ML20215N224
| ML20215N224 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/30/1986 |
| 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 | |
| ML20215N226 | List: |
| References | |
| DPR-57-A-131, TAC 10710, TAC 64785 NUDOCS 8611050041 | |
| Download: ML20215N224 (7) | |
Text
a UNITED STATES f
7 NUCLEAR REGULATORY COMMISSION
(
WASHINGTON, D. C. 20555
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 131 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated March 5, 1979 as supplemented February 7, 1984, 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 safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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 51 of the Commission's regulations dnd 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:
8611050041 861030 DR ADOCK 05000321 PDR
)
, o Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.131, 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.
FOR THE NUCLEAR REGULATO Y COMMISSION j /"
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 30, 1986
ATTACHMENT TO LICENSE AMENDMENT NO.131 hACILITYOPERATINGLICENSENO.OPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised p' ages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3.7-5 3.7-5 3.7-6 3.7-6 3.7-6a 3.7-6a 3.7-15 3.7-15 i
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I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A.2.b(2)
(c) The acceptance criteria j
for subsequent peak pressure tests shall require the new L,,
j not to exceed La-(d) The allowable operational leak rate, L,,, which shall be met prior to resumption of power operation following a test (either as measured or following repairs and retest) shall not exceed 0.75 L,.
c.
Corrective Action for Type A Tests If leak repairs are necessary to meet the allowable operational sleak rate, the integrated leak rate test need not be repeated t
provided local leakage measure-ments are conducted and the leak rate differences prior to and after repairs, when corrected to the test pressure and deducted. from the integrated leak rate measurements, yield a leak rate value not in excess 4
of the allowable operational leak rate.
d.
Frecuency for Type A Tests Af ter the initial preoperational leak ra'te test, two integrated leak rate tests shall be per-formed at approximately equal intervals between the major shutdowns for inservice inspection conducted at ten-year intervals.
i In addition, an integrated leak a
rate test shall be performed at the end of the ten-year interval, which may coincide with the inservice inspection shutdown period.
3 e.
Type B Test - Leak Tests of Pene-trations with Seals and Bellows (Tables 3.7-2 and 3.7-3) 1 Type B tests shall be performed under. the program established.
in Appendix J 'of 10CFR Part 50.
Amendment No. 131 3.7-5,
~
i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i
4."7.A.2.e. Type B Test
-Leak Tests of Pena-trations with Seals and Bellows (continued)(Jables.3.7-2 and 3.7-3)
(1) Primary containment components which seal or penetrate the pressure containing boundary of the containment shall be tested at a pressure not less than P These components shall$a. tested at each major refueling shutdown or at intervals not to exceed two years.
(2) (a)
-The personnel air lock shall be tested at in-tervals not to exceed I
six months at P by pres-surizing the com,partment between the two air lock doors.
)
During intervals of door use when containment integrity is required, the door seals shall be tested at 10 psig af ter i
each opening.
l (b)
Personnel air lock leakage shall not exceed 0.05 L,.
- f. ' Type C Tests-Local Leak Tests
' of Containment Isolation Valves (Tables.3.7-1 and.3.7-4) c.r, Type C tests shall be performed under the pro ~ ram established g
1 in Appendix J of 10CFR Part 50.
Containment isolation valves (except for main steam line iso-lation valves) shall be tested at a pressure not less than Pa.
Type C tests shall be performed at each major refueling shutdown or at intervals not to exceed two years.
1 t
Amendment No. 131
'3.7-6
LIMITIhG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS g.
Accentance Criteris for Type B and Tyne C Tests The combined leakage rate of components subject to Type B and C tests shall be determined under the program established in Appendix J of 10CFR Part 50 and shall not exceed 0.6 L,.
h.
Main Steam Line Isolation Valves
.The main steam line isola-tion valves shall be tested at a pressure of 1/2 Pa for leakage at least once per operating cycle.
If a total leak rate of 11.5 scf per hour for any one main steam line isolation valve is
-exceeded, repairs and retest shall be performed to correct this condition.
t.*r s
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t Amendment No! 131
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LIMITING CONDITIONS FOR OPERATION SURUEILLANCE REQUIREMENTS 4
i 4.7.E.
References 2.
" Testing Criteria for Integrated Leak Rate Testing of Primary Containment Structures for Nuclear Power Plants" Topical Report BN-TOP-1, Revision 1, Bechtel Corp.
Issued November 1, 1972.
1 d
a, i
e Amendment No. 32, 131 3.7-15
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