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

Submittal of Commitment Change Summary Report for July 31, 2008 Through July 30, 2009

ML092230376
Person / Time
Site:	South Texas
Issue date:	07/30/2009
From:	Harrison A South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
G25, NOC-AE-09002445, STI: 32502275
Download: ML092230376 (5)

Text

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

ýC. 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.