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Category:Inspection Report
MONTHYEARIR 05000400/20240112024-09-10010 September 2024 NRC Inspection Report 05000400/2024011 IR 05000400/20240052024-08-26026 August 2024 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400-2024005) Rev 1 IR 05000400/20240022024-07-29029 July 2024 – Integrated Inspection Report 05000400/2024002 IR 05000400/20243022024-06-27027 June 2024 – NRC Operator Licensing Examination Approval 05000400/2024302 IR 05000400/20244012024-06-25025 June 2024 – Security Baseline Inspection Report05000400/2024401 IR 05000400/20240012024-05-0505 May 2024 Integrated Inspection Report 05000400/2024001 IR 05000400/20230062024-02-28028 February 2024 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2023006 IR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 – Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 – Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML22355A5062022-12-23023 December 2022 404 Cyber Notification and RFI Letter IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 IR 05000400/20210112022-01-24024 January 2022 Triennial Fire Protection Inspection Report 05000400/2021011 IR 05000400/20210102021-12-28028 December 2021 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000400/2021010 IR 05000400/20214202021-12-0707 December 2021 Security Inspection Report 05000400/2021420 IR 05000400/20210032021-11-10010 November 2021 Integrated Inspection Report 05000400/2021003 IR 05000400/20210052021-08-26026 August 2021 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2021005) IR 05000400/20210022021-08-0202 August 2021 Integrated Inspection Report 05000400/2021002 IR 05000400/20213012021-05-18018 May 2021 NRC Operator License Examination Report 05000400/2021301 IR 05000400/20210012021-04-29029 April 2021 Integrated Inspection Report 05000400/2021001 IR 05000400/20200062021-03-0303 March 2021 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2020006 IR 05000400/20200042021-01-27027 January 2021 Integrated Inspection Report 05000400/2020004 IR 05000400/20203012021-01-0808 January 2021 301 Exam Report 05000400/2020301 IR 05000335/20204012021-01-0505 January 2021 Security Baseline Inspection Report 05000335/2020401 and 05000389/2020401 IR 05000400/20200102020-12-14014 December 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000400/2020010 IR 05000400/20200112020-12-0202 December 2020 Biennial Problem Identification and Resolution Inspection Report 05000400/2020011 IR 05000400/20204052020-11-0606 November 2020 Security Baseline Inspection Report 05000400/2020405 IR 05000400/20200032020-11-0606 November 2020 Integrated Inspection Report 05000400/2020003 IR 05000400/20204032020-10-30030 October 2020 Security Baseline Inspection Report 05000400/2020403 2024-09-10
[Table view] Category:Letter
MONTHYEARML24290A1102024-10-24024 October 2024 Notification of Licensed Operator Initial Examination 05000400/2025301 05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-Out2024-10-23023 October 2024 Automatic Reactor Trip Due to Main Generator Lock-Out IR 05000400/20240112024-09-10010 September 2024 NRC Inspection Report 05000400/2024011 IR 05000400/20240052024-08-26026 August 2024 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400-2024005) Rev 1 ML24059A4252024-08-14014 August 2024 Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications ML24213A0522024-08-0202 August 2024 Issuance of Amendment No. 201 to Extend Completion Time of Inoperable Reactor Coolant System Accumulator Using Consolidated Line Item Improvement Process ML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24170A7312024-07-29029 July 2024 – Exemption from the Requirements of 10 CFR 50.55a(H)(2) Using the Risk-Informed Process for Evaluations Letter IR 05000400/20240022024-07-29029 July 2024 – Integrated Inspection Report 05000400/2024002 05000400/LER-2024-001, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000400/20243022024-06-27027 June 2024 – NRC Operator Licensing Examination Approval 05000400/2024302 IR 05000400/20244012024-06-25025 June 2024 – Security Baseline Inspection Report05000400/2024401 ML24162A1372024-06-24024 June 2024 – Regulatory Audit Summary Related to the Review of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2)(EPID L-2024-LLE-00040) ML24136A1382024-05-20020 May 2024 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2024011) and Request for Information (RFI) ML24116A2592024-05-14014 May 2024 Staff Evaluation Related to Aging Management Plan and Inspection Plan for Reactor Vessel Internals ML24127A1592024-05-0808 May 2024 – Notification of Licensed Operator Initial Examination 05000400/2024302 IR 05000400/20240012024-05-0505 May 2024 Integrated Inspection Report 05000400/2024001 ML24100A0912024-04-10010 April 2024 Operator License Examination Report ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) IR 05000400/20230062024-02-28028 February 2024 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2023006 ML24032A2632024-02-23023 February 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0044 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 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 ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter 05000400/LER-2022-006-02, Auxiliary Feedwater Pump Inoperability2023-07-11011 July 2023 Auxiliary Feedwater Pump Inoperability IR 05000400/20243012023-05-15015 May 2023 – Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 – Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 05000400/LER-1922-006-01, Auxiliary Feedwater Pump Inoperability2023-03-10010 March 2023 Auxiliary Feedwater Pump Inoperability IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 05000400/LER-2022-007-01, Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus2023-01-26026 January 2023 Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) 05000400/LER-2022-007, Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus2022-12-20020 December 2022 Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus 2024-09-10
[Table view] |
Text
ber 5, 2007
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT - NRC EXAMINATION REPORT NO. 05000400/2007301
Dear Mr. Duncan:
During the period of August 13-16, 2007, the Nuclear Regulatory Commission (NRC)
administered operating examinations to employees of your company who had applied for licenses to operate the Shearon Harris Nuclear Power Plant. The examiners discussed preliminary findings related to the operating test and written examination submittal with those members of your staff identified in the enclosed report on August 17, 2007. The written examination was administered by your staff on August 23, 2007.
Four Senior Reactor Operator applicants and three Reactor Operator applicants passed both the written and operating examinations. There was one post examination comment. The NRC resolution to this comment is summarized in Enclosure 2. A Simulation Facility Report is included in this report as Enclosure 3.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures 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\\
Malcolm T. Widmann, Chief Operations Branch Division of Reactor Safety Docket No. 50-400 License No. NPF-63
Enclosures:
(See page 2)
CP&L 2 Enclosures: 1. Report Details 2. NRC Resolution to the Facility Comment 3. Simulation Facility Report
REGION II==
Docket Nos.: 05000400 License Nos.: NPF-63 Report Nos.: 05000400/2007301 Licensee: Carolina Power & Light Company (CP&L)
Facility: Shearon Harris Nuclear Power Plant Location: 5413 Shearon Harris Road New Hill, NC 27562 Dates: Operating Tests - August 13-16, 2007 Written Examination - August 23, 2007 Examiners: F. Ehrhardt, Chief Examiner R. Monk, Senior Resident Inspector (Examiner Certified)
P. Presby, Operations Engineer (RI)
Approved by: M. Widmann, Chief Operations Branch Division of Reactor Safety Enclosure 1
SUMMARY OF FINDINGS ER 05000400/2007301; 8/13-23/2007; Shearon Harris Nuclear Power Plant, Licensed Operator Examinations.
The NRC examiners conducted operator licensing initial examinations in accordance with the guidance of NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Rev. 9. This examination implemented the operator licensing requirements of 10 CFR §55.41,
§55.43, and §55.45.
The NRC administered the operating tests during the period of August 13-16, 2007. Members of the Shearon Harris Nuclear Power Plant training staff administered the written examination on August 23, 2007. The operator licensing initial written examinations and operating tests were developed by the licensee. Four Senior Reactor Operator (SRO) and three Reactor Operator (RO) applicants passed both the written and operating examinations. Three SRO applicants and two RO applicants were issued operating licenses. One SRO applicant and one RO applicant were issued letters stating that they passed both the written and operating examinations and that their licenses will not be issued until the licensee has certified in writing that they have completed the experience for which they were granted waivers.
The initial written examination submittal was determined to be outside of the acceptable quality range as outlined in NUREG-1021. Thirty-three out of 75 questions on the RO examination were significantly modified or replaced and seven out of 25 questions on the SRO examination were significantly modified or replaced as a result of the NRCs review of the submittal.
Individual questions were evaluated as unsatisfactory because they did not test the knowledge required by the selected topic, contained implausible distractors, and/or contained other psychometric flaws. Future examination submittals need to incorporate lessons learned from this effort.
Enclosure 1 Report Details 4. OTHER ACTIVITIES (OA)
4OA5 Operator Licensing Initial Examinations a. Inspection Scope The licensee developed the operating tests and written examinations. The NRC examination team reviewed the proposed examination material to determine whether it was developed in accordance with NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9. Examination changes agreed upon between the NRC and the licensee were made according to NUREG-1021 and incorporated into the final version of the examination materials.
The examiners reviewed the licensees examination security measures while preparing and administering the examinations to ensure examination security and integrity complied with 10 CFR 55.49, Integrity of Examinations and Tests.
The examiners evaluated four SRO and three RO applicants who were being assessed under the guidelines specified in NUREG-1021. The examiners administered the operating tests during the period of August 13-16, 2007. Members of the Shearon Harris Nuclear Power Plant training staff administered the written examination on August 23, 2007. The evaluations of the applicants and review of documentation were performed to determine if the applicants, who applied for licensees to operate the Shearon Harris Nuclear Power Plant, met requirements specified in 10 CFR Part 55.
b. Findings The initial written examination submittal was evaluated to be outside of the acceptable quality range as outlined in NUREG-1021. Thirty-three out of 75 questions on the RO examination were significantly modified or replaced and seven out of 25 questions on the SRO examination were significantly modified or replaced as a result of the NRCs review of the submittal. Individual questions were evaluated as unsatisfactory because they did not test the knowledge required by the selected topic, contained implausible distractors, and/or contained other psychometric flaws. Future examination submittals need to incorporate lessons learned from this effort.
Four SRO and three RO applicants passed both the operating test and written examination. The licensee submitted one post examination comment concerning the operating examination. The written examination, and examination references may be accessed in the ADAMS system (ADAMS Accession Number ML072760077, ML072760022, ML072760013).
Enclosure 1
4OA6 Meetings Exit Meeting Summary On August 17, 2007, the Chief Examiner discussed generic applicant performance and examination development issues with members of licensee management. The inspectors asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
On September 18, 2007, Robert Haag, former Chief, Operations Branch, discussed written examination results with Greg Kilpatrick, Superintendent - Operations Training.
PARTIAL LIST OF PERSONS CONTACTED Licensee R. Duncan, Vice President - Harris Nuclear Plant J. Warner, Manager - Operations D. McGee, Manager - Shift Operations W. Gurganious, Manager - Training T. Toler, Supervisor - Operator Initial Training D. Corlett, Supervisor - Licensing/Regulatory Programs C. Kamilaris, Manager - Nuclear Assessment M. Wallace, Senior Specialist - Licensing T. Natale, Manager - Site Support Services G. Kilpatrick, Superintendent - Operations Training NRC P. OBryan, Senior Resident Inspector M. King, Resident Inspector Enclosure 1
NRC Resolution to the Facility Comment Test Item Administrative JPM A-3: Determine and Apply the Facility Dose Limits (Calculate Stay Time)
Facility Comment Administrative JPM A-3 for the RO and SRO candidates was to determine the lowest facility limit and calculate the stay time for operation of a specific valve. Each candidate was given a survey map and a Radiological Work Permit (RWP) to use. The answer key provided with this JPM used a dose rate of 3 mr/hr for the area where the work would be performed. However, a review of the survey map shows that in addition to the two 3 mr/hr areas used in the key, there is an equidistant 4 mr/hr area adjacent to the work area as well. Using this 4 mr/hr area for calculating the stay time would be conservative for some situations depending on the assumptions the candidate makes.
NRC Resolution The licensee recommendation was accepted.
Applicant performance was evaluated as satisfactory if the applicant correctly determined a stay time by using a dose rate of either 3 mr/hr or 4 mr/hr.
Enclosure 2
Simulation Facility Report Facility Licensee: Shearon Harris Nuclear Power Plant Facility Docket No.: 05000400 Operating Tests Administered on: August 13-16, 2007 This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with IP 71111.11, are not indicative of noncompliance with 10 CFR 55.46. No licensee action is required in response to these observations.
While validating the simulator portion of the operating tests, examiners observed the following item:
Item Description PRT Rupture The Pressurizer Relief Tank pressure spikes to greater than 120 psig and Disk then decreases to ambient pressure within approximately 8 seconds of a single pressurizer PORV opening (due to controlling pressurizer pressure channel failing high.)
Correction to the PRT rupture time is warranted based on the licensees comparison of plant data from a similar actual event that occurred in 1995 with data from the simulator for this event. The licensee generated Simulator Service Request number 07-0248 to track this item.
Enclosure 3