CNL-20-077, Supplement to Watts Bar Nuclear Plant (WBN) Unit 1 - American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative IST-RR-8

Supplement to Watts Bar Nuclear Plant (WBN) Unit 1 - American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative IST-RR-8

ML20294A422
Person / Time
Site:	Watts Bar
Issue date:	10/20/2020
From:	Jerrica Johnson Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-20-077, EPID L-2020-LLR-0161
Download: ML20294A422 (7)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-20-077 October 20, 2020 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390

Subject:

Supplement to Watts Bar Nuclear Plant (WBN) Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative IST-RR-8

Reference:

TVA letter to NRC, CNL-20-052, Watts Bar Nuclear Plant (WBN) Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative IST-RR-8, dated September 1, 2020 (ML20245E518) (EPID L-2020-LLR-0161)

In the referenced letter, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, "Codes and Standards," paragraph (z)(2), Tennessee Valley Authority (TVA) requested an alternative to the inservice testing requirements of the American Society of Mechanical Engineers Operation and Maintenance Code, Subsection ISTB-6200(a), Corrective Action, which mandates that when a measured performance test parameter of an lnservice Testing Program pump falls within the alert range in Table ISTB-5121-1, Centrifugal Pump Test Acceptance Criteria, the frequency of testing specified in Subsection ISTB-3400, Frequency of Inservice Tests, shall be doubled. This alternative request applies to the Watts Bar Nuclear Plant (WBN) Unit 1 residual heat removal (RHR) pump 1B-B.

to the referenced letter contained the following commitments to be provided to the Nuclear Regulatory Commission (NRC) by October 30, 2020.

x TVA will submit to the NRC the results of the follow-up oil analysis for RHR pump 1B-B.

x TVA will submit to the NRC the results of the next quarterly Group A test for RHR pump 1B-B.

U.S. Nuclear Regulatory Commission CNL-20-077 Page 2 October 20, 2020 Accordingly, Enclosure 1 to this submittal provides the results of the follow-up oil analysis for RHR pump 1B-B. The oil analysis determined that viscosity, wear metals, and chemistry values were within normal operating ranges. No moisture was noted within this system. Enclosure 2 to this submittal provides the results of the quarterly Group A test for RHR pump 1B-B performed on August 26, 2020.

There are no new regulatory commitments associated with this submittal. Please address any questions regarding this submittal to Gordon Williams, Senior Manager, Fleet Licensing (Acting), at (423) 751-2687.

Respectfully, Jonathan T. Johnson Director, Nuclear Regulatory Affairs (Acting)

Enclosures:

1. Results of the Follow-up Oil Analysis for RHR pump 1B-B

2. Results of the Quarterly Group A test for RHR pump 1B-B cc (Enclosures):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant CNL-20-077 Results of the Follow-up Oil Analysis for RHR pump 1B-B

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Microscopic Analysis Report R&G Laboratories, Inc.

Laboratory Services Division Tampa, FL (813)643-3513 Particle Rating Max Size (m) 12 23 1

47 Key R: Normal Rubbing W ear C: Cutting W ear S: Sliding W ear L: Rolling W ear X: Red Oxides B: Black Oxides A: Abrasives O: Corrosive W ear M : M olybdenum Disulfide 1: Least Severe 4: M ost Severe 4

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Ferrous Based Nonferrous Based Contaminants Customer Name:

TVA-WATTS BAR NUCLEAR PLANT Sample Date:

08/27/20 Reservoir

Description:

1-MTR-74-20B OB Lab Number:

759507 Discussion of Results Ferrogram Interpretation: There were extreme amounts of abrasive/dust/dirt particles and moderate amounts of ferrous rubbing wear particles present on the slide. Also, there were a few ferrous cutting wear particles, spherical metallic wear particles, and fiber particles observed on the slide. The presence of cutting wear particles suggests possible misalignment and/or abrasive contamination. The presence of spherical metallic wear particles suggests possible rolling bearing fatigue and/or welding or grinding processes (contamination). The morphology of the abrasive/dust/dirt particles suggests possible contamination of the sample and/or reservoir from an external source.

Microscopic Analysis Figure 1: Ferrous Cutting Wear Particles, Ferrous Rubbing Wear Particles, and Abrasive/Dust/Dirt Particles at the Head of the Slide (Magnification 500X).

Figure 2: Ferrous Rubbing Wear Particles and Abrasive/Dust/Dirt Particles at the End of the Slide (Magnification 500X).

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CNL-20-077 E2-1 Results of the Quarterly Group A test for RHR pump 1B-B On August 26, 2020, a routine quarterly Group A pump test was performed. Overall peak vibration levels exhibited a greater value at two location/directions, a reduction at two location/directions, and one location/direction that was essentially unchanged. All location/directions remain below their respective Alert Limit.