ML20042F927
| ML20042F927 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/27/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20042F928 | List: |
| References | |
| NUDOCS 9005100177 | |
| Download: ML20042F927 (5) | |
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, UNITED STATES j'*
. J' T t, NUCLEAR REGULATORY COMMISSION'
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WASHING TON; D. C. 20555 f
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA EDWIN 1.
HATCH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE N
Amendment No.169 s
License No. DPR-57 1.
The Nuclear Regulatory Commission (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 January 15, 1990, 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; L
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,
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E.
The Issuante of this amendment is in accordance with 1
10 CFR Part 51 of the Commission's regulations and all j
applicable requirements have been satisfied.
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9005100177 900427 PDR ADOCK 05000321 p
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-S7 is.hereby amended-to read:
Technical Specifications The Technical Specifications contained in Appen ices A and B,-as revised through Amendment No.169, are hereby incorporated in the license.. The licensee shall. operate the facility in accordance with the Technical Specifications.
3.
This license amendment is ef f ective as of its date of issuance-and shall be implemented within 60 days of issuance.
i F O R T H E N'U C L E A R R E G U L A T O R Y C O M M I S S I O N
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Q -Li David B.
Matthews, Director Project Directorate II-3 Division of Reactor. Projects-!/II Of fice of Nuclear Reactor Regulation' Attachment Changes =to the Technical Specifications
-i Date 'of Issuance:. April 27, 1990 m.
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ATTACHMENT TO LICENSE AMENDt1ENT NO. ?.69 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET fJU. 50-321 Replace the following pages of the Appendix A
Tecnnical-Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove pace Insert Pace 3.2-20 3.2-20 3.2-4S 3.2-45 l
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Table'3.2-9
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e-INSTRUMENTAff0N WHICH INITIATES RECIRCULATION PUMP TRIP C
s-Perf instrisment Trip Required Trip Setting Remarks Q No.
Condition
. Opc ra bl e
{a)
Nomenc Ia ture ChanneIs per Trip System 1.
Reactor Vessel Water. Level Low (Level 2) 28*'
2-ts7 inches H 0 Power must be reduced and.the l
mode switch placed in a mode other than the RUN Mode.
2 *'
51095 psig Power must be reduced and the l
8 2.
Reactor Pressure High
( ATWS RPT) mode switch placed in a modo other than the RUM Mode.
3.
1.
Turbine Stop 2'**
1 Stop valve Trips recirculation pumps on valve Closure 590% Open turbine control valve fast 2.
Turbine Control 2.
Control Valve closure or stop valve closure Valve rast Hyd raul ic when reactor i s > 30%.* *
- Closure Press Trip Point
- ' The column entitled "Ref. No."
is only for convenience so that a one-to-one relationship can be established between items in Table 3.2-9 and items in Table is.2-9.
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- Whenever the reactor is in the RUN Mode, there shall be two operable trip systems for each parameter for
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7 each operating reci rcula t ion pttmp.
If the required number or operable channels cannot be met for one of the ro t rip systents, place the inoperable channel in the tripped condition or take the indicated action within its days.
O f r the required ntember or operable channels cannot be met for both trip systems, take the indicated action within 1 hots r.
- Anticipated T ransients Without. Scram - Recirculation Pump Trip End or Cycle - Recirculation Pump Trip
Each EOC - RPT system will trip if 2-out-of-2 fast closure signals or 2-out-of-2 stop valve signals are received.
The requirement l'o r t hese c ha nne l s a pp l i es f rom EOC-2OOO MWD / t to EOC.
The RPT system may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to provide the required monthly surveillance. tr one EOC-RPT system is inoperable for longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or ir both EOC-RPT systems are simultaneously inoperable, an orderly power reduction will be immediately initiated and reactor power will be <30% within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
g M ' Either or these two ATWS-RPT systens can trip both recirculation pumps.
Each ATWS-RPT system will trip if 2-eut-or-2 3
reactor low water level signals or 2-out-or-2 reactor high pressure signals are received.
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Oc Table 4.2-9 9
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~ CHECK AND CAllBRATION MINIMUM FREQUENCY FOR INSTRUMENTATION WillCII INITIATES RECIRCULATION PUMP TRIP
-4 Ref.
Instrument Check Instrument functional Test Instrument Calibration No.
Instrument.
Minimum frequency Minimum frequency Minimum frequency w
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1 Reactor Vessel Wa ter Level Once/ shift Once/ month (ATWS'RPT)'*'
Once/ ope mting cycle l
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Reactor Pressure Once/ shift Once/ month (ATWS RPT)
Once/ ope ra t ing cyc le l
3 EOC - RPT Trip e) initinting Logic None Once/ month None.
b) Breal e rs None (j
Once/ operating cycle None c) Response Time-None None RPT log ics + B rea ke r s,,,
Once/ operating cycle i
ta Notes for Table la.2-9 7 (a) The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be g
established between items in Talete 3.2-9 and items in Table 4.2-9
~ (b) An ATWS recirculation ptemp trip ingic system fitnctlonal test shali be performed once per operating cycle.
(c) the IOC-RPI System Resposese lime steall lie that t e me? s et t e rva l from initsal s i gesa l gerieratiers by the associated tear bene stop vs 3ve t ime t swi tcle or f rom wiscre Line turbane control valve hydratelic control oil pressure drops below tlw. pressiere switcle settpoinst tes complete sosperession af the electric arc between the fasily-open contacts of the r ec i rcen t a t ions peamp. c e rcisi t breaker, llee resportse time may be measured by any series of settuential. overlappirig, or total steps sese le that (fee crit i re resportse time is mea sie red.
tach test stea lt i nc leade a t least tise lo lee-ne neie type of chatwie l isspeet, tess bine corit rol valve fast closure or tesel>ine stop valve closeste, sese ls t ie.e t footh types of cleartewel i rspect s a r e tested at least once per 36 moenths.
the IOC-NFl System Response Time acceptance criteria associated with I
turbitte stop valve closure shall be i 155 milliseconds; tise EOC-RFI System Response Time acceptance criteria associated with the teerbine control valve fast closure shall fee 5 175 millisecoseds, l
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