ML20078A817

Submits Addendum to 941123 TS Change Request 163,modifying TS 15.3.6, Containment Sys, to Enhance Operating Conditions & Limiting Conditions for Operation for Containment Sys,Per 950112 Telcon W/Nrc

ML20078A817
Person / Time
Site:	Point Beach
Issue date:	01/12/1995
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20078A821	List: ML20078A817 ML20078A838
References
CON-NRC-95-003, CON-NRC-95-3 VPNPD-95-007, VPNPD-95-7, NUDOCS 9501250151
Download: ML20078A817 (2)

Text

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i Wisconsin

' Elecinc l

. POWER COMPANY i

231 W Mchigan. Po Box 2046 Milwaukee.WI 53201-2046 (414)221 2345 VPNPD-95-007 NRC-95-003 i

January 12, 199fI Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 l l ADDENDUM TO TECHNICAL SPECIFICATIONS CHANGE REOUEST 163 l l MODIFICATIONS TO SECTION 15.3.6, " CONTAINMENT SYSTEM" l POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 On November 23, 1993, we submitted Technical Specifications Change Request (TSCR) 163, " Modifications To Section 15.3.6, ' Containment System'," to enhance the operating conditions and limiting condi-tions for operation for containment systems.

Per our telephone conversation on January 12, 1995, we are making the following changes to our November 23, 1993, submittal:

1. Specification 15.1.D.1.a will state, " Capable of being closed by an operable automatic containment isolation valve." i

2. Specification 15.1.D.2 will state, "The equipment hatch meets the leakage acceptance criteria of TS 15.4.4.II.B."

3. Specification 15.1.D.3 will state, "Each personnel air lock meets the leakage acceptance criteria of TS 15.4.4.II.B."

4. A footnote will be added to Specification 15.1.D.4 to state, " Prior to the first startup following testing required by TS 15.4.4, the as-left containment leakage rates shall satisfy tne acceptance criteria in TS 15.4.4."

We are also modifying the Basis for Section 15.3.6, " Containment l

System," Specification A.1.a to clarify the leakage requirements ,

for containment operability and support the added footnote.

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2 Document Control Desk l l January 12, 1995 .

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We have reviewed the safety evaluation and no significant hazards consideration included in our November 23, 1993, submittal and have determined that they apply to this addendum.

If you require additional information, please contact us.

Sincerely, i ,

Bob Link '

Vice President l l

Nuclear Power l KVA/jg l l

Attachments )

i cc: NRC Regional Inspector, Region III I j NRC Resident Inspector l

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