ML20056C336

Application for Amends to Licenses NPF-9 & NPF-17,changing TS 3.7.1,Table 3.7-1 to Reduce Max Allowable power-range Neutron Flux High Setpoints W/Inoperable Steam Line Safety Valves During four-loop Operation

ML20056C336
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/13/1993
From:	Mcmeekin T DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20056C337	List: ML20056C336 ML20056C338
References
NUDOCS 9305190252
Download: ML20056C336 (4)

Text

i 11 1 Y DuCeihm Company T C M.uum McGuire Nxlear Generation Department lice hesident j !l700 Hagers Ferry R6ad(MC01A) (704)STS-4800 Huntersville, NC280784S85 (704)575-4809irx l

DUKEPOWER l May 13, 1993 U. S. Nuclear Regulatory Commission Attention: Document Control Desk I Washington, D.C. 22055 l

Subject:

McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Proposed Technical Specification Change j

Maximum Allowable Power Range Neutron Flux High Setpoints With Inoperable Steam Line Safety Valves During Four Loop Operation (T. S. 3.7.1 Table 3.7-1) j

Dear Sir:

(

Pursuant to 10CFR 50.4 and 50.90, attached is a proposed license l

amendment to Appendix A, Technical Specifications, of Facility Operating Licenses NPF-9 and NPF-17 for McGuire Nuclear Station ,

Units 1 and 2, respectively. The proposed change would reduce the maximum allowable power range neutron flux high setpoints >

l (percent of rated thermal power) as follows:

Max. t of"Inop. Safety Max. Allow. Power Range Neutron Valves on Any S/G Flux High Setpoint r (Current Value) (Proposed Value) .;'

l 1 87% 84%

2 65% 60%

3 43% 35%

The current reduced trip setpoints were derived by multiplying the ratio of the total remaining relieving capacity of the operable valves to the total relieving capacity of all valves in one steam line by the maximum trip setpoint for normal operation.

The current reduced trip setpoints are incorrect and non-L conservative. The proposed new trip setpoints are derived using-

! the actual different relieving capacities of the valves (see Attachment 2 Justification for details).

Attachment I contains the proposed Technical Specification change. Attachment 2 contains the Justification and Safety Analysis. Attachment 3 contains the Significant Hazards Considerations.

Should you have any questions, please contact P.T. Vu at (704) 875-4302.

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9305190252 930513 I l

PDR ADOCK 05000369 p PDR t l

on e nerasr a }

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U.S. NRC l 1

May 13, 1993 Page 2 r Very truly yours, pn('i4d)11 l T.C. McMeekin i PTV/TS371.sm f Attachments xc: (w/ attachments)  ;

Mr. S.D. Ebneter Administrator, Region II t U.S. Nuclear Regulatory Commission -

101 Marietta St., NW, Suite 2900 Atlanta, Ga. 30323 Mr. V. Nerses Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission  ;

One White Flint North, Mail Stop 9H3  !

Washington, D.C. 20555 Mr. P.K. VanDoorn NRC Resident Inspector McGuire Nuclear Station ,

Dayne Brown, Chief Division of Radiation Protection P.O. Box 27687 Raleigh, N.C. 27611-7687 I

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U.S. NRC May 13, 1993 ,

Page 3 i T. C. McMeekin, being duly sworn, states that he is Vice-President of Duke Power Company; that he is authorized on the part of said company to sign and file with the U.S. Nuclear Regulatory Commission these revisions to the McGuire Nuclear i Station License Nos. NPF-9 and NPF-17; and, that all statements and matters set forth therein are true and correct to the best of his knowledge.

t/

l T. C. McMeekin, Site Vice-President Subscribed and sworn to before me this thirteenth day of May 1993.

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No ary Public My Commission Expires: [

$lDbA) B,/993  :

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U.S. NRC l May 13, 1993 l Page 4 l

l bxc: (w/ attachments)  ;

l 1 NSRB (EC12A) l E.G. Blough (MG02ME) l J.J. Nolin (MG02ME) I L.S. Davis (MG02ME)  !

A.V. Carr W.M. Sample (EC05N) ,

R.O. Sharpe i R.C. Futrell (CNOIRC)

M.E. Patrick (ONO3RC) l G.D. Gilbert M.E. Paccetti (MG02ME)

B.H. Hamilton File: 801.01 File: PIR 0-M92-0136 l

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