NOC-AE-15003295, Submittal of 10CFR50.59 Summary Report of Changes, Tests and Experiments Conducted
| ML15300A532 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 09/30/2015 |
| From: | Marc-Anthony Murray South Texas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NOC-AE-15003295, STI: 34200838 | |
| Download: ML15300A532 (4) | |
Text
Nuclear Operating Company South Texas Project Eledtrc Generating Station P.O. Box 289 Wadsworth, Texas 77483 *¢v* -
September 30, 2015 NOC-AE-1 5003295 10OCFR50.59 STI: 34200838 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.59 Summary Report Pursuant to the requirements of 10OCFR50.59, the attached report contains a brief description and summary of the 10OCFR50.59 evaluations of changes, tests and experiments conducted at the South Texas Project from October 2013 through September 2015.
There are no commitments in this letter.
If there are any questions regarding this summary report, please contact Hung C. Le at (361) 972-7932 or me at (361) 972-8164.
Michael P. Murray Manager, Regulatory Affairs hcl
Attachment:
10CFR50.59 Evaluation Summaries October 2013 - September 2015
NOC-AE-1 5003295 Page 2 of 2 cc:
(paper copy) (electronic copy)
Morgqan. Lewis & Bockius LLP Steve Frantz Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511 U. S. Nuclear Regqulatory Commission Lisa M. Regner NRG South Texas LP Lisa M. Regner John Ragan SSenior Licensing Project Manager Chris O'Hara
./ U.S. Nuclear Regulatory Commission Jim von Suskil t One White Flint North (MS 8 B1) 11555 Rockville Pike CPS Energqy Rockville, MD 20852 Kevin Polio Cris Eugster L. D. Blaylock NRC Resident Inspector Crain Caton & James, P.C.
U. S. Nuclear Regulatory Commission Peter Nemeth P. O. Box 289, Mail Code: MNl16 Wadsworth, TX 77483 City of Austin C. Mele I
John Wester Texas Department of State Health Services Richard A. Ratliff Robert Free f
NOC-AE-1 5003295 Attachment Page 1 of 2 I0CFR50.59 Evaluation Summaries October 2013 - September 2015 Summaries of the following 10CFR5O.59 Evaluations are provided in this attachment:
No. Condition Report Subject Number
- 1. 11-30675-90 Methodology change from the PHOENIX-P computer code to the NEXUS/PARAGON computer codes.
- 2. 04-8245-60 High radiation monitor equipment failure setpoint change
- 3. 11-12472-20 UFSAR revision due to revised Reactor Containment Building Loss Of Coolant Accident Mass and Energy
NOC-AE-1 5003295 Attachment Page 2 of 2 10CFR50.59 Evaluation Summaries October 2013 - September 2015
- 1. 11-30675-90 - Methodology Change from the PHOENIX-P computer code to the NEXUSlPARAGON computer codes.
Description:
The subject of this evaluation is to revise the methodology in the UFSAR for the development of cross sections used by the ANC computer code from the PHOENIX-P computer code to the NEXUS/Paragon computer codes.
Summary: These computer codes have been reviewed and approved for use by the NRC. The evaluation demonstrated that the proposed change uses a NRC approved methodology that is (a) based on sound engineering practice, (b) appropriate for the intended application, and (c) within the limitations of the applicable Safety Evaluation Reports.
The evaluation determined that prior NRC approval was not required.
\t
- 2. 04-8245 High Radiation Monitor Equipment Failure Setpoint Change
/
Description:
The subject of this evaluation is to revise the equipment failure setpoint for the High Range Radiation Monitors (HRRM's) from 5 minutes to 30 minutes.
Summary: The change is being made to eliminate a false indication of a common mode failure of the HRRM's during a high energy line break.
The evaluation determined that prior NRC approval was not required.
- 3. 11-12472-20 - UFSAR Revision due to Revised Reactor Containment Building Loss Of Coolant Accident Mass and Energy
Description:
The proposed change revises UFSAR Section 6.2.1 to reflect revised containment atmospheric pressure and temperature analysis for the LOCA event.
Summary: The analysis was re-performed due to revised mass and energy releases to the containment. The GOTHIC computer code was used in place of the currently licensed CONTEMPT computer code. The results of the analysis show that the peak containment pressure of 41.2 psig in Technical Specification 6.8.3.j remains unchanged. The results also show that the peak containment temperature decreases to 2620 F (GOTHIC) from 264°F (CONTEMPT) and remains bounded by the Main Steam Line Break peak temperature of 299 0 F.
The evaluation determined that prior NRC approval was not required.
/o
Nuclear Operating Company South Texas Project Eledtrc Generating Station P.O. Box 289 Wadsworth, Texas 77483 *¢v* -
September 30, 2015 NOC-AE-1 5003295 10OCFR50.59 STI: 34200838 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.59 Summary Report Pursuant to the requirements of 10OCFR50.59, the attached report contains a brief description and summary of the 10OCFR50.59 evaluations of changes, tests and experiments conducted at the South Texas Project from October 2013 through September 2015.
There are no commitments in this letter.
If there are any questions regarding this summary report, please contact Hung C. Le at (361) 972-7932 or me at (361) 972-8164.
Michael P. Murray Manager, Regulatory Affairs hcl
Attachment:
10CFR50.59 Evaluation Summaries October 2013 - September 2015
NOC-AE-1 5003295 Page 2 of 2 cc:
(paper copy) (electronic copy)
Morgqan. Lewis & Bockius LLP Steve Frantz Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511 U. S. Nuclear Regqulatory Commission Lisa M. Regner NRG South Texas LP Lisa M. Regner John Ragan SSenior Licensing Project Manager Chris O'Hara
./ U.S. Nuclear Regulatory Commission Jim von Suskil t One White Flint North (MS 8 B1) 11555 Rockville Pike CPS Energqy Rockville, MD 20852 Kevin Polio Cris Eugster L. D. Blaylock NRC Resident Inspector Crain Caton & James, P.C.
U. S. Nuclear Regulatory Commission Peter Nemeth P. O. Box 289, Mail Code: MNl16 Wadsworth, TX 77483 City of Austin C. Mele I
John Wester Texas Department of State Health Services Richard A. Ratliff Robert Free f
NOC-AE-1 5003295 Attachment Page 1 of 2 I0CFR50.59 Evaluation Summaries October 2013 - September 2015 Summaries of the following 10CFR5O.59 Evaluations are provided in this attachment:
No. Condition Report Subject Number
- 1. 11-30675-90 Methodology change from the PHOENIX-P computer code to the NEXUS/PARAGON computer codes.
- 2. 04-8245-60 High radiation monitor equipment failure setpoint change
- 3. 11-12472-20 UFSAR revision due to revised Reactor Containment Building Loss Of Coolant Accident Mass and Energy
NOC-AE-1 5003295 Attachment Page 2 of 2 10CFR50.59 Evaluation Summaries October 2013 - September 2015
- 1. 11-30675-90 - Methodology Change from the PHOENIX-P computer code to the NEXUSlPARAGON computer codes.
Description:
The subject of this evaluation is to revise the methodology in the UFSAR for the development of cross sections used by the ANC computer code from the PHOENIX-P computer code to the NEXUS/Paragon computer codes.
Summary: These computer codes have been reviewed and approved for use by the NRC. The evaluation demonstrated that the proposed change uses a NRC approved methodology that is (a) based on sound engineering practice, (b) appropriate for the intended application, and (c) within the limitations of the applicable Safety Evaluation Reports.
The evaluation determined that prior NRC approval was not required.
\t
- 2. 04-8245 High Radiation Monitor Equipment Failure Setpoint Change
/
Description:
The subject of this evaluation is to revise the equipment failure setpoint for the High Range Radiation Monitors (HRRM's) from 5 minutes to 30 minutes.
Summary: The change is being made to eliminate a false indication of a common mode failure of the HRRM's during a high energy line break.
The evaluation determined that prior NRC approval was not required.
- 3. 11-12472-20 - UFSAR Revision due to Revised Reactor Containment Building Loss Of Coolant Accident Mass and Energy
Description:
The proposed change revises UFSAR Section 6.2.1 to reflect revised containment atmospheric pressure and temperature analysis for the LOCA event.
Summary: The analysis was re-performed due to revised mass and energy releases to the containment. The GOTHIC computer code was used in place of the currently licensed CONTEMPT computer code. The results of the analysis show that the peak containment pressure of 41.2 psig in Technical Specification 6.8.3.j remains unchanged. The results also show that the peak containment temperature decreases to 2620 F (GOTHIC) from 264°F (CONTEMPT) and remains bounded by the Main Steam Line Break peak temperature of 299 0 F.
The evaluation determined that prior NRC approval was not required.
/o