ML12067A243

Summary of Telephone Conference Call Held on January 30, 2012, Between the U.S. Nuclear Regulatory Commission and STP Nuclear Operating Company, Regarding Requests for Information on Flow-Accelerated Corrosion and Others, for the South Texa

ML12067A243
Person / Time
Site:	South Texas
Issue date:	04/03/2012
From:	Daily J License Renewal Projects Branch 1
To:	South Texas
Daily J
References
TAC ME4936, TAC ME4937
Download: ML12067A243 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 3, 2012 LICENSEE:

STP Nuclear Operating Company FACILITY:

South Texas Project

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 30, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR INFORMATION ON FLOW-ACCELERATED CORROSION AND OTHERS, 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 January 30,2012, to discuss and clarify issues related to the staff's Requests for Additional Information (RAls) regarding flow-accelerated corrosion (FAC), cast austenitic stainless steel (CASS), and applicant's aging management program (AMP) for protective coatings, for the South Texas Project, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the applicant's responses and identifying the staff's issues for the RAls. provides a listing of the participants and Enclosure 2 contains a listing of the issues discussed with the applicant, including a brief description of the status of the items.

The applicant had an opportunity to comment on this summary.

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

TELEPHONE CONFERENCE CALL SOLITH TEXAS PRO~IECT LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS January 30, 2012 i PARTICIPANTS AFFILIATIONS John Daily Nuclear Regulatory Commission (NRC)

Aloysius Obodoako NRC James Gavula NRC Seung Min NRC Kimberly Green NRC

Emma Wong NRC Arden Aldridge STP Nuclear Operating Company (STPNOC)

Ken Taplett STPNOC GaryWamer STARS Center of Business - Worley Parsons Ken Bryant STARS Center of Business - Worley Parsons Gordon Chen STARS Center of Business - Worley Parsons ENCLOSURE 1

CONFERENCE CALL WITH STPNOC REGARDING RAIS RELATED TO FAC, CASS, AND PROTECTIVE COATINGS AMP STP LICENSE RENEWAL APPLICATION January 30,2012 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 January 30, 2012, to discuss and clarify the the staff's RAls regarding flow-accelerated corrosion (FAC), cast austenitic stainless steel (CASS), and applicant's aging management program (AMP) for protective coatings, related to the license renewal application (LRA).

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

Issues and discussions:

The staff and the applicant discussed the following RAI issues:

1) 82.1.6-1 a - Flow-Accelerated Corrosion - The guidance document for the flow-accelerated corrosion programs, NSAC-202L, states that the systems may be susceptible to damage from other corrosion or degradation mechanisms, which include cavitation, erosion, liquid impingement, etc., but these mechanisms are not part of a flow-accelerated corrosion program and should be evaluated separately. However, since STP has chosen to include mechanisms other than flow-accelerated corrosion in its program, this is an enhancement to the flow-accelerated corrosion program that needs to be further described in the LRA.

2) 82.1.39-1 and 82.1.39 Protective Coatings Monitoring program - The staff explained its position in that the application does not state the specific standards used to perform coating assessment (e.g., ASTM D 5163). In addition, the frequency of Service Level 1 coating inspections seems to be inconsistent with the recommendations of the GALL Report. In addition, the AMP's operating experience program element gives a general overview of the program and does not provide specific instances of degradation and its associated repair or other corrective actions performed. Staff explained that the applicant should provide specific information on standards used, why it adopted the frequencies of inspections, and, for instances of degradation, information that demonstrates that managing the effects of aging for the included components will be effective.

3) 3.1.1.57-1 a - CASS clarifications. The staff explained its need to further confirm whether the applicant's susceptibility screening method for material is consistent with the GALL Report, especially where the GALL Report addresses guidance for ferrite content calculations using Hull's equivalent factors.

4) RAI response to 82.1.3-2a, regarding applicant details on stress limits for the damaged closure bolt. Although ASME Code Section III (1971 edition), subsections N8-3232.2,

-3233, and -3234 specify requirements for maximum allowable stress for bolts in normal, upset and emergency conditions, respectively, the staff explained its concem that the 17 percent estimated reduction in load-bearing surfaces of the partially damaged stud insert could increase the stress level applied to the lugs of the stud insert such that loss of material due to wear and cracking due to stress corrosion cracking (SCC) may be facilitated. In contrast with these ENCLOSURE 2

- 2 adverse effects on aging, the applicant's response to RAI 82.1.3-2a does not indicate whether or not the partially damaged stud insert complies with the aforementioned requirements of the American Society of Mechanical Engineers (ASME) Code Section III for the maximum service stress limit 4.5-1a - The staff discussed its concern that, for the Unit 1 control tendons, the measured liftoff forces for the year-20 surveillance were greater than the year-1 0 values; and that the applicant did not present a sufficient evaluation for why the measured increase in tendon liftoff force was acceptable.

Memorandum to File from J. Daily dated April 3, 2012.

SUB~IECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 30, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR INFORMATION ON FLOW-ACCELERATED CORROSION AND OTHERS, 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

LICENSEE:

STP Nuclear Operating Company FACILITY:

South Texas Project SUB~'ECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 30, 2012, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND STP NUCLEAR OPERATING COMPANY, REGARDING REQUESTS FOR INFORMATION ON FLOW-ACCELERATED CORROSION AND OTHERS, 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 January 30, 2012, to discuss and clarify issues related to the staff's Requests for Additional Information (RAls) regarding flow-accelerated corrosion (FAC), cast austenitic stainless steel (CASS), and applicant's aging management program (AMP) for protective coatings, for the South Texas Project, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the applicant's responses and identifying the staff's issues for the RAls. provides a listing of the participants and Enclosure 2 contains a listing of the issues discussed with the applicant, including a brief description of the status of the items.

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. ML12067a243 OFFICE NAME LARPB1 :DLR YEdmonds PM:RPB1:DLR JDailylw corrections BC:RPB1:DLR DMorey/JDaily for PM:RPB1:DLR

~'Daily DATE 3/29/12 4/2112 4/3/12 4/3/12 I

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