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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
[Table view] Category:License-Operator Examination Report (Non-Power Reactors Only)
MONTHYEARIR 05000266/20053012005-12-28028 December 2005 Er 05000266-05-301 (Drs); Er 05000301-05-301(DRS) 10/17/2005-11/18/2005; Point Beach Nuclear Plant; Initial License Examination Report IR 05000266/20033012003-10-22022 October 2003 Er 05000266/03-301(DRS) & 05000266/03-301(DRS); 09/29/03-10/03/0301; Point Beach Nuclear Plant, Units 1 and 2; Initial License Examination Report 2005-12-28
[Table view] |
Text
ber 28, 2005
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 & 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000266/2005301(DRS); 05000301/2005301(DRS)
Dear Mr. Koehl:
On November 18, 2005, the NRC completed initial operator licensing examinations at your Point Beach Nuclear Plant. The enclosed report documents the results of the examination which were discussed on November 18 and November 23, 2005, with Mr. and Mr. M. Lorek, and with other members of your staff.
The NRC examiners administered the operating test during the week of November 7 to 10 and November 14 to 17, 2005. NRC examiners and members of the Point Beach Nuclear Power Plant Training Department staff administered the written examination on November 18, 2005.
Five Reactor Operator (RO), four Senior Reactor Operator-Instant (SRO-I) and two Senior Reactor Operator-Upgrade (SRO-U) applicants were administered license examinations. The results of the examinations were finalized on December 19, 2005. All eleven applicants passed all sections of their examinations and five operator and five senior operator licenses were distributed.
During the NRCs review of initial license applications, one senior operator applicant was granted eligibility deferments so that the applicant could take the examination. This applicant will need to complete a minimum of 6 months onsite responsible power plant experience before he will receive a license. The applicant will be granted a license only after you certify in writing to the NRC that the applicant has completed the eligibility requirement that was previously deferred.
In accordance with 10 CFR Part 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 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). We will gladly discuss any questions you have concerning this examination.
Sincerely,
/RA N. Valos acting for/
Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27
Enclosures:
1. Operator Licensing Examination Report 050000266/2005301(DRS);
05000301/2005301(DRS)
2. Simulation Facility Report 3. Written Examinations and Answer Keys (RO & SRO)
REGION III==
Docket No: 50-266, 50-301 License No: DPR-24; DPR-27 Report No: 050000266/2005301(DRS)
050000301/2005301(DRS)
Licensee: Nuclear Management Company, LLC Facility: Point Beach Nuclear Plant Location: 6612 Nuclear Road Two Rivers, WI 54241-9516 Dates: October 17 through November 18, 2005 Examiners: R. K. Walton, Chief Examiner N. Valos, Examiner C. Moore, Examiner Approved by: H. Peterson, Chief Operations Branch Division of Reactor Safety Enclosure 1
SUMMARY OF FINDINGS
ER 05000266/2005301(DRS); ER 05000301/2005301(DRS) 10/17/2005-11/18/2005;
Point Beach Nuclear Plant; Initial License Examination Report.
The announced operator licensing initial examination was conducted by regional examiners in accordance with the guidance of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9.
Examination Summary:
- Eleven examinations were administered (five Reactor Operator, four Senior Reactor Operator-Instant and two Senior Reactor Operator-Upgrade).
- All eleven applicants passed all sections of their examinations, ten of these applicants were issued respective operator or senior operator licenses. One SRO applicant license was withheld pending his completion of responsible power plant experience.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other
.1 Initial Licensing Examinations
a. Examination Scope
The NRC examiners conducted an announced initial operator licensing examination during the weeks of November 7, 2005, and November 14, 2005. The NRC examiners used the guidance established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, to review the examination outline and to review the written examination and operating test. The NRC examiners and members of the Point Beach Nuclear Power Plant (PBNPP) Training Department administered the written examination on November 18, 2005. Five Reactor Operator (RO), four Senior Reactor Operator-Instant (SRO-I), and two Senior Reactor Operator-Upgrade (SRO-U)applicants were examined.
b. Findings
Written Examination The licensee developed the written examination. During their internal review, the NRC examiners determined that the examination, as submitted, was within the range of acceptability expected for a proposed examination. Written examination comments developed during review by the Point Beach staff, and as a result of examination validation were incorporated into the written examination in accordance with the guidance contained in NUREG-1021.
On November 23, 2005, the licensee discussed post-examination editorial comments with the NRC examiner which had no effect on the content or grading of the written examinations. In addition, two questions were changed during the written examination due to improper noun names; however, there were no official post-examination comments.
Operating Test The NRC examiners determined that the operating test, as originally submitted by the licensee, was within the range of acceptability expected for a proposed examination.
The examiners validated the operating test during the validation week and modified several items in the proposed operating test. Test changes, agreed upon between the NRC and the licensee, were made in accordance with NUREG-1021 guidelines.
Examination Results Eleven applicants passed all sections of their examinations. Ten of these applicants were issued respective operator or senior operator licenses. One SRO applicant has had his license withheld pending his completion of responsible power plant experience.
.2 Examination Security
a. Examination Security Scope The NRC examiners briefed the facility contact on the NRCs requirements and guidelines related to examination physical security (e.g., access restrictions and simulator considerations). The examiners observed the implementation of examination security and integrity measures (e.g., security agreements) throughout the examination process.
b. Findings
No findings were noted in this area. The licensee staff was observed to be enforcing correct examination security procedures.
4OA6 Meetings
.1 Exit Meeting
The chief examiner presented the examination team's preliminary observations and findings on November 18 and November 23, 2005, to Mr. D. Koehl and other members of the Operations and Training Department staff. The purpose of the re-exit was to acknowledge the receipt and review of the licensees post-examination comments on the written examinations. The licensee acknowledged the observations and findings presented. No proprietary information was identified by the stations staff during the exit meetings.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
Enclosure 1
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
D. Koehl Site Vice President
J. Schweitzer Engineering Director
M. Lorek Plant Manager
F. Forrest Nuclear Oversight Manager
R. Grazio Regulatory Compliance Manager
C. Hill Operations Training Supervisor
NRC
- H. Peterson Branch Chief, Operator Licensing Branch
G. Gibbs Resident Inspector
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
Attachment
LIST OF ACRONYMS USED
ADAMS Agency-Wide Document Access and Management System
DRS Division of Reactor Safety
NRC Nuclear Regulatory Commission
PARS Publicly Available Records
RO Reactor Operator
SRO Senior Reactor Operator
Attachment
SIMULATION FACILITY REPORT
Facility Licensee: Point Beach Nuclear Power Plant
Facility Docket No.: 50-266; 50-301
Operating Tests Administered: November 7 - November 17, 2005
The following documents observations made by the NRC examination team during the initial
operator license examination. These observations do not constitute audit or inspection findings
and are not, without further verification and review, indicative of non-compliance with
CFR 55.45(b). These observations do not affect NRC certification or approval of the
simulation facility other than to provide information which may be used in future evaluations.
No licensee action is required in response to these observations.
During the conduct of the simulator portion of the operating tests, the following items were
observed:
ITEM DESCRIPTION
Plant Process The plant process computer locked up during Scenario 1, Operating
Computer (PPCS) Examinations 1 and 2.
During onsite validation, when the Operator Select Switch was
returned to the Normal position from the Level Adjust Position, the
N31 Source Range
High Flux in Shutdown annunciator in the control room did not clear.
Operator Selector
Simulator operators operated the switch numerous times and the
Switch
condition did not repeat. Believed that infrequently operated switch
developed an oxide layer on contacts.
WRITTEN EXAMINATIONS AND ANSWER KEYS (RO/SRO)
RO/SRO Initial Examination ADAMS Accession #ML053610151.