ML11217A016

Commitment Change Summary Report

ML11217A016
Person / Time
Site:	South Texas
Issue date:	07/27/2011
From:	Harrison A South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
G25, NOC-AE-1 1002655, STI: 32841159
Download: ML11217A016 (4)

Text

LMM Nuclear Operating Company W EW r-South Texas Pro/ed Electric Generating Station PO. Box 289 Wadsworth, Texas 77483 & .July 27, 2011 NOC-AE-1 1002655 File No.: G25 STI: 32841159 U. S. Nuclear Regulatory Commission Attention:

Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Commitment Change Summary Report STP Nuclear Operating Company (STPNOC) submits the attached Commitment Change Summary Report for the period July 30, 2009 through June 20, 2011. This report lists each commitment for which a change was made during the reporting period and provides the basis for each change.The commitments were evaluated in accordance with the requirements of STPNOC Regulatory Commitment Change Process, which is consistent with the guidance in the Nuclear Energy Institute's NEI 99-04, "Guideline for Managing NRC Commitments." Additional documentation is available at STPNOC for your review.There are no new commitments in this letter.If there are any questions, please contact either Marilyn Kistler at 361-972-8385 or me at 361-972-7298.

\A- W-a ne Harrison Manager, Licensing mk

Attachment:

Commitment Change Summary Report A- jl~

NOC-AE-1 1002655 Page 2 of 2 cc: (paper copy)(electronic copy)Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd, Suite 400 Arlington, Texas 76011-4125 Balwant K. Singal Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 8B1)11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 289, Mail Code: MNl16 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 A. H. Gutterman, Esquire Morgan, Lewis & Bockius LLP Balwant K. Singal U. S. Nuclear Regulatory Commission John Ragan Catherine Callaway Jim von Suskil NRG South Texas LP Ed Alarcon Kevin Polio Richard Pena City Public Service Peter Nemeth Crain Caton & James, P.C.C. Mele City of Austin Richard A. Ratliff Texas Department of State Health Services Alice Rogers Texas Department of State Health Services Attachment NOC-AE-1 1002655 Page 1 of 2 Commitment Change Summary Report Condition Source Source Date of Original Commitment Revised Commitment Justification for Change Report Document Date Change Description Description Number 02-5326-113 NOC-AE-08002328 06/26/2008 12/31/2009 STPNOC submitted a clarification regarding Extension 1 -STPNOC verbally informed the NRC Response to NRC potential contingency actions for the testing Project Manager, Mohan Thadani that an Request for of the STP Emergency Core Cooling Testing plan and contingency options RAI response would not be possible by Information System (ECCS) sump strainers to the NRC provide assurance that the GS-1 91 December 31, 2009 and this was verbally Regarding STPNOC on 06/26/2008.

The submittal contained and Generic Letter 2004-02 issues accepted.

STPNOC and the NRC are still Request to Extend the following commitment.

Testing plan will be resolved for STP Units 1 and in the process of finalizing a plan and Implementation and contingency options provide assurance 2 by April 1, 2010. target dates to close this issue out. The Date for ECCS that the GSI-191 and GL2004-02 issues will revised commitment provides the time Sump Design Basis be resolved for STP Units 1 and 2 by needed to establish a realistic and December 31, 2009. achievable timeline to resolve these GL 2004-02 issues.02-5326-113 NOC-AE-08002328 06/26/2008 4/1/2010 STPNOC submitted a clarification regarding Extension 2 -Once alignment is gained on STPNOC's Response to NRC potential contingency actions for the testing RAI responses STPNOC will send the final Request for of the STP Emergency Core Cooling Testing plan and contingency options responses on the docket to the staff Information System (ECCS) sump strainers to the NRC provide assurance that the GSI-191 potentially in the 1 st week of June. The date Regarding STPNOC on 06/26/2008.

The submittal contained and Generic Letter 2004-02 issues selected of September 15, 2010 allows the Request to Extend the following commitment.

Testing plan will be resolved for STP Units 1 and staff approximately 3 months to conduct the Implementation and contingency options provide assurance 2 by September 15, 2010. review and approval process for STPNOC's Date for ECCS that the GSI-1 91 and GL2004-02 issues will RAI's to close the GL.Sump Design Basis be resolved for STP Units 1 and 2 by December 31, 2009.GL 2004-02 The due date for this action has been extended until April 1, 2012. However, the STPNOC commitment change process no longer requires inclusion of this type commitment in the Commitment Change Summary Report.02-5326-120 NOC-AE-08002372 12/11/2008 2/10/2010 When the final Safety Evaluation for Extension 1 -There is no safety evaluation report to WCAP-1 6793, "Long Term Cooling" is review at this time.Supplement 4 to the issued, STP will review it for impact; and When the final Safety Evaluation for Response to the evaluation of long term cooling will be WCAP-16793, "Long Term Cooling" Generic Letter revised as appropriate.

Expected is issued, STP will review it for 2004-02 completion date: June 30, 2009 impact; and the evaluation of long term cooling will be revised as appropriate.

Expected completion date: June 15, 2010 Attachment NOC-AE-1 1002655 Page 2 of 2 Commitment Change Summary Report Condition Source Source Date of Original Commitment Revised Commitment Justification for Change Report Document Date Change Description Description Number 02-5326-120 NOC-AE-08002372 12/11/2008 2/10/2010 When the final Safety Evaluation for Extension 2 -There is no safety evaluation report to WCAP-16793, "Long Term Cooling" is review at this time.Supplement 4 to the issued, STP will review it for impact; and When the final Safety Evaluation for Response to the evaluation of long term cooling will be WCAP-16793, "Long Term Cooling" Generic Letter revised as appropriate.

Expected is issued, STP will review it for The due date for this action has been 2004-02 completion date: June 30, 2009 impact; and the evaluation of long extended until December 15, 2011.term cooling will be revised as However, the STPNOC commitment appropriate.

Expected completion change process no longer requires date: December 15, 2010 inclusion of this type commitment in the Commitment Change Summary Report.09-11747-3 ST-HL-AE-2925 12/22/1988 6/24/2010 Fire watch personnel now change rounds Deleted Rotating personnel is not an effective Reply to a Notice of hourly to help eliminate boredom. method to ensure fire watch rounds are Violation completed.

STPNOC has implemented (Enforcement Action On July 6, 1995 STPNOC Licensing bar code scanning software to monitor fire 88-216) contacted the NRC Project Manager and watch task performance.

verbally changed this commitment to rotating the fire watch personnel every two The NRC agreed in 1995 to change the hours. original commitment and did not require STPNOC to submit the change on the docket. This change does not meet the definition of a commitment per NEI 99-04.Modifications were installed in Unit 1 and 00-2194-13 NOC-AE-00000781 3/9/2000 8/10/2010 Plant procedures have been revised to Deleted Unit 2 to change the AMSAC actuation Licensee Event direct the bypassing of AMSAC once from feedwater flow to 3 of four Steam Report 00-001 reactor power is reduced below 40% and Generators less than 25% rated feedwater Engineered Safety prior to increasing above 38% flow to AMSAC actuation on 1 narrow Feature Actuation range level on 3 of four Steam Generators Due to Anticipated less than 15%. The normal reactor trip Transient Without setpoint and Auxiliary Feedwater actuation Scram Mitigation setpoint are at 2 out 4 narrow range level System Actuation at 20% on any of the four Steam Circuitry Generators.

With Steam Generator level normally maintained at 70% at all power levels there is a large amount of margin to the normal reactor trip setpoint, and even more to the AMSAC actuation setpoint.Therefore it is very unlikely there would be an unnecessary AMSAC actuation at any power level.