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Category:Letter
MONTHYEARML24304B0512024-10-30030 October 2024 Cycle 26 Core Operating Limits Report IR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24290A1162024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance NOC-AE-240040, Nuclear Liability Certificates of Insurance2024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 ML24022A2252024-02-20020 February 2024 Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation ML24050A0082024-02-19019 February 2024 Evidence of Financial Protection ML24045A0922024-02-16016 February 2024 Response to STP FOF Move Letter (2024) 2024-09-30
[Table view] Category:Safety Evaluation
MONTHYEARML24201A0462024-07-26026 July 2024 Authorization and Safety Evaluation for Alternative Request No. RR-ENG-4-07 ML24022A2252024-02-20020 February 2024 Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation ML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) ML23279A0482023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Enclosure 4 -Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Nonproprietary Safety Evaluation) ML23015A0012023-02-0606 February 2023 Issuance of Amendment Nos. 225 and 210 to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML22300A2492022-12-0606 December 2022 Approval for Alternate Disposal Procedures for Very Low-Level Radioactive Material (EPID: L?2021?LLL?0022) ML22245A0012022-09-12012 September 2022 Relief from the Requirements of the ASME Code ML21319A3552021-12-0909 December 2021 Issuance of Amendment Nos. 224 and 209 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML21320A0022021-12-0808 December 2021 Issuance of Amendment Nos. 223 and 208 to Revise Technical Specification 3.6.3 and to Remove the Technical Specifications Index NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 22021-05-11011 May 2021 Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 ML21033A2392021-04-0808 April 2021 Issuance of Amendment Nos. 222 and 207 to Revise Technical Specifications to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML20253A0462020-09-29029 September 2020 Issuance of Amendment Nos. 220 and 205 to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML20227A3852020-09-0303 September 2020 Nonproprietary - Proposed Alternative RR-ENG-3-24 to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping ML20199M1622020-07-21021 July 2020 Proposed Alternatives PRR-01, PRR-02, PRR-03, and PRR-04 to the Requirements of the ASME OM Code (Epids L-2020-LLR-0007 to L-2020-LLR-0010) ML20141L6122020-05-28028 May 2020 Issuance of Amendment No. 219 to Revise Technical Specifications to Reduce Safety Injection Accumulators Minimum Pressures (Exigent Circumstances) ML19322A7192019-12-0909 December 2019 Issuance of Amendment Nos. 218 and 204 to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML19217A0602019-10-24024 October 2019 Issuance of Amendment Nos. 217 and 203 Revision to Technical Specification Tables to Change Terminology for the P-13 Permissive Interlock Description ML19213A1472019-08-20020 August 2019 Issuance of Amendment Nos. 216 and 202 Standby Diesel Generator Surveillance Requirements ML19142A3072019-08-13013 August 2019 Request for Relief Request RR-ENG-3-23 to Extend Volumetric Examination Interval for Reactor Vessel Closure Head Nozzles ML19067A2222019-06-0606 June 2019 Issuance of Amendment Nos. 215 and 201 Adoption of TSTF-522 Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month ML18303A2062018-11-0707 November 2018 Request for Relief from ASME Code to Extend the Inservice Inspection Interval for Category B-N-2 and B-N-3 Examinations ML18187A1492018-07-24024 July 2018 Relief Request RR-ENG-3-22 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML18177A4252018-07-24024 July 2018 Relief from the Requirements of the Asme Code Regarding the Third 10-Year Inservice Inspection Interval ML18159A2122018-07-19019 July 2018 Issuance of Amendment Nos. 214 and 200 Emergency Response Organization Time Augmentation and Staffing Chances to the Emergency Plan (CAC Nos. MG0024 and MG0025; EPID L-2017-LLA-0265) ML18128A3422018-06-0707 June 2018 Issuance of Amendment Nos. 213 and 199 to Revise TSs for Administrative Changes and to Relocate Fxy Exclusion Zones to the Colrs(Cac Nos. MG0253 and MG0254, EPID-L-2017-LLA-0300) ML17019A0022017-07-11011 July 2017 Safety Evaluation, Enclosure 3 to Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML17038A2232017-07-11011 July 2017 Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191 ML16319A0102016-12-21021 December 2016 Issuance of Amendment No. 211, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies ML16174A0912016-06-30030 June 2016 Relief Request RR-ENG-3-20, Use of ASME Code Case N-770-1, Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, for the Third 10-Year Inservice Inspection Interval ML16116A0072016-04-29029 April 2016 Issuance of Amendment Nos. 210 and 197, Revise Technical Specification 6.8.3.j, Containment Leakage Rate Testing Program, to Extend Integrated Leak Rate Test Interval from 10 to 15 Years ML15342A0032015-12-28028 December 2015 Issuance of Amendment Nos. 209 and 196, Adopt Technical Specification Task Force (TSTF)-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (CAC MF6178-MF6179) ML15343A1282015-12-11011 December 2015 Issuance of Amendment No. 208, Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Unit 1 Cycle 20 (Emergency Circumstances) ML15209A6412015-09-22022 September 2015 Issuance of Amendment Nos. 207 and 195, Revise Updated Final Safety Analysis Report Table 15.6-17 to Correct Radiological Doses Resulting from Calculation Error Performed in Support of Amendments 182 and 169 ML15218A3672015-08-21021 August 2015 Relief Request RR-ENG-17, Relief from Code Case N-770-1, Subsection 2400 and Table 1 Inspection Frequency of Reactor Vessel Cold Leg Nozzle to Safe-End Welds with Flaw Analysis, Third 10-Year ISI Interval ML15201A1952015-08-20020 August 2015 Issuance of Amendment Nos. 206 and 194, Revise the Emergency Action Level Scheme to the NRC-endorsed Scheme Contained in NEI-99, Revision 6 ML15075A1462015-04-29029 April 2015 Issuance of Amendment Nos. 205 and 193, Request to Revise Technical Specification 3.3.1, Functional Unit 20, Reactor Trip Breakers, for Required Actions and Allowed Outage Times ML15049A1292015-02-27027 February 2015 Issuance of Amendment Nos. 204 and 192, Revise Technical Specification 6.9.1.6, Core Operating Limits Report, with Respect to Analytical Methods Used to Determine Core Operating Limits ML14339A1702015-02-13013 February 2015 Issuance of Amendment Nos. 203 and 191, Revise Fire Hazards Analysis Report and Fire Protection Program License Conditions Related to Alternate Shutdown Capability ML14281A0652015-01-29029 January 2015 Issuance of Amendment Nos. 202 and 190, Revise Operating License Conditions Related to Cyber Security Plan Milestone 8 Full Implementation Date ML13221A0042013-09-0909 September 2013 Issuance of Amendment Nos. 201 and 189, Revise TS 5.0, Design Features, to Reflect Removal of Visitor'S Center Building and References to Emergency Operations Facility ML13142A1602013-06-0606 June 2013 Safety Assessment in Response to Information Request Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13008A5282013-04-25025 April 2013 Issuance of Amendment Nos. 200 and 188, Revise Technical Specification 3.3.3.6, Accident Monitoring Instrumentation ML13087A5172013-04-12012 April 2013 Relief Request RR-ENG-3-09, Request for Relief from ASME Code Requirements; Deferral of Code Repair of Essential Cooling Water System Piping Until April 2013 Refueling Outage ML13004A3392013-03-12012 March 2013 Relief Request RR-ENG-3-10, Reactor Pressure Vessel Head Flange O-Ring Leakoff Lines Non-Destructive Examination, for the Third 10-Year Inservice Inspection Interval ML13007A1362013-01-31031 January 2013 Review of Operations Quality Assurance Plan, Revision 20 ML12243A3432012-09-10010 September 2012 RR RE-ENG-3-04 to Apply Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Requirements for Examination of Class 1 and 2 Piping Welds ML12235A3472012-08-28028 August 2012 Relief Request RR-ENG-3-06 from ASME Code Requirements for Leak Testing Boundaries of Class 1 Pressure-Retaining Components, Third 10-Year Inservice Inspection Interval (TAC ME7053-ME7054) ML12201A2562012-08-16016 August 2012 Relief Request RR-ENG-3-08, Deferral of Code Repair of Flaws in U2 Essential Cooling Water Class 3 Piping Until Restart from Current Refueling Outage Scheduled for Mid-April 2012 ML12152A2452012-08-14014 August 2012 Issuance of Amendment Nos. 199 and 187, Revise Applicability of Risk-Managed Technical Specifications (TS) to TS 3.7.7, Control Room Makeup and Cleanup Filtration System ML1124402222011-11-17017 November 2011 Issuance of Amendment Nos. 198 and 186, Revise Technical Specifications 5.3.1 and 6.9.1.6 to Allow Fuel Assemblies with Optimized Zirlo Cladding 2024-07-26
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April 7, 2008 Mr. James J. Sheppard President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNIT 1 - EVALUATION OF 2006 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MD5948)
Dear Mr. Sheppard:
By letter dated April 16, 2007, as supplemented by letter dated February 7, 2008, STP Nuclear Operating Company (the licensee), submitted information summarizing the results of its 2006 steam generator tube inspections at South Texas Project Electric Generating Station (STP),
Unit 1. The 2006 tube inspections were performed during refueling outage 13.
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of your reports and concluded that you have provided the information required by the STP, Unit 1, technical specifications and that no additional review is required at this time. The NRC staff=s safety evaluation of the reports is enclosed.
If you have any questions regarding this issue, please contact me at (301) 415-1476.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-498
Enclosure:
Safety Evaluation cc w/encl: See next page
ML080780217 *memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DCI/CSGB/BC NRR/LPL4/BC NAME MThadani JBurkhardt AHiser* THiltz DATE 4/3/08 4/3/08 3/11/08 4/7/08 South Texas Project, Units 1 and 2 12/5/2007 cc:
Senior Resident Inspector S. M. Head, Manager, Licensing U.S. Nuclear Regulatory Commission STP Nuclear Operating Company P.O. Box 289 P.O. Box 289, Mail Code: N5014 Wadsworth, TX 77483 Wadsworth, TX 77483 C. M. Canady C. T. Bowman, General Manager, Oversight City of Austin STP Nuclear Operating Company Electric Utility Department P.O Box 289 721 Barton Springs Road Wadsworth, TX 77483 Austin, TX 78704 Ms. Marilyn Kistler J. J. Nesrsta/R. K. Temple Senior Staff Specialist, Licensing E. Alercon/Kevin Pollo STP Nuclear Operating Company CPS Energy P.O. Box 289, Mail Code 5014 P.O. Box 1771 Wadsworth, TX 77483 San Antonio, TX 78296 Environmental and Natural Resources INPO Policy Director Records Center P.O. Box 12428 700 Galleria Parkway Austin, TX 78711-3189 Atlanta, GA 30339-3064 Mr. Jon C. Wood Regional Administrator, Region IV Cox, Smith, & Matthews U.S. Nuclear Regulatory Commission 112 East Pecan, Suite 1800 611 Ryan Plaza Drive, Suite 400 San Antonio, TX 78205 Arlington, TX 76011 Director, Division of Compliance & Inspection Steve Winn/Christie Jacobs Bureau of Radiation Control Eddy Daniels/Marty Ryan Texas Department of State Health Services NRC Energy, Inc. 1100 West 49th Street 211 Carnegie Center Austin, TX 78756 Princeton, NJ 08540 Mr. Ted Enos Mr. Nate McDonald 4200 South Hulen County Judge for Matagorda County Suite 422
\1700 7th Street, Room 301 Ft. Worth, TX 76109 Bay City, TX 77414 Mr. Brian Almon A. H. Gutterman, Esq. Public Utility Commission of Texas Morgan, Lewis & Bockius P.O. Box 13326 1111 Pennsylvania Avenue, NW Austin, TX 78711-3326 Washington, DC 20004 E. D. Halpin, Site Vice President STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483
South Texas Project, Units 1 and 2 12/5/2007 Ms. Susan M. Jablonski Mr. Anthony P. Jones, Chief Boiler Inspector Office of Permitting, Remediation Texas Department of Licensing and Regulation and Registration Boiler Division Texas Commission on Environmental Quality E.O. Thompson State Office Building MC-122 P.O. Box 12157 P.O. Box 13087 Austin, TX 78711 Austin, TX 78711-3087 Mr. Ken Coates, Plant General Manager STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO 2006 STEAM GENERATOR TUBE INSPECTIONS FACILITY OPERATING LICENSE NO. NPF-76 STP NUCLEAR OPERATING COMPANY, ET AL.
SOUTH TEXAS PROJECT, UNIT 1 DOCKET NO. 50-498 By letter dated April 16, 2007 (Agencywide Document Access and Management System (ADAMS) Accession No. ML071140087), as supplemented by letter dated February 7, 2008 (ADAMS Accession No. ML080500210), STP Nuclear Operating Company (the licensee),
submitted information summarizing the results of its 2006 steam generator (SG) tube inspections at South Texas Project Electric Generating Station (STP), Unit 1. The 2006 tube inspections were performed during refueling outage 13 (1RE13).
STP Unit 1 has four recirculating SGs designed and fabricated by Westinghouse. The model Delta 94 SGs were put into service in 2000 during 1RE9. Each SG has 7585 thermally-treated Alloy 690 tubes which have an outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. The tubes were hydraulically expanded at each end for the full depth of the tubesheet and are supported by a flow distribution baffle, support plates, and anti-vibration bars.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.
As a result of the review of the reports, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comments/observations:
1RE13 was the first primary side eddy-current tube inspections since 1RE10 for SGs A, B, and C. SG D was inspected during 1RE12.
Several hundred small wire fragments were previously identified in the secondary side in SG D. The wire fragments were attributed to a feedwater heater cable stabilizer that migrated into SG D during cycle 11, prior to or during the shutdown for 1RE11. The licensee continued to identify and remove pieces of this wire during the 2006 outage.
Based on eddy-current inspection results, there are approximately 250 to 300 pieces of wire located on the flow distribution baffle (FDB). These pieces are distributed over the entire FDB. Five pieces of wire were left behind a stayrod on the top of the tubesheet.
The licensee plans to open the inspection port on the FDB, first tube support plate, and
second tube support plate and inspect every row/column during 1RE14. The remaining SGs are on a 3-cycle inspection interval.
SG 1A has a significantly higher number of dents/dings (with bobbin voltages greater than 5 volts), than the other three SGs. The licensee believes these dents/dings are due to the fabrication process. The licensee does not expect these dents/dings to cause corrosion-related cracking, but will monitor them in future inspections.
Tube scale profiling on SG C indicated light scale in the upper bundle. Profiling in conjunction with upper bundle visual inspection will be used to determine the need for future actions. Profiling is part of the SG long-term inspection plan.
Visual inspection of the upper steam drum, feedring and ninth tube support plate (TSP) for SG 1C, revealed no abnormalities (wear or deformation). The ninth TSP and associated tubes showed early stages of magnetite fouling. The licensee tracks tube fouling to determine if future actions to remove the fouling are necessary.
One tube in SG D (row 117 column 49) was plugged due to a wear indication (attributed to the stabilizer wire) that measured 44 percent through wall. This tube was last inspected in 1RE12 (2005). The 2005 inspection did not show any evidence of a loose part or wear at this location.
One tube in SG B has a restriction. The licensee indicated that a temporary wedge fell onto this tube when the SG was rotated into a vertical position during installation.
The wedge was removed. This tube is included in the inspection scope during each inspection outage.
The licensee has operated 52.66 effective full power months (EFPM) in its 144-EFPM sequential period.
The licensee intends to inspect a sample of the bulges and over-expansions in the tubesheet during future inspections.
Based on a review of the information provided, the NRC staff concluded that the licensee provided the information required by the STP Unit 1 technical specifications. In addition, the staff concluded that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Principal Contributor: J. Burke, NRR Date: April 7, 2008