ML20244C307
| ML20244C307 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/06/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244C310 | List: |
| References | |
| NUDOCS 8906140207 | |
| Download: ML20244C307 (17) | |
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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 N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.163 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application 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 March 27,1986, a s supplemented Arpil 22 and December 27, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amen 6ed (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 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.
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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. DPR-57 is.hereby amended to read a follows:
(2) Technical Specifications The-Technical Specifications contained-in Appendices A and B, as revised through Amendment No.163, 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
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so& V David B. tiatthews, 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: June 6, 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. DPR-57 is hereby awMed to read as follows:
(2) Te:hnical Specifications The Technical Specifications contained in Appuidices A and 6, as revised through Amendment No.163, are heretg 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 REGULAT09Y COMMISSION Original Signed By:
David B. Matthews David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulaticn
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 6, 1989 0FFICIAL RECORD COPY
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' ATTACHMENT TO LICENSE AMENDMENT NO.163 l'
FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 -
~ 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 area of change.
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GEORGIA POWER COMPANY i
OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO.~50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.100 License No. NPF-5 1.
The Nuclear Regulatory Commission (the Commission) 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, Ogletherpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated March 27, 1986, as supplemented Arpil 22 and December 27, 1988, 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 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 I
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l
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 amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
.(2) Technical Specific,ations The Technical Specifications contained in Appendices A and B, as revised through Amendment No.100, 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 V
id B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 6, 1989 1
4 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.100, 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 COMilSSION Original Signed By:
David B. Matthews 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:
June 6,1989
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o ATTACHMENT TO' LICENSE AMENDMENT NO.10,0 yg FACILITY OPERATING LICENSE N0.jl.PF-5 m
DOCKET NO. 50-466 Replace the followina. pages.of the Appendix A-Technical' Specifications with thel enclosed pages. The revised pages are identified by amendment number and contain vertical' lines indicating the area of change.
Remove Page Insert Page 3/4 3-1 3/4'3 3/?'3-5 3/4 3-5 3/4 3 3/4 3-7' 3/4'3-8 3/4 3-8 l
l
4 3/4.3 INSTRUMENTATION
.3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION
. LIMITING CONDITION FOR OPERATION 3.3.1. As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.
Set points and interlocks are given in Table 2.2.1-1.
APPLICABILITY:
As,hown in. Table 3.3.1-1.
ACTION:
With the requirements for the minimum number'of OPERABLE channels not a.
satisfied for one trip system, place at least one inoperable. channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l
- b. 'With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one inoperable channel
'in at,least one. trip system
- in the tripped condition within I hour l
and take the ACTION required by Table 3.3.1-1.
The provisions of Specification 3.0.3 are not applicable in OPERA-c.
TIONAL CONDITION 5.
SURVEILLANCE REQUIREMENTS L
4.3.1.1 Each reacter protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTION TEST and CHANNEL CALIBRATION operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1.
4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.
4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months were N is the total number of redundant channels in a specific reactor trip function.
"If both channels are inoperable in one trip system, select at least one inoperable channel in that trip system to place in the tripped conditions, except when this could cause the Trip Function to occur.
HATCH - UNIT 2 3/4 3-1 Amendnent No. 100 L
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TABLE 3.3.1-1 (Continued) o
)
REACTOR PROTECTION SYSTEM INSTRUMENTATION
+
ACTION 9 -
In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
In OPERATIONAL CONDITION 3 or 4, lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
-l In OPERATIONAL CONDITION 5 suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within I hour.
l TABLE NOTATIONS a.
A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for l
required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel'in the same trip system is monitoring that parameter, b.
The " shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accordance with Specification 3.10.3.
c.
The IRM scrams are automatically bypassed when the reactor vessel mode switch is in the Run position and all APRM channels are OPERABLE and on scale.
d.
An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than 11 LPRM inputs to an APRM channel.
l e.
These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.
f.
This function is automatically bypassed when the reactor mode switch is in other than the Run position, g.
This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
h.
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.11.1 or 3.9.11.2.
1.
These functions are bypassed when turbine first stage pressure is s250*
psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.
J.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be deter:nined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.
- Initial setpoint. Final setpoint to be determined during startup testing.
HATCH - UNIT 2 3/4 3-5 Arsndment No.100
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