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Category:Letter
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 ML24296B2152024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 03: Alternative Request Allowing Removal of the Lower Acceptance Criteria Threshold from Solenoid-Operated Valves ML24296B2142024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 02: Alternative Request Allowing Normally Closed Valves with a Safety Function to Close to Be Exercise Tested Once Per Refueling Cycle IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 ML24296B2172024-10-18018 October 2024 Submittal of Unit 1 Core Operating Limits Report, Revision 34, Unit 2 Core Operating Limits Report, Revision 26, and Unit 3 Core Operating Limits Report, Revision 3 ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 ML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report ML24285A2562024-10-11011 October 2024 License Renewal - Alloy 600 Management Program Plan Response to Request for Additional Information IR 07200044/20244012024-10-0808 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200044/2024401 ML24269A1542024-09-27027 September 2024 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed Life-of-Plant Alternatives for a Pressurizer Thermowell Nozzle Repair at Palo Verde Nuclear Generating Station, Unit 1 ML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) 05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-08-21021 August 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24208A0612024-08-20020 August 2024 Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5 IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 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 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator2024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator 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 IR 05000528/20243012024-06-17017 June 2024 NRC Examination Report 05000528/2024301; 05000529/2024301; 05000530/2024301 ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater2024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater 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 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 ML24129A1482024-05-0707 May 2024 And Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes 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) ML24109A0712024-04-22022 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 2024-09-27
[Table view] Category:License-Operator Examination Report
MONTHYEARIR 05000528/20243012024-06-17017 June 2024 NRC Examination Report 05000528/2024301; 05000529/2024301; 05000530/2024301 IR 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 2024-06-17
[Table view] |
Text
ber 3, 2003
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 - NRC EXAMINATION REPORT 05000528/2003-301; 05000529/2003-301; 05000530/2003-301
Dear Mr. Overbeck:
On July 24, 2003, the U. S. Nuclear Regulatory Commission (NRC) completed an examination at Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The enclosed report documents the examination findings, which were discussed on July 24, 2003, with Messrs. Mike Shea, Fred Riedel, and other members of your staff.
The examination included the evaluation of six applicants for reactor operator licenses and three applicants for senior operator licenses. We determined that all applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
In accordance with 10 CFR 2.790 of the NRCs "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/
Anthony T. Gody, Chief Operations Branch Division of Reactor Safety Dockets: 50-528; 50-529; 50-530 Licenses: NPF-41; NPF-51; NPF-74
Arizonal Public Service Company -2-
Enclosure:
NRC Examination Report 05000528/2003-301; 05000529/2003-301; 05000530/2003-301
REGION IV==
Dockets: 50-528, 50-529, 50-530 Licenses: NPF-41, NPF-51, NPF-74 Report : 05000528/2003-301, 05000529/2003-301, and 05000530/2003-301 Licensee: Arizona Public Service Company Facility: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 Location: 5951 S. Wintersburg Tonopah, Arizona Dates: July 21-24, 2003 Inspectors: T. F. Stetka, Chief Examiner, Operations Branch T. O. McKernon, Senior Operations Engineer R. E. Lantz, Senior Emergency Preparedness Inspector Approved By: Anthony T. Gody, Chief Operations Branch Division of Reactor Safety
-2-SUMMARY OF FINDINGS ER 05000528/2003-301, 05000529/2003-301, 05000530/2003-301; 7/21-24/2003; Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Initial Operator Licensing Examinations.
NRC examiners evaluated the competency of six applicants for reactor operator licenses and three applicants for senior operator licenses at Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The facility licensee developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Draft Revision 9. Licensee proctors administered the written examination to all applicants on July 18, 2003, in accordance with the instructions provided by the chief examiner. The NRC administered the operating tests on July 21-24, 2003.
Cornerstone: Human Performance No findings of significance were identified (Section 40A4.1).
Report Details 4. OTHER ACTIVITIES (OA)
4OA4 Initial Operator License Examination
.1 Operator Knowledge and Performance a. Examination Scope On July 18, 2003, the licensee proctored the administration of the written examinations to all nine applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis to the NRC on July 24, 2003.
The NRC examination team administered the various portions of the operating examination to all nine applicants on July 21-24, 2003. The six applicants for reactor operator licenses and the three upgrade applicants for senior operator licenses participated in two dynamic simulator scenarios. The six applicants for reactor operator participated in a control room and facilities walkthrough test consisting of 11 system tasks, and an administrative test consisting of 4 administrative tasks. The three applicants for upgrade to senior operator participated in a control room and facilities walkthrough test consisting of 5 system tasks, and an administrative test consisting of 5 administrative tasks.
b. Findings All nine of the applicants passed all parts of the examinations. The applicants demonstrated good 3-way communications, alarm response, and peer checking.
For the written examinations, the reactor operator applicants average score was 91 percent and ranged from 88 to 96 percent, the senior operator applicants average score was 95 percent and ranged from 92 to 98 percent. The overall written examination average was 93 percent. The text of the examination questions may be accessed in the ADAMS system under the accession numbers noted in the attachment.
The licensee conducted a performance analysis for the written examinations, submitting them to the chief examiner on July 24, 2003. The analysis identified no common knowledge deficiency. No remediation training was determined to be necessary following the examinations.
No findings of significance were identified.
.2 Initial Licensing Examination Development The licensee developed the examinations in accordance with NUREG-1021, Draft Revision 9. All licensee facility training and operations staff involved in examination preparation and validation were on a security agreement.
-2-
.2.1 Examination Outline and Examination Package a. Examination Scope The facility licensee submitted the integrated examination outlines on March 24, 2003.
The chief examiner reviewed the submittal against the requirements of NUREG-1021, Draft Revision 9, and provided comments to the licensee. The facility licensee submitted the final draft examination package on May 23, 2003. The chief examiner reviewed the draft submittal against the requirements of NUREG-1021, Draft Revision 9, and provided comments to the licensee on the examination on June 12, 2003. The NRC conducted an onsite validation of the operating examinations and provided further comments during the week of June 30, 2003. The licensee satisfactorily completed comment resolution on July 14, 2003.
b. Findings The NRC approved the initial examination outline and advised the licensee to proceed with the operating examination development.
The examiners determined that the written and operating examinations initially submitted by the licensee were within the range of acceptability expected for a proposed examination.
No findings of significance were identified.
.3 Simulation Facility Performance a. Examination Scope The examiners observed simulator performance with regard to plant fidelity during the examination validation and administration.
b. Findings No findings of significance were identified.
.4 Examination Security a. Examination Scope The examiners reviewed examination security both during the onsite preparation week and examination administration week for compliance with NUREG-1021 requirements.
Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.
-3-b. Findings While the examination team considered examination security to be adequate, one event occurred that had the potential to compromise examination security. The NUREG 1021, Draft Revision 9, allows examination material to be sent via e-mail if it is password protected. The NUREG further states that the Chief Examiner be notified of the password via telephone or regular mail. The intent of this process is to use a different sending method for the password to further assure examination security. However, when the licensee e-mailed the final examination to the NRC, they also e-mailed the password immediately after the examinations in a separate e-mail.
The examination team reviewed this occurrence to determine if examination security was compromised. The team noted that the licensee took the following actions during transmittal of the examinations and password:
- The messages were sent from the examination room, a secure location;
- No one had access to the messages;
- There were no ccs or bccs sent with the messages; and,
- The messages were immediately deleted from all mailboxes following completion of the transmittal.
In addition, the licensee developed a sign-up sheet for the candidates to provide certification that the candidates had no prior knowledge of the examination material.
Based on these activities, the team concluded that an examination security compromise did not occur. No other findings of significance were identified.
4OA5 Management Meeting
.1 Exit Meetings The chief examiner presented the examination results to Messrs. Mike Shea, Training Director, Fred Riedel, Operations Training Manager, and other members of the licensee's management staff on July 24, 2003. The licensee acknowledged the findings presented.
The licensee did not identify as proprietary any information or materials examined during the examination.
ATTACHMENT KEY POINTS OF CONTACT Licensee F. Riedel, Operations Training Manager W. Potter, Simulator Support-Section Leader P. Capehart, Nuclear Training Instructor T. Stahler, Nuclear Training Instructor L. Wilhelm, Nuclear Training Instructor W. Drey, Nuclear Training Instructor NRC N. Salgado, Senior Resident Inspector ADAMS DOCUMENTS REFERENCED Accession No. ML032260469 - Written examination for reactor operators Accession No. ML032260479 - Written examination for senior reactor operators Accession No. ML032260490 - Written examination performance analysis