NOC-AE-07002144, CFR50.59 Summary Report: Difference between revisions

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{{#Wiki_filter:Nuclear Operating Company South Texas Proect Electnrc Generating Station P0. Box 289 Wadsworth.
{{#Wiki_filter:Nuclear Operating Company South Texas Proect Electnrc GeneratingStation P0. Box 289 Wadsworth. Texs 77483                       lvvv"---
Texs 77483 lvvv"---April 16, 2007 NOC-AE-07002144 1OCFR50.59 U. S. Nuclear Regulatory Commission Attention:
April 16, 2007 NOC-AE-07002144 10CFR50.59 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.59 Summary Report Pursuant to the requirements of 10CFR50.59, the attached report contains a brief description and summary of the 10CFR50.59 evaluations of changes, tests and experiments conducted at the South Texas Project.
Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 1OCFR50.59 Summary Report Pursuant to the requirements of 1OCFR50.59, the attached report contains a brief description and summary of the 1OCFR50.59 evaluations of changes, tests and experiments conducted at the South Texas Project.There are no commitments in this letter.If there are any questions regarding this summary report, please contact J. R. Morris at (361) 972-8652 or me at (361) 972-7136.Scott M. Head Manager, Licensing awh  
There are no commitments in this letter.
If there are any questions regarding this summary report, please contact J. R. Morris at (361) 972-8652 or me at (361) 972-7136.
Scott M. Head Manager, Licensing awh


==Attachment:==
==Attachment:==
2007 10CFR50.59 Evaluation Summaries STI:32143330


2007 1OCFR50.59 Evaluation Summaries STI:32143330 NOC-AE-07002144 Page 2 of 2 cc: (paper copy)(electronic copy)Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN116 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189 A. H. Gutterman, Esquire Morgan, Lewis & Bockius LLP Mohan C. Thadani U. S. Nuclear Regulatory Commission Steve Winn Christine Jacobs Eddy Daniels Marty Ryan NRG South Texas LP Ed Alarcon J. J. Nesrsta R. K. Temple Kevin Pollo City Public Service Jon C. Wood Cox Smith Matthews C. Kirksey City of Austin Attachment NOC-AE-07002144 Page 1 of 3 Summaries of the following 1OCFR50.59 Evaluations are provided in this attachment:
NOC-AE-07002144 Page 2 of 2 cc:
1.2.3.05-15364-10 04-12793-3 05-4840-4 Preheater Bypass Valve Test at Power Change to Failure Modes & Effects Analysis for Auxiliary Feedwater Change to Hot, Full-Power Feedwater Temperature Attachment NOC-AE-07002144 Page 2 of 3 10CFR50.59 Evaluation Summaries 1. Preheater Bypass Valve Test at Power
(paper copy)                             (electronic copy)
Regional Administrator, Region IV         A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission       Morgan, Lewis & Bockius LLP 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064               Mohan C. Thadani U. S. Nuclear Regulatory Commission Senior Resident Inspector                 Steve Winn U. S. Nuclear Regulatory Commission       Christine Jacobs P. 0. Box 289, Mail Code: MN116           Eddy Daniels Wadsworth, TX 77483                       Marty Ryan NRG South Texas LP C. M. Canady                             Ed Alarcon City of Austin                           J. J. Nesrsta Electric Utility Department               R. K. Temple 721 Barton Springs Road                   Kevin Pollo Austin, TX 78704                         City Public Service Richard A. Ratliff                       Jon C. Wood Bureau of Radiation Control               Cox Smith Matthews Texas Department of State Health Services 1100 West 49th Street                     C. Kirksey Austin, TX 78756-3189                     City of Austin


== Description:==
Attachment                                                        NOC-AE-07002144 Page 1 of 3 Summaries of the following 10CFR50.59 Evaluations are provided in this attachment:
: 1.        05-15364-10  Preheater Bypass Valve Test at Power
: 2.          04-12793-3  Change to Failure Modes & Effects Analysis for Auxiliary Feedwater
: 3.          05-4840-4  Change to Hot, Full-Power Feedwater Temperature


Summary: This evaluation supports a change to the Preheater Bypass Valve Operability Test procedure, to perform testing required by Technical Specification 4.6.3.1, Containment Isolation Valves. The valve operability testing will be performed for Containment isolation valve A2FW-FV-7192, Steam Generator 2D Preheater Outside *Reactor Containment Bypass Valve. The test will stroke the valve during at-power operation.
Attachment                                                                NOC-AE-07002144 Page 2 of 3 10CFR50.59 Evaluation Summaries
All equipment impacted by the proposed test will stay within its design basis. All code requirements will be satisfied.
: 1.     Preheater Bypass Valve Test at Power
In addition, the ensuing transient will not result in changing from a Condition I to a Condition II event. This test does not impact accident scenarios and the current dose analysis remains bounding.2. Change to Failure Modes & Effects Analysis for Auxiliary Feedwater


== Description:==
== Description:==
This evaluation supports a change to the Preheater Bypass Valve Operability Test procedure, to perform testing required by Technical Specification 4.6.3.1, Containment Isolation Valves. The valve operability testing will be performed for Containment isolation valve A2FW-FV-7192, Steam Generator 2D Preheater Outside *Reactor Containment Bypass Valve. The test will stroke the valve during at-power operation.
Summary:    All equipment impacted by the proposed test will stay within its design basis. All code requirements will be satisfied. In addition, the ensuing transient will not result in changing from a Condition I to a Condition II event. This test does not impact accident scenarios and the current dose analysis remains bounding.
: 2.      Change to Failure Modes & Effects Analysis for Auxiliary Feedwater


Summary: The change revises the STP UFSAR to reflect revised failure modes and effects analysis (FMEA) for the AFW system electrical components in the isolation valve cubicle (IVC). The change also revises accident analyses to credit faulted steam generator isolation using the safety-grade AFW outside containment isolation valves (OCIV) instead of the AFW regulating valves.The proposed change replaces the faulted SG isolation function from the operator closing the AFW REG valves to the operator closing the AFW OCIVs. The AFW OCIVs are qualified to "harsh" environment conditions.
== Description:==
The proposed change takes credit for the existing operator actions to isolate the faulted steam generator by closing the AFW OCIV or securing the pump. No new operator actions, procedure changes or equipment qualification will be performed.
The change revises the STP UFSAR to reflect revised failure modes and effects analysis (FMEA) for the AFW system electrical components in the isolation valve cubicle (IVC). The change also revises accident analyses to credit faulted steam generator isolation using the safety-grade AFW outside containment isolation valves (OCIV) instead of the AFW regulating valves.
The required operator actions already exist in plant procedures No evaluation methodology is changed and no equipment or component needs to be requalified.
Summary:    The proposed change replaces the faulted SG isolation function from the operator closing the AFW REG valves to the operator closing the AFW OCIVs. The AFW OCIVs are qualified to "harsh" environment conditions. The proposed change takes credit for the existing operator actions to isolate the faulted steam generator by closing the AFW OCIV or securing the pump. No new operator actions, procedure changes or equipment qualification will be performed. The required operator actions already exist in plant procedures         No evaluation methodology is changed and no equipment or component needs to be requalified. No changes will be made to equipment important to safety or to operator actions. The proposed UFSAR change revises analysis to reflect plant conditions and does not change plant configuration. The change does not introduce the possibility of a malfunction of an SSC important to safety with a different result because no new failure modes are introduced. This change does not impact accident scenarios and the current dose analysis remains bounding.
No changes will be made to equipment important to safety or to operator actions. The proposed UFSAR change revises analysis to reflect plant conditions and does not change plant configuration.
The change does not introduce the possibility of a malfunction of an SSC important to safety with a different result because no new failure modes are introduced.
This change does not impact accident scenarios and the current dose analysis remains bounding.
Attachment NOC-AE-07002144 Page 3 of 3 3. Change to Hot, Full-Power Feedwater Temperature


==
Attachment                                                              NOC-AE-07002144 Page 3 of 3
Description:==
: 3.      Change to Hot, Full-Power Feedwater Temperature


Summary: The proposed change revises the UFSAR to reflect the observed hot full-power feedwater temperature.
== Description:==
This change revises the upper end of the hot full-power feedwater temperature range to 448 'F for all safety analyses described in the UFSAR.There is no change made to the operating parameters.
The proposed change revises the UFSAR to reflect the observed hot full-power feedwater temperature. This change revises the upper end of the hot full-power feedwater temperature range to 448 'F for all safety analyses described in the UFSAR.
The results of the evaluation for higher HFP feedwater temperature show that all acceptance limits continue to be met, and the design basis limits for the fission product barriers are not exceeded.}}
Summary:    There is no change made to the operating parameters. The results of the evaluation for higher HFP feedwater temperature show that all acceptance limits continue to be met, and the design basis limits for the fission product barriers are not exceeded.}}

Latest revision as of 08:09, 23 November 2019

CFR50.59 Summary Report
ML071140189
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 04/16/2007
From: Head S
South Texas
To:
Document Control Desk, NRC/NRR/ADRO
References
NOC-AE-07002144
Download: ML071140189 (5)
v • d • e


Text

Nuclear Operating Company South Texas Proect Electnrc GeneratingStation P0. Box 289 Wadsworth. Texs 77483 lvvv"---

April 16, 2007 NOC-AE-07002144 10CFR50.59 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.59 Summary Report Pursuant to the requirements of 10CFR50.59, the attached report contains a brief description and summary of the 10CFR50.59 evaluations of changes, tests and experiments conducted at the South Texas Project.

There are no commitments in this letter.

If there are any questions regarding this summary report, please contact J. R. Morris at (361) 972-8652 or me at (361) 972-7136.

Scott M. Head Manager, Licensing awh

Attachment:

2007 10CFR50.59 Evaluation Summaries STI:32143330

NOC-AE-07002144 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 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mohan C. Thadani U. S. Nuclear Regulatory Commission Senior Resident Inspector Steve Winn U. S. Nuclear Regulatory Commission Christine Jacobs P. 0. Box 289, Mail Code: MN116 Eddy Daniels Wadsworth, TX 77483 Marty Ryan NRG South Texas LP C. M. Canady Ed Alarcon City of Austin J. J. Nesrsta Electric Utility Department R. K. Temple 721 Barton Springs Road Kevin Pollo Austin, TX 78704 City Public Service Richard A. Ratliff Jon C. Wood Bureau of Radiation Control Cox Smith Matthews Texas Department of State Health Services 1100 West 49th Street C. Kirksey Austin, TX 78756-3189 City of Austin

Attachment NOC-AE-07002144 Page 1 of 3 Summaries of the following 10CFR50.59 Evaluations are provided in this attachment:

1. 05-15364-10 Preheater Bypass Valve Test at Power
2. 04-12793-3 Change to Failure Modes & Effects Analysis for Auxiliary Feedwater
3. 05-4840-4 Change to Hot, Full-Power Feedwater Temperature

Attachment NOC-AE-07002144 Page 2 of 3 10CFR50.59 Evaluation Summaries

1. Preheater Bypass Valve Test at Power

Description:

This evaluation supports a change to the Preheater Bypass Valve Operability Test procedure, to perform testing required by Technical Specification 4.6.3.1, Containment Isolation Valves. The valve operability testing will be performed for Containment isolation valve A2FW-FV-7192, Steam Generator 2D Preheater Outside *Reactor Containment Bypass Valve. The test will stroke the valve during at-power operation.

Summary: All equipment impacted by the proposed test will stay within its design basis. All code requirements will be satisfied. In addition, the ensuing transient will not result in changing from a Condition I to a Condition II event. This test does not impact accident scenarios and the current dose analysis remains bounding.

2. Change to Failure Modes & Effects Analysis for Auxiliary Feedwater

Description:

The change revises the STP UFSAR to reflect revised failure modes and effects analysis (FMEA) for the AFW system electrical components in the isolation valve cubicle (IVC). The change also revises accident analyses to credit faulted steam generator isolation using the safety-grade AFW outside containment isolation valves (OCIV) instead of the AFW regulating valves.

Summary: The proposed change replaces the faulted SG isolation function from the operator closing the AFW REG valves to the operator closing the AFW OCIVs. The AFW OCIVs are qualified to "harsh" environment conditions. The proposed change takes credit for the existing operator actions to isolate the faulted steam generator by closing the AFW OCIV or securing the pump. No new operator actions, procedure changes or equipment qualification will be performed. The required operator actions already exist in plant procedures No evaluation methodology is changed and no equipment or component needs to be requalified. No changes will be made to equipment important to safety or to operator actions. The proposed UFSAR change revises analysis to reflect plant conditions and does not change plant configuration. The change does not introduce the possibility of a malfunction of an SSC important to safety with a different result because no new failure modes are introduced. This change does not impact accident scenarios and the current dose analysis remains bounding.

Attachment NOC-AE-07002144 Page 3 of 3

3. Change to Hot, Full-Power Feedwater Temperature

Description:

The proposed change revises the UFSAR to reflect the observed hot full-power feedwater temperature. This change revises the upper end of the hot full-power feedwater temperature range to 448 'F for all safety analyses described in the UFSAR.

Summary: There is no change made to the operating parameters. The results of the evaluation for higher HFP feedwater temperature show that all acceptance limits continue to be met, and the design basis limits for the fission product barriers are not exceeded.

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