ML20101F713

Supplemental ISI Rept Cycle 5 Refueling Outage for Feb-Mar 1995 for Unit 2

ML20101F713
Person / Time
Site:	Byron
Issue date:	03/31/1995
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20101F704	List: ML20101F702 ML20101F713
References
NUDOCS 9603260129
Download: ML20101F713 (11)

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l COMED BYRON UNIT 2 COMMERCIAL OPERATION AUGUST 21,1987 SUPPLEMENTAL INSERVICE INSPECTION REPORT CYCLE 5 REFUELING OUTAGE FEBRUARY-M ARCil 1995 l

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! Comed l P.O. Box 767 Chicago, IL 60690 i Byron Nuclear Power Station

\ 4450 North German Church Road Byron, IL 61010 l

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l Q Date Compi eted: February 12, 1996 9603260129 960320 PDR ADOCK 05000455 G PDR

TAlli.E OF CONTENTS Section Description Eau l.0 Introduction 1 2.0 Examination Summary 2 ATTACllMENT I NDE

SUMMARY

TABULATION ATTACilMENT 2 ASME FORM NIS l'S

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l SbPPIEMENT TO IWRON (H2R05) l ASME SECTION XI

SUMMARY

REPORT

1. INTitODUCTION l

l \ This report is a supplement to the Byron B2R05 ASME Section XI Summary Report completed on June 21,1995. The l examinations detailed below were intentionally omitted from the original report due to technical issues that required l resolution. The examinations were state-of the-art automated ultrasonic examinations of vessel nozzle inner radius inspections. The technical issues related to the calibration of the phased array equipment using the vendor supplied calibration l block and the acoustic similarity to the ASME calibration blocks. These issues were resolved and the calibration acoustics were demonstrated to the Authorized Inspection Agency. This report is being issued as required by ASME Section XI, IWA-6000, to allow Comed Byron Station to credit these examinations as being completed and acceptable to the requirements of ASME Section XI, IWB!C 2500,1983 Edition, Summer 1983 Addenda.

1.1 Identification of examination requirements The ISI Program contains the NDE program Tables. These tables are presented in a tabular format consistent with the tables found la subsections IWB and IWC of the ASME Code. The NDE tables include the corresponJing code category, code item number, and component selection in conformance with Class I and 2 examination requirement and intent of j l subsection IWA, IWB and IWC of Section XI of the ASME Code, Program Notes and relief requests, and additional l information are identified in the remarks colunm.

l 1.3 Implementation of the ISI Program I I

Comed, or their designee, examined the Class 1 and Class 2 nozzle inner radius volumes. The components examined were due to compliance with the ISI Program Schedule.

! Certified personnel performed and evaluated all NDE. Personnel were certined to the requirements of the American i l

Society for Non-destructive Testing SNT-TC-l A,1980 Edition. The NDE procedures were developed and certified in

( p conformance with ASME Section V and XI,1983 Edition through Summer 1983 Addenda, as applicable. I O l All ISI NDE, including evaluation of Haw indications were performed in accordance with the requirements stipulated l

under Section XI Subarticle IWA-2200," Examination Methods"

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I 1.4 Witness and Verification of Examination 1 The Inservice hspections were witnessed and'or verified by the Authorized Nuclear Inservice Inspector (ANil), Mr. J.

( llendricks from the llartford Steam Boiler inspection and Insurance Company ofIlartford Connecticut, Chicago Branch, l whose address is 2443 Warrenville Rd. Suite 500, Lisle, Illinois 60532-9871.

l 2.0 EXASilNATION SUM 51Al(Y l

i The following is a summary of the automated nozzle inner radius examinations performed during the Byron Station Unit 2  !

fifth refueling c)cle t

l 2.1 NDE Summary (Nozzle Inner Radius)

u. Steam Generator A

- 3 vessel nozzle inner radius were volumetrically examined

b. Steam Generator B i - 2 vessel nozzle inner radius were volumetrically examined

c. Steam Generator C

- 2 vessel nozzle inner radius were volumetrically examined Page 1 of 2

SUPPIEMENT TO IlYRON 012R05)

ASME SECTION XI

SUMMARY

REPORT d Steam Generator D 2 vessel nozzle inner radius were volumetrically examined

e. Pressuri:cr (PZR) 5 vessel nozzle inner radius wcre volumetrically examined i

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0 0 e ATTACilMENT 1 NDE SUMM ARY TABULATION (2 PAGES ATTACIIED) i I

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t Coined Ilyron Unit 2 - Il2R05 NDE SU.%ISI ARY TAllUI.ATION System: Interval: Period:

Presstirizer Vessel (PZR) First Third OllS Code isometric Componciit/l.ine Component / Weld - Exam Type Number Item Number - Identification Weld Num! v- surrace volume visual

38 1103.120 2PZR-1 2RY-Ol-S PN-02 X 40 f303.120 2PZR-1 2RY-01-S PN-03 X 42 1303.120 2PZR-1 2RY-01-S PN-04 X

. 44 1103.120 2PZR1 2RY-01 S PN-05 X 46 1103.120 2PZR-1 2 RY-01 -S PN4)6 X i

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. 1 Comed Ilyron Unit 2 - Il2R05 l NDE SUM.\1 AltY TAllUI.ATION System: Interval: Period:

Steam Generators (SG) First Tliird OllS . Cmle ~ isometric Comixment/Line Component / Weld - Exam Type Numl>cr Item Numl>er Identification Weld Numlier surrace niume visuai 152 B03.140 2SG-01 2RColBA N-1A X 153 B03.140 2SG-01 2RC01BA N-1B X 155 CO2.022 2SG-01 2RC0lilA SGN-02 X 159 B03.140 2SG-03 2RC01BB N-1A X 160 B03.140 2SG-03 2RC01BB N-IB X 156 B03.140 2SG-02 2RC01BC N-1A N 157 B03.140 2SG-02 2RColBC N-1B X 161 B03.140 2SG-04 2RC01BD N-1A N 162 B03.140 2SG-04 2RColBD N-1B X b4 v

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@ ATTACllMENT 2 ASME FORM NIS l'S (3 PAGES ATTACilED) )

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l FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS O As Required by the Provisions of the ASME Code Rules

1. Owner: Comed. P.O. Box 767. Chicago. Illinois 60690 ,

(Name and Address of Owner) i

2. Plant: Byron Nuclear Power Station. 4450 North German Church Road. Byron. Illinois 61010 l (Name and Address of Plant) l 3. Plant Unit: Two (2) 4. Owner Certificate of Authorization: N/A 1

5. Comercial Service Date: 03Bl/87 5. National Board Number of Unit: N-200 l

7. Components inspected: Pressurizer Vessel (PZR) l l Component or Stanufacturer or Stanufacturer or State or Prminee National lloard j Appurtenance Installer Installer Serial No. Number Number B03.120 PN-02 Westinghouse 2RY-01-S Corporation 1741 U-201441 W13582 l

l B03.120 PN-03 Westinghouse i 2 P.Y-01-S Corporation 1741 U-201441 W13582 B03.120 PN-04 Westinghouse  ;

I 2RY-01-S Corporation 1741 U-201441 W13582 l

' U O B03.120 PN-05 Westinghouse 2 R Y-01-S Corporation 1741 U-201441 W13582 B03.120 PN-06 Westinghouse 2 RY-01-S Corporation 1741 U-201441 W13582 r

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FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules

1. Owner: Comed. P.O. Box 767. Chicaco. I!!inois 60690 (Name and Address of Owner)

2. Plant: Byron Nuclear Power Station. 4450 North German Church Road. Byron. Illinoir 61010 l (Name and Address of Plant)

3. Plant Unit: Two (2) 4. Owner Certificate of Authorization: N/A

5. Comercial Service Date: 08/21/87 6. National Board Number of Unit: N-200

7. Components Inspected: Steam Generator Vessel (SG) l Component or Manufacturer or Stanufacturer or State or Province National lloard Appurtenance Installer installer Serial No. Number Number CO2.022 SG N-02 Westinghouse 2RC01BA Corporation 2095 U-201435 15 l

B03.140 N-1A Westinghouse l 2RC01 BA Corporation 2095 U-201435 15 B03.140 N 1B Westinghouse l s 2RC01BA Corporation 2095 U-201435 15

(, B03.140 N 1A Westinghouse l

l 2RC01BB Corporation 2096 U-201436 16 B03.140 N 1B Westinghouse 1 2RC01BB Corporation 2096 U-201436 16 B03.140 N 1A Westinghouse I 2RC01BC Corporation 2097 U-201437 17 l B03.140 N-1 B Westinghouse l 2RC01BC Corporation 2097 U-201437 17 i B03.140 N lA Westinghouse 2RC01BD Corporation 2098 U-201438 18 B03.140 N-1B Westinghouse 2RC01BD Corporation 2098 U-201438 18 l

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I FORM NIS-1 (Itack) l O - . 8. Examination Dates _10/26/93 to 3/25/95 9. Inspection Interval from 08/2I/87 to 08/21/97 l

10. Abstract of Examinations, include a list of examinations and a statement concerning status of work required for current l

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Refer to the attached ASME Summary report.

11. Abstract of Conditions Noted Refer to the attached ASME Summary report.  !

1 12, Abstract of Corrective Measures Recommended and Taken Refer to the attached ASME Summary report.

We certify that the statements made in this report are correct and the examinations and corrective measures taken j conform to the rules of the ASME Code,Section XI. l Certificate of Authorization No. (if applicable) Not Anplicable Expiration Date Not Apol/able /f Date -c;- 19' 96 Signed For Commonwealth Edison Company By ,

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! ' C Owner '/

l d CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the' National Board of Boiler andfressure Vessel Inspectors and the State or Province of ff/Mp/5 and employed by //fd I VI. fa,of A[V/[r/ 4aa///M have inspected .

the components described in this Owner's Report during the period zv/.,r#//3 to 34r/#f , and state that to the best of I my knowledge and belief, the Owner has performed examinations aifd taken correc6ve' measures described in this Owner's )

! Report in accordance with the requirements of the ASME Code,Section XI. l l By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

! M44s /// ',/ Commissions /// /,(SY j h4j6(eto/s Signat'ure National Board, State, Province, and Endorsements l

Date M / ( 19 M8 4

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