|
---|
Category:Letter
MONTHYEARIR 05000354/20240032024-10-23023 October 2024 Integrated Inspection Report 05000354/2024003 ML24295A3742024-10-23023 October 2024 Project Manager Assignment ML24291A0572024-10-17017 October 2024 License Amendment Request (LAR) – Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 1 LR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) LR-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024 2024 Annual 10 CFR 50.46 Report LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024 Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle IR 05000272/20244022024-09-23023 September 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) ML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities 05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 ML24200A0572024-07-18018 July 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves NUREG-1433, – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 52024-07-16016 July 2024 – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5 ML24197A0552024-07-15015 July 2024 Requalification Program Inspection ML24145A1772024-07-15015 July 2024 And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves IR 05000272/20245012024-06-12012 June 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20240112024-04-0101 April 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 LR-N24-0028, And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal IR 05000272/20244032024-03-20020 March 2024 And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 LR-N24-0021, And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums 05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0027, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report IR 05000354/20230062024-02-28028 February 2024 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2023006) IR 05000272/20244012024-02-26026 February 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024401, 05000272/2024401 and 05000311/2024401 (Cover Letter Only) LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges 05000354/LER-2023-003, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-02-12012 February 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval ML24009A1022024-01-26026 January 2024 – Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 2024-09-05
[Table view] Category:License-Operator Examination Report
MONTHYEARIR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 ML22350A4692022-12-16016 December 2022 301 Exam Administrative Items (2 Year Delayed release)(ADAMS-2A-3) IR 05000354/20213012021-04-0101 April 2021 Initial Operator Licensing Examination Report 05000354/2021301 IR 05000354/20193012019-10-17017 October 2019 Initial Operator Licensing Examination Report 05000354/2019301 IR 05000354/20183022018-08-22022 August 2018 Retake Operator Licensing Examination Report 05000354/2018302 IR 05000354/20163012016-10-25025 October 2016 NRC Initial Operator Licensing Examination Report 05000354/2016301 IR 05000354/20153012015-04-28028 April 2015 Er 05000354/2015301; 02/23-27/15, 03/03, 06, 31/15, and 04/01/15; Hope Creek Generating Station; Initial Operator Licensing Examination Report IR 05000354/20123012012-04-18018 April 2012 Er 05000354-12-301; March 5-14, 2012; Hope Creek Generating Station, Unit 1; Initial Operator Licensing Examination Report IR 05000354/20113012011-02-14014 February 2011 Er 05000354-11-301, on January 27, 2011, Hope Creek Generating Station - Unit 1, Initial Operator Licensing Retake Examination Report IR 05000354/20103012010-10-0404 October 2010 Er 05000354/10-301 for Hope Creek Generating Station, Unit 1, Initial Operator Licensing Examination Report IR 05000354/20093012009-03-20020 March 2009 Er 05000354-09-301, on February 2-18, 2009, Hope Creek Generating Station, Initial Operator Licensing Examination Report IR 05000354/20073012007-11-26026 November 2007 Er 05000354-07-301; Exam Dates 9/24-28, 2007; Hope Creek Generating Station; Initial Senior Reactor Operator (SRO) Licensing Examination IR 05000354/20053012006-01-13013 January 2006 IR 05000354-05-301; November 28 to December 5, 2005; Hope Creek; Initial Operator Licensing Examination. Two of Two Applicants Passed the Examination (One Reactor Operator (Ro), One Senior Reactor Operator (SRO) Instant) NTD-05-046, Response to NRC Form 536 (RIS 2005-19) Operator Licensing Examination Data2005-10-31031 October 2005 Response to NRC Form 536 (RIS 2005-19) Operator Licensing Examination Data IR 05000354/20023022002-08-0808 August 2002 IR 05000354/2002-302, on July 19, 2002; Hope Creek Generating Station; Initial Reactor Operator (RO) Licensing Retake Examination ML0220000482002-07-10010 July 2002 Response to NRC Form 536 (RIS 2002-9) Operator Licensing Examination Data ML0213506732002-05-15015 May 2002 IR 05000387/2002-301 and IR 05000388/2002-301, Hope Creek Station, Inspection on March 11-18, 2002, Related to Initial Operator Licensing Examinations. Four of Five Reactor Operator Applicants Passed All Portions of the Examination 2024-04-10
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406
-2713 October 25, 201 6 Mr. Peter P. Sena, III President and Chief Nuclear Officer PSEG Nuclear LLC
- N09 P. O. Box 236
Hancocks Bridge, NJ 08038
SUBJECT: HOPE CREEK GENERATING STATION, UNIT 1 - NRC INITIAL OPERATOR LICENSING EXAMINATION REPORT 05000 354/20 1 6301
Dear Mr. Sena:
On August 31, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an examination at Hope Creek Generating Station. The enclosed examination report documents the examination results, which were discussed on September 27, 2016, with Mr. Robert Boesch, Training Manager, and other members of your staff.
The examination included the evaluation of three applicants for reactor operator licenses, six applicants for instant senior reactor operator licenses, and one applicant for an upgrade senior reactor operator license. The NRC developed the written and operating examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10. The license examiners determined that all ten applicants satisfied the requirements o f Title 10 of the Code of Federal Regulation (10 CFR) Part 55, and the appropriate licenses were issued on September 27, 2016.
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 NRC's Agencywide Document s Access Management System (ADAMS). ADAMS is accessible from the NRC w ebsite http://www.nrc.gov/reading
-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/ Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Docket No.: 50-354 License No
.: NPF-57
Enclosure:
Examination Report 05000 354/2016301
w/Attachment:
Supplementary Information cc w/encl: Distribution via ListServ
Mr. Peter
SUMMARY
ER 05000354/2016301
- August 22-26, 2016 and August 31, 2016; Hope Creek Generating Station, Unit 1; Initial Operator Licensing Examination Report. Six NRC examiners evaluated the competency of three applicants for reactor operator licenses, six applicants for instant senior reactor operator licenses, and one applicant for an upgrade senior reactor operator license. The NRC developed the written and operating examinations using NUREG
-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10. The facility administered the written examination August 31, 2016. NRC examiner s administered the operating tests August 22-26, 2016. The NRC examiner s determined that all 10 applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
No findings were identified.
3
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other Activities
- Initial Operator License Examination
.1 License Applications
a. Scope
The chief examiner reviewed all 10 license applications submitted by the licensee to ensure the applications reflected that each applicant satisfied relevant license eligibility requirements. The applications were submitted on NRC Form 398, "Personal Qualification Statement," and NRC Form 396, "Certification of Medical Examination by Facility Licensee." The chief examiner also audited five license application s 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 identified.
.2 Operator Knowledge and Performance
a. Examination Scope
On August 31, 2016, the licensee proctored the administration of the written examinations to all 10 applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis to the NRC on September 7, 2016
. The NRC examination team administered the various portions of the operating examination to all applicants August 22-26, 2016. The applicants for reactor operator licenses participated in at least two dynamic simulator scenarios, in a control room and facilities walkthrough test consisting of 11 system tasks, and an administrative test consisting of four administrative tasks. The applicants seeking an instant senior reactor operator license participated in at least two dynamic simulator scenarios, a control room and facilities walkthrough test consisting of 10 system tasks, and an administrative test consisting of five administrative tasks. The applicant for an upgrade senior reactor operator license participated in two dynamic simulator scenarios, a control room and facilities walkthrough test consisting of five system tasks, and an administrative tes t consisting of five administrative tasks.
b. Findings
All applicants passed all parts of the test. For the written examinations, the reactor operator applicants' average score was 89.18 percent and ranged from 86.48 to 94.59 percent. The senior operator applicants' average score was 91.33 percent and ranged from 86.86 t o 95.96 percent.
Chapter ES
-403 and Form ES 1 of NUREG 1021 require the licensee to analyze the validity of any written examination questions that were missed by half or more of the applicants. The licensee conducted this analysis and submitted the analysis to the chief examiner. Th e analysis recommended that one of the questions (Exam question #
73) be deleted from the exam. The NRC reviewed the facility's post
-exam comment and accepted facility
's recommendation for question #73. The question was deleted from both the reactor operator and senior reactor operator exams. The text of the entire written examination and the licensee's post
-examination comment with the NRC resolution may be accessed in the ADAMS system under the accession numbers noted in the Attachment 1. In accordance with current NRC policy the release of th e examination will be delayed for 2 years.
.3 Initial Licensing Examination Development
a. Examination Scope
The NRC developed the examinations in accordance with NUREG
-1021, Revision 10. All licensee facility training and operations staff involved in examination preparation and validation were listed on a security agreement. The NRC conducted an onsite validation of the operating examinations and incorporated facility training staff comments during the week of July 18, 2016.
b. Findings
No findings were identified.
.4 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 were identified.
.5 Examination Security
a. Examination Scope
The examiners reviewed examination security for examination development and during both the onsite preparation week and examination administration week for compliance with NUREG
-1021, Revision 10 requirements. 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 examination results to Mr. Robert Boesch, Training Manager, and other members of the licensee's management staff on September 27, 2016. The licensee acknowledged the findings presented.
The licensee did not identify any information or materials used during the examination as proprietary.
ATTACHMENT S:
=SUPPLEMENTARY
INFORMATION=
KEY POINTS OF CONTACT
Licensee Personnel
- R. Boesch, Training Manager
- M. Shaffer, Operations Training Supervisor
- S. Dennis, Facility Exam Team
- D. Rein, Facility Exam Team
ITEMS OPENED, CLOSED, AND DISCUSSED
NONE
ADAMS DOCUMENTS REFERENCED
Accession No. ML16295A056 -
- FINAL-Written Exam (Note:
- In accordance with current NRC policy, the release of this written examination in ADAMS to the public will be delayed for 2
years.) Accession No. ML16295A057 -
- FINAL-Operating Exam Accession No. ML16295A055 -
- FINAL-Post Exam Comment and NRC Resolution