ML20238F822

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Rev 2 to Braidwood Station Units 1 & 2 Second Interval ISI Program Plan
ML20238F822
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 08/25/1998
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20238F818 List:
References
PROC-980825, NUDOCS 9809040354
Download: ML20238F822 (8)


Text

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BRAIDWOOD STATION UNITS 1 AND 2 l 1

SECOND INTERVAL INSERVICE INSPECTION i

l PROGRAM PLAN-NRC SUBMITTAL i

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Revision 2 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL REVISION

SUMMARY

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7-26 to 7-27 1 7/28/98 j 7-29 to 7-31 0 2/20/98 j 7-32 1 7/28/98 )

7 33 to 7-34 0 2/20/98 7-35 2 8/25/98 l 7-36 to 7-39 0 2/20/98 8-1 0 2/20/98 8-2 1 7/28/98 8-3 2 8/25/98 84 1 7/28/98 i 8-5 to 8-8 0 2/20/98 l 8-9 to 8-13 1 7/28/98 8-14 to 848 0 2/20/98 8-49 to 8-56 1 7/28/98 i 8-57 to 8-63 0' 2/20/98 8-64 to 8-66 1 7/28/98 8-67 to 8-69 2 8/25/98 8-70 to 8-107 0 2/20/98 8-108 to 8-109 1 7/28/98 8-110 to 8-113 ,

0 2/20/98 8-114 to 8-121 1 7/28/98 9-1 to 9-26 0 2/20/98

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Revision 2 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL

. . TABLE 8.0 ISI PROGRAM RELIEF REQUEST INDEX (Cont'd) l Relief Request Summary Revision 12R-15 Alternative Rules For the Selection and Examination of Class 1, 2 2 and 3 Integrally Welded Attachments - Use of Code Case N-509 12R-16 Alternative Rules for Deferral ofInspections on Nozzle-to- 0 Vessel Welds, Inside Radius Sections and Nozzle-to-Safe End Welds of the Reactor Vessel - Use of Code Case N-521 12R-17 Alternate Examination Requirements for Longitudinal Welds in 0 Class 2 Piping - Use of Code Case N-524 I2R-18 Limited Volumetric Examination of Reactor Pressure Vessel 0 Circumferential Shell Welds and Lower Head Circumferential Welds 12R-19 Use of Alternative Examination Requirements, Examination 0 Method, and Acceptance Standard for Reactor Vessel Closure Head Nuts 12R-20 Limited Volumetric Examination of Reactor Pressure Vessel 0 (RPV) Head-to-Flange Weld 12R-21 Alternate Rules for the Deferral of Inspections on the Reactor 0 Pressure Vessel (RPV) Shell-to-Flange Weld (s)

)

12R-22 Limited Volumetric Examination of Reactor Pressure Vessel 0 )

Nozzle-to-Vessel Welds 12R-23 Alternative Examination Requirements For Seals and Gaskets 0 12R-24 Alternative Visual Examination Requirements for Minimum 0 Illumination and Maximum Direct Examination Distance of  !

Class CC Components '

1 I2R-25 Alternative Requirements for Preservice Examination of Paints 0  !

and Coatings j 12R-26 Alternative Requirements for Examination of Paints and 0 j Coatings Prior to Removal l

I2R-27 Deleted 1 l

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Revision 2 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST 12R-15 (Page 1 of 3)

COh1PONENT IDENTIFICATION Code Classes: 1,2 and 3

References:

Table IWB-2500-1, Table IWC-2500-1, Table IWD-2500-1 '

Examination Categories: B-H, B-K-1, C-C, D-A, D-B, D-C l Item Numbers: B8.10, B8.20, B8.30, B10.10, B10.20, B10.30, C3.10, C3.20, ,

C3.30, C3.40, D1.20, D1.30, D1.40, D1.50, D1.60, D2.20, D2.30, D2.40, D2.50, D2.60 l

Description:

Alternative Rules for the Selection and Examination of Class 1,2 I and 3 Integrally Welded Attachments - Use of Code Case N-509 Component Numbers:

)

All Class 1, 2 and 3 Integral Attachments Subject to Inservice l Inspection CODE REOUIRENIENTS Class 1 Attachments Table IWB-2500-1, Examination Categories B-H and B-K-1 require the performance of surface or volumetric examinations, as applicable, on integral attachments with a design thickness of 5/8 inch or greater. i Class 2 Attachments Table IWC-2500-1, Examination Category C-C requires the performance of a surface examination on integral attachments with a design thickness of 3/4 inch or greater.

Class 3 Attachments Table IWD-2500-1, Examination Categories D-A, D-B and D-C require the performance of a visual VT-3 examination on integral attachments.

For complete details on ASME Section XI Code examination requirements, see Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1.

CODE REOUIREh1ENTS FRON! WHICH RELIEF IS REOUESTED Relief is requested for the selection of components for examination, and examinations required by Table IWB-2500-1, Categories B-H and B-K-1 on integral attachments with a design thickness of 5/8 inch or greater.

Relief is requested for the selection of components for examination, and examinations required by Table IWC-2500-1, Category C-C on integral attachments with a design thickness of 3/4 inch or greater.

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Revision 2 l BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMITTAL RELIEF REQUEST I2R-15 (Page 2 of 3)

Relief is requested for the selection of components for examination, and examinations required by Table IWD-2500-1, Categories D-A~, D-B and D-C.

BASIS FOR RELIEF Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested on the basis that the proposed alterCives provide an acceptable level of quality and safety.

Relief is being requested to allow the use of alternate requirements for the examination and selection of Class 1,2 and 3 integral attachments detailed in Code Case N-509, with exception to the requirement to inspect the integrally welded attachments associated with the component supports selected for examination under the 1990 Addenda, IWF-2510 (Reference footnote 5 of Category B-K and Category C-C Code Case N-509 tables). The basis for this request is as follows:

1) No Inservice flaws which would affect the structural integrity of any component or piping system have been detected .as a result of the integrally welded attachment exams performed during the first interval at Braidwood Station.
2) Integral attachment failures have been very rare within the commercial nuclear power industry. Failures and inservice defects that have been detected are usually associated with support damage caused by a system transient or other abnormal events during operational periods. Therefore, degradation is typical y identified during inspections that are performed after a system transient or other abnormal events which have occurred. Code Case N-509 requires the examination of integral attachments when deformation of the associated component support members is identified. This requiremer.t will ensure degraded integral attachments are identified and therefore increase the level of quality and safety provided by these alternatives n% as compared to the rules of the 1989 Edition of Section XI.
3) Significant amount of man-rem exposure and cost associated with the scheduled examination of Class 1, 2, and 3 integral attachments would be saved.

-4) Contrary to the requirements specified in ASME Section XI 1989 Edition, the alternate selection criteria of Code Case N-509 does not impose a minimum thickness

, requirement for the examination of an integral attachment. Therefore, a larger

! population of integral attachments will be available for examination because the f_ selection population will not be limited to those above an arbitrary thickness. This L provision improves the quality and safety level established by these examinations.

5) The alternate rules of Code Case N-509 provide an acceptable level of quality and l safety.

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Revision 2 l

, BRAIDWOOD STATION UNITS 1 & 2 SECOND INTERVAL ISI PROGRAM PLAN-NRC SUBMrITAL RELIEF REQUEST 12R-15 (Page 3 of 3)

6) The selection of component supports for examination per Code Case N-491 is an acceptable alternative approved by the NRC on Regulatory Guide 1.147.

PROPOSED ALTERNATE PROVISIONS '

The requirements of Code Case N-509 will be used to select and examine integrally welded attachments, with exception to the requirement to inspect the integrally welded attachments associated with the component supports selected for examination under the 1990 Addenda, IWF-2510 (Reference footnote 5 of Category B-K and Category C-C Code Case N-509 tables).

Braidwood is implementing Code Case N-491 for support selections and will inspect the integrally welded attachments associated with the component supports selected for examination under Code Case N-491. In addition to those conditions specified in Code Case N 509, a 10%

minimum sample ofintegrally welded attachments for each item in each code class will be inspected. This minimum 10% sampling is consistent with Draft Regulatory Guide DG-1050, Revision 12 to Regulatory Guide 1.147, dated May 1997. The minimum 10% sample shall be distributed proportionally by system.

PERIOD FOR WHICH RELIEF IS REOUESTED Relief is requested for the second ten-year inspection interval of the Inservice Inspection Program for Braidwood Unit 1 and Unit 2.

l 1

)

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