ML12080A055

From kanterella
Jump to navigation Jump to search

STP - Record of Conference Call-03082012 on RAIs-SGTI-RxHeadStudClosures
ML12080A055
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: ML12080A055 (6)


Text

f-jl.1'\ REG u( UNITED STATES

~,§.,\; "1'>-01' NUCLEAR REGULATORY COMMISSION

! '~ WASHINGTON, D.C. 20555-0001

<{ 0 Iii  :

~"i April 11, 2012

"'? ~o

        • 1<

LICENSEE: STP Nuclear Operating Company FACILITY: South Texas Project

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 8, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION - SET 15, FOR THE SOUTH TEXAS PRO~'ECT, 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 March 8,2012, to discuss requests for additional information (RAls) on steam generator tube integrity and reactor head closure studs (RAI Set 15), for the South Texas Project, Units 1 and 2, license renewal application. 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.

The applicant had an opportunity to comment on this summary.

JO~ D::::ni~e~er Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499

Enclosures:

As stated cc w/encls: Listserv

TELEPHONE CONFERENCE CALL SOUTH TEXAS PROJECT LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS March 8, 2012 PARTICIPANTS AFFILIATIONS John Daily Nuclear Regulatory Commission (NRC)

Angela Buford NRC Ken Karwoski NRC Aloysius Obodoako NRC Seung Min NRC OnYee NRC Ching Ng NRC Arden Aldridge STP Nuclear Operating Company (STPNOC)

Dan Sicking STPNOC STARS Center of Business - Worley Gary Warner Parsons STARS Center of Business - Worley Gordon Chen Parsons STARS Center of Business - Worley Bret Lynch Parsons ENCLOSURE 1

CONFERENCE CALL WITH STPNOC REGARDING RAI SET 15 STP LICENSE RENEWAL APPLICATION March 8. 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 March 8. 2012, to discuss requests for additional information (RAls) on steam generator tube integrity and reactor head closure studs (RAI Set 15), 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:

Steam Generator Tube Integrity Program RAI B2.1.8-2 The staff notes that secondary side access covers and secondary nozzles are not within the scope of GALL Report AMP XI.M19. "Steam Generator Tube Integrity Program." The GALL Report AMP does not manage secondary side external components which are normally considered part of the shell of the steam generator. It is not clear to the staff why the applicant included these components within the scope of this program.

In discussion of this RAI. the applicant indicated that the secondary side access cover inserts and secondary nozzles in question are included in this aging management program (AMP) since they are internal to the steam generator. such as the SG feedwater ring, the thermal sleeve for the auxiliary feedwater spray pipe. and insert covers for some access covers. The applicant also stated that, as listed in license renewal application (LRA) Table 3.1.2-4, external components typically associated with the SG shell, such as the secondary nozzles and safe ends, the secondary access covers. and SG secondary shell. which are made of carbon steel.

are included in the applicant's American Society of Mechanical Engineers (ASME) Code Section XI, Inservice Inspection, Subsection IWB. IWC, and IWD program and other programs for managing their respective aging effects. consistent with the GALL Report recommendations. As a result of these clarifications of material present in the LRA, the staff agreed with the applicant's designations and stated that the RAI would be dropped since it was no longer necessary.

Reactor Head Closure Studs Program RAI B2.1.3-2b The staff noted that the applicant's responses to earlier RAls regarding Unit 2 stud insert #30 indicate that no additional visual inspection has been performed on the stud insert to confirm no additional reduction in the load bearing surfaces after the damaged stud insert was placed in service in 2007. The staff also expressed a concern that the applicant's proposed visual inspection schedule for stud insert #30 appeared to possibly delay successive visual inspections as late as 10 years after entering the period of extended operation (PEO); thus the presence of any additional loss of load bearing surfaces would be unknown prior to entering the PEO.

ENCLOSURE 2

- 2 The staff and applicant further discussed: (a) baseline information regarding the depth of the damaged areas of the stud insert lugs; (b) clarification as to why the applicant's response dated January 18, 2012, refers to the Unit 1 Stress Report dated October 1977, rather than Unit 2 Stress Reports; (c) confirmation whether the applicant's analysis includes relevant transients; and (d) how the damaged stud insert complies with the stress limits of ASME Code Section III.

The staff also noted that the applicant's responses do not provide sufficient information to justify why the partially rolled lugs of stud insert #30 do not make any change to the original stress analysis results that were based on the undamaged stud insert lugs. Finally, the discussion addressed a need to clarify how the applicant determined that the increase in the stress at the maximum usage factor location would be less than 17 percent and how the applicant could determine the increase in stress at the location of maximum usage factor would not result in exceeding the Code design limit of 1.0.

As a result of the discussions on these issues, the staff agreed to consider revisions to the RAI in order to better clarify the remaining issues and the information desired to close them.

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

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 8, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION - SET 15, FOR THE SOUTH TEXAS PROJECT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC. NOS. ME4936 AND ME4937)

DISTRI BUTION:

E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb'1 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:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 8, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR ADDITIONAL INFORMATION - SET 15, 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 March 8, 2012, to discuss requests for additional information (RAls) on steam generator tube integrity and reactor head closure studs (RAI Set 15), 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 applicant's questions for the RAls. provides a listing of the participants and Enclosure 2 contains a summary of the discussion.

The applicant had an opportunity to comment on this summary.

IRA!

John Daily, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499

Enclosures:

As stated cc w/encls: Listserv DISTRIBUTION: See next page ADAMS Accession No ... ML12080a055 OFFICE LARPB1 :DLR PM:RPB1 :DLR BC:RPB1:DLR PM:RPB1 :DLR NAME YEdmonds JDaily DMorey ..IDaily DATE 4/4/12 4/5/12 4/5/12 4/11/12 OFFICIAL RECORD COpy