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| The examiner determined that both the applicant for the instant senior reactor operator license and the applicant for upgrade senior reactor operator license satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued. | | The examiner determined that both the applicant for the instant senior reactor operator license and the applicant for upgrade senior reactor operator license satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued. |
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| ===NRC-Identified and Self-Revealing Findings=== | | ===NRC-Identified and Self-Revealing Findings=== |
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| None. | | None. |
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| ===B. Licensee-Identified Violations=== | | ===Licensee-Identified Violations=== |
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| None. | | None. |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ===4. ===
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| ==OTHER ACTIVITIES (OA)== | | ==OTHER ACTIVITIES (OA)== |
| {{a|4OA5}} | | {{a|4OA5}} |
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Category:Letter
MONTHYEARIR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24129A1482024-05-0707 May 2024 and Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) IR 05000528/20243012024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24068A2522024-03-0808 March 2024 License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Using Risk-Informed Process for Evaluations ML24066A0472024-03-0606 March 2024 Response to Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown and TS IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 ML24053A3972024-02-22022 February 2024 License Renewal - Alloy 600 Management Program Plan ML24047A3632024-02-16016 February 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX177, AMZDFX178, AMZDFX179 Vertical Concrete Cask Identification No. AMZDNE179, AMZDNE178 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program 2024-08-08
[Table view] Category:License-Operator Examination Report
MONTHYEARIR 05000528/20223012022-06-21021 June 2022 NRC Examination Report 05000528/2022301, 05000529/2022301, and 05000530/2022301 IR 05000528/20193012020-01-28028 January 2020 NRC Initial Examination Report 05000528/2019301, 05000529/2019301, and 05000530/2019301 IR 05000528/20183022018-10-31031 October 2018 NRC Retake Examination Report 05000528/2018302; 05000529/2018/2018302; 05000530/2018302 IR 05000528/20183012018-06-0404 June 2018 NRC Examination Report 05000528/2018301; 05000529/2018301; 05000530/2018301 IR 05000528/20163012016-12-0505 December 2016 NRC Examination Report 05000528/2016301; 05000529/2016301; 05000530/2016301 ML15182A1192015-06-19019 June 2015 Response to Regulatory Issue Summary (RIS) 2015-05, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20153012015-06-10010 June 2015 Er 05000528/2015301; 05000529/2015301; 05000530/2015301; 04/13/2015 - 05/13/2015; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examination Report IR 05000528/20133012013-12-17017 December 2013 Er 05000528/2013301; 05000529/2013301; 05000530/2013301; October 1 - November 20, 2013; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examination Report IR 05000528/20123012012-05-31031 May 2012 Er 05000528-12-301, 05000529-12-301 & 05000530-12-301, March 16 - May 23, 2012, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Initial Operator Licensing Examination Report IR 05000528/20103012010-12-22022 December 2010 Er 05000528-10-301; 05000529-10-301; 05000530-10-301; November 5-17, 2010; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examination Report IR 05000528/20093012009-12-15015 December 2009 Er 05000528-09-301, 05000529-09-301, 05000530-09-301, on November 6, 2009, Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examination Report IR 05000528/20073012007-09-21021 September 2007 Er 05000528-07-301, 05000529-07-301, 05000530-07-301; 07/20 - 08/21/2007, Palo Verde Nuclear Generating Station Units 1, 2 and 3, Operator Licensing Initial Examination Report ML0527602712005-09-21021 September 2005 Response to RIS 2005-19, Preparation and Scheduling of Operator Licensing Examinations. ML0432300042004-11-16016 November 2004 Use of Plant Equipment for Limited Senior Operator Examinations (Examination Report 50-528/-529/-530/2004-301) ML0409200332004-03-30030 March 2004 Generic Fundamentals Section of the Written Operator Licensing Examination IR 05000528/20033012003-09-0303 September 2003 Er 05000528-03-301, 05000529-03-301, 05000530-03-301; on 7/21-24/2003; for Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examinations ML0324806192003-09-0303 September 2003 Er 05000528-03-301, 05000529-03-301, 05000530-03-301; on 7/21-24/2003; for Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examinations 2022-06-21
[Table view] |
Text
ber 31, 2018
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 - NRC RETAKE EXAMINATION REPORT 05000528/2018302; 05000529/2018302; 05000530/2018302
Dear Mr. Bement:
On September 26, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an initial operator license retake examination at Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The enclosed report documents the examination results and licensing decisions. The preliminary examination results were discussed on September 26, 2018, with Mr. Paul Bury, Training Director, and other members of your staff. A telephonic exit meeting was conducted on October 12, 2018, with Mr. Bury, who was provided with the NRC licensing decisions.
The examination included the evaluation of one applicant for an instant senior reactor operator license and one applicant for an upgrade senior reactor operator license. The license examiner determined that both 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 contains details of this report.
No findings 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 NRCs 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. 50-528, 50-529, and 50-530 License Nos. NPF-41, NPF-51, and NPF-74
Enclosure:
NRC Examination Report 05000528/2018302; 05000529/2018302; 05000530/2018302 w/Attachment: Supplemental Information
REGION IV==
Dockets: 05000528; 05000529; 05000530 Licenses: NPF-41; NPF-51; NPF-74 Reports: 05000528/2018302; 05000529/2018302; 05000530/2018302 Licensee: Arizona Public Service Company Facility: Palo Verde Nuclear Generating Station Location: Tonopah, Arizona Dates: September 26, 2018 Inspector: D. Bacon, Chief Examiner, Senior Operations Engineer Approved By: Vincent G. Gaddy, Chief Operations Branch Division of Reactor Safety Enclosure
SUMMARY
ER 05000528/2018302; 05000529/2018302; 05000530/2018302; 9/26/2018; Palo Verde
Nuclear Generating Station, Units 1, 2, and 3; Retake Initial Operator Licensing Examination Report.
An NRC examiner evaluated the competency of one applicant for an instant senior reactor operator license and one applicant for an upgrade senior reactor operator license at Palo Verde Nuclear Generating Station, Units 1, 2, and 3.
The licensee developed the retake examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 11. The retake examination for the instant senior reactor applicant consisted of only the administrative topics portion of the operating test. The retake examination for the upgrade senior reactor operator applicant consisted of the entire walkthrough portion of the operating test. Both applicants were granted excusals for the written exam and the simulator scenario portion of the operating test. The NRC examiner administered the operating tests on September 26, 2018.
The examiner determined that both the applicant for the instant senior reactor operator license and the applicant for upgrade senior reactor operator license satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
NRC-Identified and Self-Revealing Findings
None.
Licensee-Identified Violations
None.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other Activities (Retake 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.
b. Findings
No findings were identified.
.2 Examination Development
a. Scope
The NRC examiner 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
The NRC examiner provided outline, draft examination, and post-validation comments to the licensee. The licensee satisfactorily completed comment resolution prior to examination administration.
The NRC examiner determined the 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
The NRC examiner administered the applicable portions of the operating tests to both applicants on September 26, 2018.
b. Findings
No findings were identified.
Both the instant senior reactor operator applicant and the upgrade senior reactor operator applicant passed the operating tests.
There were no post examination comments as indicated in the licensee submittal.
Copies of all individual examination reports were sent to the facility training manager for evaluation and determination of appropriate remedial training.
.4 Simulation Facility Performance
a. Scope
The NRC examiner 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 examiner reviewed examination security during the onsite preparation 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
Exit Meeting The chief examiner presented the preliminary examination results to Mr. P. Bury and other members of your staff on September 26, 2018. A telephonic exit was conducted on October 12, 2018, between Mr. V. Gaddy, Chief, Operations Branch, and Mr. P. Bury, Director, Nuclear Training.
The licensee did not identify any information or materials used during the examination as proprietary.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- J. Allison, Section Leader, Training
- P. Bury, Director, Nuclear Training
- S. Dornseif, Senior Consultant, Regulatory Affairs
- D. Elkington, Section Leader, Regulatory Affairs/Compliance
- J. Fearn, Operations Manager, Training
- M. Kura, Department Leader, Regulatory Affairs
- Z. Goldwasser, Department Leader, Operations Training
- D. Lowdermilk, Nuclear Operations Coordinator, Licensing
- J. Rodgers, Senior Operations Training Instructor
NRC Personnel
- V. Gaddy, Chief, Operations Branch
- D. Bacon, Senior Operations Engineer, RII, Operations Branch 1
ADAMS DOCUMENTS REFERENCED