ML20245J090
| ML20245J090 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/28/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245J092 | List: |
| References | |
| TAC-71999, NUDOCS 8905030632 | |
| Download: ML20245J090 (5) | |
Text
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'o UNITED STATES 8:
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~,'n NUCLEAR REGULATORY COMMISSION g
- E WASHINGTON, D. C. 20555
\\.....l GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET N0. 50-366 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 99 License No. NPF-5 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The app (lication for amendment to the Edwin I. Hatch Nuclear Plant, A.
Unit 2 the facility) Facility Operating License No. NPF-5 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated,lanuary 23, 1989, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and j
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 common defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license emendment, and i
paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, 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.
F R THE NUCLEAR REGULATORY. COMMISSION
/ Avid B. Matthews, Director U
Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation 1
Attachment:
Changes to the-Technical Specifications Date of Issuance:
April 28,1989
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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and
. paragraph. 2.C.(2) of. Facility Operating License No. NPF-5 is hereby
' amended to read as.follows:
l-(2)' ' Technical Specifications
.The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
99, 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
/s David B. Matthews, Director Project. Directorate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
'Date of Issuance: April 28,1989 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATIllG LICENSE 110. NPF-5
,D_0CKET N0. 50-366
- Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove Page Insert Page 3/4 6-5 3/4 6-5 4 '
m CONTAINMENT SYSTEMS 5 SURVEILLANCE REQUIREMENTS (Continued) b..
If any periodic Type A test fails to meet 'either.75 La. or
.75 L, the test schedule for subsequent Type A te:;ts shall be t
reviewed and approved by the Commissior!.
If two consecutive Type A tests fail to meet either.75 La or.75 L, a Type A t
test shall be performed at least every 18 months until two consecutive Type A tests meet either.75 La or.75 L, at t
which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the difference between th'e' supplemental data and the Type A test data is within 0.25 La or 0.25 L.
t 2.
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental tast, and 3.
Requires the quantity of gas injected into the contain-ment or bled from the containment during the supplemental l
test,to be equivalent to at least 25 percent of the l
. total ' measured leakage at Pa, 57.'5' psig, ob P, 28.8 i
psig.
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d.
Type B and 'C tests
- shall be conducted at Pa, 57.5 psig,
.j during each reactor shutdown for refueling but in no case j
at intervals greater than 2 years except for tests involving:
1.
Air locks, which shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3, and 2.
Main steam line isolation valves, which shall be leak tested at 28.8 psig.
e.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be per-formed to select a balanced integrated leakage measurement system.
f.
The provisions of Specification 4.0.2 are not applicable.
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- All Type B and Type C Leakage Tests (i.e., Local Leak Rate Tests) that fail (i.e., test leakage is such that an LER would be required)'duririg an outage shall be reported according to 10 CFR 50.73 by one 30-day written report that is due within 30 days of the first leakage test failure in the outage. All 1
other leakage test failures discovered during the outage will be reported in a revision to the -original report due within 30 days after the end of the
- outage, HATCH - UNIT 2 3/4 6-5 Amendment No. 99
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