ML22070B051

301 Post Exam Comments

ML22070B051
Person / Time
Site:	Mcguire, McGuire
Issue date:	03/11/2022
From:	NRC/RGN-II
To:
References
Download: ML22070B051 (3)

Text

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.