U-600652, Submits Updated Listing of Piping Subsystems Which Had Arbitrary Intermediate Breaks Eliminated,Per Chapter 3 of FSAR &

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Submits Updated Listing of Piping Subsystems Which Had Arbitrary Intermediate Breaks Eliminated,Per Chapter 3 of FSAR &
ML20211Q792
Person / Time
Site: Clinton Constellation icon.png
Issue date: 07/23/1986
From: Spangenberg F
ILLINOIS POWER CO.
To: Butler W
Office of Nuclear Reactor Regulation
References
U-600652, NUDOCS 8607280005
Download: ML20211Q792 (2)


Text

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o o U-600652 L30-86(07-23)-L 1A.120 ILLINDIS POWER 00MPANY CLINTON POWER STATION. P.O. BOX 678. CLINTON, ILLINOIS 61727 July 23, 1986 Docket No. 50-461 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Clinton Power Station FSAR Chapter 3

Dear Dr. Butler:

In recent amendments to the Clinton Power Station Final Safety Analysis Report (FSAR), several figures and text in Sections 3.6 and B3.6 were revised to reflect the NRC's approval of Illinois Power Company's April 16, 1985, request to eliminate arbitrary intermediate pipe breaks. In recent discussions with your staff, it was requested that any breaks which were not identified in the April 16, 1985 letter, but which have been eliminated,- be documented in a letter to the NRC Staff.

In Amendment 37, Section 3.6.2.1.6.2.1.1 (p. 3.6-17 and p. 3.6-18) was updated to identify those piping subsystems which had arbitrary intermediate breaks eliminated. For the subsystems identified, only the following subsystems are in addition to those requested in the April 16, 1985 letter.

Class 1 Piping subsystems System Subsystem FSAR Reference Reactor Recirculation (RR) RR 32 Figure B3.6-29 Table B3.6-29 RR 33 Figure B3.6-30 Table B3.6-30 Class 2 and 3 Piping subsystems System Subsystem FSAR Reference Reactor Water Clean Up (RT) RT 06 Figure B3.6-26 Table B3.6-26 RT 07 Figure B3.6-27 Table B3.6-27 8607280005 860723 '8"#* *

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PDR ADOCK 05000461 Table B3.6-28 A PDR g gll) l l tjO t

U-600652 L30-86(07-23)-L 1A.120 System Subsystem FSAR Reference Residual Heat Removal (RH) RH 07 Figure B3.6-18 Table B.6-18 RH 08 Figure B3.6-19 Table B3.6-19 RH 14 Figure B3.6-21 Table B3.6-21 Reactor Core Isolation RI 02 Figure B3.6-21 Cooling (RI) Table B3.6-21 The technical justification for these piping subsystems is the same as for those piping subsystems identified in the April 16, 1985, letter to the Staff. Please contact us if you have any questions on this matter.

Sincerely yours.

F. A. Spangen [ berg Manager - Licensing and Safety JLP/kaf cc: B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Illinois Department of Nuclear Safety Regional Administrator, Region III, USNRC

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