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| {{Adams | | {{Adams |
| | number = ML16197A258 | | | number = ML15356A828 |
| | issue date = 07/13/2016 | | | issue date = 12/22/2015 |
| | title = NRC Operator License Examination Report 05000413/2016301 and 05000414/2016301, May 16 19, 2016 and May 26, 2016 | | | title = Notification of Licensed Operator Initial Examination 05000413/2016301 and 05000414/2016301 |
| | author name = Mccoy G | | | author name = Mccoy G |
| | author affiliation = NRC/RGN-II/DRS | | | author affiliation = NRC/RGN-II/DRS |
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| | license number = NPF-035, NPF-052 | | | license number = NPF-035, NPF-052 |
| | contact person = | | | contact person = |
| | document report number = ER 2016301 | | | document report number = 50-413/16-301, 50-414/16-301 |
| | document type = Letter, License-Operator, License (New/Renewal/Amend) DKT 55 | | | document type = Letter, License-Operator, Part 55 Examination Related Material |
| | page count = 15 | | | page count = 4 |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION uly 13, 2016 | | {{#Wiki_filter:UNITED STATES ecember 22, 2015 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| CATAWBA NUCLEAR STATION - NRC OPERATOR LICENSE EXAMINATION REPORT 05000413/2016301 AND 05000414/2016301 | | CATAWBA NUCLEAR STATION - NOTIFICATION OF LICENSED OPERATOR INITIAL EXAMINATION NOS. - 05000413/2016301 AND 05000414/2016301 |
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| ==Dear Mr. Henderson:== | | ==Dear Mr. Henderson:== |
| During the period May 16 - 19, 2016, the Nuclear Regulatory Commission (NRC) administered operating tests to employees of your company who had applied for licenses to operate the Catawba Nuclear Station. At the conclusion of the tests, the examiners discussed preliminary findings related to the operating tests and the written examination submittal with those members of your staff identified in the enclosed report. The written examination was administered by your staff on May 26, 2016. | | During a telephone conversation on December 16, 2015, between Mr. Bruce Boyette, Operations Training Instructor, and Mr. Michael Meeks, Senior Operations Engineer, arrangements were made for the administration of licensing examinations at Catawba Nuclear Station. The operating test is scheduled to be administered during the week of May 16, 2016. |
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| |
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| Three Reactor Operator (RO) and seven Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One RO applicant failed the written examination. There were four post-administration comments concerning the written examination and one post-administration comment concerning the operating test. These comments, and the NRC resolution of these comments, are summarized in Enclosure 2.
| | The written examination is scheduled to be administered the week of May 23, 2016. The on-site preparatory week is scheduled for the week of April 18, 2016. |
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| A Simulator Fidelity Report is included in this report as Enclosure 3.
| | As agreed during the telephone conversation, your staff will prepare both the operating test and written examination based on the guidelines in Revision 10 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The U.S. Nuclear Regulatory Commission (NRC) regional office will discuss with your staff any changes that might be necessary before the examinations are administered. Your staff has also agreed to make copies of all examination materials that are necessary for administering the examination. |
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| The initial examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and your staff were made according to NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 10. | | To meet the above schedule, it will be necessary for your staff to furnish the operating test outline by February 16, 2016. Mr. Meeks provided the written examination outline to your staff in September, 2015. The operating test, written examination, and the supporting reference materials identified in Attachment 3 to ES-201 will be due by March 17, 2016. Pursuant to Title 10, Section 55.40(b)(3), of the Code of Federal Regulations (10 CFR 55.40(b)(3)), an authorized representative of the facility licensee shall approve the outline, examination, and test before they are submitted to the NRC for review and approval. All materials shall be complete and ready-to-use. |
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| 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 the NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room). If you have any questions concerning this letter, please contact me at (404) 997-4551.
| | We request that any personal, proprietary, sensitive unclassified, or safeguards information in your response be contained in a separate enclosure and appropriately marked. Any delay in receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled. In order to conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-402, and to make the simulation facility available on the dates noted above. In accordance with ES-302, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and levels) generated during the dynamic operating tests until the examination results are final. |
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| |
|
| Sincerely,
| | Appendix E of NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations and operating tests are being administered. |
| /RA/
| |
| Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety Docket Nos: 50-413, 50-414 License Nos: NPF-35, NPF-52 Enclosures: 1. Report Details 2. Facility Comments and NRC Resolution 3. Simulator Fidelity Report
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| _________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS SIGNATURE GXG MKM3 VIA EMAIL AXT6 VIA EMAIL SXS31 VIA EMAIL NAME GMCCOY MMEEKS ATOTH SSHAH DATE 7/13/2016 7/11/2016 7/11/016 7/11/2016 E-MAIL COPY? YES NO YES NO YES NO YES NO YES YES NO YES NO
| | To permit timely NRC review and evaluation, your staff should submit preliminary reactor operator and senior reactor operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024), |
| | and waiver requests (if any) (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date. |
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| U.S. NUCLEAR REGULATORY COMMISSION | | This letter contains information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the OMB under approval number 3150-0018, which expires on April 30, 2016. The public reporting burden for this collection of information is estimated to average 2500 hours per response, including the time for reviewing instructions, gathering and maintaining the data needed, writing the examinations, and completing and reviewing the collection of information. Send comments on any aspect of this collection of information, including suggestions for reducing the burden, to the Information and Records Management Branch (T-6 F33), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet electronic mail at infocollectsresource@nrc.gov; and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and Budget, Washington, DC 20503. |
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|
| ==REGION II==
| | The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection, unless it displays a currently valid OMB control number. |
| Docket No.: 50-413, 50-414 License No.: NPF-35, NPF-52 Report No.: 05000413/2016301, 05000414/2016301 Licensee: Duke Energy Carolinas, LLC Facility: Catawba Nuclear Station, Units 1 & 2 Location: York, SC 29745 Dates: Operating Test - May 16 - 19, 2016 Written Examination - May 26, 2016 Examiners: M. Meeks, Chief Examiner, Senior Operations Engineer J. A. Toth, Operations Engineer S. Shah, Operations Engineer Approved by: Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety Enclosure 1
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|
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| =SUMMARY=
| | 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 the NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room). Thank you for your cooperation in this matter. Mr. Boyette has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the NRC's examination procedures and guidelines, please contact Mr. Meeks at (404) 997-4467, (Internet E-mail: |
| ER 05000413/2016301, 05000414/2016301; May 16 - 19, 2016 & May 26, 2016; Catawba
| | Michael.Meeks@nrc.gov), or me at (404) 997-4551, (Internet E-mail: Gerald.McCoy@nrc.gov). |
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|
| Nuclear Station; Operator License Examinations.
| | Sincerely, |
| | | /RA/ |
| Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in accordance with the guidelines in Revision 10 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.
| | Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52 cc: Distribution via Listserv |
| | |
| Members of the Catawba Nuclear Station staff developed both the operating tests and the written examination. The initial operating test, written Reactor Operator (RO) examination, and written Senior Reactor Operator (SRO) examination submittals met the quality guidelines contained in NUREG-1021.
| |
| | |
| The NRC administered the operating tests during the period May 16 - 19, 2016. Members of the Catawba Nuclear Station training staff administered the written examination on May 26, 2016. Three RO and seven SRO applicants passed both the operating test and written examination. One RO applicant passed the operating test, but did not pass the written examination. Nine applicants were issued licenses commensurate with the level of examination administered. The issuance of a license for one RO applicant has been delayed pending final resolution of any further appeals that may impact the licensing decision.
| |
| | |
| There were five post-examination comments.
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| | |
| No findings were identified.
| |
| | |
| =REPORT DETAILS=
| |
| | |
| ==OTHER ACTIVITIES==
| |
| {{a|4OA5}}
| |
| ==4OA5 Operator Licensing Examinations==
| |
| | |
| ====a. Inspection Scope====
| |
| The NRC evaluated the submitted operating test by combining the scenario events and Job Performance Measures (JPMs) in order to determine the percentage of submitted test items that required replacement or significant modification. The NRC also evaluated the submitted written examination questions (Reactor Operator (RO) and Senior Reactor Operator (SRO) questions considered separately) in order to determine the percentage of submitted questions that required replacement or significant modification, or that clearly did not conform with the intent of the approved knowledge and ability (K/A) statement. Any questions that were deleted during the grading process, or for which the answer key had to be changed, were also included in the count of unacceptable questions. The percentage of submitted test items that were unacceptable was compared to the acceptance criteria of NUREG-1021, Operator Licensing Standards for Power Reactors.
| |
| | |
| The NRC reviewed the licensees examination security measures while preparing and administering the examinations in order to ensure compliance with 10 CFR §55.49, Integrity of examinations and tests.
| |
| | |
| The NRC administered the operating tests during the period May 16 - 19, 2016. The NRC examiners evaluated four RO and seven SRO applicants using the guidelines contained in NUREG-1021. Members of the Catawba Nuclear Station training staff administered the written examination on May 26, 2016. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Catawba Nuclear Station, met the requirements specified in 10 CFR Part 55, Operators Licenses.
| |
| | |
| The NRC evaluated the performance or fidelity of the simulation facility during the preparation and conduct of the operating tests.
| |
| | |
| ====b. Findings====
| |
| No findings were identified.
| |
| | |
| The NRC developed the written examination sample plan outline. Members of the Catawba Nuclear Station training staff developed both the operating tests and the written examination. All examination material was developed in accordance with the guidelines contained in Revision 10 of NUREG-1021. The NRC examination team reviewed the proposed examination. Examination changes agreed upon between the NRC and the licensee were made per NUREG-1021 and incorporated into the final version of the examination materials.
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| | |
| The NRC determined, using NUREG-1021, that the licensees initial examination submittal was within the range of acceptability expected for a proposed examination.
| |
| | |
| Three RO applicants and seven SRO applicants passed both the operating test and written examination. One RO applicant passed the operating test but did not pass the written examination. Two RO applicants and seven SRO applicants were issued licenses.
| |
| | |
| One RO applicant passed the operating test, but passed the written examination with overall scores between 80% and 82%. This applicant was issued a letter stating that they passed the examination and issuance of their license has been delayed pending any written examination appeals that may impact the licensing decision for their application.
| |
| | |
| Copies of all individual examination reports were sent to the facility Training Manager for evaluation of weaknesses and determination of appropriate remedial training.
| |
| | |
| The licensee submitted one post-examination comment concerning the operating test and four post-examination comments concerning the written examination. A copy of the final written examination and answer key, with all changes incorporated, may be accessed not earlier than July 10, 2018, in the ADAMS system (ADAMS Accession Number(s) ML16166A099 and ML16166A102). A full copy of the licensees post-examination comments may be accessed in the ADAMS system as ML16166A106.
| |
| | |
| {{a|4OA6}}
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| ==4OA6 Meetings, Including Exit==
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| | |
| ===Exit Meeting Summary===
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| | |
| On May 24, 2016, the NRC examination team discussed generic issues associated with the operating test with K. Henderson, Site Vice President, and members of the Catawba Nuclear Station staff via telephone.
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| | |
| On June 28, 2016, the NRC examination team discussed the results of the examination with A. Honeggar, Operations Training Manager, and members of the Catawba Nuclear Station staff via telephone. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified.
| |
| | |
| ATTACHMENT:
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| =SUPPLEMENTARY INFORMATION=
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| KEY POINTS OF CONTACT
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| ===Licensee personnel===
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| : [[contact::K. Alcorn]], Operations Training Supervisor (ILT)
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| : [[contact::S. Andrews]], Senior Nuclear Engineer
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| : [[contact::C. Bigham]], Organizational Effectiveness Director
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| : [[contact::B. Boyette]], NRC Exam Developer
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| : [[contact::R. Exley]], ILT Lead Instructor
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| : [[contact::B. Haynes]], Assistant Operations Manager (Training)
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| : [[contact::K. Henderson]], Site Vice President
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| : [[contact::A. Honeggar]], Operations Training Manager
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| : [[contact::W. Jarman]], Assistant Operations Manager (Shift)
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| : [[contact::B. Leonard]], Training Manager
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| : [[contact::R. Miller]], NRC exam developer
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| : [[contact::T. Simril]], Plant Manager
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| : [[contact::S. Tripi]], Operations Training Supervisor (NLOCT/exam development)
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| : [[contact::B. Webster]], Operations Training Supervisor (LOCT)
| |
| ===NRC personnel===
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| : [[contact::A. Hutto]], Senior Resident Inspector
| |
| FACILITY POST-EXAMINATION COMMENTS AND NRC RESOLUTIONS
| |
| A complete text of the licensees post-examination comments can be found in ADAMS under
| |
| Accession Number ML16166A106.
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| Item
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| Question 17, K/A W/E11EG2.4.20
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| Comment
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| The licensee recommends that that two correct answers (A and B) be accepted for this this
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| question as both answers are correct based on conflicting information contained within a
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| procedure note and the Operations governing document for EP/AP implementation.
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| 1. EP/1/A/5000/ECA-1.1 (Loss of Emergency Coolant Recirculation) contains a note which | |
| states An invalid SPDS orange path may briefly exist between opening NS suction
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| valve from sump and starting NS pump. FR-Z.1 should not be entered unless NS pump
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| fails to start.
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| 2. The purpose of this note is to prevent a crew from needlessly transitioning to a CSF
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| procedure while attempting to restore the ability to align for Cold Leg Recirculation.
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| 3. The signal generated is actually valid as the logic for this condition is met due to the
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| alignment specified by this procedure (see attached logic diagram).
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| 4. OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines) states that an
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| SPDS signal is only invalid if caused by an instrument malfunction or computer related
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| failure (see attached note). Since this document governs all Emergency and Abnormal
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| Procedures, this guidance would apply to ECA-1.1.
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| 5. Operations Department management has determined that the orange SPDS signal that
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| is generated is technically VALID, however current wording of the note in ECA-1.1 states
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| to consider it invalid. Ultimately the reason for the note is to ensure that an unnecessary
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| transition to FR-Z.1 is not made. A procedure change request has been generated to
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| modify this note (in ECA-1.1), to remove the term invalid, in order to eliminate the
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| conflict discovered during this exam.
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| NRC Resolution
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| The licensees recommendation was rejected.
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| The NRC recognized the licensees contention that conflicting guidance existed between the
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| NOTE in EOP ECA-1.1 and the referenced NOTE in the administrative procedure OMP 1-7.
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| The OMP 1-7 NOTE is included in a section that details generic rules of usage for
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| implementation of the critical safety function determination process. Specifically, the NOTE is
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| listed before a step that details how operators are required to validate the critical safety
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| function status before transitioning to any Critical Safety Function (CSF) procedure. A later
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| bulleted step states, If a valid red path is encountered and then provides the applicable
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| guidance to the operators on how to transition to the applicable CSF procedure.
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| Therefore, correct application of the NOTE in ECA-1.1 before step 7.d. would be to recognize
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| that the momentary invalid orange path should not be used as a directive to transition to the
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| orange path CSF procedure. This NOTE in ECA-1.1 is specific to the conditions in that
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| procedure and takes precedence over any general rules of usage guidance provided in
| |
|
| |
|
| administrative conduct-of-operations procedures. Furthermore, the stem of the first part
| | _________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE GJM1 FOR MKM3 GJM1 NAME MMEEKS GMCCOY DATE 12/22/2015 12/22/2015 12/ /2015 12/ /2015 12/ /2015 12/ /2015 12/ /2015 E-MAIL COPY? YES NO YES NO YES YES NO YES NO YES NO YES NO N |
| question statement directs the applicant to answer the question statement Per ECA-1.1, and
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| not as a general question, or per OMP 1-7. This statement strongly ties the first part question
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| statement to the ECA-1.1 procedure steps, NOTEs, and CAUTION statements in opposition to
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| any other procedural guidance that may not be considered exclusively internally consistent.
| |
| There are other cases in the Westinghouse emergency operating procedures where specific
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| NOTES or CAUTIONS override more general usage guidance. For example, in Catawba
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| emergency operating procedure EP/1/A/5000/E-3, Steam Generator Tube Rupture, there is a
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| CAUTION statement at step 8 RNO that stated: NC T-Cold indication in ruptured loop may
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| cause an invalid Integrity Status Tree condition. This statement is very similar to the NOTE
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| listed in ECA-1.1 in that it applies only to a specific condition during performance of a specified
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| procedure; that is, performance of this particular procedure at this step may result in an invalid
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| critical safety function status.
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| The NRC acknowledges that the facility licensee has initiated its processes for enhancing the
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| clarity and consistency of the procedural guidance in question.
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| However, as given, Question 17 has only one technically correct answer, and the NRC
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| determined that no change to the official answer key was warranted in accordance with
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| NUREG-1021.
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| Item
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| Question 28, K/A 003K5.02
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| Comment
| |
| The licensee recommends that this question be removed from the exam as no correct answer to
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| part 1 is listed.
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| 1. Part 1 of this question is technically correct concerning the loss of a Reactor Coolant
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| Pump with no other plant transient in progress.
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| 2. With the given conditions, a Reactor trip will occur based on P-8 (Single Loop Loss of
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| Flow Reactor Trip > 48%) resulting in a fluctuation of all S/G levels.
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| 3. Post exam simulator analysis revealed that the identified S/G level (1C) would actually
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| begin to shrink first and at a faster rate but not to a lower level when compared with
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| other S/Gs.
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| 4. The question did not specify a detailed time frame for analysis. Initially is open to
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| interpretation as the applicable S/G level varies considerably within a relatively short
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| period of time (as compared to other S/G levels).
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| 5. The listed answer is technically incorrect. The other available answer is also technically
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| incorrect as S/G swell will not occur.
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| NRC Resolution
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| The licensees recommendation was rejected.
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| The first part question statement specifically asks that applicant to determine whether the initial
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| Steam Generator (S/G) water level trend in the idle reactor coolant loop will be of the S/G level
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| shrink[ing] lower or swell[ing] higher as compared to the other S/G levels in the reactor
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| coolant loops with operating reactor coolant pumps. The given time frame in the question is
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| specified as initially after the 1C NC [reactor coolant] pump trips. Therefore, the
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| question is asking the applicant to determine the initial 1C S/G level trend immediately after the
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| 1C NC pump trips, as compared to the operating loop S/G level trends.
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| As detailed in the simulator traces provided by the facility licensee, immediately after the 1C NC
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| pump trips, the 1C S/G level begins to lower below the other loops S/G levels. There is a short
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| period where the other loops S/G levels begin to increase (swell), just before the reactor trip
| |
| occurs. For a time period of approximately 16 seconds after the NC pump trips, the 1C S/G
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| level is lower, and lowering faster, than the other S/Gs. Therefore, the simulator data clearly
| |
| demonstrates that the initial 1C S/G level trend after the 1C NC pump trips is characterized by
| |
| 1C S/G level shrink[ing] lower.
| |
| Therefore, as given, Question 28 has only one technically correct answer, and the NRC
| |
| determined that no change to the official answer key was warranted in accordance with
| |
| NUREG-1021.
| |
| Item
| |
| Question 50, K/A 063A1.01
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| Comment
| |
| The licensee recommends that question 50 be deleted from the exam due to not having enough
| |
| information in the stem of the question in order to answer it correctly.
| |
| 1. The stem of the question states that battery 1EBA is supplying AC vital bus 1ERPA
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| through inverter 1EIA without a battery charger connected. Even though this would be
| |
| the lineup if a battery charger were to fail, it does not provide a complete load profile for
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| this battery. 1EBA would be supplying 1EDA and Panelboard 1EPA as well as other
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| loads (see system drawing).
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| 2. The question stem also states that only the voltage range of 125 VDC to 120 VDC is
| |
| taken into account. Battery discharge tests in the plant suggest that the battery would
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| only be in this voltage range for mere seconds (see 1EBA discharge test data sheet).
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| 3. Due to the short duration of being in the specified voltage range and the unknown load
| |
| profile for the specific battery listed, it is the opinion of CNS that there is not enough
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| information to answer this question correctly and it should be deleted from the exam.
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| NRC Resolution
| |
| The licensees recommendation was accepted.
| |
| During the development of this question, the facility licensee and the NRC agreed upon adding
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| a plant-specific battery and a plant-specific bus to the question stem as follows: Vital battery
| |
| 1EBA is supplying 1ERPA through inverter 1EIA without a battery charger on line. The intent
| |
| of this editorial modification was to simplify the electrical plant line-up in question for the
| |
| applicants. The question then asks the applicants to determine the trend of battery current flow
| |
| and battery discharge rate as battery terminal voltage decreased from 125 VDC to 120 VDC.
| |
| However, as detailed by the licensee, the actual electrical line-up is more complicated than
| |
| intended by the exam writers and reviewers. In actuality, the isolated battery 1EBA would be
| |
| supplying various other loads that are not supported by the question stem.
| |
| Therefore, the question unintentionally presented an unclear stem that did not provide all of the
| |
| necessary information needed to elicit the correct answer. Furthermore, given the additional
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| complexity of the electrical circuit to be analyzed in order to answer the question (albeit
| |
| unintentionally), it is arguable whether the question as given would be operationally valid as a
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| test item from the standpoint of the reactor operator job requirements.
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| Therefore, the NRC agreed with the facility licensee, and deleted Question 50 from the written
| |
| examination in accordance with NUREG-1021 ES-403 section D.1.b.
| |
| Item
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| Question 75, K/A G2.4.43
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| Comment
| |
| The licensee recommends that the Exam Key be changed to list the correct answer as C
| |
| (approved exam listed D as correct answer).
| |
| 1. Several CNS procedures list the sound powered phone circuit power supply for each
| |
| unit, but omit information concerning a permanent cross-tie installed per NSM 50307.
| |
| 2. Post exam review identified conflicting information concerning split versus cross-tied
| |
| power supplies.
| |
| 3. CNS Engineering staff has verified that a previously installed modification tied sound
| |
| powered phone circuits together ensuring availability from the opposite unit following a
| |
| loss of one units essential B train power (see attached email and NSM).
| |
| 4. Per the listed conditions, the emergency sound power phone circuit will be available, via
| |
| Unit 2 power supply. Answer D is technically incorrect. Answer C is technically
| |
| correct.
| |
| NRC Resolution
| |
| The licensees recommendation was accepted.
| |
| During written exam development, the technical reference used to support Question 75 was
| |
| Note 1 of Enclosure 4.9, Emergency Communications, of procedure OP/1/A/6100/020, which
| |
| stated:
| |
| The emergency sound powered phone circuit receives backup, emergency
| |
| power from the B train essential switchgear. If the B Train essential
| |
| switchgear is de-energized concurrent with a loss of offsite power, the
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| emergency sound powered phone circuit will be inoperable.
| |
| Accordingly, the exam writers wrote an operationally valid question that provided a loss of the
| |
| B train essential switchgear concurrent with a loss of offsite power in the stem, in order to test
| |
| the application of this plant condition to the availability of the emergency sound powered phone
| |
| circuit.
| |
| However, as detailed by the facility licensee, there was an installed plant modification (NSM
| |
| 50307) that was identified during post-exam review that provides for a permanent cross-tie
| |
| installation for the emergency sound powered phone circuit. The existence of this electrical
| |
| cross-tie negates the technical accuracy of the referenced procedural NOTE used in the
| |
| question development. This newly discovered technical information supports a change in the
| |
| question answer key from D to C. There is no other conflicting information in the question
| |
| stem or distractors.
| |
| Therefore, the NRC agreed with the facility licensee, and changed the answer for Question 75
| |
| from D to C in accordance with NUREG-1021 ES-403 section D.1.b.
| |
| Item
| |
| Job Performance Measure F, Shift Operating Condenser Circulating Water Pumps
| |
| Comment
| |
| The licensee recommends that step 7 be changed to remove the Critical Step designation.
| |
| 1. The as submitted JPM F (Shift Operating RC (Condenser Circulating Water) Pumps by
| |
| placing 1D RC Pump in service and securing 1B RC Pump) step 7 is labeled as a critical
| |
| step.
| |
| 2. The purpose of securing the pump by closing its discharge valve is to prevent exposing
| |
| the pump suction line from the discharge pressure of the remaining running pumps. In
| |
| this case that would be RC pumps 1A, 1C, and 1D.
| |
| 3. If the step for closing the discharge valve were not performed and the 1B RC pump were
| |
| secured by just depressing the OFF pushbutton, then the discharge valve would
| |
| automatically close in approximately 50 seconds. This would allow the discharge
| |
| pressure of the remaining running pumps to be introduced to the suction of the 1B RC
| |
| pump for those 50 seconds.
| |
| 4. According to the engineering department (Mike Classe - Manager Nuclear Engineering),
| |
| the maximum discharge pressure of any running pump would be from the 2C RC pump
| |
| (~66 PSIG at an operating temperature of 105-110 degrees F).
| |
| The suction piping for this system is Pipe Spec 150.4 seen in the chart (provided by the
| |
| licensee). For a conservative temperature of 200 degrees F, the maximum design pressure for
| |
| the suction piping would be 215 PSI
| |
| : [[contact::G. Therefore]], having the suction piping subjected to design
| |
| discharge pressure for a short duration of time is of no major consequence, and should
| |
| therefore not be credited as a critical step. The critical part of securing 1B RC pump is to
| |
| depress the OFF pushbutton and verify the discharge valve is closed, and therefore step 8 of
| |
| the JPM should remain the critical step.
| |
| NRC Resolution
| |
| The licensees recommendation was accepted.
| |
| As described in the facility licensees recommendation, there are no adverse consequences to
| |
| subjecting the suction piping to pump discharge pressure for a short period of time. Therefore,
| |
| this newly discovered technical information supports changing the designation of JPM step 7
| |
| from critical to non critical. Based on the design of the JPM, the interlock between the
| |
| discharge valve closing resulting in an automatic pump trip was defeated; however, the interlock
| |
| between manually tripping the pump causing an automatic closure of the discharge valve was
| |
| not defeated. As a result of this newly discovered technical information, the NRC determined
| |
| that manually securing the RC pump remained a critical step in successfully completing the JPM
| |
| overall, but manually closing the discharge valve before manually securing the RC pump was
| |
| evaluated as not being a critical step in the JP
| |
| : [[contact::M.
| |
| Therefore]], the NRC agreed with the licensee to change the designation of JPM step 7 to non-
| |
| critical in accordance with NUREG-1021, and all of the applicants performance on this JPM
| |
| was evaluated accordingly.
| |
| SIMULATOR FIDELITY REPORT
| |
| Facility Licensee: Catawba Nuclear Station
| |
| Facility Docket No.: 50-413, 50-414
| |
| Operating Test Administered: May 16 - 19, 2016
| |
| 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 Inspection
| |
| Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee
| |
| action is required in response to these observations.
| |
| No simulator fidelity or configuration issues were identified.
| |
| 3
| |
| }} | | }} |
|
---|
Category:Letter
MONTHYEARML24255A8312024-09-23023 September 2024 Project Manager Assignment ML24261B9782024-09-19019 September 2024 Notification of an NRC Fire Protection Team Inspection NRC Inspection Report 05000413-2024010, 05000414-2024010 and Request for Information IR 05000414/20240912024-09-0505 September 2024 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter-NRC Inspection Report 05000414-2024091 IR 05000413/20240052024-08-26026 August 2024 Updated Inspection Plan for Catawba Nuclear Station (Report 05000413/2024005 & 05000414/2024005) ML24235A1542024-08-22022 August 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000413-2024402 and 05000414-2024402) IR 05000413/20240022024-08-0808 August 2024 Integrated Inspection Report 05000413-2024002 and 05000414-2024002 and Apparent Violation IR 05000413/20244032024-08-0101 August 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000413/2024403; 05000414/2024403 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 ML24178A0552024-06-26026 June 2024 Requalification Program Inspection – Catawba Nuclear Station IR 05000414/20240902024-06-24024 June 2024 NRC Inspection Report 05000414/2024090 and Preliminary White Finding and Apparent Violation ML24170A8632024-06-11011 June 2024 Flowserve June 11, 2024, Part 21 Notification - Redacted Version for Publishing ML24144A1162024-05-28028 May 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000413/20240012024-05-10010 May 2024 Integrated Inspection Report 05000413/2024001 and 05000414/2024001 and Apparent Violation ML24095A1072024-04-0808 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report (C1R27) IR 05000413/20243012024-03-12012 March 2024 – Notification of Licensed Operator Initial Examination 05000413/2024301 and 05000414/2024301 ML24017A0652024-03-0808 March 2024 Issuance of Amendment Nos. 319 and 315 to Technical Specification 3.7.11, Control Room Area Chill Water System (Cracws) IR 05000413/20230062024-02-28028 February 2024 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - (NRC Inspection Report 05000413/2023006 and 05000414/2023006) IR 05000413/20230042024-02-0202 February 2024 – Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 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 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 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 IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue 2024-09-05
[Table view] Category:License-Operator
MONTHYEARRA-24-0093, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-0202 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000413/20243012024-03-12012 March 2024 – Notification of Licensed Operator Initial Examination 05000413/2024301 and 05000414/2024301 ML23079A0902023-03-20020 March 2023 1B- Post Exam Comments IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML21321A0882021-11-17017 November 2021 301 File 2B Exam Draft Items ML21320A3282021-11-16016 November 2021 301 File 2A2 Exam Draft Items (1).pdf ML21320A3312021-11-16016 November 2021 301 File 2A3 Exam Draft Items ML21286A5252021-10-13013 October 2021 1A Final SRO Exam, Answer Key, References ML21286A3632021-10-13013 October 2021 1A Final RO Exam, Answer Key, References ML21258A3892021-09-15015 September 2021 Operating Licensing Examination Approval 05000413/2021301 and 05000414/2021301 ML21055A6072021-02-23023 February 2021 301 Exam Corporate Notification Letter ML21019A3932021-01-11011 January 2021 1 GFE Annual Letter for Fy 2021 RA-20-0075, Response to NRC Regulatory Issue Summary 2020-01 Preparation and Scheduling of Operator Licensing Examinations2020-03-16016 March 2020 Response to NRC Regulatory Issue Summary 2020-01 Preparation and Scheduling of Operator Licensing Examinations ML20007F7572020-01-0707 January 2020 Annual Letter - Generic Fundamentals Examination (GFE) Section of the Written Operator Licensing Examination for 2020 ML19308A2502019-11-0404 November 2019 301 ADAMS 2D Page 1 Exam Admin Items Normal Release ML19281E0172019-10-0808 October 2019 301 Exam Report Items Delayed Release RO as Given ML19281E0202019-10-0808 October 2019 301 Post Exam Comments IR 05000413/20193012019-09-0303 September 2019 Operator Licensing Written Examination Approval 05000413/2019301 and 05000414/2019301 ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs RA-19-0237, Catawba Station, Shearon Plant, McGuire Station, Oconee Nuclear Station and H.B. Robinson Plant - Response to NRC Regulatory Issue Summary 2019-02 Preparation and Scheduling of Operator Licensing Examinations2019-05-15015 May 2019 Catawba Station, Shearon Plant, McGuire Station, Oconee Nuclear Station and H.B. Robinson Plant - Response to NRC Regulatory Issue Summary 2019-02 Preparation and Scheduling of Operator Licensing Examinations ML19018A0882019-01-17017 January 2019 Annual Letter - Generic Fundamentals Examination (GFE) Section of the Written Operator Licensing Examination for 2019 ML18086B0442018-02-16016 February 2018 Facility Cover Letter - Rii - March 2018 - GFE ML17241A2282017-08-29029 August 2017 301 ADAMS2D Page 1 Exam Admin Items Immediate Release ML17241A2162017-08-29029 August 2017 301 ADAMS2B Final Exam Items Delay Release ML17241A2232017-08-29029 August 2017 301 ADAMS 2C Exam Admin Items Delay Release IR 05000413/20173012017-08-15015 August 2017 NRC Operator License Examination Report 05000413/2017301 and 05000414/2017301 ML17215A7792017-08-0303 August 2017 301 Post Exam Comments ML17215A7942017-08-0303 August 2017 301 Exam Report Items RO as Given - Delay Release ML17215A8012017-08-0303 August 2017 301 Exam Report Items SRO as Given - Delay Release ML17192A1792017-07-11011 July 2017 301 Exam Final Items 2B - Delay Release 2 Yrs ML17192A1812017-07-11011 July 2017 301 Exam Administrative Items 2C - Delay Release 2 Yrs ML17178A2942017-06-21021 June 2017 Operator Licensing Written Examination Approval 05000413, 414/2017301 ML17032A2792017-01-27027 January 2017 Annual Letter - Generic Fundamentals Examination (GFE) Section of the Written Operator Licensing Examination for 2017 IR 05000413/20163012016-07-13013 July 2016 NRC Operator License Examination Report 05000413/2016301 and 05000414/2016301, May 16 19, 2016 and May 26, 2016 ML16166A1062016-06-13013 June 2016 301 Facility Post Exam Comments ML16166A0992016-06-13013 June 2016 301 as Given RO Written Exam with References and Answer Key ML16166A1022016-06-13013 June 2016 301 as Given SRO Written Exam with References and Answer Key ML16104A4262016-04-0808 April 2016 March 2016 - Catawba NRC Generic Fundamentals Examination Results ML15356A8282015-12-22022 December 2015 Notification of Licensed Operator Initial Examination 05000413/2016301 and 05000414/2016301 ML15245A3012015-08-31031 August 2015 Initial Exam 2015-301 Draft Sim In-plant JPMs ML15245A3162015-08-31031 August 2015 Initial Exam 2015-301 General Correspondence ML15245A2942015-08-31031 August 2015 Initial Exam 2015-301 Draft RO Written Exam ML15245A3112015-08-31031 August 2015 Initial Exam 2015-301 Post Exam Comments ML15245A3092015-08-31031 August 2015 Initial Exam 2015-301 Final Administrative JPMs ML15245A3072015-08-31031 August 2015 Initial Exam 2015-301 Final Sim In-Plant JPMs ML15245A3052015-08-31031 August 2015 Initial Exam 2015-301 Final Simulator Scenarios ML15245A2962015-08-31031 August 2015 Initial Exam 2015-301 Draft SRO Written Exam ML15245A3032015-08-31031 August 2015 Initial Exam 2015-301 Final Administrative Documents 2024-04-02
[Table view] Category:Part 55 Examination Related Material
MONTHYEARRA-24-0093, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-0202 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000413/20243012024-03-12012 March 2024 – Notification of Licensed Operator Initial Examination 05000413/2024301 and 05000414/2024301 ML23079A0902023-03-20020 March 2023 1B- Post Exam Comments IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) ML21321A0882021-11-17017 November 2021 301 File 2B Exam Draft Items ML21320A3282021-11-16016 November 2021 301 File 2A2 Exam Draft Items (1).pdf ML21320A3312021-11-16016 November 2021 301 File 2A3 Exam Draft Items ML21286A5252021-10-13013 October 2021 1A Final SRO Exam, Answer Key, References ML21286A3632021-10-13013 October 2021 1A Final RO Exam, Answer Key, References ML21258A3892021-09-15015 September 2021 Operating Licensing Examination Approval 05000413/2021301 and 05000414/2021301 ML21055A6072021-02-23023 February 2021 301 Exam Corporate Notification Letter ML21019A3932021-01-11011 January 2021 1 GFE Annual Letter for Fy 2021 RA-20-0075, Response to NRC Regulatory Issue Summary 2020-01 Preparation and Scheduling of Operator Licensing Examinations2020-03-16016 March 2020 Response to NRC Regulatory Issue Summary 2020-01 Preparation and Scheduling of Operator Licensing Examinations ML19308A2502019-11-0404 November 2019 301 ADAMS 2D Page 1 Exam Admin Items Normal Release ML19281E0172019-10-0808 October 2019 301 Exam Report Items Delayed Release RO as Given ML19281E0202019-10-0808 October 2019 301 Post Exam Comments IR 05000413/20193012019-09-0303 September 2019 Operator Licensing Written Examination Approval 05000413/2019301 and 05000414/2019301 RA-19-0237, Catawba Station, Shearon Plant, McGuire Station, Oconee Nuclear Station and H.B. Robinson Plant - Response to NRC Regulatory Issue Summary 2019-02 Preparation and Scheduling of Operator Licensing Examinations2019-05-15015 May 2019 Catawba Station, Shearon Plant, McGuire Station, Oconee Nuclear Station and H.B. Robinson Plant - Response to NRC Regulatory Issue Summary 2019-02 Preparation and Scheduling of Operator Licensing Examinations ML17241A2282017-08-29029 August 2017 301 ADAMS2D Page 1 Exam Admin Items Immediate Release ML17241A2162017-08-29029 August 2017 301 ADAMS2B Final Exam Items Delay Release ML17241A2232017-08-29029 August 2017 301 ADAMS 2C Exam Admin Items Delay Release IR 05000413/20173012017-08-15015 August 2017 NRC Operator License Examination Report 05000413/2017301 and 05000414/2017301 ML17215A7792017-08-0303 August 2017 301 Post Exam Comments ML17215A7942017-08-0303 August 2017 301 Exam Report Items RO as Given - Delay Release ML17215A8012017-08-0303 August 2017 301 Exam Report Items SRO as Given - Delay Release ML17192A1792017-07-11011 July 2017 301 Exam Final Items 2B - Delay Release 2 Yrs ML17192A1812017-07-11011 July 2017 301 Exam Administrative Items 2C - Delay Release 2 Yrs ML17178A2942017-06-21021 June 2017 Operator Licensing Written Examination Approval 05000413, 414/2017301 ML17032A2792017-01-27027 January 2017 Annual Letter - Generic Fundamentals Examination (GFE) Section of the Written Operator Licensing Examination for 2017 ML16166A1022016-06-13013 June 2016 301 as Given SRO Written Exam with References and Answer Key ML16166A0992016-06-13013 June 2016 301 as Given RO Written Exam with References and Answer Key ML16166A1062016-06-13013 June 2016 301 Facility Post Exam Comments ML16104A4262016-04-0808 April 2016 March 2016 - Catawba NRC Generic Fundamentals Examination Results ML15356A8282015-12-22022 December 2015 Notification of Licensed Operator Initial Examination 05000413/2016301 and 05000414/2016301 ML15245A3072015-08-31031 August 2015 Initial Exam 2015-301 Final Sim In-Plant JPMs ML15245A3052015-08-31031 August 2015 Initial Exam 2015-301 Final Simulator Scenarios ML15245A3032015-08-31031 August 2015 Initial Exam 2015-301 Final Administrative Documents ML15245A3022015-08-31031 August 2015 Initial Exam 2015-301 Draft Administrative JPMs ML15245A3012015-08-31031 August 2015 Initial Exam 2015-301 Draft Sim In-plant JPMs ML15245A3112015-08-31031 August 2015 Initial Exam 2015-301 Post Exam Comments ML15245A3162015-08-31031 August 2015 Initial Exam 2015-301 General Correspondence ML15245A2932015-08-31031 August 2015 Initial Exam 2015-301 Draft Administrative Documents ML15245A2992015-08-31031 August 2015 Initial Exam 2015-301 Draft Simulator Scenarios ML15245A2942015-08-31031 August 2015 Initial Exam 2015-301 Draft RO Written Exam ML15181A2322015-06-30030 June 2015 Initial Exam 2015-301 Final SRO Written Exam ML15181A2292015-06-30030 June 2015 Initial Exam 2015-301 Final RO Written Exam ML14290A3322014-10-27027 October 2014 301 Post Exam Comments ML14290A3042014-10-27027 October 2014 301 Final Administrative Documents ML14240A6662014-10-27027 October 2014 301 Draft SRO Written Examination 2024-04-02
[Table view] |
Text
UNITED STATES ecember 22, 2015
SUBJECT:
CATAWBA NUCLEAR STATION - NOTIFICATION OF LICENSED OPERATOR INITIAL EXAMINATION NOS. - 05000413/2016301 AND 05000414/2016301
Dear Mr. Henderson:
During a telephone conversation on December 16, 2015, between Mr. Bruce Boyette, Operations Training Instructor, and Mr. Michael Meeks, Senior Operations Engineer, arrangements were made for the administration of licensing examinations at Catawba Nuclear Station. The operating test is scheduled to be administered during the week of May 16, 2016.
The written examination is scheduled to be administered the week of May 23, 2016. The on-site preparatory week is scheduled for the week of April 18, 2016.
As agreed during the telephone conversation, your staff will prepare both the operating test and written examination based on the guidelines in Revision 10 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The U.S. Nuclear Regulatory Commission (NRC) regional office will discuss with your staff any changes that might be necessary before the examinations are administered. Your staff has also agreed to make copies of all examination materials that are necessary for administering the examination.
To meet the above schedule, it will be necessary for your staff to furnish the operating test outline by February 16, 2016. Mr. Meeks provided the written examination outline to your staff in September, 2015. The operating test, written examination, and the supporting reference materials identified in Attachment 3 to ES-201 will be due by March 17, 2016. Pursuant to Title 10, Section 55.40(b)(3), of the Code of Federal Regulations (10 CFR 55.40(b)(3)), an authorized representative of the facility licensee shall approve the outline, examination, and test before they are submitted to the NRC for review and approval. All materials shall be complete and ready-to-use.
We request that any personal, proprietary, sensitive unclassified, or safeguards information in your response be contained in a separate enclosure and appropriately marked. Any delay in receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled. In order to conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-402, and to make the simulation facility available on the dates noted above. In accordance with ES-302, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and levels) generated during the dynamic operating tests until the examination results are final.
Appendix E of NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations and operating tests are being administered.
To permit timely NRC review and evaluation, your staff should submit preliminary reactor operator and senior reactor operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024),
and waiver requests (if any) (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date.
This letter contains information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the OMB under approval number 3150-0018, which expires on April 30, 2016. The public reporting burden for this collection of information is estimated to average 2500 hours0.0289 days <br />0.694 hours <br />0.00413 weeks <br />9.5125e-4 months <br /> per response, including the time for reviewing instructions, gathering and maintaining the data needed, writing the examinations, and completing and reviewing the collection of information. Send comments on any aspect of this collection of information, including suggestions for reducing the burden, to the Information and Records Management Branch (T-6 F33), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet electronic mail at infocollectsresource@nrc.gov; and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and Budget, Washington, DC 20503.
The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection, unless it displays a currently valid OMB control number.
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 the NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room). Thank you for your cooperation in this matter. Mr. Boyette has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the NRC's examination procedures and guidelines, please contact Mr. Meeks at (404) 997-4467, (Internet E-mail:
Michael.Meeks@nrc.gov), or me at (404) 997-4551, (Internet E-mail: Gerald.McCoy@nrc.gov).
Sincerely,
/RA/
Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52 cc: Distribution via Listserv
_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE GJM1 FOR MKM3 GJM1 NAME MMEEKS GMCCOY DATE 12/22/2015 12/22/2015 12/ /2015 12/ /2015 12/ /2015 12/ /2015 12/ /2015 E-MAIL COPY? YES NO YES NO YES YES NO YES NO YES NO YES NO N