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Category:Letter
MONTHYEARIR 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 05000445/20243012024-10-15015 October 2024 NRC Initial Operator Licensing Examination Approval 05000445/2024301 and 05000446/2024301 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 ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 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 ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma 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 ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana 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 ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma 2024-09-30
[Table view] Category:License-Operator Examination Report
MONTHYEARIR 05000445/20233012023-08-21021 August 2023 NRC Examination Report 05000445/2023301 and 05000446/2023301 ML23156A2302023-06-0606 June 2023 NRC Initial Operator Licensing Examination Approval 05000445/2023301 and 05000446/2023301 IR 05000445/20213012021-10-19019 October 2021 NRC Examination Report 05000445/2021301 and 05000446/2021301 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 2023-08-21
[Table view] |
Text
August 1, 2018
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 - NRC EXAMINATION REPORT 05000 445/2018301; 05000 446/2018301
Dear Mr. Peters:
On July 19, 20 18, 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 15, 2018 , with members of your staff.
A telephonic exit meeting was conduct ed on July 19, 2018 , with M s. Donna Christiansen, Training Director
, who was provided the NRC licensing decisions.
The examination included the evaluation of six applicants for reactor operator licenses, six applicants for instant senior reactor operator licenses, and three applicant s for upgrade senior reactor operator license s. The license examiners determined that fourteen of the fifteen applicants satisfied the requirements of Title 10 of the Code of Federal Regulations (CFR) Part 55, and the appropriate licenses have been issued.
There was one post examination comment submitted by your staff.
Enclosure 1 contains details of this report and Enclosure 2 summarizes post examination comment resolution
. No violations were identified during this examination
. In accordance with 10 CFR 2.390 of the NRC's "Agency Rules of Practice and Procedure," 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 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD ARLINGTON, TX 76011-4511 NRC's Agencywide Documents Access and Management 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/ Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety Docket Nos.
50-445, 50-446 License Nos.
NPF-87, NPF-89 Enclosure s: 1. Examination Report 05000445/2018301; 05000446
/2018301
w/Attachment:
Supplemental Information 2. NRC Post Examination Comment Resolution COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2
- NRC EXAMINATION REPORT 05000445/2018301; 05000 446/2018301 DATED AUGUST 1, 2018 DISTRIBUTION:
KKennedy, RA SMorris, DRA AVegel, DRP MShaffer, DRS JClark, DRS RLantz, DRP DCylkowski, RC JJosey, DRP RKumana, DRP MHaire, DRP RAlexander, DRP AAthar, DRP LNewman, DRP LReyna, DRP JBowen, RIV/OEDO VDricks, ORA JWeil, OCA MO'Banion, NRR AMoreno, RIV/CAO BMaier, RSLO JBridges, OB GGeorge, IPAT PJayroe, DRP/IPAT MHerrera, DRMA R4Enforcement
REGION IV Docket Nos.: 50-445, 50-446 License Nos.: NPF-87, NPF-89 Report No s.: 05000445/2018301; 0500044 6/2018301 Licensee: Vistra Operations Company LLC Facility: Comanche Peak Nuclear Power Plant, Units 1 and 2 Location: Glen Rose, Texas Dates: June 11 - July 19 , 201 8 Inspectors:
K. Clayton, Chief Examiner, Senior Operations Engineer J. Kirkland , Senior Operations Engineer C. Osterholtz, Senior Operations Engineer M. Hayes, Operations Engineer Approved By:
Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety
2
SUMMARY
ER 05000 445/2018301; 05000 446/2018301; June 11 - July 19 , 2018; 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, six applicants for instant senior reactor operator licenses and three applicant s for upgrade senior reactor operator license at Comanche Peak Nuclear Power Plant, Units 1 and 2
. The NRC developed the examinations using NUREG
-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 11. The written examination was administered by the licensee on June 20, 2018. NRC examiners administered the operating tests on June 11 - 17, 2018. The examiners determined that fourteen of the fifteen applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
A. NRC-Identified and Self-Revealing Findings
None.
B. Licensee-Identified Violations
None.
3
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other Activities (Initial Operator License Examination)
.1 License Applications
a. Scope
NRC examiners reviewed all license application s submitted to ensure each applicant satisfied relevant license eligibility requirements.
Examiners also audited three of the license applications in detail to confirm that they accurately reflected the subject applicant's qualifications. This audit focused on the applicant's experience and on
-the-job training, including control manipulations that provided significant reactivity changes.
b. Findings
No findings were identifie d.
.2 Examination Development
a. Scope
The NRC developed the written exam and operating tests in accordance the requirements of NUREG
-1021. The NRC examination team conducted an on
-site validation of the operating tests.
b. Findings
No findings were identified.
.3 Operator Knowledge and Performance
a. Scope
On June 20, 2018, the licensee proctored the administration of the written examinations to all applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis and post examination comments to the NRC on June 25, 2018
. The NRC examination team administered the various portions of the operating test s to all applicants on June 11 - 17, 2018.
b. Findings
No findings were identified.
All applicants passed the written examination and fourteen of fifteen applicants passed all portions of the operating test. The final written examination s and post examination analysis and comments may be accessed in the ADAMS system under the accession numbers noted in the attachment.
The examination team note d five generic weaknesses associated with applicant performance on the operating tests. All of the weaknesses were attributed to knowledge weaknesses on the topic and included the following items:
1. Several crews (2/4) could not adequately determine a fuel failure event was in progress during a scenario
. 2. Several applicants (3/4) could not adequately operate the control room ventilation system. 3. Applicants had difficulty with anti-pump features of handswitches and their associated breakers
. 4. Several crews (3/4) had difficulty diagnosing a faulted a nd ruptured steam generator during a scenario.
5. Several crews struggled with proper communications during the scenario s.
The licensee identified five generic weaknesses associated with applicant performance on the written examinations. All of the weaknesses were attributed to knowledge weaknesses on the topic and included the following items:
1. Applicants were unfamiliar with design features of the containment sump
. 2. Applicants were unfamiliar with Abnormal Procedure ABN
-901, Fire Protection System Alarms or Malfunctions
. 3. Applicants had difficulty recalling safety-related battery capacities.
4. Applicants were unfamiliar with the immediate operability requirements regarding fuel oil for the emergency diesel generators and their Technical Specification requirements (day tank requirements).
5. Applicants had difficulty determining what system to use during emergency procedures to lower containment hydrogen during a Loss of Coolant Accident
. Copies of all individual examination reports were sent to the facility Training Manager for evaluation and determination of appropriate remedial training.
The licensee generated Issue Report IR-2018-004425 for resolution of all operating test and written examination generic weaknesses.
.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.
.5 Examination Security
a. Scope
The NRC examiners reviewed examination security for examination development 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.
4OA 6 Meetings, Including Exit
Exit Meeting Summary
The chief examiner presented the preliminary examination results to M r. Thomas McCool, Site Vice President, and other members of the staff on June 15, 2018. A telephonic exit was conducted on July 19, 2018 between Mr. K. Clayton, Chief Examiner, and M s. Donna Christiansen, Training Director
. The licensee did not identify any information or materials used during the examination as proprietary.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- T. McCool, Site Vice President
- D. Christiansen, Training Director
- J. Lloyd, Operations Support Manager
- J. Ruby, Exam Developer
NRC Personnel
- J. Josey, Senior Resident Inspector
ADAMS DOCUMENTS REFERENCED