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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2014 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 | ||
FACILITY: Indian Point Nuclear Generating Unit Nos. 2 and 3 | -0001 September 10, 2014 LICENSEE: | ||
Entergy Nuclear Operations, Inc. | |||
FACILITY: | |||
Indian Point Nuclear Generating Unit Nos. 2 and 3 | |||
==SUBJECT:== | ==SUBJECT:== | ||
SUMMARY OF CONFERENCE CALL HELD ON JULY 30, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., REGARDING A DRAFT REQUEST FOR ADDITIONAL INFORMATION ON REMOVAL OF CERTAIN AGING MANAGEMENT REVIEW ITEMS Representatives of the U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. (Entergy or the applicant), held a conference call on July 30, 2014, regarding draft request for additional information (RAI) 3.4.2.1-1 transmitted to Entergy by e-mail dated June 30, 2014. A list of the participants is enclosed. By letter dated September 26, 2012, Entergy provided changes to aging management review (AMR) tables in its license renewal application (LRA). Upon review of the information, the staff questioned the removal of specific AMR items that were previously identified as subject to cracking due to fatigue, which were to be managed by the metal fatigue time-limited aging analysis (TLAA). Therefore, by e-mail dated June 30, 2014, the staff sent a draft RAI to Entergy regarding the basis provided for removal of the specific AMR items. After subsequent discussion among the NRC staff, it requested a call with Entergy to provide clarification on its draft RAI. During the call, the staff stated that what it needed to understand was whether Entergy's basis for removing the AMR items was that the aging effect did not apply because of a temperature threshold or if Entergy was saying that it | SUMMARY OF CONFERENCE CALL HELD ON JULY 30, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., REGARDING A DRAFT REQUEST FOR ADDITIONAL INFORMATION ON REMOVAL OF CERTAIN AGING MANAGEMENT REVIEW ITEMS Representatives of the U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. (Entergy or the applicant) | ||
Entergy stated that the TLAA does not apply to the specific components because the components do not experience the temperatures where cracking due to fatigue is an aging effect of concern; however, the TLAA still exists and had not been eliminated. Entergy stated that its approach is supported by information in the EPRI Fatigue Management Handbook, and Appendix H to the EPRI Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools. Appendix H to EPRI Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools suggests that cracking due to fatigue is not a concern for non-reactor coolant pressure boundary in-line stainless steel components if the maximum temperature of the fluid is less than 270 °F, and is not a concern for non-reactor coolant pressure boundary in-line carbon steel components if the maximum fluid temperature is less than 220 °F. | , held a conference call on July 30, 2014, regarding draft request for additional information (RAI) 3.4.2.1 | ||
-1 transmitted to Entergy by e | |||
-mail dated June 30, 2014. | |||
A list of the participants is enclosed. | |||
By letter dated September 26, 2012, Entergy provided changes to aging management review (AMR) tables in its license renewal application (LRA). Upon review of the information, the staff questioned the removal of specific AMR items that were previously identified as subject to cracking due to fatigue, which were to be managed by the metal fatigue time | |||
-limited aging analysis (TLAA). Therefore, by e | |||
-mail dated June 30, 2014, the staff sent a draft RAI to Entergy regarding the basis provided for removal of the specific AMR items. | |||
After subsequent discussion among the NRC staff, it requested a call with Entergy to provide clarification on its draft RAI. During the call, the staff stated that what it needed to understand was whether Entergy's basis for removing the AMR items was that the aging effect did not apply because of a temperature threshold or if Entergy was saying that it eliminat ed the TLAA. | |||
Entergy stated that the TLAA does not apply to the specific components because the components do not experience the temperatures where cracking due to fatigue is an aging effect of concern; however, the TLAA still exists and had not been eliminated. Entergy stated that its approach is supported by information in the EPRI Fatigue Management Handbook, and Appendix H to the EPRI Non | |||
-Class 1 Mechanical Implementation Guideline and Mechanical Tools. Appendix H to EPRI Non | |||
-Class 1 Mechanical Implementation Guideline and Mechanical Tools suggests that cracking due to fatigue is not a concern for non | |||
-reactor coolant pressure boundary in | |||
-line stainless steel components if the maximum temperature of the fluid is less than 270 °F, and is not a concern for non | |||
-reactor coolant pressure boundary in | |||
-line carbon steel components if the maximum fluid temperature is less than 220 °F. | |||
The staff considered the information in Appendix H to the EPRI Non | |||
-Class 1 Mechanical Implementation Guideline and Mechanical Tools. Based on the staff's review of the information, it determined that no additional information is required. Therefore, the staff will not issue a formal RAI | |||
. The applicant had an opportunity to comment on this summary. | |||
/RA/ Kimberly J. Green, Sr. Mechanical Engineer Aging Management of Plant Systems Branch Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50 | |||
-247 and 50 | |||
-286 | |||
==Enclosure:== | ==Enclosure:== | ||
ML14238A726 | List of Participants | ||
cc w/encl: Listserv | |||
ML14238A726 | |||
*concurrence via e | |||
-mail OFFICE LA: DLR/RPB2 | |||
* PM: DLR/RAPB BC: RPB1:DLR PM: DLR/RAPB NAME IKing KGreen YDiaz KGreen DATE 9/2/2014 9/10/14 9/10/14 9/10/14 | |||
==SUBJECT:== | ==SUBJECT:== | ||
SUMMARY OF CONFERENCE CALL HELD ON JULY 30, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., REGARDING A DRAFT REQUEST FOR ADDITIONAL INFORMATION ON REMOVAL OF CERTAIN AGING MANAGEMENT REVIEW ITEMS HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource | SUMMARY OF CONFERENCE CALL HELD ON JULY 30, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., REGARDING A DRAFT REQUEST FOR ADDITIONAL INFORMATION ON REMOVAL OF CERTAIN AGING MANAGEMENT REVIEW ITEMS HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDeE vib Resource RidsRgn1MailCenter RidsNrrPMIndianPoint RidsOgcMailCenter Resource | ||
------------- | |||
YDiaz MGray, RI KGreen ABurritt, RI JPoehler DonaldJackson, RI SRosenberg MModes, RI AHiser NSheehan, RI OPA AustinYoung DScrenci, RI OPA GCheruvenki DTifft, RI STurk, OGC NMcNamara, RI BMizuno, OGC GNewman, RI DRoth, OGC JSStewart, RI BHarris, OGC AmiPatel, RI SBurnell, OPA DMcIntyre, OPA EDacus, OCA | |||
ENCLOSURE TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JULY 30, 2014 PARTICIPANT S AFFILIATION Kim Green U.S. Nuclear Regulatory Commission (NRC) | |||
Allen Hiser NRC Roger Waters Entergy Nuclear Operations, Inc. (Entergy) | |||
Charlie Caputo Entergy John Curry Entergy Ted Ivy Entergy Alan Cox Entergy}} | |||
Revision as of 11:35, 1 July 2018
| ML14238A726 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/10/2014 |
| From: | Green K J NRC/NRR/DLR/RASB |
| To: | |
| Green K, 415-1627 | |
| References | |
| Download: ML14238A726 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555
-0001 September 10, 2014 LICENSEE:
Entergy Nuclear Operations, Inc.
FACILITY:
Indian Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
SUMMARY OF CONFERENCE CALL HELD ON JULY 30, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., REGARDING A DRAFT REQUEST FOR ADDITIONAL INFORMATION ON REMOVAL OF CERTAIN AGING MANAGEMENT REVIEW ITEMS Representatives of the U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. (Entergy or the applicant)
, held a conference call on July 30, 2014, regarding draft request for additional information (RAI) 3.4.2.1
-1 transmitted to Entergy by e
-mail dated June 30, 2014.
A list of the participants is enclosed.
By letter dated September 26, 2012, Entergy provided changes to aging management review (AMR) tables in its license renewal application (LRA). Upon review of the information, the staff questioned the removal of specific AMR items that were previously identified as subject to cracking due to fatigue, which were to be managed by the metal fatigue time
-limited aging analysis (TLAA). Therefore, by e
-mail dated June 30, 2014, the staff sent a draft RAI to Entergy regarding the basis provided for removal of the specific AMR items.
After subsequent discussion among the NRC staff, it requested a call with Entergy to provide clarification on its draft RAI. During the call, the staff stated that what it needed to understand was whether Entergy's basis for removing the AMR items was that the aging effect did not apply because of a temperature threshold or if Entergy was saying that it eliminat ed the TLAA.
Entergy stated that the TLAA does not apply to the specific components because the components do not experience the temperatures where cracking due to fatigue is an aging effect of concern; however, the TLAA still exists and had not been eliminated. Entergy stated that its approach is supported by information in the EPRI Fatigue Management Handbook, and Appendix H to the EPRI Non
-Class 1 Mechanical Implementation Guideline and Mechanical Tools. Appendix H to EPRI Non
-Class 1 Mechanical Implementation Guideline and Mechanical Tools suggests that cracking due to fatigue is not a concern for non
-reactor coolant pressure boundary in
-line stainless steel components if the maximum temperature of the fluid is less than 270 °F, and is not a concern for non
-reactor coolant pressure boundary in
-line carbon steel components if the maximum fluid temperature is less than 220 °F.
The staff considered the information in Appendix H to the EPRI Non
-Class 1 Mechanical Implementation Guideline and Mechanical Tools. Based on the staff's review of the information, it determined that no additional information is required. Therefore, the staff will not issue a formal RAI
. The applicant had an opportunity to comment on this summary.
/RA/ Kimberly J. Green, Sr. Mechanical Engineer Aging Management of Plant Systems Branch Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50
-247 and 50
-286
Enclosure:
List of Participants
cc w/encl: Listserv
- concurrence via e
-mail OFFICE LA: DLR/RPB2
- PM: DLR/RAPB BC: RPB1:DLR PM: DLR/RAPB NAME IKing KGreen YDiaz KGreen DATE 9/2/2014 9/10/14 9/10/14 9/10/14
SUBJECT:
SUMMARY OF CONFERENCE CALL HELD ON JULY 30, 2014, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., REGARDING A DRAFT REQUEST FOR ADDITIONAL INFORMATION ON REMOVAL OF CERTAIN AGING MANAGEMENT REVIEW ITEMS HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDeE vib Resource RidsRgn1MailCenter RidsNrrPMIndianPoint RidsOgcMailCenter Resource
YDiaz MGray, RI KGreen ABurritt, RI JPoehler DonaldJackson, RI SRosenberg MModes, RI AHiser NSheehan, RI OPA AustinYoung DScrenci, RI OPA GCheruvenki DTifft, RI STurk, OGC NMcNamara, RI BMizuno, OGC GNewman, RI DRoth, OGC JSStewart, RI BHarris, OGC AmiPatel, RI SBurnell, OPA DMcIntyre, OPA EDacus, OCA
ENCLOSURE TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JULY 30, 2014 PARTICIPANT S AFFILIATION Kim Green U.S. Nuclear Regulatory Commission (NRC)
Allen Hiser NRC Roger Waters Entergy Nuclear Operations, Inc. (Entergy)
Charlie Caputo Entergy John Curry Entergy Ted Ivy Entergy Alan Cox Entergy