ML13171A368: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
(One intermediate revision by the same user not shown) | |||
Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 July 2,2013 LICENSEE: | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 2,2013 LICENSEE: Entergy Nuclear Operations, Inc. | ||
Entergy Nuclear Operations, Inc. FACILITY: | FACILITY: IndiaI'! Point Nuclear Generating Unit Nos. 2 and 3 | ||
IndiaI'! Point Nuclear Generating Unit Nos. 2 and 3 | |||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF CONFERENCE CALL HELD ON JUNE 4, 2013, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO RAIS REGARDING THE REACTOR VESSEL INTERNALS PROGRAM AT INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 Representatives of the U.S. Nuclear Regulatory Commission (NRC or the staff), and representatives of Entergy Nuclear Operations, Inc., (Entergy or the applicant) and Westinghouse, held a conference call on June 4, 2013, for the staff to obtain clarification on a response to a request for additional information (RAI) dated May 7,2013 (ADAMS Accession No. ML13142A202) related to the Indian Point (IP) Nuclear Generating Unit Nos. 2 and 3 license renewal application. | OF CONFERENCE CALL HELD ON JUNE 4, 2013, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO RAIS REGARDING THE REACTOR VESSEL INTERNALS PROGRAM AT INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 Representatives of the U.S. Nuclear Regulatory Commission (NRC or the staff), and representatives of Entergy Nuclear Operations, Inc., (Entergy or the applicant) and Westinghouse, held a conference call on June 4, 2013, for the staff to obtain clarification on a response to a request for additional information (RAI) dated May 7,2013 (ADAMS Accession No. ML13142A202) related to the Indian Point (IP) Nuclear Generating Unit Nos. 2 and 3 license renewal application. A list of the participants is enclosed. | ||
A list of the participants is enclosed. | |||
The staff requested clarification on the following responses: | The staff requested clarification on the following responses: | ||
Response to RAI 11a: Clarify whether the evaluation of the lower support columns will be performed regardless of the results of the screening for thermal embrittlement susceptibility. | Response to RAI 11a: | ||
* Clarify whether the evaluation of the lower support columns will be performed regardless of the results of the screening for thermal embrittlement susceptibility. | |||
The applicant stated that the staff's understanding of the response is correct-Entergy will perform the evaluation of the lower support columns if they screen for thermal or irradiation embrittlement. | The applicant stated that the staff's understanding of the response is correct-Entergy will perform the evaluation of the lower support columns if they screen for thermal or irradiation embrittlement. | ||
The staff does not require a follow-up RAI for this matter. Does Entergy plan to revise its response to RAI 11 a based on information that was presented during the public meeting held on May 21, 2013? Entergy stated that it would revise its response to RAI 11 a if necessary, but that could not be determined until the industry document has been issued and it has had an opportunity to review the document. | The staff does not require a follow-up RAI for this matter. | ||
The staff will not issue a follow-up RAI at this time, but might issue one in the future if warranted. Can Entergy verify the grade the cast austenitic stainless steel for the lower support columns? Entergy can provide the grade information. | * Does Entergy plan to revise its response to RAI 11 a based on information that was presented during the public meeting held on May 21, 2013? | ||
-The staff will issue a follow-up RAI to obtain this information on the docket. | Entergy stated that it would revise its response to RAI 11 a if necessary, but that could not be determined until the industry document has been issued and it has had an opportunity to review the document. | ||
Entergy stated that it can define what it means by "significant tensile stresses." The staff will issue a follow-up RAI to obtain Entergy's definition of "significant tensile stresses." Response to RAI 15a: There is an apparent inconsistency between the correction that was made to the response to RAI 12 regarding the term "Class 1" and the mark up to LRA Sections A.2.2.2.1 and A.3.2.2.1 in response to RAI 15a. . *Entergy stated that it can remedy the inconsistency. | The staff will not issue a follow-up RAI at this time, but might issue one in the future if warranted. | ||
* Can Entergy verify the grade the cast austenitic stainless steel for the lower support columns? | |||
Entergy can provide the grade information. | |||
- 2 The staff will issue a follow-up RAI to obtain this information on the docket. | |||
* Can Entergy provide a more detailed basis for the number of columns that will be assumed to contain flaws, including a description of any relevant operating experience | |||
. or research supporting the assumed incidence of cracking in the columns? | |||
Entergy stated that it can provide a technical basis. | |||
The staff will issue a follow-up RAI to obtain a detailed basis for the assumptions relative to the number of columns that will be assumed to contain flaws. | |||
* Can Entergy define what is meant by "significant tensile stresses"? | |||
Entergy stated that it can define what it means by "significant tensile stresses." | |||
The staff will issue a follow-up RAI to obtain Entergy's definition of "significant tensile stresses." | |||
Response to RAI 15a: | |||
There is an apparent inconsistency between the correction that was made to the response to RAI 12 regarding the term "Class 1" and the mark up to LRA Sections A.2.2.2.1 and A.3.2.2.1 in response to RAI 15a. . | |||
*Entergy stated that it can remedy the inconsistency. | |||
The staff will issue a follow-up RAI to request that Entergy fix the inconsistency. | |||
The applicant had an opportunity to comment on this summary. | |||
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 | |||
TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JUNE 4,2013 PARTICIPANTS: AF FI LlATIONS: | |||
Kim Green U.S. Nuclear Regulatory Commission (NRC) | |||
Jeffrey Poehler NRC Allen Hiser NRC Roger Waters Entergy Nuclear Operations, Inc. (Entergy) | |||
Alan Cox Entergy Nelson Azevedo Entergy Peter Guglielmino Entergy John Curry Entergy Michael Burke Westinghouse David Radonovich Westinghouse Bradford Grimmel Westinghouse Sallie Carrera Westinghouse ENCLOSURE | |||
-2 The staff will issue a follow-up RAI to obtain this information on the docket. | |||
* Can Entergy provide a more detailed basis for the number of columns that will be assumed to contain flaws, including a description of any relevant operating experience or research supporting the assumed incidence of cracking in the columns? | |||
The staff will issue a follow-up RAI to obtain a detailed basis for the aSl?umptions relative to the number of columns that will be assumed to contain flaws. | |||
* Can Entergy define what is meant by "significant tensile stresses"? | |||
Entergy stated that it can define what it means by "significant tensile stresses." | |||
The staff will issue a follow-up RAI to obtain Entergy's definition of "significant tensile stresses." | |||
Response to RA115a: | |||
There is an apparent inconsistency between the correction that was made to the response to RAI12 regarding the term "Class 1"and the mark up to LRA Sections A.2.2.2.1 and A.3.2.2.1 in response to RAI 15a. | |||
Entergy stated that it can remedy the inconsistency. | |||
The staff will issue a follow-up RAI to request that Entergy fix the inconsistency. | The staff will issue a follow-up RAI to request that Entergy fix the inconsistency. | ||
The applicant had an opportunity to comment on this summary. 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 | The applicant had an opportunity to comment on this summary. | ||
IRA! | |||
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:== | ||
L~st of Participants cc w/encl: Listserv DISTRIBUTION: | |||
See next page ADAMS Accession No.: *concurrence via e-mail r===========~======= | |||
LA: DLR/RPB1* PM: BC: RPB1 :DLR PM: DLRI NAME YEdmonds KGreen YDiaz KGreen DATE 7/2/13 7/2/13 7/2/13 7/2/13 OFFICIAL RECORD COpy | |||
LA: DLR/RPB1* | |||
BC: RPB1 :DLR PM: DLRI | |||
==SUBJECT:== | ==SUBJECT:== | ||
Line 50: | Line 82: | ||
OF CONFERENCE CALL HELD ON JUNE 4,2013, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO RAIS REGARDING THE REACTOR VESSEL INTERNALS PROGRAM AT INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DISTRIBUTION: | OF CONFERENCE CALL HELD ON JUNE 4,2013, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO RAIS REGARDING THE REACTOR VESSEL INTERNALS PROGRAM AT INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DISTRIBUTION: | ||
HARDCOPY: | HARDCOPY: | ||
DLRRF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDraAfpb Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource YDiaz KGreen JTrapp, RI JPoehler DJackson, RI AHiser DScrenci, RI OPA DPickett PCataldo, RI STurk,OGC NMcNamara, RI BMizuno, OGC BWelling, RI SBurnell, OPA KDunham, RI DMclntyre,OPA MCatts, RI EDacus,OCA MHalter, RI NSheehan, RI OPA SStewart, RI GMeyer, RI APatel, RI}} | DLRRF E-MAIL: | ||
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDraAfpb Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource YDiaz KGreen JTrapp, RI JPoehler DJackson, RI AHiser DScrenci, RI OPA DPickett PCataldo, RI STurk,OGC NMcNamara, RI BMizuno, OGC BWelling, RI SBurnell, OPA KDunham, RI DMclntyre,OPA MCatts, RI EDacus,OCA MHalter, RI NSheehan, RI OPA SStewart, RI GMeyer, RI APatel, RI}} |
Latest revision as of 04:44, 6 February 2020
ML13171A368 | |
Person / Time | |
---|---|
Site: | Indian Point |
Issue date: | 07/02/2013 |
From: | Kimberly Green NRC/NRR/DLR/RAPB |
To: | |
Green K, 415-1627 | |
References | |
Download: ML13171A368 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 2,2013 LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: IndiaI'! Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
SUMMARY
OF CONFERENCE CALL HELD ON JUNE 4, 2013, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO RAIS REGARDING THE REACTOR VESSEL INTERNALS PROGRAM AT INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 Representatives of the U.S. Nuclear Regulatory Commission (NRC or the staff), and representatives of Entergy Nuclear Operations, Inc., (Entergy or the applicant) and Westinghouse, held a conference call on June 4, 2013, for the staff to obtain clarification on a response to a request for additional information (RAI) dated May 7,2013 (ADAMS Accession No. ML13142A202) related to the Indian Point (IP) Nuclear Generating Unit Nos. 2 and 3 license renewal application. A list of the participants is enclosed.
The staff requested clarification on the following responses:
Response to RAI 11a:
- Clarify whether the evaluation of the lower support columns will be performed regardless of the results of the screening for thermal embrittlement susceptibility.
The applicant stated that the staff's understanding of the response is correct-Entergy will perform the evaluation of the lower support columns if they screen for thermal or irradiation embrittlement.
The staff does not require a follow-up RAI for this matter.
- Does Entergy plan to revise its response to RAI 11 a based on information that was presented during the public meeting held on May 21, 2013?
Entergy stated that it would revise its response to RAI 11 a if necessary, but that could not be determined until the industry document has been issued and it has had an opportunity to review the document.
The staff will not issue a follow-up RAI at this time, but might issue one in the future if warranted.
- Can Entergy verify the grade the cast austenitic stainless steel for the lower support columns?
Entergy can provide the grade information.
- 2 The staff will issue a follow-up RAI to obtain this information on the docket.
- Can Entergy provide a more detailed basis for the number of columns that will be assumed to contain flaws, including a description of any relevant operating experience
. or research supporting the assumed incidence of cracking in the columns?
Entergy stated that it can provide a technical basis.
The staff will issue a follow-up RAI to obtain a detailed basis for the assumptions relative to the number of columns that will be assumed to contain flaws.
- Can Entergy define what is meant by "significant tensile stresses"?
Entergy stated that it can define what it means by "significant tensile stresses."
The staff will issue a follow-up RAI to obtain Entergy's definition of "significant tensile stresses."
Response to RAI 15a:
There is an apparent inconsistency between the correction that was made to the response to RAI 12 regarding the term "Class 1" and the mark up to LRA Sections A.2.2.2.1 and A.3.2.2.1 in response to RAI 15a. .
- Entergy stated that it can remedy the inconsistency.
The staff will issue a follow-up RAI to request that Entergy fix the inconsistency.
The applicant had an opportunity to comment on this summary.
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
TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JUNE 4,2013 PARTICIPANTS: AF FI LlATIONS:
Kim Green U.S. Nuclear Regulatory Commission (NRC)
Jeffrey Poehler NRC Allen Hiser NRC Roger Waters Entergy Nuclear Operations, Inc. (Entergy)
Alan Cox Entergy Nelson Azevedo Entergy Peter Guglielmino Entergy John Curry Entergy Michael Burke Westinghouse David Radonovich Westinghouse Bradford Grimmel Westinghouse Sallie Carrera Westinghouse ENCLOSURE
-2 The staff will issue a follow-up RAI to obtain this information on the docket.
- Can Entergy provide a more detailed basis for the number of columns that will be assumed to contain flaws, including a description of any relevant operating experience or research supporting the assumed incidence of cracking in the columns?
The staff will issue a follow-up RAI to obtain a detailed basis for the aSl?umptions relative to the number of columns that will be assumed to contain flaws.
- Can Entergy define what is meant by "significant tensile stresses"?
Entergy stated that it can define what it means by "significant tensile stresses."
The staff will issue a follow-up RAI to obtain Entergy's definition of "significant tensile stresses."
Response to RA115a:
There is an apparent inconsistency between the correction that was made to the response to RAI12 regarding the term "Class 1"and the mark up to LRA Sections A.2.2.2.1 and A.3.2.2.1 in response to RAI 15a.
Entergy stated that it can remedy the inconsistency.
The staff will issue a follow-up RAI to request that Entergy fix the inconsistency.
The applicant had an opportunity to comment on this summary.
IRA!
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:
L~st of Participants cc w/encl: Listserv DISTRIBUTION:
See next page ADAMS Accession No.: *concurrence via e-mail r===========~=======
LA: DLR/RPB1* PM: BC: RPB1 :DLR PM: DLRI NAME YEdmonds KGreen YDiaz KGreen DATE 7/2/13 7/2/13 7/2/13 7/2/13 OFFICIAL RECORD COpy
SUBJECT:
SUMMARY
OF CONFERENCE CALL HELD ON JUNE 4,2013, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING RESPONSES TO RAIS REGARDING THE REACTOR VESSEL INTERNALS PROGRAM AT INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 DISTRIBUTION:
HARDCOPY:
DLRRF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDraAfpb Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource YDiaz KGreen JTrapp, RI JPoehler DJackson, RI AHiser DScrenci, RI OPA DPickett PCataldo, RI STurk,OGC NMcNamara, RI BMizuno, OGC BWelling, RI SBurnell, OPA KDunham, RI DMclntyre,OPA MCatts, RI EDacus,OCA MHalter, RI NSheehan, RI OPA SStewart, RI GMeyer, RI APatel, RI