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Category:Letter
MONTHYEARCP-202400424, (Cpnpp), Core Operating Limits Report (Colr), Unit 2 Cycle 22, (ERX-24-001, Revision 0)2024-11-0404 November 2024 (Cpnpp), Core Operating Limits Report (Colr), Unit 2 Cycle 22, (ERX-24-001, Revision 0) IR 05000445/20240032024-10-30030 October 2024 Integrated Inspection Report 05000445/2024003 and 05000446/2024003 IR 05000445/20244042024-10-23023 October 2024 Security Baseline Inspection Report 05000445/2024404 and 05000446/2024404 (Public) IR 07200074/20244012024-10-10010 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200074/2024401 Public 05000445/LER-2024-002-01, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-10-0303 October 2024 Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions 05000446/LER-2024-001-01, Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-09-30030 September 2024 Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel ML24031A6322024-09-11011 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4), Final Safety Analysis Report Update Schedule (EPID L-2023-LLE-0023) - Letter ML24243A0152024-09-0303 September 2024 – Notification of Comprehensive Engineering Team Inspection (05000445/2025012 and 05000446/2025012) and Request for Information ML24194A1332024-08-28028 August 2024 Issuance of Amendment Nos. 190 and 190, Respectively, Revision to Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24228A2252024-08-22022 August 2024 Relief to Use Later Code Edition for Inservice Inspection Program ML24179A0772024-08-20020 August 2024 Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 IR 05000445/20240052024-08-15015 August 2024 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005) CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024 (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality ML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) ML24187A0372024-07-15015 July 2024 Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants 05000445/LER-1924-002, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-06-0303 June 2024 (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator 05000446/LER-2024-001, (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-05-13013 May 2024 (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications 05000445/LER-2024-001, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning2024-05-0606 May 2024 Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma 2024-09-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 25, 2009 Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043 SUB~IECT: COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 1 - REVIEW OF THE 2008 STEAM GENERATOR TUBE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 1RF13 (TAC NO. ME0367)
Dear Mr. Flores:
By letter dated January 7, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. IVIL090300118), as supplemented by letter dated April 21, 2009 (ADAMS Accession No. ML091180326), Luminant Generation Company LLC (the licensee),
submitted information summarizing the results of the 2008 steam generator tube inspections performed at the Comanche Peak Steam Electric Station (CPSES), Unit 1 during the thirteenth refueling outage (1 RF13).
The U.S. Nuclear Regulatory Commission (NRC) has completed its review of these reports and concludes that the licensee provided the information required by the CPSES, Unit 1, Technical Specifications and that no additional follow-up action is required at this time. The results of the NRC staff's review of the reports submitted by the licensee are summarized in the enclosure to this letter. If you have any questions, please contact me at 301-415-3016 or via e-mail at balwant.singal@nrc.gov.
Sincerely, b"", \W~~ t~~\1~~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-445
Enclosure:
As stated cc w/encl: Distribution via Listserv
OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF INSPECTION REPORTS FOR 2008 STEAM GENERATOR TUBE INSPECTIONS PERFORMED DURING UNIT 1 REFUELING OUTAGE 1RF13 LUMINANT GENERATION COMPANY LLC COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 1 DOCKET NO. 50-445 By letter dated January 7, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090300118), as supplemented by letter dated April 21 ,2009 (ADAMS Accession No. ML091180326), Luminant Generation Company LLC (the licensee),
submitted information summarizing the results of the 2008 steam generator (SG) tube inspections performed at the Comanche Peak Steam Electric Station (CPSES), Unit 1 during refueling outage "RF13.
CPSES, Unit 1 has four Westinghouse Model Delta 76 SGs. Each SG contains 5,532 thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of % inch and a nominal wall thickness of 0.043 inch. The row 1 and 2 tubes have a nominal wall thickness of 0.044 inch. The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by four sets of type 405 stainless steel 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, such as tube plugging, taken in response to the inspection findings. The tubes in all four SGs were inspected during CPSES, Unit 1 thirteenth refueling outage (1 RF13).
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by the licensee, and has the following comments and observations:
- The licensee replaced its SGs in 2007 during CPSES, Unit 1 refueling outage 12 (1 RF12). The 2008 inspections were the first inservice inspections of the SGs since the replacement.
- During the pre-service inspection, a condition was identified that suggested reduced tube-to-tube clearance in the U-bend region in the eddy current data in 28 tubes. These indications are classified as trackable anomalies and there was no tube wear associated with this condition. The licensee reported that there was no change in these eddy current signals between the pre-service inspection Enclosure
-2 and the 2008 inspection.
- Bobbin inspections in SG1 resulted in the identification of possible loose part indications in six tubes. Further investigation of these signals with a rotating probe suggested that the bobbin signals were the result of the presence of axially oriented deposits on the outside surface of the tube. These deposits were reported to generally increase with proximity to the 10lh hot leg tube support plate and, in some cases, extend through the tube support plate at the trefoil lobe.
These deposits were observed visually.
- The licensee provided its operational assessment for tube wear indications.
Although the NRC staff did not review this analysis in detail, the results appear reasonable based on operating experience at similarly designed and operated units.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Technical Specifications. In addition, the NRC staff concludes 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: A. Obodoako Date: September 25, 2009
September 25, 2009 Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 1 - REVIEW OF THE 2008 STEAM GENERATOR TUBE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 1RF13 (TAC NO. ME0367)
Dear Mr. Flores:
By letter dated January 7, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090300118), as supplemented by letter dated April 21, 2009 (ADAMS Accession No. ML091180326), Luminant Generation Company LLC (the licensee),
submitted information summarizing the results of the 2008 steam generator tube inspections performed at the Comanche Peak Steam Electric Station (CPSES), Unit 1 during the thirteenth refueling outage (1 RF13).
The U.S. Nuclear Regulatory Commission (NRC) has completed its review of these reports and concludes that the licensee provided the information required by the CPSES, Unit 1, Technical Specifications and that no additional follow-up action is required at this time. The results of the NRC staff's review of the reports submitted by the licensee are summarized in the enclosure to this letter. If you have any questions, please contact me at 301-415-3016 or via e-mail at balwant.singal@nrc.gov.
Sincerely, Ira/
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-445
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLAJBurkhardt Resource LPLIV Reading RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource RidsRgn4MailCenter Resource RidsNrrDciCsgb Resource AObodoako, NRR/DCI/CSGB RidsNrrDorlLpl4 Resource KKarwoski, NRR/DCI RidsNrrPMComanchePeak Resource ADAMS Accession No: ML092600269
- Memo dated 9/1/09 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRR/CSGB/BC(A) NRR/LPL4/BC NRR/LPL4/PM NAME BSingal JBurkhardt MGavriias' MMarkley BSingal DATE 9/25/09 9/24/09 9/1109 9/25/09 9/25/09 OFFICIAL AGENCY RECORD