ML19332E925
| ML19332E925 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/04/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332E926 | List: |
| References | |
| NUDOCS 8912130162 | |
| Download: ML19332E925 (10) | |
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UNITED STATES 2
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NUCLEAR RECULATORY COMMISSION p
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321-t EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.167 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The app (lication for amendment to the Edwin I. Hatch Nuclear Plant, Uni t 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 October 20, 1989, complies with l
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 conformity with the application, the i
provisions of the Act, and the rules and regulations of the l
Comission; 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 l
in compliar.ce 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 l'
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.
8912130162 891204 ADOCK0500ggi DR
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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 as folicws:
Technical Specifications The Technical Specifications containad in Appendices A and B, as revised through Amendment No.167, 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 David B. Matthews, Dlirector V
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gg Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Cate of Issuance:
December 4, 1989 i
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ATTACHMENT TO LICENSE AMENDMENT NO.167
- FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Page Insert Page 3.2-45 3.2-45 i
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-4 Table is.2-9 O
y CllLCK AND CAtIBRAllON HINIMUM IRfQUINCY SOR $NSIRUMENTAllON Will Cll INiil Alf S ftlCIRCULAIION l' UMP T R I P c-Ite t'.
I n s t r aemen t Clicek '
f rist riement f annct ional Test ins t risment Ca l ib ra t ion a'
No.
I ris t rumen t Z 191_
Minimum f regeency Minimum I'requency Minimum Frequency
~
l Heactor Vessel Wa ter l evel Once/ day Once/operat ing cycle Once/ operating cycle (AlWS RPI)'**
2 fteactor Pressure None (AIWS RPI)
Once/ opera ting cycle Once/ operating cycle 3
IOC - RPI Irip a)
Initiating iogic None Once/montto None b) Breakers None once/operatirig cycle None c) Response Time Nnne None RPI logic + Dreakers
Once/ operating cycle
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m Notes for table is.?-9 e
M (a) the coltimn entitled "Nef.
No." is only ior convenience so that a orie-to-one rela tionship can be established betweets items en table 3.2-9 and items in lable t.?-9 i
(b) An AlWS recirculation pump trip logic system functional test shall he performed once per operating cycle.
(c) the IOC-ItPI System flesponse lime shall be that time i n t e rva l from initial signal generat ion by the associated tear tsine stop valve limat switch or f r om when time turbific control valve hydraulic control oil pressure drops below the presstare switch setroint to complete suppression of' the electric are between the f'ully-open contacts ol' tise reci r caslat ion pasmp ci rcuit tarcaker.
Ilie response time may be measured by any se ries of' sequent ia l, overlapping, or total steps seech that the crit i re response time is mea sis t ed. Each test shall iniclude at least the logic of one type of channel i npt s t. turbine control valve f~a s t closure or tur bine stop va lve closter e, sescle that both types of charinel inputs are tested
- 3 at least once per % months.
Ihe loc-HPI System itesponse t ime acceptance cri teria associated wi th g
turbine stop valve closure shall be 5 155 millisecontis; the LOC-StP1 System Response Time acceptance o
criteria associated wath the turbine control va lve fast. clostere sha l l be 5 175 milliseconds.
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION L
MUNICIPAL ELECTAIC AUTHORITY CF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.103 License No. NPF-5 f
1.
The Nuclear Regulatory Comission (the Comission) has found that:
i 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 October 20, 1989. complies with the standards and seqt.Vements of the Atomic higy Avt tf +i934, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; L
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 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.
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-2 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 i
amended to read as follows:
_ Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103, are hereby incorporated in the license. The-licensee shall o the Technical Specifications. perate the facility in accordance with 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 L
David B. Matthews, Direc s
Project Directorate 11-3 i
Division of Reactor Projects-1/II*.
)
- Office of Nuclear Reactor Regulation
Attachment:
ChanSes to the Technical
- Specifications Cate of Issuance:
December 4, 1989
r
. 4
-9 i
ATTACHMENT TO LICENSE AMENDMENT NO.103 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the followin the enclosed pages. g pages of the Appendix A Technical Specifications with-The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages 1-2a 1-2a 3/4 3-73 3/4 3-73*
3/4 3-74 3/4 3-74
-*0verleaf page included to maintain document completeness.
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1.0 DEFINITIONS'(Continued) f g
.EM{RGENCYCORECOOLINGSYSTEM(ECCS)RESPONSETIME i
The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its
}
ECCS actuation setpoint at the channel sensor until the ECCS eouipment is capable of performing its safety function (i.e.,
ths valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
'END-OF-CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) SYSTEM RlSPONSE TIME The END-OF-CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) SYSTEM RESPONSE TIME shall be that time interval from initial signal generation by the associated turbine stop valve limit switch or from when the turbine control valve hydraulic control oil pressure drops below the pressure switch setpoint to complete suppression of the
' electric are between the fully-open contacts of the recirculation pump circuit breaker.
The response +,ime may be measured by any series of sequential, overlapping, or total steps, such that the entire response time is measured.
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