ML20054G361

Forwards Changes to Preservice Insp Program Transmitted 820223,SWRI-NDT-600-11,Revision 34,SWRI-NDT-600-41,Revision 4 & SWRI-NDT-900-4,Revision 23.Info Closes Out SER Outstanding Issue 8

ML20054G361
Person / Time
Site:	Clinton
Issue date:	06/11/1982
From:	Wuller G ILLINOIS POWER CO.
To:	Bernard H Office of Nuclear Reactor Regulation
Shared Package
ML20054G362	List: ML20054G361 ML20054G370 ML20054G375 ML20054G384
References
L30-82(06-11)-L, L30-82(6-11)-L, U-0500, U-500, NUDOCS 8206210482
Download: ML20054G361 (12)

Text

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__. U-0500 ILLINDIS POWER 00MPANY y L30.g2(06 11).t 500 SOUTH 27TH STREET, DECATUR, ILLINOIS 62525 June 11, 15'82 l

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Mr. Harold Bernard, Acting Chief Standardization & Special Projects Branch Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Letter 2/23/82 (U-0422), G. E. Wuller, IP to J. R. Miller, NRC - transmitted Preservice Inspection Program Clinton Power Station Unit 1 Docket No. 50-461 Transmitted herewith are some changes to our Preservice Inspection (PSI) Program which was furnished via the referenced letter. The PSI program changes consist of additional or re-vised material which is provided as replacement pages for the referenced submittal. A sheet of change out instructions is also furnished.

Included with this submittal are three Southwest Research Institute (SwRI) nondestructive testing (NDT) procedures; and five drawings (identified as Appendix B Figures) which were not previously available, namely:

1) SwRI-NDT-600-11, Revision 34, February 1982 (not previously submitted)

2) SwRI-NDT-600-41, Revision 4, March 1982 (replacement due to revision)

3) SwRI-NDT-900-4, Revision 23, February 1982 (not previously submitted)

4) Figures B-72 through B-77 I

QoD 206210402 820611 DRADOCKOS000j6g

U-0500 L30-82(06-11)-L Page 2 This submittal should close out the Clinton SER out-standing issue #8. Please let us hear soon if you have any questions on this material.

Sincerely,

~

G. E. Wuller Supervisor - Licensing Nuclear Station Engineering GEW/1t ec: Mr. J.11. Willf ams , NRC Clinton Project Manager (w/o Enc. )

Mr. 11. H. Livermore , NRC Resident Inspector Mr. M. R. Hum, NRC MTEB Illinois Dept. of Nuclear Safety (w/o Enc.)

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.:111nois Power Company C: inton Power Station Unit 1 Instructior.s for Updating the Clinton Preservice Inspection Program VOLUME II APPENDICES - Examination Plan for the Preservice Examination Remove Insert Appendix B Page B-iii Page B-iii (Change 2)

Pages B-85 through B-90 Pages B-85 through B-90 (Change 2)

Appendix D Page D-i & D-il Page D-i & D-il (Change 2)

After Procedure Procedure SwRI-NDT-600-11 SwRI-NDT-600-5 Rev. 34, Feb. 1982 Rev. 33 (Page 14)

Procedure SwRI-NDT-600-41 Procedure SwRI-NDT-600-41 Rev. 1, Aug. 1981 (32 pages) Rev. 4, Mar. 1982 (17 pages)

After Procedure Procedure SwRI-NDT-900-4 SwRI-NDT-900-2 Rev. 23, Feb. 1982 (5 pages)

Rev. 7, Mar. 1978 (Page 6) 1 l

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-- -. .. . . ~ . - - - _ _ , _ - _ _ _ _ .. _ _ _ . .,___ - __ _ _ - . . _

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Change 2 APPENDIX B CLASS 2 WELD AND COMPONEVE IDENTIFICATION FIGURES Table of Contents (Cont'd)

Figure Title Page B-52a Line IRH50AA-10 Inch B-61 B-52b Line 1RH50AA-10 Inch B-62 B-53a Line IRH50AB-10 Inch B-63 Line IRH50GB-10 Inch B-53b Line IRH50AB-10 Inch B-64 B-53c Line IRH50AB-10 Inch B-65 B-54 Line IRH51CA-10 Inch B-66 B-55 Line IRH51CB-10 Inch B-67 B-56 Line IRH97A-10 Inch B-68 B-57a Line 1RIO3A-6 Inch B-69 B-57b Line 1RIO3A-6 Inch B-70 B-58 Line 1RIO4B-8 Inch B-71 B-59 Line 1RIO7A-12 Inch B-72 B-60a Line 1RIO8A-12 Inch B-73 B-60b Line 1RIO8A-12 Inch B-74 B-61 Line 1RIO8B-12 Inch B-75 B-62 Line 1RIO8C-12 Inch B-76

) B-63 Line 1RI43A-8 Inch B-77 B-64 Line 1RI69A-10 Inch B-78 B-65 Line IVP02BA-10 Inch B-79 B-66 Line IVP02BB-10 Inch B-80 B-67 Line IVP03DA-10 Inch B-81 B-68 Line IVP03DB-10 Inch B-82 B-69 Residual Heat Removal Pump B-83 B-70 Low Pressure Core Spray Pump B-84 B-72 Low Pressure Core Spray Water B-85 Leg Pump B-73 High Pressure Core Spray Pump B-86 B-74 High Pressure Core Spray Water B-87 Leg Pump B-75 Reactor Core Isolation Cooling B-88 Pump B-76 Reactor Core Isolation Cooling B-89 Water Leg Pump B-77 Standby Liquid Control Pump B-90 l 1 B-iii

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Chrng, 2 D APPENDIX D SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURES Table of Contents Procedure No. Title SwRI-NDT-200-1/54 Liquid Penetrant Examination Color Contrast Method SwRI-NDT-300-1/24 Dry Powder Magnetic Particle Examination SwRI-NDT-300-2/32 Fluorescent Magnetic Particle Examination SwRI-NDT-600-5/33 Manual Ultrasonic Examination of Nuclear Reactor Pressure Vessel Flange Ligaments SwRI-NDT-600-11/34 Manual Ultrasonic Examination of Vessel-to-Nozzle Inner Radius Sections SwRI-NDT-600-13/28 Manual Ultrasonic Examination of the Reactor Pres-sure Vessel Flange-to-Shell Weld I

SwRI-NDT-600-14/14 Manual Ultrasonic Examinations of Studs and Bolts SwRI-NDT-600-15/47 Manual Ultrasonic Examination of Pressure Vessel Welds SwRI-NDT-600-16/24 Manual Ultrasonic Examination of Vessel Support Skirt Attachment Welds SwRI-NDT-600-18/32 Manual Ultrasonic Examination of Pressure-Retaining Studs and Bc1ts 2 Inches or Greater in Diameter Containing Access Holes SwRI-NDT-600-19/29 Manual Ultrasonic Examination of Pressure-Retaining Round Nuts 2 Inches or Greater in Diameter SwRI-NDT-600-24/4 Manual Ultrasonic Examination of Straight Cylindrical Sections of BWR Feedwater Nozzles SwRI-NDT-600-37 /4 Manual Ultrasonic Examination of Hexagonal Nuts SwRI-NDT-600-41/4 Manual Ultrasonic Examination of Ferritic Pressure Piping Uelds I

D-i

Chang, 2 APPENDIX D SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURES Table of Contents (cont'd)

Procedure No. Title SwRI-NDT-700-5/8 Mechanized Ultrasonic Examination of Vessel Components, Vessel Welds and Piping Welds

• SwRI-NDT-700-6/9 Mechanized Ultrasonic Examinations of Ferritic Vessels 2-1/2 Inches or Greater in Thickness

• SwRI-NDT-800-53/5 Manual Ultrasonic Examination of Nozzle Inside Radius Sections with Bore Diameters of 2 to 6 Inches

• SwRI-NDT-800-77/0 Manual Ultrasonic Examination of Austenitic Pressure Piping Welds at Clinton Power Station Unit 1 SwRI-NDT-900-1/49 Visual Examination of Nuclear Reactor Components by Direct or Remote Viewing SwRI-NDT-900-2/7 Visual Examination of Nuclear Reactor Internals by Direct or Remote Viewing SwRI-NDT-900-4/23 Visual Examination of Support Members and Structures for Piping, Valves, and Pumps by Direct or Remote Viewing l

• In preparation D-il