ML20091M731

Forwards Rev 0 to Augmented Inservice Insp Plan,Comanche Peak Steam Electric Station, in Response to NRC 911004 Telcon Request.Westinghouse Technical Bulletin NSD-TB-75-1 Re Reactor Coolant Pump Thermal Barrier Also Encl

ML20091M731
Person / Time
Site:	Comanche Peak
Issue date:	01/24/1992
From:	William Cahill, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20091M734	List: ML20091M731 ML20091M740
References
TXX-92030, NUDOCS 9201290208
Download: ML20091M731 (2)

Text

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%""2 C Log # TXX-92030 L Z File # 10010 7 Ref. # 10CFR2.102 TUEUC7RIC January 24, 1992 William J. Cahnl, Jr.

Group Dce Pmident U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) UNIT 1 -

DOCKET NO. 50-445 REQUEST FOR ADDITIONAL INFORMATION FOR THE FIRST 10-YEAR INTERVAL UNIT 1 INSERVICr INSPECTION (ISI) PROGRAM PLAN Gentlemen:

TV Electric has asoembled the information rq uested by the NRC staff and EG&G Idaho during a teleconference on October 4, 1991. The information requested is enclosed. The information includes:

Enclosure (1) -

The Augmented loservice Inspection (ISI) Plan.

TU Electric, Comanche Peak Steam Electric Station, Revision 0:

Enclosure (2) -

CPSES/FSAR pages 1A(N)-75 and 1A(N) 76 dated July 31, 1987, which describes the CPSES commitment with respect to compliance with U.S. NRC Regulatory Guide 1.150:

Enclosure (3) - Westinghouse Nuclear Service Division Technical Bulletin NSD-TB '5-1 dated 01/31/75 concerning the Reactor Coolant Pump Thermal Barrier.

Enclosure (4) TU Electric Inservice Inspection Boundary Diagram for the Component Cooling Water System, Sheets 11 and 12.

The Augmented ISI Plan is maintained and updated on site and the latest approved revision is always available for NRC audit or inspection.

EG&G Idaho asked if the component cooling water piping, designed for reactor coolant pressure, is included in relief request 0-1. Our response is that the relief request D-1 is for the reactor coolant pump thermal barrier and does

, not apply to the component cooling water system piping which is attached (flanged) to the thermal barrier. Therefore the Component Cooling Water piping will be tested as described in the 151 ?ror; ram Pl an.

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9 p' nL v 9201290208 920124 400 N. Ouve street LB. 81 Dallas, Texas 75201 J' -()

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TXX-92030 Page 2-of 2 Should you need any additional information concerning the A5ML Section X1 151 Program Plan, please let us know.

Sg.p,gg .

William J. Cahill, Jr.

By: Mb Mr. Roger D. Walker Manager of Nuclear Licensing CEJ/gj Enclosures c: Mr. R. D. Martin. Region IV (clo)

Perident inspectors CPSES (2 clo)

Mr. Boyd Brown EG&G Idaho (w/ enclosures)

Mr. T. A. Bergman (w/ enclosure 1)

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