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Category:Letter
MONTHYEARML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program IR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23222A2762023-08-10010 August 2023 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canister Identification Numbers AMZDFX175 and AMZDFX176 and Vertical Concrete Cask Identification Numbers AMZDNE175, and AMZDNE176 ML23199A2942023-08-0909 August 2023 Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 ML23207A2482023-07-26026 July 2023 License Renewal Pressurizer Surge Line Inspection ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owners Activity Report Number 2R24 ML23166B0832023-07-0505 July 2023 Independence Spent Fuel Storage Installation - Issuance of Exemption ML23181A1602023-06-30030 June 2023 2 to Updated Final Safety Analysis Report, and Revision 3 to Operations Quality Assurance Program Description ML23180A2222023-06-29029 June 2023 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) - Operating, TS 3.5.2, Safety Injection Tanks (Sits) - Shutdown, and TS 3.6.5, Containment Air Temperature ML23181A0772023-06-29029 June 2023 Program Review - Simulator Testing Methodology ML23157A1292023-06-0101 June 2023 Annual Report of Guarantee of Payment of Deferred Premium ML23144A3722023-05-24024 May 2023 Response to Regulatory Issue Summary (RIS) 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23143A3912023-05-23023 May 2023 Independent Spent Fuel Storage Installation - Request for Exemption from NAC-MAGNASTOR Certificate of Compliance 72-1031 - Cask Lid Batch 3 Design Requirements ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23132A3392023-05-12012 May 2023 Application to Revise Technical Specifications 3.3.11 to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23128A0692023-05-0808 May 2023 Notification of Biennial Problem Dentification and Resolution Inspection and Request for Information ML23122A1822023-04-29029 April 2023 Transmittal of Technical Specification Bases Revision 76 ML23122A1912023-04-29029 April 2023 Unit 1 Core Operating Limits Report Revision 32, Unit 2 Core Operating Limits Report Revision 25, Unit 3 Core Operating Limits Report Revision 31 ML23116A2772023-04-26026 April 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2022 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 ML23115A4982023-04-25025 April 2023 2022 Annual Environmental Operating Report IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML23103A4642023-04-13013 April 2023 Annual Radiological Environmental Operating Report 2022 ML23103A4312023-04-13013 April 2023 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022 IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 ML23102A3292023-04-12012 April 2023 Application for Authorized Use of Mururoa Single-Use, Supplied Air Suits, Models V4F1 and MTH2 ML23102A3242023-04-12012 April 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-107-A, Separate Control Rods That Are Untrippable Versus Inoperable ML23089A4002023-03-30030 March 2023 Consolidated Decommissioning Funding Status Report - 2022 ML23088A4012023-03-30030 March 2023 Project Manager Assignment IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) ML23080A3002023-03-21021 March 2023 Present Levels of Financial Protection 2024-01-19
[Table view] Category:License-Operator
MONTHYEARIR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23151A6492023-05-11011 May 2023 11-PV-2023-05 Public Forms ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML22196A3782022-07-15015 July 2022 Notification of NRC Initial Operator Licensing Examination 05000528/2023301; 05000529/2023301; 05000530/2023301 ML22143A9892022-05-19019 May 2022 PV-2022-05-Post Exam Comments ML22178A1772022-04-12012 April 2022 PV-2022-05-Public Forms ML23193A8502022-04-12012 April 2022 PV-2022-05-Form 2.3-1 Examination Outline Quality Checklist ML22070A1382022-03-10010 March 2022 Response to Regulatory Issue Summary (RIS) 2022-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20213012021-06-21021 June 2021 NRC Initial Examination Report 05000528/2021301, 05000529/2021301, and 05000530/2021301 ML21160A0832021-06-21021 June 2021 NRC Initial Examination Report 05000528/2021301, 05000529/2021301, and 05000530/2021301 ML21147A5452021-05-0606 May 2021 04 Public Forms ML21147A5442021-05-0606 May 2021 04 Post Examination Analysis ML21106A3042021-04-16016 April 2021 Response to Regulatory Issue Summary (RIS) 2021-01, Preparation and Scheduling of Operator Licensing Examinations ML21106A2842021-04-14014 April 2021 Generic Fundamentals Examination Results March 2021 ML21020A0982020-12-10010 December 2020 2020-11 Draft Operating Test Comments ML21020A0942020-12-10010 December 2020 11 Draft Written Examination ML21020A1032020-12-10010 December 2020 11 Post Examination Analysis ML21020A1042020-12-10010 December 2020 11 Public Forms ML21020A0932020-12-10010 December 2020 11 Draft Written Examination Comments ML21020A0962020-12-10010 December 2020 11 Final Outlines ML21020A0952020-12-10010 December 2020 11 Final Operating Test ML21020A0902020-12-10010 December 2020 11 Draft Operating Test ML21020A0972020-12-10010 December 2020 11 Final Written Examination ML21020A0912020-12-10010 December 2020 11 Draft Outline Comments ML21020A0922020-12-10010 December 2020 11 Draft Outlines ML20325A3682020-11-20020 November 2020 NRC Initial Operator Licensing Examination Approval 05000528/2020301; 05000529/2020301; 05000530/2020301 ML20199M3832020-07-17017 July 2020 Response to Regulatory Issue Summary (RIS) 2020-01, Preparation and Scheduling of Operator Licensing Examinations ML20003E2762019-10-11011 October 2019 PV-2019-10 Post Exam Comments and Analysis ML19273C8072019-09-30030 September 2019 NRC Initial Operator Licensing Exam Approval Letter 05000528/529/530/2019301 ML19135A3352019-05-15015 May 2019 Response to Regulatory Issue Summary (RIS) 2019-02, Preparation and Scheduling of Operator Licensing Examinations ML20042C1192019-03-12012 March 2019 PV-2019-10 Public Forms ML19045A3732019-02-12012 February 2019 March 2019 GFE Cover Letter Riv ML19011A3712019-01-10010 January 2019 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2019 ML18284A4942018-09-25025 September 2018 NRC Retake Initial Operator Licensing Examination Approval 05000528/2018302, 05000529/2018302 and 05000530/2018302 ML18184A3552018-06-29029 June 2018 Response to Regulatory Issue Summary (RIS) 2018-02, Preparation and Scheduling of Operator Licensing Examinations - Update ML18122A3722018-05-0101 May 2018 Response to Regulatory Issue Summary (RIS) 2018-02, Preparation and Scheduling of Operator Licensing Examinations ML18086B0842018-02-16016 February 2018 Facility Cover Letter - Riv - March 2018 - GFE ML18009A9852018-01-0808 January 2018 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018 ML17124A2082017-05-0404 May 2017 Response to Regulatory Issue Summary (RIS) 2017-03, Preparation and Scheduling of Operator Licensing Examinations ML17013A5482017-01-13013 January 2017 Generic Fundamentals Section of the Written Operator Licensing Examination Scheduled for 2017 ML16321A4722016-11-0303 November 2016 10 Draft Written Exam Pedigree ML16321A4632016-11-0303 November 2016 Palo VERDE-2016-10 Final Written Exam ML16321A4682016-11-0303 November 2016 2016-10 Draft Outlines ML16321A4662016-11-0303 November 2016 Palo VERDE-2016-10 Post-Exam Comments ML16321A4652016-11-0303 November 2016 Palo VERDE-2016-10 Final Operating Test ML16321A4692016-11-0303 November 2016 2016-10-DRAFT Outline Comments Rev 2 with PVNGS Response ML16321A4832016-11-0303 November 2016 Palo VERDE-2016-10 Draft Operating Test ML16321A4862016-11-0303 November 2016 Palo VERDE-2016-10 Draft Operating Test Comments ML16321A4882016-11-0303 November 2016 Palo VERDE-2016-10 Final Outlines 2023-09-06
[Table view] Category:Part 55 Examination Related Material
MONTHYEARIR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23151A6492023-05-11011 May 2023 11-PV-2023-05 Public Forms ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML22196A3782022-07-15015 July 2022 Notification of NRC Initial Operator Licensing Examination 05000528/2023301; 05000529/2023301; 05000530/2023301 ML22143A9892022-05-19019 May 2022 PV-2022-05-Post Exam Comments ML23193A8502022-04-12012 April 2022 PV-2022-05-Form 2.3-1 Examination Outline Quality Checklist ML22178A1772022-04-12012 April 2022 PV-2022-05-Public Forms ML22070A1382022-03-10010 March 2022 Response to Regulatory Issue Summary (RIS) 2022-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20213012021-06-21021 June 2021 NRC Initial Examination Report 05000528/2021301, 05000529/2021301, and 05000530/2021301 ML21160A0832021-06-21021 June 2021 NRC Initial Examination Report 05000528/2021301, 05000529/2021301, and 05000530/2021301 ML21147A5452021-05-0606 May 2021 04 Public Forms ML21147A5442021-05-0606 May 2021 04 Post Examination Analysis ML21106A3042021-04-16016 April 2021 Response to Regulatory Issue Summary (RIS) 2021-01, Preparation and Scheduling of Operator Licensing Examinations ML21020A1032020-12-10010 December 2020 11 Post Examination Analysis ML21020A1042020-12-10010 December 2020 11 Public Forms ML21020A0972020-12-10010 December 2020 11 Final Written Examination ML21020A0952020-12-10010 December 2020 11 Final Operating Test ML21020A0942020-12-10010 December 2020 11 Draft Written Examination ML21020A0932020-12-10010 December 2020 11 Draft Written Examination Comments ML21020A0912020-12-10010 December 2020 11 Draft Outline Comments ML21020A0982020-12-10010 December 2020 2020-11 Draft Operating Test Comments ML21020A0962020-12-10010 December 2020 11 Final Outlines ML21020A0922020-12-10010 December 2020 11 Draft Outlines ML21020A0902020-12-10010 December 2020 11 Draft Operating Test ML20325A3682020-11-20020 November 2020 NRC Initial Operator Licensing Examination Approval 05000528/2020301; 05000529/2020301; 05000530/2020301 ML20199M3832020-07-17017 July 2020 Response to Regulatory Issue Summary (RIS) 2020-01, Preparation and Scheduling of Operator Licensing Examinations ML20003E2762019-10-11011 October 2019 PV-2019-10 Post Exam Comments and Analysis ML19273C8072019-09-30030 September 2019 NRC Initial Operator Licensing Exam Approval Letter 05000528/529/530/2019301 ML19135A3352019-05-15015 May 2019 Response to Regulatory Issue Summary (RIS) 2019-02, Preparation and Scheduling of Operator Licensing Examinations ML20042C1192019-03-12012 March 2019 PV-2019-10 Public Forms ML18284A4942018-09-25025 September 2018 NRC Retake Initial Operator Licensing Examination Approval 05000528/2018302, 05000529/2018302 and 05000530/2018302 ML18184A3552018-06-29029 June 2018 Response to Regulatory Issue Summary (RIS) 2018-02, Preparation and Scheduling of Operator Licensing Examinations - Update ML18122A3722018-05-0101 May 2018 Response to Regulatory Issue Summary (RIS) 2018-02, Preparation and Scheduling of Operator Licensing Examinations ML18009A9852018-01-0808 January 2018 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018 ML17124A2082017-05-0404 May 2017 Response to Regulatory Issue Summary (RIS) 2017-03, Preparation and Scheduling of Operator Licensing Examinations ML16321A4652016-11-0303 November 2016 Palo VERDE-2016-10 Final Operating Test ML16321A4632016-11-0303 November 2016 Palo VERDE-2016-10 Final Written Exam ML16321A4832016-11-0303 November 2016 Palo VERDE-2016-10 Draft Operating Test ML16321A4682016-11-0303 November 2016 2016-10 Draft Outlines ML16321A4722016-11-0303 November 2016 10 Draft Written Exam Pedigree ML16321A4792016-11-0303 November 2016 2016-10 Draft Written Exam Comments ML16321A4862016-11-0303 November 2016 Palo VERDE-2016-10 Draft Operating Test Comments ML16340B6372016-11-0303 November 2016 Palo VERDE-2016-10 Public Forms ML16321A4662016-11-0303 November 2016 Palo VERDE-2016-10 Post-Exam Comments ML16321A4692016-11-0303 November 2016 2016-10-DRAFT Outline Comments Rev 2 with PVNGS Response ML16321A4882016-11-0303 November 2016 Palo VERDE-2016-10 Final Outlines ML16293A1212016-10-18018 October 2016 2016-11-Examination Approval ML16203A1502016-07-15015 July 2016 Response to Regulatory Issue Summary (RIS) 2016-09, Preparation and Scheduling of Operator Licensing Examinations ML16089A0712016-03-29029 March 2016 Generic Fundamentals Examination Results for March 9, 2016 2023-09-06
[Table view] |
Text
PVNGS 2013 LOIT Exam Analysis
(> 50% failure Rate)
Q35 During the exam review there was a short discussion of surveillance testing of valves.
The majority of those who missed the question chose distracter B, green light on. It was pointed out that during stroke testing; valve indication goes from a single light to dual indication to single light representing valve position. Everyone agreed that the question is correct, fair and relevant.
No issues were identified with applicant knowledge or testing.
The question will remain as written.
Q91 (SRO 16) During the exam review there was a discussion about this question, the majority who missed the question chose distracter D, Trip the Reactor. This would have been the correct answer if countrate doubled 4 times (stated in stem) at Hold Point 1 or 2. Many of the applicants assumed that CR had doubled 4 times prior to Hold Point 3 and therefore chose D. Some also stated that they were reluctant to pick an answer that indicated nothing was wrong, continue the startup. The question appears to be somewhat confusing but it was agreed that for the conditions given B was in fact the correct answer. Based on the discussions we are going to make the following revisions:
- 1. Change the question stem such that the two ACPs are outside of the minus 500 pcm position making D the correct answer.
- 2. Create a new question with the correct answer being that the Startup may continue but use actual plant data provided by Reactor Engineering to create the stem.
No issues were identified with applicant knowledge or testing.
80 (SRO 5) ID: Q44153 Points: 1.00 With regards to the (EW) Essential Cooling Water system in mode 1, which of the following is the correct application of Tech Specs?
(1) When cross connected to the Nuclear Cooling Water (NCW) system, EW is INOPERABLE...
(2) When cross connected to the Fuel Pool Cooling, EW is INOPERABLE...
A. (1) and remains inoperable while cross connected.
(2) and remains inoperable while cross connected.
B. (1) and remains inoperable while cross connected.
(2) but operability can be restored if a flow balance is performed because the EW system is sized to supply the SDC heat exchanger, Essential Chiller and the SFP heat exchanger.
C. (1) but operability can be restored if a flow balance is performed because the EW system is sized to supply the NCW priority loads and the SDC heat exchanger.
(2) and remains inoperable while cross connected.
D. (1) but operability can be restored if a flow balance is performed because the EW system is sized to supply the NCW priority loads and the SDC heat exchanger.
(2) but operability can be restored if a flow balance is performed because the EW system is sized to supply the SDC heat exchanger, Essential Chiller and the SFP heat exchanger.
Answer: B Justification:
A Wrong Operability is not restored for EW when cross tied to NC even if a flow balance is B Correct completed. EW is not sized to supply both NC priority loads and the SDC heat exchanger.
C Wrong EW is sized to carry the SFP heat exchanger, Essential chiller and the SDC heat D Wrong exchanger.
Operability is restored if a flow balance is completed after cross ting to Fuel Pool Cooling.
Distracters A and D are plausible because one part of the answer is correct.
Distracter C is plausible because the answers are true for the opposite condition Proposed reference to be provided: None Technical
Reference:
40OP-9EW01, Essential Cooling Water K&A: Ability to explain and apply system limits and precautions. Loss of Nuclear Service Water OPTRNG_EXAM Page: 1 of 2 24 September 2013
Question 80 Info Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 44048 User-Defined ID: Q44048 Topic: Q44153 explanation of notes and cautions in the EW procedure RO 3.8 SRO 4.0 KA# 2.1.32 Revision 09/24/2013 rev; 0 Replaces Q44048 Question 80 Table-Item Links Q - 10CFR Sections 55.43 (2) Facility operating limitations in the technical specifications and their bases.
Q - Cognitive Level Memory Q - Question Source New Q - SRO Exam SRO Exam 2013 O - SRO Tier Group Designation Tier 1 Group 1 Associated objective(s):
describe how flow to the RCPs is increased after EW has been cross tied OPTRNG_EXAM Page: 2 of 2 24 September 2013
80 (SRO 5) ID: Q44153 Points: 1.00 With regards to the (EW) Essential Cooling Water system in mode 1, which of the following is the correct application of Tech Specs?
(1) When cross connected to the Nuclear Cooling Water (NCW) system, EW is INOPERABLE...
(2) When cross connected to the Fuel Pool Cooling, EW is INOPERABLE...
A. (1) and remains inoperable while cross connected.
(2) and remains inoperable while cross connected.
B. (1) and remains inoperable while cross connected.
(2) but operability can be restored if a flow balance is performed because the EW system is sized to supply the SDC heat exchanger, Essential Chiller and the SFP heat exchanger.
C. (1) but operability can be restored if a flow balance is performed because the EW system is sized to supply the NCW priority loads and the SDC heat exchanger.
(2) and remains inoperable while cross connected.
D. (1) but operability can be restored if a flow balance is performed because the EW system is sized to supply the NCW priority loads and the SDC heat exchanger.
(2) but operability can be restored if a flow balance is performed because the EW system is sized to supply the SDC heat exchanger, Essential Chiller and the SFP heat exchanger.
Answer: A&B Justification:
A Correct Originally B was identified as the only correct answer but after review it has been B Correct determined that A is also correct.
C Wrong Given only conditions stated in the stem, A and B are correct answers.
D Wrong EW is INOPERABLE when cross connected to either the NC or SFP cooling systems. EW may be restored to OPERABLE when connected to SFP cooling if a flow balance is performed. The stem makes no reference to a flow balance being performed.
A would have been wrong if the statement read (1) and remains inoperable when cross connected regardless of performing a flow balance.
B is still correct (1) is correct and (2) is correct in stating that operability is restored if a flow balance is performed.
C & D are both still wrong because (1) is a wrong statement for both.
Operability is not restored for EW when cross tied to NC even if a flow balance is completed. EW is not sized to supply both NC priority loads and the SDC heat exchanger. EW is sized to carry the SFP heat exchanger, Essential chiller and the SDC heat exchanger. Operability is restored if a flow balance is completed after cross ting to Fuel Pool Cooling.
Distracters D are plausible because one part of the answer is correct.
Distracter C is plausible because the answers are true for the opposite condition OPTRNG_EXAM Page: 1 of 2 24 September 2013
Proposed reference to be provided: None Technical
Reference:
40OP-9EW01, Essential Cooling Water K&A: Ability to explain and apply system limits and precautions. Loss of Nuclear Service Water Question 80 Info Points: 1.00 Time to Complete: 3 Difficulty: 3.00 System ID: 44048 User-Defined ID: Q44048 Q44153 explanation of notes and cautions in the EW Topic:
procedure RO 3.8 SRO 4.0 KA# 4.2 062 2.1.32 Revision 09/24/2013 rev; 0 - Replaces Q44048 11/04/2013 rev: 1 - identifies two correct answers Question 80 Table-Item Links Q - 10CFR Sections 55.43 (2) Facility operating limitations in the technical specifications and their bases.
Q - Cognitive Level Memory Q - Question Source New Q - SRO Exam SRO Exam 2013 O - SRO Tier Group Designation Tier 1 Group 1 Associated objective(s):
describe how flow to the RCPs is increased after EW has been cross tied OPTRNG_EXAM Page: 2 of 2 24 September 2013
PVNGS NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 27 of 118 Revision Essential Cooling Water System (EW) Train A 40OP-9EW01 22 NOTE
___ Cross tieing Essential Cooling Water to Spent Fuel Pool Cooling impacts OPERABILITY of Essential Cooling Water until a flow balance has been completed.
___ 6.6.9 Open EWA-HCV-67, A Essential Cooling Water Isol Valve From SFP Heat Exchanger.
___ 6.6.10 Open EWA-HCV-133, A ECW Isolation Valve To Spent Fuel Pool Heat Exchanger.
___ 6.6.11 Monitor EWN-LG-0089, A ECW Surge Tank Level Sightglass, for a stable level between 20 and 50 inches during venting.
(120 Aux Bldg, West)
___ 6.6.12 Perform the following to vent from NCA-V203, Vent Vlv on Fuel Pool HT EX A Inlet Line:
(100 Aux Bldg South of ECW HX A)
___ 6.6.12.1 Install a vent hose at NCA-V203, Vent Vlv on Fuel Pool HT EX A Inlet Line.
___ 6.6.12.2 Vent from NCA-V203, Vent Vlv on Fuel Pool HT EX A Inlet Line.
___ 6.6.12.3 WHEN venting from NCA-V203, Vent Vlv on Fuel Pool HT EX A Inlet Line, is complete, THEN close NCA-V203, Vent Vlv on Fuel Pool HT EX A Inlet Line.
___ 6.6.12.4 Remove vent hose from NCA-V203, Vent Vlv on Fuel Pool HT EX A Inlet Line.
___ 6.6.12.5 Install a pipe cap at NCA-V203, Vent Vlv on Fuel Pool HT EX A Inlet Line.
___ 6.6.13 Perform the following to vent from NCA-V205, Vent Vlv on Fuel Pool HX A Dischg Line:
(100 Aux Bldg South of ECW HX A)
___ 6.6.13.1 Install a vent hose at NCA-V205, Vent Vlv on Fuel Pool HX A Dischg Line.
___ 6.6.13.2 Vent from NCA-V205, Vent Vlv on Fuel Pool HX A Dischg Line.
___ 6.6.13.3 WHEN venting from NCA-V205, Vent Vlv on Fuel Pool HX A Dischg Line, is complete, THEN close NCA-V205, Vent Vlv on Fuel Pool HX A Dischg Line.
PVNGS NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 36 of 118 Revision Essential Cooling Water System (EW) Train A 40OP-9EW01 22 Required Positioned Verified Number Name Location Position By By NCN-FI-256, equalizing 100' Fuel Bldg NA Open valve FPHX A NCN-FI-256, local low 100' Fuel Bldg NA Closed side isolation valve FPHX A NCA-V109 NCN-FI-256 Root 100' Fuel Bldg Closed Isolation FPHX A NCA-V110 NCN-FI-256 Root 100' Fuel Bldg Closed Isolation FPHX A N/A (component) NOT manipulated Date Completed:
___ 6.7.17 Ensure restoration of components controlled by 40AC-0ZZ06, Locked Valve, Breaker, and Component Control, is documented per 40DP-9OP19, Locked Valve, Breaker and Component Tracking.
___ 6.7.18 Notify the SM/CRS of BOTH of the following:
- Train A EW flow is balanced
- Train A EW may be evaluated for OPERABILITY End of Section 6.7
PVNGS NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 44 of 118 Revision Essential Cooling Water System (EW) Train A 40OP-9EW01 22 6.9 Placing EW Train A In Service On Nuclear Cooling Water System
6.9.1 Purpose
EW system may be lined up to supply ALL of the following Nuclear Cooling Water (NC) loads:
- Control Element Drive Motor Air Cooling Units (CEDM ACUs)
___ 6.9.2 The following Prerequisites are met:
___ 6.9.2.1 Nuclear Cooling Water pump handswitches are in pull-to-lock per 40OP-9NC01, Nuclear Cooling Water (NC)
___ 6.9.2.2 Train A Essential Spray Pond is in operation per 40OP-9SP01, Essential Spray Pond (SP) Train A
___ 6.9.2.3 Train A EW System is aligned per ONE of the following:
- Section 6.1, Placing EW Train A In Standby Operation
- Section 6.3, Manual Operation of EW Train A
- Section 6.4, Returning EW Train A to Standby After Running
___ 6.9.3 Initial Condition: REP has been issued if required.
___ 6.9.4 Check Train B Safety Equipment is OPERABLE.
CAUTION
___ Cross-connecting EW and NC impacts OPERABILITY of Train A EW and supported systems.
___ 6.9.5 Close NCN-UV-99 using handswitch NCN-HS-99, Nuclear Clg Wtr Cntmt Hdr Return Vlv UV-99.
___ 6.9.6 IF EW A System is NOT in operation, There are no THEN perform the following to start Essential Cooling Waterrecovery Pump A:steps if EW is aligned to support the NC system
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 44 of 71 Revision 40DP-9AP17 Standard Appendices Technical Guideline 25 Appendix 63 Cross-connect EW to NC This appendix will be used during an event where the Nuclear Cooling Water Pumps are lost and Essential Cooling Water is required to supply cooling water to the Nuclear Cooling Water priority loads.
Essential Cooling Water flow will be throttled down at the SDHX outlet in order to force flow through the NC piping. Prior to throttling flow, the normal chiller NC outlet valves for the B, C and E02 chillers are closed or checked closed to maximize flow through the RCP seals. This is based on the assumption that this appendix is being used during a Loss of Offsite Power and the A Normal Chiller will be started.
Flow should be throttled until the RCP seal cooler alarms are clear with the NC outlet valve for the A Normal Chiller open. Total EW system flow as read on B02 should not be allowed to go below 8500 gpm.
Attachment 63-A directsReasons actions to for cross-connect Train A Essential Cooling Water to Operability/Inop Nuclear Cooling Water and throttle flow through the Shutdown Cooling Heat Exchanger.
when EX is cross connected to Attachment 63-B directsNCW actions ortoSFP cross-connect cooling Train B Essential Cooling Water to Nuclear Cooling Water and throttle flow through the Shutdown Cooling Heat Exchanger.
Appendix 64 Align EW to SFP The NC system is the normal cooling medium for the normal fuel pool heat exchangers.
On a LOOP, the NC system is lost and will cause the spent fuel pool temperature to rise.
Essential cooling water is the alternate cooling water for the fuel pool heat exchangers.
The design of the EW system is such that one train of EW is sized to supply the SDCHX, the essential chiller and one SFP heat exchanger. The train of EW that supplies nuclear cooling priority loads is sized to supply only these loads.
Attachment 64-A directs actions to align Train A Essential Cooling Water to the Train A Spent Fuel Pool Heat Exchanger. Direction is also given to throttle EW System flow and Essential Chiller EW flow.
Attachment 64-B directs actions to align Train B Essential Cooling Water to the Train B Spent Fuel Pool Heat Exchanger. Direction is also given to throttle EW System flow and Essential Chiller EW flow.
Values for EW flow settings are based on EW flows directed by the Essential Cooling Water System Normal Operating Procedures 40OP-9EW01 and 40OP-9EW02 which satisfy requirements of the EW Design Basis Manual and account for instrument uncertainties.
EW flow to the Essential Chillers is normally controlled by the Refrigerant Head Pressure Control Valve, However, when Spray Pond Temperature is 65 °F or more, manual adjustment of EW flow is needed to ensure design flow requirements are satisfied.
Note for the exam file:
The staff at Palo Verde did not include the post exam comments for Question 80 in the post exam comments file. It was sent via e-mail and the body of their discussion on the recommended change to accept both distracter A and original answer B as correct answers for this question is contained in the pedigree section of the modified Q80 worksheet. Both the original question worksheet as administered (rev 0) and the proposed Q80 worksheet (rev 1) with this explanation on why the staff at PV believe both answers are correct are contained in this document for clarity and also included in the exam report as required by NUREG-1021.
Kelly Clayton Chief Examiner