ML20031D176

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Notice of Issuance & Availability of Amend 5 to License NPF-9
ML20031D176
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 09/23/1981
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20031D173 List:
References
TAC-46812, NUDOCS 8110130031
Download: ML20031D176 (8)


Text

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i UNITED STATES NUCLEAR REGULATORY C0!4tISSION i

DOCKET H0. 50-369 DUKE POWER C0!!PANY NOTICE OF ISSUANCE OF AMENDliENT FACILITY OPERATING LICENSE NO. HPF-9 The U.S. Nuclear Regulatory Comission (the Comission) has issued Amendment No. 5 to Facility Operating License No. NPF-9, issued to Duke Power Company e

l (licensee) for the licGuire Nuclear Station, Unit 1 (the facility) located in Hecklenburg County, North Carolina. This amendment corrects the setpoint assoc 1-4 ated with the reactor trip initiated by a turbine trip. The amendment is effec-ttve as of its date of issuance.

I The application for the amendment complies with the standards and require-i nents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's I

regulations. The Comission has made appropriate findings as required by the Act and the Comission's regulations in 10 CFR Chapter I, which are set forth in the license amendment. Prior public notice of this anendment was not required since the amendment does not involve a significant hazards consideration.

The Comission has determined that the issuence of this amendnent will not result in any significant environmental impact and that pursuant to 10 CFR 51.5(d)(4) an environmental ir.: pact statement, or negative declaration and environ-nie$

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o.o menta'i impact appraisal need not be prepared in connection with issuance of this o

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amendment.

86 For further details with respect to this action, see (1) Duke Power Company 88 j

g4 letter dated September 21,1981,(2) Amendment No. S to Facility Operating License

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110. NPF-9 with Appendix A Technical Specification page change, and (3) the Com-

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All of these itens are available for public inspection at the Comission's Public Document Room,1717 !! Street, fl.W., Washington, D. C., and the Atkins Library, University of Ilorth Carolina, Charlotte (U!{CC Station), North Carolina 28223. A copy of items 2 and 3 nay be obtained upon request addressed to the U. S. I!uclear flegulatory Comission. Washington, D. C.

20555, Attention: Director, Division of Licensing.

  1. d Dated at Dethesda, Maryland, this 23 day of Septem1.ar 1981.

FOR THE !!UCLEAR REGULATORY C0 ;11SS10!1

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Elinor G. Adensam, Acting Chief Licensing Branch No. 4 Division of Licensing, ilRR l

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j 28223. A copy of Arendment Ho. 5 may be obtained upon request addressed to the U. S. Nuclear Regulatory Cotuission, Washington, D. C.

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Elinor G. Adensam, Acting Chief Licensing Branch No. 4 Division of Licensing, NRR i

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Rei NcCu$rcliuclearStation h6 b QfW Froposed Amendment to Ldcenoo liPT-9 Docket No. 50-369

< b-P Dest Mr. Dentoni AttachedisaproposedciongekofinoH:Cuire7;ucicarStatdon,Onit$4Techni-cal Specifications., This chango. corrects the actroint associated with the renetor trip initiated by a turbine trip.

This citange h:ts been rev1 cue and b kaas been determined tktat there are no adverne enfety or envz.ronmental Arnpacts associated with the proposed change,

'Ihs proposed change is considered to,be a Class,IIL anondment pursuant to

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1 10 CFR 170.22.

Therefore, enclosed is a chech.in the amount of $4000.,

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Vary truly yours; e

c/Hillints O. Parker;.fr.

William,O. Parker, Jr.

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CIC/smb cci its. N. 3. Cralists br. Jance'P. O'P.cilly. D$rictor Rentdent Inspector

!!ccuire l'ucicar Stntkon U. S. t!udoar Regu14 tory"Coyanics.fon Region II:

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101 Ifarietta Street, Suite 3100 N

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  • Tcchnical specificarfon 2.2 - Itcactoc Trip Instrumentation setpoinem

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Change Values on Iters 128 in Tablo 2. "-1 to read

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12A) Low Syncean Pressure Trip - Trip Setpoinc > 45 poig

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Allouable alue > 42 psig Juut ifIcation and _ Saf aty Analysis

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, m The design of the Turbano Trip / React Trip circuit is based on the control oil systen which is used to control

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El byotca oil pressure through an interface valve.

When a turbina trip signa in initiated', a soction of the control oil syutes is bled off which in turn dumps the pressure on the Deli systect to close the turbine control and atop val.ves.

Thid control oil system generates a low pecm.ure signal at 45 paia through 2 out of ~, logLc to trip the reactor above the P-8 uctpoint.

'Ihe Deft lou pressure trip at 900 psig cervos to close the turbino control and atop valvos which in turn would trip the rea' tor throug

.E the turbine stop valve closure suitch at 11 open.

However, the DEI! system ow *.

pecc.sira trip does not directly feed the reactor trip circuit.

Therefore, he actpoint upecific.d uhould Lo for tha control oil pressure suitches uhich.ifir-eetly init:tato the reactor trip.

This propo sed change cocrects the current Technical Specifications to correctly specify the trip notpoint and as such does not result in any adverse safety la-plications.

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