ML042430649

Limiting Safety System Settings and Instrumentation Withdrawal of Change to Functional Unit 17 (TAC No. MB6166) License Basis Document Change Request (LBDCR 3-5-02)

ML042430649
Person / Time
Site:	Millstone
Issue date:	08/30/2004
From:	Hartz L Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
04-522, TAC MB6166
Download: ML042430649 (5)

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Dominion Nuclear Connecticut, lnc.

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August 30,2004 U.S. Nuclear Regulatory Commission Serial No.04-522 Attention: Document Control Desk MPS Lic/MAE RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 LIMITING SAFETY SYSTEM SETTINGS AND INSTRUMENTATION WITHDRAWAL OF CHANGE TO FUNCTIONAL UNIT 17 (TAC NO. MB6166)

LICENSE BASIS DOCUMENT CHANGE REQUEST (LBDCR 3-5-02)

In an August 7, 2002, LBDCR application, Dominion Nuclear Connecticut, Inc. (DNC) proposed changes to the Millstone Unit No. 3 Limiting Safety System Settings and Instrumentation Technical Specifications. This change was intended to achieve consistency with a similar change previously reviewed and approved by the NRC under Millstone Unit 3 Amendment 129.

In a recent conference call, the Nuclear Regulatory Commission (NRC) identified a concern with DNC's proposal to delete Functional Unit 17, "Safety Injection Input from ESF," from Table 2.2-1. DNC hereby withdraws that portion of the LBDCR 3-5-02 proposal related to the deletion of Functional Unit 17. A revised mark up of the affected page is provided as Attachment 1.

The change addressed by this submittal does not affect the conclusions of the Safety Summary and Significant Hazards Consideration Discussion provided in the DNC August 7, 2002, submittal.

If you have any questions or require additional information, please contact Mr. Paul R.

Willoughby at (804) 273-3572.

Very truly yours, Leslie N. Hartz Vice President - Nuclear Engineering

Serial No.04-522 Limiting Safety System Settings and Instrumentation Page 2 of 2 Attachments: 1 Commitments made in this letter: None.

cc: US. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station

Serial No.04-522 Docket No. 50-423 Withdrawal of change to Functional Unit 17 COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Leslie N. Hartz, who is Vice President - Nuclear Engineering, of Dominion Nuclear Connecticut, Inc. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of her knowledge and belief.

Acknowledged before me this day of/fi@,,f , 2004.

J My Commission Expires:

(SEAL)

Serial No.04-522 Docket No. 50-423 ATTACHMENT 1 LICENSE BASIS DOCUMENT CHANGE REQUEST (LBDCR 3-5-02)

LIMITING SAFETY SYSTEM SETTINGS AND INSTRUMENTATION MARK UP OF THE CURRENT TECHNICAL SPECIFICATION PAGE MILLSTONE POWER STATION UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC.

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 0

z NOMINAL FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE 2 16. Turbine Trip w

a a. Low Fluid Oil Pressure 500 psig 2 450 psig

b. Turbine Stop Valve 1% open 2 1% open Closure

17. Safety Injection Input N.A. N.A.

Y from ESF 4

18. Reactor Trip System Interlocks

a. Intermediate Range 1 x lo- amp 2 9.0 x lo-" amp Neutron Flux, P-6

b. Low Power Reactor Trips Block, P-7

?owER R+?.IJGtzh\C"TleOU Lux 1IP' - 1o input mote 5 ) 11% of RTP** I 11.6% of RTP**

2) P-13 input 10% RTP*

• Turbine I 10.6% RTP** Turbine 8 t -ii'uRDtUe (M.&5f &-%

Impulse Pressure Equivalent Impulse Pressure Equivalent E

CD 2

z

?

c. Power Range Neutron Flux, P-8 mmuRE 37.5% of RTP** 538.1% of RTP**

U d

CD 0

bo

• • RTP = RATED THERMAL POWER 8 5

w 0

N 0

0 w