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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 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 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-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 ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town 2024-09-30
[Table view] Category:License-Operator Examination Report
MONTHYEARML23156A2302023-06-0606 June 2023 NRC Initial Operator Licensing Examination Approval 05000445/2023301 and 05000446/2023301 ML21236A3332021-08-25025 August 2021 CP2021301-Revised Exam Approval Ltr ML18207A9422018-08-0101 August 2018 NRC Examination Report 05000445/2018301, 05000446/2018301 IR 05000445/20173012017-07-11011 July 2017 NRC Examination Report 05000445/2017301; 05000446/2017301 IR 05000445/20163012016-09-23023 September 2016 NRC Examination Report 05000445/2016301; 05000446/2016301 IR 05000445/20153022015-06-26026 June 2015 Er 05000445/2015302; 05000446/2015302; on 06/01/2015 - 06/23/2015; the Comanche Peak Nuclear Power Plant, Units 1 and 2; Initial Operator Licensing Examination Report IR 05000445/20143012014-06-27027 June 2014 Er 05000445-14-301; 05000446-14-301; on June 9-16, 2014; the Comanche Peak Nuclear Power Plant, Units 1 and 2; Initial Operator Licensing Examination Report IR 05000445/20133012013-04-24024 April 2013 Er 05000445-13-301 & 05000446-13-301, 03/04/2013 - 04/22/2013, Comanche Peak Nuclear Power Plant, Units 1 and 2, Initial Operator Licensing Examination Report IR 05000445/20123012012-08-23023 August 2012 Er 05000445-12-301, & 05000446-12-301, June 11 Through July 23, 2012, Comanche Peak Nuclear Power Plant, Units 1 and 2, Initial Operator Licensing Examination Report IR 05000445/20113012011-07-0808 July 2011 Initial Operator Licensing Examination Report 05000445/2011301; 05000446/2011301 IR 05000445/20103022010-07-30030 July 2010 Er 05000445-10-302 on 07/07/10 07/08/10 for Comanche Peak Nuclear Power Plant, Unit 1 & 2, Initial Operator Licensing Examination Report IR 05000445/20093012009-05-0808 May 2009 Er 05000445-09-301, 05000446-09-301 on 03/30/09 - 04/14/09 for Comanche Peak, Units 1 and 2 IR 05000445/20053022005-11-0909 November 2005 Er 05000445-05-302; 05000446-05-302; 09/26/2005; Comanche Peak Steam Electric Station; Retake Operator Licensing Examination Report ML0409200332004-03-30030 March 2004 Generic Fundamentals Section of the Written Operator Licensing Examination 2023-06-06
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UNITED STATES NUC LE AR RE G UL AT O RY C O M M I S S I O N uly 8, 2011
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 -
NRC EXAMINATION REPORT 05000445/2011301; 05000446/2011301
Dear Mr. Flores:
On June 13, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator license examination at Comanche Peak Nuclear Power Plant, Units 1 and 2. The enclosed report documents the examination results and licensing decisions. The preliminary examination results were discussed on June 10, 2011, with Mr. Steven Sewell, Operations Director, and other members of your staff. A telephonic exit meeting was conducted on June 27, 2011, with Mr. Garry Struble, Simulator and License Examination Manager, who was provided the NRC licensing decisions.
The examination included the evaluation of six applicants for reactor operator licenses, two applicants for instant senior reactor operator licenses, and five applicants for upgrade senior reactor operator licenses. The license examiners determined that all of the applicants satisfied the requirements of 10 CFR Part 55 and the appropriate licenses have been issued. There were no post-examination comments submitted by your staff. The enclosure to this letter contains the details of this report.
No findings were identified during this examination.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Mark S. Haire, Chief Operations Branch Division of Reactor Safety
Luminant Generation Company, LLC -2-Dockets: 50-445; 50-446 Licenses: NPF-87; NPF-89 Enclosure:
NRC Examination Report 05000445/2011301; 05000446/2011301 Distribution via Listserv for Comanche Peak Nuclear Power Plant
Luminant Generation Company, LLC -3-Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
Deputy Regional Administrator (Art.Howell@nrc.gov)
DRP Director (Kriss.Kennedy@nrc.gov)
Acting DRP Deputy Director (Jeff.Clark@nrc.gov)
DRS Director (Anton.Vegel@nrc.gov)
Acting DRS Deputy Director (Robert Caldwell@nrc.gov)
Senior Resident Inspector (John.Kramer@nrc.gov)
Resident Inspector (Brian.Tindell@nrc.gov)
Branch Chief, DRP/A (Wayne.Walker.nrc.gov)
Senior Project Engineer, DRP/A (David.Proulx@nrc.gov)
Project Engineer, DRP/A (Chris.Henderson@nrc.gov)
CP Administrative Assistant (Sue.Sanner@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Balwant.Singal@nrc.gov)
Branch Chief, DRS/TSB (Dale.Powers@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
OEMail Resource RIV/ETA: OEDO (John.McHale@nrc.gov)
DRS/TSB STA (Dale.Powers@nrc.gov)
SUNSI Review Completed: __BTL__ ADAMS: Yes No Initials: __BTL__
Publicly Available Non-Publicly Available Sensitive Non-Sensitive SOE:OB SOE:OB OE:OB OE:OB C:PBA C:OB BLarson COsterholtz CSteely TFarina WWalker MHaire
/RA/ /RA/ /RA/ /RA/ /RA/ /RA/
7/6/11 7/6/11 7/7/11 7/7/11 7/7/11 7/8/11 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Dockets: 50-445, 50-446 Licenses: NPF-87, NPF-89 Report: 05000445/2011301; 05000446/2011301 Licensee: Luminant Generation Company, LLC Facility: Comanche Peak Nuclear Power Plant, Units 1 and 2 Location: FM-56, Glen Rose, Texas Dates: June 6-27, 2011 Inspectors: B. Larson, Senior Operations Engineer C. Osterholtz, Senior Operations Engineer C. Steely, Operations Engineer T. Farina, Operations Engineer Approved by: Mark S. Haire, Chief Operations Branch Division of Reactor Safety 1 Enclosure
SUMMARY OF FINDINGS
ER05000445/2011301; 05000446/2011301; June 6-27, 2011; Comanche Peak Nuclear Power
Plant, Units 1 and 2; Initial Operator Licensing Examination Report.
NRC examiners evaluated the competency of six applicants for reactor operator licenses, two applicants for instant senior reactor operator licenses, and five applicants for upgrade senior reactor operator licenses at Comanche Peak Nuclear Power Plant, Units 1 and 2.
The licensee developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9, Supplement 1. The written examination was administered by the licensee on June 13, 2011. NRC examiners administered the operating tests on June 6-10, 2011.
The examiners determined that all of the applicants satisfied the requirements of 10 CFR Part 55 and the appropriate licenses have been issued.
NRC-Identified and Self-Revealing Findings
No findings were identified.
Licensee-Identified Violations
None.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other Activities (Initial Operator License Examination)
.1 License Applications
a. Scope
NRC examiners reviewed all license applications submitted to ensure each applicant satisfied relevant license eligibility requirements. The examiners also audited five of the license applications in detail to confirm that they accurately reflected the subject applicants qualifications. This audit focused on the applicants experience and on-the-job training, including control manipulations that provided significant reactivity changes.
b. Findings
No findings were identified.
.2 Examination Development
a. Scope
NRC examiners reviewed integrated examination outlines and draft examinations submitted by the licensee against the requirements of NUREG-1021. The NRC examination team conducted an onsite validation of the operating tests.
b. Findings
No findings were identified.
NRC examiners provided outline, draft examination and post-validation comments to the licensee. The licensee satisfactorily completed comment resolution prior to examination administration.
NRC examiners determined that the written examinations and operating tests initially submitted by the licensee were within the range of acceptability expected for a proposed examination.
.3 Operator Knowledge and Performance
a. Scope
On June 13, 2011, the licensee proctored the administration of the written examinations to all thirteen applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis to the NRC on June 16, 2011.
The NRC examination team administered the various portions of the operating tests to all thirteen applicants on June 6-10, 2011.
b. Findings
No findings were identified.
All of the applicants passed the written examination and all parts of the operating test.
The final written examinations, final operating tests, and post-examination analysis may be accessed in the ADAMS system under the accession numbers noted in the attachment. There were no post-examination comments as indicated in the licensee submittal.
The examination team noted the following generic weaknesses: 1) all crews demonstrated a weakness on the use of the Boration Matrix and completion of boration fifteen minutes prior to reaching final power level and 2) six of seven senior reactor operator applicants missed a written examination question that required knowledge of Technical Specification Section 3.8.1, AC Sources, for actions required when two required offsite circuits are inoperable.
The licensee entered these deficiencies into their corrective action program as CR-2011-006939.
.4 Simulation Facility Performance
a. Scope
The NRC examiners observed simulator performance with regard to plant fidelity during examination validation and administration.
b. Findings
No findings were identified.
During performance of a simulator Job Performance Measure (JPM), power momentarily dropped out on valve 1/1-8809B, RHR TO CL 3 & 4 INJ ISOL VLV. This caused the valve to stop in mid-position. The valve was overridden from the simulator operator station and the JPM was completed. This was identified as a simulator hardware issue and was entered into the licensee corrective action program as CR-2011-006892.
.5 Examination Security
a. Scope
The NRC examiners reviewed examination security during both the onsite preparation week and examination administration week for compliance with 10 CFR 55.49 and NUREG-1021. Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
The chief examiner presented the preliminary examination results to Messrs. Mike Paige, Training Director, Eugene Skelton, Operations Training Manager, Coy Rice, Acting Initial License Operator Training, and other members of the staff on June 10, 2011. A telephonic exit was conducted on June 27, 2011, between Ms. Laura Hurley, Operator Licensing Assistant, and Garry Struble, Simulator and License Examination Manager.
The licensee did not identify any information or materials used during the examination as proprietary.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
Garry Struble, Simulator and License Examination Manager
NRC Personnel
John Kramer, Senior Resident Inspector
ADAMS DOCUMENTS REFERENCED