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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 ML23307A0772023-11-0303 November 2023 301 ADAMS 2B ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station – Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22089A1642022-03-30030 March 2022 301 ADAMS 2B ML22070B0512022-03-11011 March 2022 301 Post Exam Comments ML22047A1812022-02-0909 February 2022 301 Written Exam Approval Letter ML21062A0762021-03-0303 March 2021 301 Corporate Notification Letter ML21054A1872021-02-23023 February 2021 302 (Normal release)2B Exam Administrative Items ML21054A1272021-02-23023 February 2021 302 Exam Final Items 2A-2 (2 Year Delayed Release) ML21054A1342021-02-23023 February 2021 302 Exam Administrative Items 2A-3 (2 Year Delayed Release) ML21034A6102021-02-0303 February 2021 302 1A Final RO Written Exam & Key (2-Year Delayed Release) ML21034A6142021-02-0303 February 2021 302 1A Final SRO Written Exam & Key (2-Year Delayed Release) ML21019A3932021-01-11011 January 2021 1 GFE Annual Letter for Fy 2021 ML20321A1912020-11-12012 November 2020 302 Retake Exam Approval Letter ML20140A0652020-05-19019 May 2020 ADAMS 2B ML20140A0822020-05-19019 May 2020 ADAMS 2C ML20084L4312020-03-24024 March 2020 2020 NRC Exam Post Exam Comments 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 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 ML18242A6992018-08-30030 August 2018 301 ADAMS2D Page 1 Exam Admin Items ML18136A7762018-05-16016 May 2018 301 Post Exam Comments ML18106A3102018-04-11011 April 2018 William B. McGuire Nuclear Station - Operator Licensing Written Examination Approval 05000369/2018301 and 05000370/2018301 ML17188A2832017-07-0707 July 2017 Mcguire 2016301 Exam Administrative Items - Delay Release 2 Yrs ML17188A2802017-07-0707 July 2017 Exam Final Items - Delay Release 2 Yrs ML17188A2782017-07-0707 July 2017 McGuire 2016301 Exam Draft Items - Delay Release 2 Yrs ML17032A2792017-01-27027 January 2017 Annual Letter - Generic Fundamentals Examination (GFE) Section of the Written Operator Licensing Examination for 2017 ML17023A3442017-01-19019 January 2017 December 2016 - McGuire NRC Generic Fundamentals Examination Results Letter IR 05000369/20163012016-05-31031 May 2016 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2016301 and 05000370/2016301 ML16119A4342016-04-26026 April 2016 301 Post Exam Comments ML16119A4262016-04-26026 April 2016 301 Final RO Written Exam ML16119A4292016-04-26026 April 2016 301 Final SRO Written Exam ML15203B0922015-07-22022 July 2015 301 Final Simulator Scenarios ML15203B1312015-07-22022 July 2015 301 Other Documents for Retention ML15203B1272015-07-22022 July 2015 301 General Correspondence ML15203B1092015-07-22022 July 2015 301 Post Exam Comments ML15203B1002015-07-22022 July 2015 301 Final Administrative JPMs ML15203B0982015-07-22022 July 2015 301 Final Simulator and in Plant JPMs ML15203B0312015-07-22022 July 2015 301 Final Administrative Documents ML15203B0192015-07-22022 July 2015 301 Draft Administrative JPMs ML15203A9822015-07-22022 July 2015 301 Draft Simulator and in Plant JPMs ML15203A9702015-07-22022 July 2015 301 Draft Simulator Scenarios ML15203A9652015-07-22022 July 2015 301 Draft SRO Written Exam ML15203A9582015-07-22022 July 2015 301 Draft RO Written Exam ML15203A9512015-07-22022 July 2015 301 Draft Administrative Documents IR 05000369/20153012015-06-0303 June 2015 Operator License Examination 05000369/2015301 and 05000370/2015301, McGuire, 04/27/2015 - 05/02/2015 ML15141A1732015-05-20020 May 2015 301 Final SRO As-Given Written Exam ML15141A1662015-05-20020 May 2015 301 Final RO As-Given Written Exam 2024-04-02
[Table view] Category:Part 55 Historical Related Material
MONTHYEARML22070B0512022-03-11011 March 2022 301 Post Exam Comments ML15125A4642015-05-0505 May 2015 Initial Exam 2014-301 Draft RO Written Exam 2022-03-11
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ML22070B051 McGuire Nuclear Station ILT 22-1 NRC Exam Post-Exam Comments Operating Exam After conducting a post-examination review of the ILT 22-1 MNS NRC Operating Examination, three items were identified that required post examination comments:
- 1. Admin JPM A1a SRO (SGTL Action Levels):
Explanation:
During administration of SRO JPM A1a, a S/G Tube Leak on 1D S/G was given that reached 138.0 GPD. The original submittal identified Tech Spec 3.4.13 (RCS Operational Leakage) condition B, required actions B1 and B2, as being the applicable Tech Specs for this condition. It has since been determined that Tech Spec 3.4.18 (SG Tube Integrity) Condition B is also applicable for this particular condition in the JPM. The following information is from the Tech Spec 3.4.18 Bases:
A SG tube has tube integrity when it satisfies the SG performance criteria. The SG performance criteria are defined in Specification 5.5.9, Steam Generator (SG) Program, and describe acceptable SG tube performance. The Steam Generator Program also provides the evaluation process for determining conformance with the SG performance criteria.
There are three SG performance criteria: structural integrity, accident induced leakage, and operational LEAKAGE. Failure to meet any one of these criteria is considered failure to meet the LCO.
Based on the fact that the operational LEAKAGE for this JPM exceeded the limit of 135 Gallons Per Day identified in Tech Spec 3.4.13, Tech Spec 3.4.18 LCO is also not met, and Condition B is applicable.
Resolution:
Request that JPM A1a SRO be updated to include required application of T.S.
3.4.18 Condition B following the 1B S/G Tube Leak.
McGuire Nuclear Station ILT 22-1 NRC Exam Post-Exam Comments
- 2. Admin JPM A1a RO (Manual AFD Calculation):
Explanation:
The Task Standard for Admin JPM A1a RO is as follows:
AFD is determined to be within (+) 0.02% of the following values:
PR-41 = -24.80 PR-42 = -16.10%
PR-43 = -25.97%
PR-44 = -17.99%
The operator determines the AFD associated with N41 and N43 exceeds the COLR limit of (-21.60%) at 90% RTP and informs the CRS.
The allowed band was determined based on rounding all calculations to two decimal places.
Applicants performed the calculation correctly. However, the applicants rounded to various significant digits which resulted in answers that were not within the allowed band of the Task Standard (+/-) 0.02.
Resolution:
The facility endorsed position is that the applicants performed the calculations correctly and a new allowed band should be added to the Task Standard.
Request that JPM A1a RO Task Standard be updated to include the new allowed band listed below for each individual detector.
McGuire Nuclear Station ILT 22-1 NRC Exam Post-Exam Comments PR-41 = -24.80% (-23.9 to -25.2)
PR-42 = -16.10% (-14.5 to -16.4)
PR-43 = -25.97% (-24.9 to -29.9)
PR-44 = -17.99% (-17.1 to -19.6)
- 3. Scenario N22-1-1, Event 7 PZR PORV 1NC-34 fails OPEN and Block valve fails OPEN:
Explanation:
The original submittal identified Tech Spec 3.4.11 (PZR PORVS) condition C, required actions C.1, C.2 and C.3 and condition H, required actions H.1, H.2 and H.3 as being the applicable Tech Specs for this failure.
Due to the failure resulting in a small break LOCA, it has since been determined that Tech Spec 3.4.13 (RCS OPERATIONAL LEAKAGE) condition B, required actions B.1 and B.2 and SLC 16.9.7 (STANDBY SHUTDOWN SYSTEM) condition C, required actions C.1 and C.2 are applicable for this particular event.
Resolution:
Request the applicable ES-D-2 be updated to reflect that entry into Tech Spec 3.4.13 (RCS OPERATIONAL LEAKAGE) and SLC 16.9.7 (STANDBY SHUTDOWN SYSTEM) are required.