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{{#Wiki_filter:REGI/{ UNITED STATES NUCLEAR REGULATORY COMMISSION  
{{#Wiki_filter:~",R REGI/{                                     UNITED STATES
! WASHINGTON, D.C. 20555-0001 0 : April 11, 2012 STP Nuclear Operating Company South Texas Project SUMMAHY OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 16, 2012, BETWEEN THE U.s. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION ON REACTOR VESSEL INTERNALS.
    ~.;:,(,'"          "1;.o~                  NUCLEAR REGULATORY COMMISSION
FOR THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, liCENSE RENEWAL APPLICATION (TAC. NOS. ME4936 AND ME4937) The U.S. Nuciear Regulatory Commission (NRC or the staff) and representatives of STP Nuclear Operating Company (STPNOC or the applicant) held a telephone conference call on February 16, 2012, to discuss requests for additional information (RAls) on aspects of the applicant's reactor vessel internals (RVis), for the South Texas Project, Units 1 and 2, license renewal application, The telephone conference call was useful in clarifying the staffs requests and the al)plicant's questions for the RAls. Enclosure 1 provides a listing of the participants and 2 contains a summary of tt1e discussion, The applicant had an opportunity to comment on this sUmmal-Y.
!                           ~                          WASHINGTON, D.C. 20555-0001
John Daily, Senior Project Manager Prcjects Branch 1 Division of License Renewa! Office of Nuclear Reactor Regulation Docket Nos 50-498 and 50-499  
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~!  ~.,              ~o April 11, 2012
            ****~
LICENSEE:      STP Nuclear Operating Company FACILITY:      South Texas Project
 
==SUBJECT:==
SUMMAHY OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 16, 2012, BETWEEN THE U.s. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION ON REACTOR VESSEL INTERNALS. FOR THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, liCENSE RENEWAL APPLICATION (TAC. NOS. ME4936 AND ME4937)
The U.S. Nuciear Regulatory Commission (NRC or the staff) and representatives of STP Nuclear Operating Company (STPNOC or the applicant) held a telephone conference call on February 16, 2012, to discuss requests for additional information (RAls) on aspects of the applicant's reactor vessel internals (RVis), for the South Texas Project, Units 1 and 2, license renewal application, The telephone conference call was useful in clarifying the staffs requests and the al)plicant's questions for the RAls.
Enclosure 1 provides   a listing of the participants and Enc;t)sur~ 2 contains a summary of tt1e discussion, The applicant had an opportunity to comment on this sUmmal-Y.
John Daily, Senior Project Manager Prcjects Branch 1 Division of License Renewa!
Office of Nuclear Reactor Regulation Docket Nos 50-498 and 50-499


==Enclosures:==
==Enclosures:==


As stated cc w/encls: Listserv TELEPHONE CONFERENCE SOUTH TEXAS LICENSE RENEWAL LIST OF February 16, PARTICIPANTS AFFILIATIONS John Daily Nuclear Regulatory Commission (NRC) Seung Min NRC Arden Aldridge STP Nuclear Operating Company (STPNOC) Ken Taplett STPNOC Gary Warner STARS Center of Business -Worley Parsons Gordon Chen STARS Center of Business -Worley Parsons ENCLOSURE CONFERENCE CALL WITH REGARDING CERTAIN ASPECTS OF RVI STP LICENSE RENEWAL February 16, The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Nuclear Operating Company (STPNOC or the applicant) held a telephone conference call February 16, 2012, to discuss requests for additional information (RAls) on aspects of applicant's reactor vessel internals (RVls), for the South Texas Project, Units 1 and 2, renewal The participants indicated that the calls were useful in clarifying the questions The staff and the applicant discussed the Reactor Vessel Internals  
As stated cc w/encls: Listserv
-Cast Austenitic Stainless Steel (073) RAI3.1.1.80-1a The staff explained its need for clarification as to whether the PWR Reactor Internals Program identifies the upper core plate as an expansion component linked to the Control Rod Guide Tube (CRGT) lower flange welds to manage loss of material due to wear and cracking due to fatigue, as specified in the staffs safety evaluation (June 22,2011) of MRP-227, Revision O. In addition, the staff also explained the request to clarify whether the applicant's PWR Reactor Internals Program identifies the lower internals assembly lower support forging, or casting, as an expansion component linked to the CRGT lower flange welds to ensure adequate aging management and structural integrity, consistent with the staff's safety evaluation (June 22, 2011) of MRP-227, Revision O. RAI 3.1.1.80-2a The staff discussed the request concerning whether the CRGT lower flanges are made of Cast Austenitic Stainless Steel (CASS). If the CRGT lower flanges are made of CASS, the staff needs to further clarify if loss of fracture toughness, in addition to cracking, is considered as an aging effect to be managed by the PWR Reactor Internals Program for these components.
 
In addition, the staff needs clarification as to why cracking is the only aging effect to be managed by the PWR Reactor Internals Program for the BMI column bodies, without inclusion of aging management for loss of fracture toughness.
TELEPHONE CONFERENCE CALL SOUTH TEXAS PRO,JECT LICENSE RENEWAL APPLICATIOI\l LIST OF PARTICIPANTS February 16, 2012 PARTICIPANTS                     AFFILIATIONS John Daily                       Nuclear Regulatory Commission (NRC)
RAI 3.1.2.1-1a The staff noted that, while the applicant confirmed that the minimum examination coverage criteria of the applicant's program are consistent with the Topical Report Conditions in the staffs safety evaluation (June 22, 2011) of MRP-227, Revision 0, its response did not indicate whether the applicant performed further evaluation(s) for the aging effect in the inaccessible locations of partially accessible components (including a set of multiple components such as bolts), consistent with the GALL Report and SRP-LR, in cases where that aging effect would be ENCLOSURE 2
Seung Min                       NRC Arden Aldridge                   STP Nuclear Operating Company (STPNOC)
-detected in the accessible locations of the components.
Ken Taplett                     STPNOC STARS Center of Business - Worley Gary Warner Parsons STARS Center of Business - Worley Gordon Chen Parsons ENCLOSURE 1
In addition, the staff sought clarification as to whether the applicant's aging management will perform further evaluation(s) to ensure adequate aging management for the inaccessible locations of partially-accessible components, if an aging effect were identified in the accessible locations of the components.
 
CONFERENCE CALL WITH STPNOC REGARDING CERTAIN ASPECTS OF RVI COMPONENTS STP LICENSE RENEWAL APPLICATION February 16, 2012 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of STP Nuclear Operating Company (STPNOC or the applicant) held a telephone conference call on February 16, 2012, to discuss requests for additional information (RAls) on aspects of the applicant's reactor vessel internals (RVls), for the South Texas Project, Units 1 and 2, license renewal application.
The participants indicated that the calls were useful in clarifying the questions discussed.
Discussion:
The staff and the applicant discussed the following:
Reactor Vessel Internals - Cast Austenitic Stainless Steel (073)
RAI3.1.1.80-1a The staff explained its need for clarification as to whether the PWR Reactor Internals Program identifies the upper core plate as an expansion component linked to the Control Rod Guide Tube (CRGT) lower flange welds to manage loss of material due to wear and cracking due to fatigue, as specified in the staffs safety evaluation (June 22,2011) of MRP-227, Revision O. In addition, the staff also explained the request to clarify whether the applicant's PWR Reactor Internals Program identifies the lower internals assembly lower support forging, or casting, as an expansion component linked to the CRGT lower flange welds to ensure adequate aging management and structural integrity, consistent with the staff's safety evaluation (June 22, 2011) of MRP-227, Revision O.
RAI 3.1.1.80-2a The staff discussed the request concerning whether the CRGT lower flanges are made of Cast Austenitic Stainless Steel (CASS). If the CRGT lower flanges are made of CASS, the staff needs to further clarify if loss of fracture toughness, in addition to cracking, is considered as an aging effect to be managed by the PWR Reactor Internals Program for these components. In addition, the staff needs clarification as to why cracking is the only aging effect to be managed by the PWR Reactor Internals Program for the BMI column bodies, without inclusion of aging management for loss of fracture toughness.
RAI 3.1.2.1-1a The staff noted that, while the applicant confirmed that the minimum examination coverage criteria of the applicant's program are consistent with the Topical Report Conditions in the staffs safety evaluation (June 22, 2011) of MRP-227, Revision 0, its response did not indicate whether the applicant performed further evaluation(s) for the aging effect in the inaccessible locations of partially accessible components (including a set of multiple components such as bolts),
consistent with the GALL Report and SRP-LR, in cases where that aging effect would be ENCLOSURE 2
 
                                                - 2 detected in the accessible locations of the components. In addition, the staff sought clarification as to whether the applicant's aging management will perform further evaluation(s) to ensure adequate aging management for the inaccessible locations of partially-accessible components, if an aging effect were identified in the accessible locations of the components.
As a result of the discussions, the applicant indicated it understood the staff's issues and would formulate responses to address them.
As a result of the discussions, the applicant indicated it understood the staff's issues and would formulate responses to address them.
Memorandum to File from J. Daily dated April 11, 2012


==SUMMARY==
Memorandum to File from J. Daily dated April 11, 2012
OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 16, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION ON REACTOR VESSEL INTERNALS, FOR THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (T AC. NOS. ME4936 AND ME4937) DISTRIBUTION:
E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDraApla Resource RidsOgcMailCenter JDaily TTran DMclntyre, OPA BSingal, DORL WWalker, RIV JDixon, RIV BTharakan, RIV WMaier, RIV VDricks, RIV NOKeefe, RIV AVegel, RIV GPick, RIV LICENSEE:
STP Nuclear Operating Company FACILITY:
South Texas Project


==SUBJECT:==
==SUBJECT:==


==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 16, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION ON REACTOR VESSEL INTERNALS, FOR THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC. NOS. ME4936 AND ME4937) The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of STP Nuclear Operating Company (STPNOC or the applicant) held a telephone conference call on February 16, 2012, to discuss requests for additional information (RAls) on aspects of the applicant's reactor vessel internals (RVls), for the South Texas Project, Units 1 and 2, license renewal application.
OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 16, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION ON REACTOR VESSEL INTERNALS, FOR THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC. NOS. ME4936 AND ME4937)
The telephone conference call was useful in clarifying the staff's requests and the applicant's questions for the RAls. Enclosure 1 provides a listing of the participants and Enclosure 2 contains a summary of the discussion.
DISTRIBUTION:
The applicant had an opportunity to comment on this summary. IRAJ John Daily, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
E-MAIL:
 
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDraApla Resource RidsOgcMailCenter JDaily TTran DMclntyre, OPA BSingal, DORL WWalker, RIV JDixon, RIV BTharakan, RIV WMaier, RIV VDricks, RIV NOKeefe, RIV AVegel, RIV GPick, RIV
==Enclosures:==


As stated cc w/encls: Listserv DISTRIBUTION:
... I\IIL12080a040 OFFICE LA: RPB 1:DLR           PM:RPB1 :DLR         BC:RPB1:DLR       PM:RPB1:DLR NAME       YEdmonds             JDaily               DMorey             JDaily DATE       4/4/12               4/5/12               4/5/12             4/11 112}}
See next page ADAMS Accession No . .. I\IIL 12080a040 OFFICE LA: RPB 1: DLR PM:RPB1 :DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds JDaily DMorey JDaily DATE 4/4/12 4/5/12 4/5/12 4/11 112 OFFICIAL RECORD}}

Latest revision as of 06:38, 12 November 2019

STP - Record of Conference Call-020162012 on RAIs-RVIs-31180-etc
ML12080A040
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 04/11/2012
From: Daily J
License Renewal Projects Branch 1
To:
License Renewal Projects Branch 1
Daily J
References
TAC ME4936, TAC ME4937
Download: ML12080A040 (6)
v • d • e


Text

~",R REGI/{ UNITED STATES

~.;:,(,'" "1;.o~ NUCLEAR REGULATORY COMMISSION

! ~ WASHINGTON, D.C. 20555-0001

<l:

~ :0

~! ~., ~o April 11, 2012

        • ~

LICENSEE: STP Nuclear Operating Company FACILITY: South Texas Project

SUBJECT:

SUMMAHY OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 16, 2012, BETWEEN THE U.s. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION ON REACTOR VESSEL INTERNALS. FOR THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, liCENSE RENEWAL APPLICATION (TAC. NOS. ME4936 AND ME4937)

The U.S. Nuciear Regulatory Commission (NRC or the staff) and representatives of STP Nuclear Operating Company (STPNOC or the applicant) held a telephone conference call on February 16, 2012, to discuss requests for additional information (RAls) on aspects of the applicant's reactor vessel internals (RVis), for the South Texas Project, Units 1 and 2, license renewal application, The telephone conference call was useful in clarifying the staffs requests and the al)plicant's questions for the RAls.

Enclosure 1 provides a listing of the participants and Enc;t)sur~ 2 contains a summary of tt1e discussion, The applicant had an opportunity to comment on this sUmmal-Y.

John Daily, Senior Project Manager Prcjects Branch 1 Division of License Renewa!

Office of Nuclear Reactor Regulation Docket Nos 50-498 and 50-499

Enclosures:

As stated cc w/encls: Listserv

TELEPHONE CONFERENCE CALL SOUTH TEXAS PRO,JECT LICENSE RENEWAL APPLICATIOI\l LIST OF PARTICIPANTS February 16, 2012 PARTICIPANTS AFFILIATIONS John Daily Nuclear Regulatory Commission (NRC)

Seung Min NRC Arden Aldridge STP Nuclear Operating Company (STPNOC)

Ken Taplett STPNOC STARS Center of Business - Worley Gary Warner Parsons STARS Center of Business - Worley Gordon Chen Parsons ENCLOSURE 1

CONFERENCE CALL WITH STPNOC REGARDING CERTAIN ASPECTS OF RVI COMPONENTS STP LICENSE RENEWAL APPLICATION February 16, 2012 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of STP Nuclear Operating Company (STPNOC or the applicant) held a telephone conference call on February 16, 2012, to discuss requests for additional information (RAls) on aspects of the applicant's reactor vessel internals (RVls), for the South Texas Project, Units 1 and 2, license renewal application.

The participants indicated that the calls were useful in clarifying the questions discussed.

Discussion:

The staff and the applicant discussed the following:

Reactor Vessel Internals - Cast Austenitic Stainless Steel (073)

RAI3.1.1.80-1a The staff explained its need for clarification as to whether the PWR Reactor Internals Program identifies the upper core plate as an expansion component linked to the Control Rod Guide Tube (CRGT) lower flange welds to manage loss of material due to wear and cracking due to fatigue, as specified in the staffs safety evaluation (June 22,2011) of MRP-227, Revision O. In addition, the staff also explained the request to clarify whether the applicant's PWR Reactor Internals Program identifies the lower internals assembly lower support forging, or casting, as an expansion component linked to the CRGT lower flange welds to ensure adequate aging management and structural integrity, consistent with the staff's safety evaluation (June 22, 2011) of MRP-227, Revision O.

RAI 3.1.1.80-2a The staff discussed the request concerning whether the CRGT lower flanges are made of Cast Austenitic Stainless Steel (CASS). If the CRGT lower flanges are made of CASS, the staff needs to further clarify if loss of fracture toughness, in addition to cracking, is considered as an aging effect to be managed by the PWR Reactor Internals Program for these components. In addition, the staff needs clarification as to why cracking is the only aging effect to be managed by the PWR Reactor Internals Program for the BMI column bodies, without inclusion of aging management for loss of fracture toughness.

RAI 3.1.2.1-1a The staff noted that, while the applicant confirmed that the minimum examination coverage criteria of the applicant's program are consistent with the Topical Report Conditions in the staffs safety evaluation (June 22, 2011) of MRP-227, Revision 0, its response did not indicate whether the applicant performed further evaluation(s) for the aging effect in the inaccessible locations of partially accessible components (including a set of multiple components such as bolts),

consistent with the GALL Report and SRP-LR, in cases where that aging effect would be ENCLOSURE 2

- 2 detected in the accessible locations of the components. In addition, the staff sought clarification as to whether the applicant's aging management will perform further evaluation(s) to ensure adequate aging management for the inaccessible locations of partially-accessible components, if an aging effect were identified in the accessible locations of the components.

As a result of the discussions, the applicant indicated it understood the staff's issues and would formulate responses to address them.

Memorandum to File from J. Daily dated April 11, 2012

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 16, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION ON REACTOR VESSEL INTERNALS, FOR THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC. NOS. ME4936 AND ME4937)

DISTRIBUTION:

E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDraApla Resource RidsOgcMailCenter JDaily TTran DMclntyre, OPA BSingal, DORL WWalker, RIV JDixon, RIV BTharakan, RIV WMaier, RIV VDricks, RIV NOKeefe, RIV AVegel, RIV GPick, RIV

... I\IIL12080a040 OFFICE LA: RPB 1:DLR PM:RPB1 :DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds JDaily DMorey JDaily DATE 4/4/12 4/5/12 4/5/12 4/11 112

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