ML093010525
| ML093010525 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/28/2009 |
| From: | Kalyanam N Office of Nuclear Reactor Regulation |
| To: | Susan Lent Office of Nuclear Reactor Regulation |
| Kalyanam N, NRR/DORL/LP4, 415-1480 | |
| References | |
| TAC ME2411 | |
| Download: ML093010525 (3) | |
Text
From:
Kalyanam, Kaly Sent:
Wednesday, October 28, 2009 2:30 PM To:
Lent, Susan
Subject:
FW: FORMAL RAI for W3-ISI-016 From: Kalyanam, Kaly Sent: Wednesday, October 28, 2009 1:51 PM To: 'MURILLO, ROBERT J'; 'POLLOCK, JIM'
Subject:
FORMAL RAI for W3-ISI-016 By letter dated October 19, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092940243), Entergy Operations, Inc. (the licensee), submitted its third 10-year inservice inspection interval Request for Alternative, W3-ISI-016, from the inspection requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Code Case N-729-1, for Waterford 3 Steam Electric Station, Unit 3 (Waterford 3).
We have reviewed the application and determined that additional information contained in the enclosure is needed to complete the review. The U.S. Nuclear Regulatory Commission staff discussed the need for additional information on October 28, 2009, with Mr. J. Pollock of your staff. Mr. Pollock agreed to provide a response in as short a time as possible, in view of the request being outage related. Also, in view of the short turn around time, this email, which will be included in the ADAMS, may please be treated as a formal RAI.
If you have any questions, please contact me at (301) 415-1480 or by electronic mail at kaly.kalyanam@nrc.gov.
OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR ALTERNATIVE W3-ISI-016, INSPECTION OF REACTOR PRESSURE VESSEL HEAD CONTROL ELEMENTDRIVE MECHANISM NOZZLES DURING THIRD TEN-YEAR INSERVICE INSPECTION INTERVAL WATERFORD STEAM ELECTRIC STATION, UNIT 3 ENTERGY OPERATIONS, INC.
DOCKET NO.: 50-382
- 1. Please specify the manufacturer, heat and heat treatment of the control element drive mechanism (CEDM) penetration tubes. Has this specific material shown an industry history of primary water stress corrosion cracking?
- 2. Please describe any changes in the values of the free span lengths in the Table Waterford 3 CEDM Nozzle As-Built Free Span Lengths in Enclosure 2 of Reference 1 that have resulted from previous inspections.
- 3. Please describe any changes due to further analysis that have been made in the predicted crack growth per cycle found in Table 13 in Reference 2.
- 4. Please verify that comparing the free span length values found in Reference 1 with the values found in the column Growth / Cycle in Table 13 of Reference 2 is appropriate to show that postulated cracks outside of the ultrasonic examination area will not propagate to the toe of the J-groove weld during one refueling cycle.
- 5. Please verify that the bounding estimate of the crack growth per cycle for each nozzle is that for the nozzle angle in Table 13 that is greater than or equal to the nozzle angle being considered.
References
- 1. Letter dated August 13, 2004, Response to NRC Request for Additional Information Pertaining to Waterford 3 Relaxation Request #4 to NRC Order EA-03-009 for the Control Element Drive Mechanism Nozzles (TAC No. MC2643), ADAMS Accession No. ML0432320558.
- 2. Letter dated September 15, 2003, Enclosure 2 to CNRO-2004-00039, ADAMS Accession No. ML032790354.
E-mail Properties Mail Envelope Properties (94A2A4408AC65F42AC084527534CF416B4D30559)
Subject:
FW: FORMAL RAI for W3-ISI-016 Sent Date: 10/28/2009 2:30:23 PM Received Date: 10/28/2009 2:30:23 PM From: Kalyanam, Kaly Created By: Kaly.Kalyanam@nrc.gov Recipients:
Susan.Lent@nrc.gov (Lent, Susan)
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HQCLSTR01.nrc.gov
Files Size Date & Time MESSAGE 13118 10/28/2009 Options Expiration Date:
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