.
FSAR Section 5.3, Secondary Contairment System
,.4 ij 4.
FSAR Section 12.4.4, Governing Code s and Regulations 5.
FSAR Section 10.3, Spent Fuel. Storz ge
.d 6.
FSAR Section 10.2, New Fuel Storage i
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,' i Amendment No. 128,
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TABIE 5.0.G-1 m
g MP0NENT CYCLIC OR TRANSIENT LIMITS l
o 8
mo CYCLIC OR DESIGN CYCLE I
o
,o COMPONENT TRANSIENT LIMIT OR TRANSIENT
-ro A.
Reactor Pressure Vessel (Normal, Upset anl Testing Conditions)
L20 heatup and cooldown Cold Shutdown to 100% Rated Power 10,000 Reduction to 75% Nated Power 2,000 Reduction to 50% Rated Pcwer 80 Loss of feedwriter hester 195 Scram from 100% Rated Power 2
Improper start of cold recirculation loop sn O
I(,a e
9 I
f odNISTRATIVE CCNTEOL t
ECORD RETENTION (Ccntinued)
Reccrcs of raciation exposure for all incivicuals entering raciaticn c.
control areas, l
d.
Reccrcs of gaseous and licuid radicactive material releasec to tre i
environs.
e.
Reccrds of transient or operational cycles for those unit correonen:s identified in Table 5.0.G-1 f.
Recoros of reactor tests and experiments.
g.
Reccres of training and cualification for current members of the uni:
staff.
~
.h.
Recoros of in-service inspections performec pursuant to these Technical Specifications.
1.
Recercs of Quality Assurance activities recuirec cy the CA Manual.
j.
Recer::s of reviews performed for changes mace to prececures or eculoment or reviews of tests ano experiments pursuant to 10 CFR 50.59.
J k.
Reccrcs of meetings of the PRS and SRS.
1.
Reccrcs for Environmental Qualification whien are covered uncer the i
previsions of paragraph 6.15.
m.
Reccrcs of analyses required by f.he Radiclogical Environmental Honitoring Program, i
n.
Records of the service lives of all safety-related hydraulic and mechanical snutters including the date at which the service life i
connances and associated insta13ation and maintenance records.
6.11 RADIATICN PROTECTICH PROGRAM Procedures fcr perscnnel radiation protection shall be preparec consistent with l
the requirements of 10' CFR Part 20 ar.d shall be approved maintained anc a mered to for all operations involving personnel radiation exp,osure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control deviceE or " alarm signal" reouired by paragrapn 20.2C3(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 arem/hr but less than 1000 mrem /hr shall be barricaced and conspicuously posted as a high radiation area and entrance thereto shall be controlled by reouiring issuance of a Radiation Work Permit *.
Any individual or grow of individuals permitted
- Neaitn Pnysics personnel, or personnel escorted by Health Physics personnel in accordance with approved emergency procecures, shall be exengt from the RWP issuance requirement during the performance of their assigned radiation i'
protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
MATCH LNIT 1 6-20 Amendment No.
gf, p.
10/H/00. M.
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