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Category:Letter type:DCL
MONTHYEARDCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-008, Schedule Considerations for Review of the DCPP License Renewal Application2024-01-17017 January 2024 Schedule Considerations for Review of the DCPP License Renewal Application DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-01-15015 January 2024 Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel DCL-23-122, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-14014 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation DCL-23-128, Emergency Plan Update2023-12-13013 December 2023 Emergency Plan Update DCL-23-125, Core Operating Limits Report for Unit 1 Cycle 252023-12-0606 December 2023 Core Operating Limits Report for Unit 1 Cycle 25 DCL-23-121, Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System2023-11-16016 November 2023 Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023 License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application DCL-2023-520, Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)2023-10-19019 October 2023 Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP) DCL-23-103, Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System2023-10-13013 October 2023 Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System DCL-23-092, Material Status Report for the Period Ending August 31, 20232023-09-28028 September 2023 Material Status Report for the Period Ending August 31, 2023 DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-27027 September 2023 License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors DCL-23-083, Upcoming Meeting with Nuclear Security and Incident Response Staff2023-09-13013 September 2023 Upcoming Meeting with Nuclear Security and Incident Response Staff DCL-23-078, Nuclear Material Transaction Report for New Fuel2023-09-0606 September 2023 Nuclear Material Transaction Report for New Fuel DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application2023-08-16016 August 2023 Withdrawal of Request Regarding Senior Reactor Operator License Application DCL-23-068, Nuclear Material Transaction Report for New Fuel2023-08-0909 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-066, Nuclear Material Transaction Report for New Fuel2023-08-0303 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-065, Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure2023-07-27027 July 2023 Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure DCL-23-064, Nuclear Material Transaction Report for New Fuel2023-07-26026 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-07-13013 July 2023 License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-055, Nuclear Material Transaction Report for New Fuel2023-07-0606 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-042, Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 02023-05-24024 May 2023 Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 0 DCL-23-032, Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program2023-05-22022 May 2023 Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program DCL-23-041, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20222023-05-22022 May 2023 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2022 DCL-23-038, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule2023-05-15015 May 2023 Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Nonradiological Environmental Operating Report DCL-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Radiological Environmental Operating Report DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023 2022 Annual Radioactive Effluent Release Report DCL-2023-512, Submittal of Receiving Water Monitoring Program 2022 Annual Report2023-04-27027 April 2023 Submittal of Receiving Water Monitoring Program 2022 Annual Report DCL-23-035, Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application2023-04-24024 April 2023 Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application DCL-23-028, Technical Specification Bases, Revision 142023-04-24024 April 2023 Technical Specification Bases, Revision 14 DCL-2023-511, Report on Discharge Monitoring for the First Quarter of 20232023-04-20020 April 2023 Report on Discharge Monitoring for the First Quarter of 2023 DCL-23-031, Submittal of Annual Report of Occupational Radiation Exposure for 20222023-04-19019 April 2023 Submittal of Annual Report of Occupational Radiation Exposure for 2022 DCL-23-024, Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System2023-04-0404 April 2023 Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System DCL-23-022, 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant2023-03-29029 March 2023 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant DCL-23-023, Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 22023-03-28028 March 2023 Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 2 DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update2023-03-23023 March 2023 Independent Spent Fuel Storage Installation, Emergency Plan Update DCL-23-020, Responses to NRC Questions Regarding License Renewal Efforts2023-03-17017 March 2023 Responses to NRC Questions Regarding License Renewal Efforts DCL-23-009, Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage2023-02-22022 February 2023 Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage DCL-23-008, Request Regarding Senior Reactor Operator License Application2023-02-22022 February 2023 Request Regarding Senior Reactor Operator License Application DCL-2023-503, Annual Sea Turtle Report2023-01-26026 January 2023 Annual Sea Turtle Report DCL-2023-502, (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring2023-01-18018 January 2023 (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring DCL-22-091, Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage2022-12-20020 December 2022 Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage DCL-22-089, Core Operating Limits Report for Unit 2 Cycle 242022-12-20020 December 2022 Core Operating Limits Report for Unit 2 Cycle 24 DCL-22-085, Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application2022-10-31031 October 2022 Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application DCL-22-041, Site-Specific Decommissioning Cost Estimate, Revision 12022-10-12012 October 2022 Site-Specific Decommissioning Cost Estimate, Revision 1 DCL-22-042, Post-Shutdown Decommissioning Activities Report, Revision 12022-10-12012 October 2022 Post-Shutdown Decommissioning Activities Report, Revision 1 2024-01-29
[Table view] Category:License-Operator
MONTHYEARIR 05000275/20243012023-08-24024 August 2023 Notification of NRC Initial Operator Licensing Examination 05000275/2024301; 05000323/2024301 IR 05000275/20213012023-08-0909 August 2023 Errata for Diablo Canyon Power Plant, Units 1 and 2 - NRC Examination Report 050002752021301 and 050003232021301 ML22342B2442022-12-13013 December 2022 DC-2023-07 Corporate Notification Letter ML21075A2312021-02-12012 February 2021 DC-2021-01 Public Forms DCL-21-017, DC-2021-01 Post Exam Comments Analysis2021-02-12012 February 2021 DC-2021-01 Post Exam Comments Analysis DCL-20-017, 2020-02-Post-Exam Comments2020-03-18018 March 2020 2020-02-Post-Exam Comments ML20106E2762020-03-0606 March 2020 2020-02-Public Forms ML20106F1862020-03-0606 March 2020 2020-02-Form ES-403-1-Written Examination Grading.Pdf ML20106E4702020-03-0606 March 2020 2020-02-FINAL Outlines ML20097A4502020-03-0606 March 2020 2020-02-FINAL Written Exam ML20106E4612020-03-0606 March 2020 2020-02-DRAFT Operating Test Comments ML20097A4462020-03-0606 March 2020 2020-02-FINAL Operating Test ML20106E4632020-03-0606 March 2020 2020-02-DRAFT Operating Test ML20106E4682020-03-0606 March 2020 2020-02-DRAFT Written Exam ML20106E4652020-03-0606 March 2020 2020-02-Draft Outline Comments ML20106E4662020-03-0606 March 2020 2020-02-DRAFT Outlines ML20106E4672020-03-0606 March 2020 2020-02-DRAFT Written Exam Comments DCL-19-027, Supplement to Request for Exemption from Operator Written Examination and Operating Test2019-04-0303 April 2019 Supplement to Request for Exemption from Operator Written Examination and Operating Test ML19011A3712019-01-10010 January 2019 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2019 ML19007A1132019-01-0303 January 2019 NRC Initial Operator Licensing Examination Approval 05000275/2019301; 05000323/2019301 DCL-18-039, Response to NRC Regulatory Issue Summary (RIS) 2018-02, Preparation and Scheduling of Operator Licensing Examinations2018-05-14014 May 2018 Response to NRC Regulatory Issue Summary (RIS) 2018-02, Preparation and Scheduling of Operator Licensing Examinations IR 05000275/20183012018-03-20020 March 2018 NRC Examination Report 05000275/2018301; 05000323/2018301 ML18064A3562018-02-27027 February 2018 DC 2018-01 Post Examination Analysis ML18064A3572018-02-0909 February 2018 DC-2018-01 Draft Written Examination ML18064A3552018-02-0909 February 2018 DC 2018-01 Final Written Examination ML18064A3482018-02-0909 February 2018 DC 2018-01 Draft Operating Test Comments ML18064A3502018-02-0909 February 2018 DC 2018-01 Draft Outline Comments ML18064A3542018-02-0909 February 2018 DC 2018-01 Final Outlines ML18064A3492018-02-0909 February 2018 DC 2018-01 Draft Operating Test ML18064A3512018-02-0909 February 2018 DC 2018-01 Draft Outlines ML18081A9642018-02-0909 February 2018 DC 2018-01 Public Forms ML18064A3522018-02-0909 February 2018 DC 2018-01 Draft Written Examination Comments ML18064A3532018-02-0909 February 2018 DC 2018-01 Final Operating Test ML18019A0162018-01-19019 January 2018 NRC Initial Operator Licensing Examination Approval 05000275/2018301; 05000323/2018301 ML18009A9852018-01-0808 January 2018 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018 DCL-17-042, Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations2017-05-0505 May 2017 Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations ML17103A2512017-04-13013 April 2017 Notification of NRC Initial Operator Licensing Examination 05000275/2018301; 05000323/2018301 ML17013A5482017-01-13013 January 2017 Generic Fundamentals Section of the Written Operator Licensing Examination Scheduled for 2017 ML16321A2432016-10-20020 October 2016 2016-10 Final Written Exam ML16321A2602016-10-20020 October 2016 2016-10 Final Operating Test ML16321A3212016-10-20020 October 2016 2016-10 Post Examination Comments DCL-16-112, Diablo Canyon-2016-10 Post Examination Comments2016-10-20020 October 2016 Diablo Canyon-2016-10 Post Examination Comments ML16336A5752016-10-20020 October 2016 2016-10 Final Outlines ML16336A5722016-10-20020 October 2016 2016-10 Draft Outlines ML16336A5732016-10-20020 October 2016 Diablo-2016-10 Draft Written Examination ML16337A0232016-10-20020 October 2016 2016-10 Public Forms ML16336A5782016-10-20020 October 2016 2016-10 Written Exam Comments ML16336A5762016-10-20020 October 2016 2016-10 Operating Test Comments ML16336A5572016-10-20020 October 2016 2016-10 Draft Operating Test ML16336A5712016-10-14014 October 2016 2016-10 Draft Outline Comments 2023-08-09
[Table view] Category:Part 55 Examination Related Material
MONTHYEARIR 05000275/20243012023-08-24024 August 2023 Notification of NRC Initial Operator Licensing Examination 05000275/2024301; 05000323/2024301 IR 05000275/20213012023-08-0909 August 2023 Errata for Diablo Canyon Power Plant, Units 1 and 2 - NRC Examination Report 050002752021301 and 050003232021301 ML22342B2442022-12-13013 December 2022 DC-2023-07 Corporate Notification Letter ML21075A2312021-02-12012 February 2021 DC-2021-01 Public Forms DCL-21-017, DC-2021-01 Post Exam Comments Analysis2021-02-12012 February 2021 DC-2021-01 Post Exam Comments Analysis DCL-20-017, 2020-02-Post-Exam Comments2020-03-18018 March 2020 2020-02-Post-Exam Comments ML20097A4502020-03-0606 March 2020 2020-02-FINAL Written Exam ML20106E2762020-03-0606 March 2020 2020-02-Public Forms ML20106F1862020-03-0606 March 2020 2020-02-Form ES-403-1-Written Examination Grading.Pdf ML20106E4662020-03-0606 March 2020 2020-02-DRAFT Outlines ML20106E4702020-03-0606 March 2020 2020-02-FINAL Outlines ML20106E4682020-03-0606 March 2020 2020-02-DRAFT Written Exam ML20106E4632020-03-0606 March 2020 2020-02-DRAFT Operating Test ML20106E4672020-03-0606 March 2020 2020-02-DRAFT Written Exam Comments ML20106E4612020-03-0606 March 2020 2020-02-DRAFT Operating Test Comments ML20097A4462020-03-0606 March 2020 2020-02-FINAL Operating Test ML20106E4652020-03-0606 March 2020 2020-02-Draft Outline Comments DCL-19-027, Supplement to Request for Exemption from Operator Written Examination and Operating Test2019-04-0303 April 2019 Supplement to Request for Exemption from Operator Written Examination and Operating Test ML19007A1132019-01-0303 January 2019 NRC Initial Operator Licensing Examination Approval 05000275/2019301; 05000323/2019301 DCL-18-039, Response to NRC Regulatory Issue Summary (RIS) 2018-02, Preparation and Scheduling of Operator Licensing Examinations2018-05-14014 May 2018 Response to NRC Regulatory Issue Summary (RIS) 2018-02, Preparation and Scheduling of Operator Licensing Examinations IR 05000275/20183012018-03-20020 March 2018 NRC Examination Report 05000275/2018301; 05000323/2018301 ML18064A3562018-02-27027 February 2018 DC 2018-01 Post Examination Analysis ML18064A3482018-02-0909 February 2018 DC 2018-01 Draft Operating Test Comments ML18064A3502018-02-0909 February 2018 DC 2018-01 Draft Outline Comments ML18064A3542018-02-0909 February 2018 DC 2018-01 Final Outlines ML18064A3532018-02-0909 February 2018 DC 2018-01 Final Operating Test ML18064A3492018-02-0909 February 2018 DC 2018-01 Draft Operating Test ML18064A3552018-02-0909 February 2018 DC 2018-01 Final Written Examination ML18064A3512018-02-0909 February 2018 DC 2018-01 Draft Outlines ML18064A3522018-02-0909 February 2018 DC 2018-01 Draft Written Examination Comments ML18081A9642018-02-0909 February 2018 DC 2018-01 Public Forms ML18064A3572018-02-0909 February 2018 DC-2018-01 Draft Written Examination ML18019A0162018-01-19019 January 2018 NRC Initial Operator Licensing Examination Approval 05000275/2018301; 05000323/2018301 ML18009A9852018-01-0808 January 2018 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018 DCL-17-042, Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations2017-05-0505 May 2017 Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations ML17103A2512017-04-13013 April 2017 Notification of NRC Initial Operator Licensing Examination 05000275/2018301; 05000323/2018301 ML16337A0232016-10-20020 October 2016 2016-10 Public Forms ML16336A5572016-10-20020 October 2016 2016-10 Draft Operating Test ML16336A5752016-10-20020 October 2016 2016-10 Final Outlines ML16336A5732016-10-20020 October 2016 Diablo-2016-10 Draft Written Examination ML16336A5722016-10-20020 October 2016 2016-10 Draft Outlines ML16336A5782016-10-20020 October 2016 2016-10 Written Exam Comments ML16336A5762016-10-20020 October 2016 2016-10 Operating Test Comments ML16321A3212016-10-20020 October 2016 2016-10 Post Examination Comments DCL-16-112, Diablo Canyon-2016-10 Post Examination Comments2016-10-20020 October 2016 Diablo Canyon-2016-10 Post Examination Comments ML16321A2602016-10-20020 October 2016 2016-10 Final Operating Test ML16321A2432016-10-20020 October 2016 2016-10 Final Written Exam ML16336A5712016-10-14014 October 2016 2016-10 Draft Outline Comments ML16278A6092016-10-0404 October 2016 NRC Initial Operator Licensing Examination Approval 05000275/2016302; 05000323/2016302 ML16272A1472016-09-28028 September 2016 Generic Fundamentals Examination Results Sept 2016 2023-08-09
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Text
Enclosure 3 Contains Personally Identifiable Information -Withhold Under 10 CFR 2.390 When separated Enclosure 3, this document is decontrolled.
Pacific Gas and Electric Company~
Erik M. Werner Diablo Canyon Power Plant Manager P.O. Box 56 Operations Training Avila Beach, CA 93424 805.545.6417 Internal: 691.6417 Fax: 805.545.4907 May 5, 2016 PG&E Letter DCL-16-058 Mr. Christian B. Cowdrey 10 CFR 55.40 U.S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 -Initial Operator Licensing Examination: Post-Examination Materials
Dear Mr. Cowdrey:
In accordance with the guidance provided in Revision 10 of NUREG 1021, "Operator Licensing Examination Standards for Power Reactors," ES-501, Section C.1.a, Pacific Gas and Electric Company (PG&E) has previously provided the following post-examination materials in electronic format:
- Graded Written Examinations
- Applicant's Answer Sheets
- Master Examination and Answer Key
- Questions & Answers Provided to Applicants
- Examination Seating Chart
- Examination Performance Analyses
- Notifications Generated During the Examination
- Simulator Change Request- SCR 2016-046
- Examination Schedule In addition to the electronic examination materials, PG&E is submitting the following materials:
- Enclosure 1 - ES-403-1, "Written Examination Grading Quality Checklist"
- Enclosure 2- ES-403.D.1.b- Recommended Examination Changes
- Enclosure 3 - Completed Form ES-201-3, "Examination Security Agreement" A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Wolf Creek Enclosure 3 Contains Personally Identifiable Information -Withhold Under 10 CFR 2.390 When separated Enclosure 3, this document is decontrolled.
Enclosure 3 Contains Personally Identifiable Information -Withhold Under 10 CFR 2.390 When separated Enclosure 3, this document is decontrolled.
Mr. Christian B. Cowdrey PG&E Letter DCL-16-058 May 5, 2016 Page 2 PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.
If you have any questions, please contact Mr. John M. Becerra, Simulator and Exam Support Supervisor, at 805-545-4006.
Sincerely,
~J~
Erik M. Werner Operations Training Manager M EM6/4539/50817941-28 Enclosures (Post-Examination Materials) cc: John M. Becerra, Simulator and Examination Support Supervisor Edward D. Halpin, Senior Vice President, Generation & Chief Nuclear Officer Abdul Kadir, Operations Initial License Training Supervisor Dennis B. Petersen, Learning Services Director John Reynoso, NRC Acting Senior Resident Inspector Enclosure 3 Contains Personally Identifiable Information -Withhold Under 10 CFR 2.390 When separated Enclosure 3, this document is decontrolled.
High Miss Questions:
All L141 NRC Written exam questions have been reviewed by the Training staff with the candidates. The following question was missed by more than 50% of the candidates and remediated with the class.
Any additional actions are documented at the end of the question.
Question 14: Pass rate: 38.5% (5/13)
Examination Outline Cross-Reference Level RO Tier # 2 026 K4.06 - Knowledge of CSS design feature(s) and/or Group # 1 interlock(s) which provide for the following: Iodine scavenging K/A # 026 K4.06 via the CSS Rating 2.8 Question 14 A design basis LOCA occurs and Containment Spray actuates.
Which of the following completes the statements below:
- 1) If there is at least 60% level in the Sodium Hydroxide tank when containment spray actuates, post-LOCA, the minimum pH in Containment Sump will be .
- 2) For the Containment Spray Eductor valves, CS-8994A and B, to automatically open, an SI signal required.
A. 1) 8.0 2) is (2 selected)
B. 1) 9.5 2 ) is (4 selected)
C. 1) 8.0 2) is NOT D. 1) 9.5 2) is NOT (2 selected)
Proposed Answer: C. 1) 8.0 2) is NOT Explanation:
The NaOH tank is designed to deliver sufficient solution to establish a minimum pH in the Containment sump of 8.0 if at least 60% level is maintained. A full tank with NaOH of 32%
establishes an upper limit in the sump of 9.5. The basic pH helps the spray droplets entrain gaseous fission products, particularly iodine.
An SI signal is required to open the CS pump discharge valves and start the CS pumps. SI is NOT required to open the eductor valves, they open on high-high containment pressure.
A. Incorrect. pH is correct. SI is not required.
B Incorrect. pH is not correct (maximum) and SI is not required. (Both incorrect) C Correct. minimum pH is 8.0 and SI is NOT required.
D Incorrect. pH is incorrect (maximum). SI is NOT required (correct)
Technical
References:
LI-2, OIM page B-6-8 Learning Objective: Explain significant Containment Spray System design features and the importance to nuclear safety. (40802)
Question Source: New Question History: Last Two NRC Exams No Question Cognitive Level: Memory/Fundamental X 10CFR Part 55 Content: 55.41.7
Resolution: Adequately covered in the training material. Question is valid. Reviewed the bases and interlock with the class, no comments.
Additional actions: none
Question 29: Pass rate: 46.1% (6/13)
Examination Outline Cross-Reference Level RO 001 A3.02 Ability to monitor automatic operation of the CRDS, Tier # 2 including: Rod height Group # 2 K/A # 001 A3.02 Rating 3.7 Question 29 Unit 1 control rods are ARO at 230 steps.
A load rejection occurs and control rods begin to insert. When the rod motion stops, the following Control Bank D rod heights are displayed on DRPI:
Group step counters indicate as follows: Group 1 - 189 Group 2 - 190 What is the status of the Control Bank D rod alignment?
A. 1 rod is misaligned, 8 rods are in alignment B. 3 rods are misaligned, 6 rods are in alignment (2 selected)
C. 5 rods are misaligned, 4 rods are in alignment (3 & Labranche)
D. 6 rods are misaligned, 3 rods are in alignment (1 selected)
Proposed Answer: A. 1 rod is misaligned, 8 rods are in alignment Explanation:
Have to determine/know that each indicated position is in 6 step increments and a rod is misaligned if 12 steps from its respective bank step counter F2 is at 192 - 3 steps out B6 is at 204 steps - 14 steps out B10 is at 186 - 6 steps out F14 is at 180 steps -
10 steps out Resolution: Adequately covered in the training material. Question is valid. Reviewed the both the Tech Spec definition and the procedure requirement (STP I-1A, Routine Checks and OP AP-12B, Control Rod Misalignment) with the class, no comments.
Additional actions: none
Question 94: Pass rate: 42.8% (3/7)
Examination Outline Cross-Reference Level SRO Tier # 3 G2.1.37 - Knowledge of procedures, guidelines, or Group # 1 limitations associated with reactivity management. K/A # G2.1.37 Rating 4.6 Question 94 According to OP1.ID3, Reactivity Management, which of the following evolutions require a reactivity brief:
- 1. Transferring letdown filters
- 2. Starting or stopping a circulating water pump
- 3. Placing a cation bed back in service last used five days ago A. 1 and 2, only B. 1 and 3, only (1 selected)
C. 2 and 3, only (1 selected)
D. 1 and 2 and 3 (2 selected)
Proposed Answer:
A. 1 and 2 only Explanation:
A. Correct. placing a cation bed in service when last placed in service less than a week before does not require a reactivity brief. The other evolutions do.
B. Incorrect. If a cation bed has been out of service for less than a week, no brief is required C. Incorrect. Cation bed does not require a brief.
D. Incorrect. Cation bed does not require a brief.
NOTE: all answers are used 3 times, thinking any one is not done, will rule out 3 answers, but you have to know which one does not. Otherwise, all 3 require a brief would seem the logical answer.
Technical
References:
OP1.ID3, step 5.2.4 References to be provided to applicants during exam: none Learning Objective: 67250 -Describe reactivity management requirements and expectations Resolution: Adequately covered in the training material. Question is valid. Reviewed the section of OP1.ID3 with the class, no comments.
Additional actions: none