ML012700108
| ML012700108 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 09/24/2001 |
| From: | Strosnider J R Division of Engineering |
| To: | Marion A Nuclear Energy Institute |
| Carpenter C E, NRR/EMCB, 415-2169 | |
| References | |
| Download: ML012700108 (6) | |
Text
September 24, 2001Mr. Alex Marion, Director Engineering Nuclear Energy Institute 1776 I Street, N.W., Suite 400 Washington, D.C. 20006-3708
SUBJECT:
FLAW EVALUATION CRITERIA
Dear Mr. Marion:
On August 15, 2001, members of the U.S. Nuclear Regulatory Commission (NRC) staffparticipated in a public meeting held at the NRC offices in Rockville, Maryland, with representatives from the Nuclear Energy Institute (NEI), various operating nuclear reactor licensees, and members of the public to discuss NRC expectations regarding pressurized water reactor licensee responses to NRC'sBulletin 2001-01 on circumferential cracking of reactor pressure vessel head penetration nozzles. During this meeting, a request was made of the staff regarding flaw acceptance criteria. The following is our response, which is intended for appropriate use by the industry and the staff. At this time, we are forwarding these criteria to you for comment.FLAW CHARACTERIZATION Flaws must be characterized by both their length and depth. There is currently insufficient dataavailable to assume an aspect ratio if only the flaw length has been determined.
"The proximity rules of ASME Code Section XI for considering flaws as separatemay be used (Figure IWA 3400-1).
"When a flaw is detected, its projections in both the axial and circumferentialdirections shall be determined. Note that the axial direction is always the same for each nozzle head penetration, but that the circumferential direction will be different depending on the angle of intersection of the penetration with the head.
The circumferential direction of interest here is along the top of the attachment weld as illustrated in Figure 1, enclosed. It is this angle along which separation of the nozzle penetration from the head could occur.
"Flaws that are equal to or greater than 45-degrees from the vertical centerline ofthe CRDM nozzle, or those that are within plus or minus 10-degrees of the angle (if less than 45-degrees) that the plane of the partial-penetration attachment weld (J-groove weld) makes with the vertical centerline of the CRDM nozzle, are considered to be circumferential flaws.
Mr. Alex Marion "The location of the flaw relative to the top and bottom of the J-groove weld shallbe determined since the potential exists for development of a leak path if a flaw progresses up the nozzle past this weld. The flaw acceptance criteria are as specified below depending on whether the flaw is in the pressure boundary or in the portion of the nozzle below the J-groove weld.FLAW ACCEPTANCE CRITERIA CRDM Nozzle Pressure BoundaryThe CRDM nozzle pressure boundary includes the J-groove weld and the portion of the nozzleprojecting above the weld. While the CRDM nozzle is an integral part of the reactor vessel, no flaw evaluation rules exist for nonferritic vessels or parts thereof in Section XI. Therefore, the rules for austenitic piping shall be applied with the following exceptions:
"The allowable flaw standards for austenitic piping in Section XI, IWB-3514.3 maybe applied for inside diameter (ID) initiated axial flaws only.
"The rules of IWB-3640 shall apply and the margins maintained after crackgrowth is evaluated for the period of service until the next inspection. The maximum flaw depth allowed by IWB-3640 is 75-percent of the nozzle thickness (refer to crack growth rate below).
"All outside diameter (OD) initiated flaws, regardless of orientation (axial orcircumferential), shall be repaired.
"All ID-initiated circumferentially oriented flaws shall be repaired.
"Any flaw detected in the J-groove weld, its heat affected zone (or adjacent basematerial) must be repaired. Alternatives to Code required repairs will be considered for approval if justified.CRDM Nozzle Below the J-Groove Weld "Axially oriented flaws (either ID- or OD-initiated) are acceptable regardless ofdepth as long as their upper extremity does not reach the bottom of the weldduring the period of service until the next inspection.
"Circumferential flaws (either ID- or OD-initiated) are acceptable provided thatcrack growth is evaluated for the period of service until the next inspection. In no case shall the projected end of cycle circumferential flaw length exceed 75-percent of the nozzle circumference.
"Intersecting axial and circumferential flaws shall be removed or repaired becauseof the greater propensity to develop into loose parts. Note: while flaws below the J-groove weld have no structural significance, loose parts must be avoided.
Mr. Alex Marion- 3 -CRACK GROWTH RATECRDM Nozzle Pressure Boundary "Crack growth to be used for axial ID initiated flaws shall be determined fromCrack Growth and Microstructural Characterization of Alloy 600 Vessel Head Penetration Materials, by Bamford, W. H., and Foster, J. P., EPRI, Palo Alto,CA:1997. TR-109136 (Proprietary).
"There is currently no accepted crack growth rate for the Alloy 182 J-groove weldmaterial.CRDM Nozzle Below the J-Groove Weld "The crack growth rate to be used for the flaws in this region of the nozzle, shallbe the same as that used for ID initiated axial flaws within the CRDM nozzle pressure boundary.Comments or questions should be directed to Keith Wichman of my staff at 301-415-2757.Sincerely,/ra/Jack Strosnider, DirectorDivision of Engineering Office of Nuclear Reactor RegulationProject No. 689 cc: See next page Mr. Alex Marion- 3 -CRACK GROWTH RATECRDM Nozzle Pressure Boundary "Crack growth to be used for axial ID initiated flaws shall be determined fromCrack Growth and Microstructural Characterization of Alloy 600 Vessel Head Penetration Materials, by Bamford, W. H., and Foster, J. P., EPRI, Palo Alto,CA:1997. TR-109136 (Proprietary).
"There is currently no accepted crack growth rate for the Alloy 182 J-groove weldmaterial.CRDM Nozzle Below the J-Groove Weld "The crack growth rate to be used for the flaws in this region of the nozzle, shallbe the same as that used for ID initiated axial flaws within the CRDM nozzle pressure boundary.Comments or questions should be directed to Keith Wichman of my staff at 301-415-2757.Sincerely,Jack Strosnider, DirectorDivision of Engineering Office of Nuclear Reactor RegulationProject No. 689 cc: See next pageDistribution
- EMCB R/FSDuraiswamy
JLarkins BWSheronWDTraversWFKane SJCollins JRJohnsonJAZwolinskiGMHolahan DBMatthews
BABogerMEMayfieldNCChokshi CACarpenter PCWenWHKooMAMitchell CMCraig DHoodWDLanning, R1CCasto, R2 JGrobe, R3 AHowell, R4Document Name: C:\Program Files\Adobe\Acrobat 4.0\PDF Output\NEI Flaw Evaluation Criteria.wpdINDICATE IN BOX: "C"=COPY W/O ATTACHMENT/ENCLOSURE, "E"=COPY W/ATT/ENCL, "N"=NO COPY EMCB:DEEEMCB:DEEEMCB:DEEDE:DECECarpenter:cecKRWichman:krwWHBateman:whbJRStrosnider:jrs 09/14/200109/24/200109/ 24/200109/24/2001OFFICIAL RECORD COPY cc:Ralph Beedle, Senior Vice President and Chief Nuclear Officer Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708Mr. Jack Bailey, Chair Materials Reliability Program 1101 Market Street - LP 6A Chattanooga, TN 37402Larry Mathews, MRP Southern Nuclear Operating Company Manager, Inspection and Testing Services P. O. Box 1295 Birmingham, AL 35201Vaughn Wagoner, Technical Chair Assessment Committee Carolina Power & Light Company One Hannover Square 9C1 P.O. Box 1551 Raleigh, NC 27612Frank Ammirato, EPRI Inspection Manager EPRI NDE Center P. O. Box 217097 1300 W. T. Harris Blvd.
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