ML073381315: Difference between revisions
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| issue date = 12/03/2007 | | issue date = 12/03/2007 | ||
| title = Draft RAI for Relief Request No. 15 | | title = Draft RAI for Relief Request No. 15 | ||
| author name = Tam P | | author name = Tam P | ||
| author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1 | | author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1 | ||
| addressee name = Arias J, Blake T, Loeffler R | | addressee name = Arias J, Blake T, Loeffler R | ||
| Line 9: | Line 9: | ||
| docket = 05000263 | | docket = 05000263 | ||
| license number = | | license number = | ||
| contact person = tam P | | contact person = tam P, NRR/ADRO/DORL, 415-1451 | ||
| case reference number = TAC MD6854 | | case reference number = TAC MD6854 | ||
| document type = E-Mail | | document type = E-Mail | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:From: | {{#Wiki_filter:From: Peter Tam To: Arias, Jesus; Loeffler, Rick; tmblake@nmcco.com Date: 12/3/2007 1:31:07 PM | ||
==Subject:== | ==Subject:== | ||
Monticello - Draft RAI for Relief Request No.15 (TAC MD6854) | Monticello - Draft RAI for Relief Request No.15 (TAC MD6854) | ||
Rick, Jay: | Rick, Jay: | ||
By letter dated September 26, 2007, Nuclear Management Company requested relief from certain examination coverage requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, for the Monticello Nuclear Generating Plant. Our reviewer, John Tsao, has written the following draft RAI questions. We would like to discuss these with you in a conference call in the near future. However, with or without the conference call, I plan to formally issue the questions in a formal RAI in early January 2008. . | |||
By letter dated September 26, 2007, Nuclear Management Company requested relief from certain examination coverage requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, for the Monticello Nuclear Generating Plant. Our reviewer, John Tsao, has written the following draft RAI questions. We would like to discuss these with you in a conference call in the near future. However, with or without the conference call, I plan to formally issue the questions in a formal RAI in early January 2008. . | : 1. Discuss the applicable edition or addenda of the ASME Code, Section XI, Appendix VIII, for the ultrasonic examination of the subject welds during the 2007 refueling outage and for the remaining fourth 10-year inservice inspection (ISI) interval. | ||
: 1. Discuss the applicable edition or addenda of the ASME Code, Section XI, Appendix VIII, for the ultrasonic examination of the subject welds during the 2007 refueling outage and for the remaining fourth 10-year inservice inspection (ISI) interval. | : 2. Discuss the future inspection frequency of the subject welds in the fourth ISI interval. | ||
: 2. Discuss the future inspection frequency of the subject welds in the fourth ISI interval. | : 3. On page 4 of Request No. 15, the licensee discussed the UT inspection of the subject welds during the 2007 outage without providing the previous history of the ultrasonic examinations. Discuss the history of volumetric examinations of the subject welds, including specific year and during which ISI interval, inspection results, and examination coverage. | ||
: 3. On page 4 of Request No. 15, the licensee discussed the UT inspection of the subject welds during the 2007 outage without providing the previous history of the ultrasonic examinations. Discuss the history of volumetric examinations of the subject welds, including specific year and during which ISI interval, inspection results, and examination coverage. | Discuss whether relief was requested for the examination coverage of the subject welds in the previous 10-year ISI intervals. If not, discuss why the 100% examination coverage was achieved in the previous examination(s) but not in the 2007 refueling outage. | ||
Discuss whether relief was requested for the examination coverage of the subject welds in the previous 10-year ISI intervals. If not, discuss why the 100% examination coverage was achieved in the previous examination(s) but not in the 2007 refueling outage. | : 4. On page 5 of Request No.15, the licensee stated that the materials for subject components are A508 Class II nozzle forgings welded to A533, Class I vessel shell plate. | ||
: 4. On page 5 of Request No.15, the licensee stated that the materials for subject components are A508 Class II nozzle forgings welded to A533, Class I vessel shell plate. | |||
However, the material specifications of the welds and associated piping were not provided. | However, the material specifications of the welds and associated piping were not provided. | ||
Discuss material specifications for the following components: welds, pipes, safe ends, and butter (if applicable). | Discuss material specifications for the following components: welds, pipes, safe ends, and butter (if applicable). | ||
: 5. On page 5 of Request No. 15, the licensee stated that a review of operating experience within the nuclear industry did not reveal any instance of cracking in this [the nozzle] location and the type of weldment. The staff notes that feedwater nozzles to the reactor vessel have experienced cracking as discussed in the NRC report, NUREG-0619, ABWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking,@ November 1980. Discuss whether the feedwater nozzles in Monticello have experienced cracking and whether feedwater nozzle inspection frequency follows NUREG-0619. | : 5. On page 5 of Request No. 15, the licensee stated that a review of operating experience within the nuclear industry did not reveal any instance of cracking in this [the nozzle] location and the type of weldment. The staff notes that feedwater nozzles to the reactor vessel have experienced cracking as discussed in the NRC report, NUREG-0619, ABWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking,@ November 1980. Discuss whether the feedwater nozzles in Monticello have experienced cracking and whether feedwater nozzle inspection frequency follows NUREG-0619. | ||
: 6. In Enclosure 2, Table A, of the September 26, 2007, submittal, the licensee calculated various percentages of examination coverage obtained for each of the five welds. The staff calculated the percentages of examination coverage of the subject welds using the diagrams in | : 6. In Enclosure 2, Table A, of the September 26, 2007, submittal, the licensee calculated various percentages of examination coverage obtained for each of the five welds. The staff calculated the percentages of examination coverage of the subject welds using the diagrams in of the submittal. However, the staff was not able to verify the percentages of coverage as shown in Table A. Provide detailed calculations of the percentages of coverage. | ||
It is not clear from the diagrams in Enclosure 3 of the September 26, 2007, submittal whether | |||
It is not clear from the diagrams in Enclosure 3 of the September 26, 2007, submittal whether | |||
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | the unexamined volume is in the reactor vessel nozzles, the welds, butter, or safe ends. Please provide the axial dimensions for the weld, piping, and safe end. Also identify the interface line among the weld, nozzle, safe end, and pipe. | ||
This e-mail aims solely to prepare you and others for the proposed conference call. It does not convey a formal NRC staff position, and does not formally request for information. | |||
e-mail: pst@nrc.gov | Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation e-mail: pst@nrc.gov Tel.: 301-415-1451 CC: Chawla, Mahesh; Terence Chan; Tsao, John Mail Envelope Properties (47544B6B.C28 : 12 : 35330) | ||
CC: Chawla, Mahesh; | |||
Mail Envelope Properties (47544B6B.C28 : 12 : 35330) | |||
==Subject:== | ==Subject:== | ||
Monticello - Draft RAI for Relief Request No.15 (TAC MD6854) | Monticello - Draft RAI for Relief Request No.15 (TAC MD6854) | ||
Creation Date 12/3/2007 1:31:07 PM From: | Creation Date 12/3/2007 1:31:07 PM From: Peter Tam Created By: PST@nrc.gov Recipients Action Date & Time nmcco.com Transferred 12/3/2007 1:31:33 PM Jesus.Arias (Jesus Arias) | ||
Richard.Loeffler (Rick Loeffler) tmblake (tmblake@nmcco.com) | Richard.Loeffler (Rick Loeffler) tmblake (tmblake@nmcco.com) nrc.gov OWGWPO03.HQGWDO01 Delivered 12/3/2007 1:31:15 PM MLC CC (Mahesh Chawla) Opened 12/3/2007 2:03:18 PM TLC CC (Terence Chan) nrc.gov TWGWPO02.HQGWDO01 Delivered 12/3/2007 1:31:07 PM JCT CC (John Tsao) Opened 12/3/2007 1:56:15 PM Post Office Delivered Route nmcco.com OWGWPO03.HQGWDO01 12/3/2007 1:31:15 PM nrc.gov | ||
nrc.gov OWGWPO03.HQGWDO01 Delivered 12/3/2007 1:31:15 PM MLC CC (Mahesh Chawla) Opened 12/3/2007 2:03:18 PM TLC CC (Terence Chan) | |||
TWGWPO02.HQGWDO01 12/3/2007 1:31:07 PM nrc.gov Files Size Date & Time MESSAGE 5088 12/3/2007 1:31:07 PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed | |||
==Subject:== | ==Subject:== | ||
No | No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened}} | ||
Latest revision as of 01:05, 23 November 2019
| ML073381315 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/03/2007 |
| From: | Tam P NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Arias J, Blake T, Loeffler R Nuclear Management Co |
| tam P, NRR/ADRO/DORL, 415-1451 | |
| References | |
| TAC MD6854 | |
| Download: ML073381315 (3) | |
Text
From: Peter Tam To: Arias, Jesus; Loeffler, Rick; tmblake@nmcco.com Date: 12/3/2007 1:31:07 PM
Subject:
Monticello - Draft RAI for Relief Request No.15 (TAC MD6854)
Rick, Jay:
By letter dated September 26, 2007, Nuclear Management Company requested relief from certain examination coverage requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, for the Monticello Nuclear Generating Plant. Our reviewer, John Tsao, has written the following draft RAI questions. We would like to discuss these with you in a conference call in the near future. However, with or without the conference call, I plan to formally issue the questions in a formal RAI in early January 2008. .
- 1. Discuss the applicable edition or addenda of the ASME Code,Section XI, Appendix VIII, for the ultrasonic examination of the subject welds during the 2007 refueling outage and for the remaining fourth 10-year inservice inspection (ISI) interval.
- 2. Discuss the future inspection frequency of the subject welds in the fourth ISI interval.
- 3. On page 4 of Request No. 15, the licensee discussed the UT inspection of the subject welds during the 2007 outage without providing the previous history of the ultrasonic examinations. Discuss the history of volumetric examinations of the subject welds, including specific year and during which ISI interval, inspection results, and examination coverage.
Discuss whether relief was requested for the examination coverage of the subject welds in the previous 10-year ISI intervals. If not, discuss why the 100% examination coverage was achieved in the previous examination(s) but not in the 2007 refueling outage.
- 4. On page 5 of Request No.15, the licensee stated that the materials for subject components are A508 Class II nozzle forgings welded to A533, Class I vessel shell plate.
However, the material specifications of the welds and associated piping were not provided.
Discuss material specifications for the following components: welds, pipes, safe ends, and butter (if applicable).
- 5. On page 5 of Request No. 15, the licensee stated that a review of operating experience within the nuclear industry did not reveal any instance of cracking in this [the nozzle] location and the type of weldment. The staff notes that feedwater nozzles to the reactor vessel have experienced cracking as discussed in the NRC report, NUREG-0619, ABWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking,@ November 1980. Discuss whether the feedwater nozzles in Monticello have experienced cracking and whether feedwater nozzle inspection frequency follows NUREG-0619.
- 6. In Enclosure 2, Table A, of the September 26, 2007, submittal, the licensee calculated various percentages of examination coverage obtained for each of the five welds. The staff calculated the percentages of examination coverage of the subject welds using the diagrams in of the submittal. However, the staff was not able to verify the percentages of coverage as shown in Table A. Provide detailed calculations of the percentages of coverage.
It is not clear from the diagrams in Enclosure 3 of the September 26, 2007, submittal whether
the unexamined volume is in the reactor vessel nozzles, the welds, butter, or safe ends. Please provide the axial dimensions for the weld, piping, and safe end. Also identify the interface line among the weld, nozzle, safe end, and pipe.
This e-mail aims solely to prepare you and others for the proposed conference call. It does not convey a formal NRC staff position, and does not formally request for information.
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation e-mail: pst@nrc.gov Tel.: 301-415-1451 CC: Chawla, Mahesh; Terence Chan; Tsao, John Mail Envelope Properties (47544B6B.C28 : 12 : 35330)
Subject:
Monticello - Draft RAI for Relief Request No.15 (TAC MD6854)
Creation Date 12/3/2007 1:31:07 PM From: Peter Tam Created By: PST@nrc.gov Recipients Action Date & Time nmcco.com Transferred 12/3/2007 1:31:33 PM Jesus.Arias (Jesus Arias)
Richard.Loeffler (Rick Loeffler) tmblake (tmblake@nmcco.com) nrc.gov OWGWPO03.HQGWDO01 Delivered 12/3/2007 1:31:15 PM MLC CC (Mahesh Chawla) Opened 12/3/2007 2:03:18 PM TLC CC (Terence Chan) nrc.gov TWGWPO02.HQGWDO01 Delivered 12/3/2007 1:31:07 PM JCT CC (John Tsao) Opened 12/3/2007 1:56:15 PM Post Office Delivered Route nmcco.com OWGWPO03.HQGWDO01 12/3/2007 1:31:15 PM nrc.gov
TWGWPO02.HQGWDO01 12/3/2007 1:31:07 PM nrc.gov Files Size Date & Time MESSAGE 5088 12/3/2007 1:31:07 PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed
Subject:
No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened