ML20235L716
| ML20235L716 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/14/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235L721 | List: |
| References | |
| TAC-56049, TAC-59542, NUDOCS 8707160798 | |
| Download: ML20235L716 (14) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _.
8(Y UNITED STATES NUCLEAR REGULATORY COMMISSION o
e 5
e,E WASH WG TON, D. C. 20555 l
\\
/
1 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION 3
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA l
CITYOFDklTON, GEORGIA i
DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No '143 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated August 20, 1985, and January 7, 1986, and supplemented June 26, 1986, comply 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 v
Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission'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 amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
6707iNMS h
PDR i
4 '
2.
Accordingly, the license is amended by changes to the Technical Specif1-cations 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:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 143, are hereby incorporated in the license. The licensee shall operate the facility in accordance with I
the Technical Specifications.
I 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 B. J. Youngblood, Director Project Directorate II-3 l
Division of Reactor Projects-I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 14, 1987 l
l
k ATTACHMENT TO LICENSE AMENDMENT N0.143 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 i
Replace the following pages of the Appendix A Technical Specifications with i
the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert Page Page 3.7-16 3.7-16 3.7-20 3.7-20 3.2-3 3.2-3 3.2-25 3.2-25
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Notes to Table 3.7-1 (Concluded)
(f) Requires a Group 2 signal or a Primary Containment high radiation isolation signal.
For all entries in Table 3.7-1 where the number of isolation v'alves is equal to one outside containment and none inside containment the valve is in a series path with at least one other containment isolated valve in the Table.
For example, T48-F118 is in a series path with T48-F104, thus providing two in series power operated containment isolation valves.
m l
s.
3.7-20 Amendment No. 143
p i
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UNITED STATES
[
o.,j NUCLEAR REGULATORY COMMISSION 5
- E WASHINGTON, D. C. 20555 s.,
)
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET N0. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
78 License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, 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 September 5, 1984, as supplemented June 26, 1986, 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 operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
' 2.
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:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 78, 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 c'
B. J. Youngblood, Director Project Directorate II-3 Division of Reactor Projects-I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 14, 1987
1 ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert Page Page 3/4 3-11 3/4 3-11 3/4 3-15 3/4 3-15 3/4 3-16 3/4 3-16 3/4 3-21 3/4 3-21 e
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' TABLE 3.3.2-1 (Contirued)
ISOIATION ACnJATION INSTRUMENTATION ACTION ACTION 20 - Be in at least ICT SH'JIDOW within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CDLD ShvIDOW within the next 3C tm r s.
ACTION 21 - Be in at least STARTUP with the' main steam line isolation yalves closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least ICT SIUIDOW within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in!CDID SFUID3WN within the next 30 bcurs.
ACTION 22 - Be in at least STARTUP within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ACTION 23 - Be in at least STARTUP with tre Group 1 isolation valves closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or in at least ICT SIUIDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 24 - Establish SECONDARY CDNIADNENT INTB3RI'IY with the standby gas treatment system operating within one ra r.
ACTION 25 - Isolate the reactor water cleanJp system.
ACTICU 26 - Close the affected system isolation valves and declare tie affected system inoperable.
l l
ACTION 27 - Verify power availability to the tus at least once per 12 hoars or close the affected system isolation valves ard de:lare the affected system inoperable.
'~
~
ACTION 28 - Close the stutdown cooling supply and reactor vessel head spray isolation valves
~
unless reactor steam dme pressure $ 145 psig.
ACTION 29 - Eitler close the affected isolation valves within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in tot stutdown within tre next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold stutdown within tie next 30 tars.
N7TES 4
Actuates operation of tre main control room environmental control system in the pressurization mode of operation.
Actuates tie standby gas treatment system.
hten handling irradiated fuel in the secondary containment, See Specification 3.6.3, Table 3.6.3-1 for valves in each valve groJp.
l a.
{
b.
A channel may be placed in an inoperable status for up to 2 tars for reo: ired surveillance without placing tie trip system in the tripped condition provided at least one otter OPERABLE channel in tie same trip system is monitorirg that parameter, With a design providing only one channel per trip system, an inoperable crannel need not c.
be placed in the tripped cordition where this would caJse the Trip Dnction to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 rars ot tie ACTION regaired by Table 3.3.2-1 for that Trip Nnction shall be taken, d.
Trips the mechanical vacuum pamps.
e.
A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.
f.
May be bypassed with all turbine stop valtes closed.
g.
Closes only RG outlet isolation valve 2G31-F004, b.
Alarm only.
- i. Adjustable up to 60 mirutes.
- j. Isolates contairrnent surge and vent valves.
l HATCH - UNIT 2 3/4 3-15 Amendment No. 78
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