View source for NOC-AE-09002445, Submittal of Commitment Change Summary Report for July 31, 2008 Through July 30, 2009

{{Adams
| number = ML092230376
| issue date = 07/30/2009
| title = Submittal of Commitment Change Summary Report for July 31, 2008 Through July 30, 2009
| author name = Harrison A
| author affiliation = South Texas Project Nuclear Operating Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000498, 05000499
| license number = 
| contact person = 
| case reference number = G25, NOC-AE-09002445, STI: 32502275
| document type = Letter type:NOC, Report, Miscellaneous
| page count = 5
}}

=Text=
{{#Wiki_filter:Nuclear Operating Company South Tas Pmct Elecdric Gcncrab'ng Station PC. Box 289 Wadsworth, Ts 77483                          -
July 30, 2009 NOC-AE-09002445 File No.: G25 STI: 32502275 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 South Texas Proiect Commitment Change Summary Report Attached is the South Texas Project (STP) Commitment Change Summary Report for the period July 31, 2008 through July 30, 2009. 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 STP's Regulatory Commitment Change Process, which is consistent with the guidance in the Nu*clear Energy Institute's NEI 99-04, "Guideline for Managing NRC Commitments." Additional documentation is available at STP 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.
                                                                           ~~eA.W    eHrrison Manager, Licensing mk

==Attachment:==
Commitment Change Summary Report 4001

NOC-AE-09002445 Page 2 of 2 cc:
(paper copy)                        (electronic copy)
Regional Administrator, Region IV   A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 612 East Lamar Blvd, Suite 400 Arlington, Texas 76011-4125         Mohan C. Thadani U. S. Nuclear Regulatory Commission Mohan C. Thadani                    Kevin Howell Senior Project Manager              Catherine Callaway U.S. Nuclear Regulatory Commission  Jim von Suskil One White Flint North (MS 8B1A)     NRG South Texas LP 11555 Rockville Pike Rockville, MD 20852 Ed Alarcon Senior Resident Inspector           J. J. Nesrsta U. S. Nuclear Regulatory Commission R. K. Temple P. O. Box 289, Mail Code: MN116    Kevin Polio Wadsworth, TX 77483                 City Public Service
&#xfd;C. M. Canady                       Jon C.. Wood City of Austin                      Cox Smith Matthews Electric Utility Department 721 Barton Springs Road             C. Mele Austin, TX 78704                    City of Austin Richard A. Ratliff Texas Department of State Health Services Alice Rogers Texas Department of State Health Services

Attachment NOC-AE-09002445 Page 1 of 3 Condition   Source            1Source     Date of D          Original Commitment                             Revised Commitment                     Justification for Change Report      Document           Date       Change     Description                                     Description Number 08-16399-1  HL-AE-5414         07/09/1996 10/28/2008 STPNOC submitted information (ST-HL-AE-         Alternative:
5414) to the NRC regarding single train                                                The Alternative Source Term License 06-7904-4   AE-HL-94678        10/31/1996            Engineered Safety Feature mitigation            Delete Commitment                      Amendment (NOC-AE-07002127) provided capabilities to support a License Amendment                                            justification to change the design bases NOC-AE-07002127    03/22/2007 Request for extending the Allowed Outage                                               accident analyses where the mitigating AE-NOC-08001743    03/06/2008            Time for an inoperable standby diesel                                                  capabilities of the Fuel Handling Building generator. STP described steps placed in a                                             HVAC system are not credited. License plant procedure for providing power to the                                             Amendments 182/169 to adopt the Train B Fuel Handling Building HVAC                                                    Alternative Source Term (ST-AE-NOC-exhaust filter heaters in the event that only C                                        08001743) approved deletion of the Fuel Engineered Safety Feature diesel is                                                    Handling Building HVAC system from the available. The NRC Safety Evaluation                                                   Technical Specifications. In the Report (ST-AE-HL-94678) that approved the                                              accompanied Safety Evaluation Report, the License Amendment Request relied on this                                               NRC based their approval on the fact that capability of a single train of Engineered                                             the accident mitigation capabilities of the Safety Feature equipment to mitigate the                                                Fuel Handling Building HVAC filter system consequences of a design basis event to                                                are no longer credited in any of the Design determine the safety impact of the proposed                                             Basis Accident analyses.
amendment. Thus, the procedure steps became a commitment for supporting the                                                 With this change, the capability of a single safety impact evaluation of.the licensing                                              train of Fuel Handling Building HVAC to amendment.                                                                             mitigate the consequences of a design basis event no longer needs to be considered to determine safety impact if the train becomes unavailable. Therefore, there no longer needs to be a commitment for procedure steps to provide power to the Train B Fuel Handling Building HVAC exhaust filter heaters in the event that only C Engineered Safety Feature diesel is available for maintaining a basis for the extended diesel Allowed Outage Time license amendment.
06-15147-86 NOC-AE-01001212    11/19/2001 4/14/2009  Revise the Essential Cooling Water System       Delete commitment                      The Original Equipment Manufacturer has 01-14883                                             operating procedure to require an Essential                                            designed a product lubricated bearing License Event                            Cooling Water pump to be stopped if the         Operations will revise their operating  pump that does not rely upon an external Report 01-001                            associated lube water flow indicator does       procedures to remove reference to      source of bearing lubrication /cooling Essential Cooling                        not indicate greater than 3.0 gpm flow          the lube water supply for each         water.
Water Pump 1CC                           within 45 seconds after a pump start,           Essential Cooling Water pump as it     On initial pump start, the pumped fluid Failure Following                        including pump starts for Fill and Vent         is replaced with a                      immediately flows over the bearings Maintenance                              evolutions.                                     converted/overhauled pump.             providing lubrication and cooling. The original design depended upon pump

Attachment NOC-AE-09002445 Page 2 of 3 Condition Source   Source Date of Original Commitment Revised Commitment                     Justification for Change Report    Document Date   Change  Description         Description Number The original commitment is no longer required. Checking for adequate        discharge pressure down stream from the external lube water flow will continue pump to supply this lubricating/cooling flow to be a normal operating procedure     which resulted in initial dry bearing starts step as it applies to the original     for the pump. Initial starting of the pumps and will remain applicable for   Pump provides the most stress and wear all-Essential Cooling Water pumps      on the bearing surfaces due to initial pump that have not been converted to a      torque and impeller hydraulic forces. This product lubricated bearing design. is the most critical time for the bearings.
Normal operation produces very little wear on the bearings.
The initial commitment to provide lubricating water to each Essential Cooling Water pump will no longer apply to a new product lubricated bearing designed Essential Cooling Water pump. The flow instrument used to determine adequate lube water flow per the commitment is part of the system that is being deleted. Visual lube water flow indication therefore, can not be verified by the operators. Essential Cooling Water pump 2B is the first pump of the product lubricated bearing design to be replaced at STP. The remaining six Essential Cooling Water pumps will be converted/overhauled by the Original Equipment Manufacturer to a product lubricated design over the next few years and this commitment would no longer be applicable after all operating pumps are of the Droduct lubricated desian.

Attachment NOC-AE-09002445 Page 3 of 3 Condition Source             Source       Date of     Original Commitment                              Revised Commitment                           Justification for Change Report    Document           Date         Change      Description                                      Description Number 05-1655-5 ST-HL-AE-1 129 -   10/19/1984   7/20/2009   Table 1 of the October 1984 Control of           Revise Table 1:                              The load cell linkage shall be attached to Control of Heavy                            Heavy Loads Report includes the Reactor          Special Lifting Device = "None"              the Internals Lift Rig for lifts that involve the Loads Report                                Vessel Internals Lift Rig as a load carried      When Internals Lift Rig is being lifted      upper internals and the lower internals by the Reactor Containment Building Polar .      by itself (i.e., the Internals Lift Rig is   packages. For movement of the Internals ST-HL-AE-718       8/24/1981                Crane. The Load Cell Linkage is given as a       supporting noloads)                          Lift Rig by itself and for lifts of other items ST-HL-AE-1738      9/5/1986                 special lifting device required for this load.                                                using the Internals Lift Rig, the use of the ST-HL-AE-1 862     1/27/1987                                                                                                              load cell linkage is not required but may be I_           I           I                                                I                                            I needed as a good rigging practice.}}