ML21218A147

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August 5, 2021 N-769 Relief Pre-Submittal Meeting Summary
ML21218A147
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 08/11/2021
From: Michael Wentzel
Plant Licensing Branch II
To: Jim Barstow
Tennessee Valley Authority
Buckberg P, NRR/DORL/LPL2-2, 415-1383
References
EPID L-2021-LRM-0070
Download: ML21218A147 (4)


Text

August 11, 2021 LICENSEE: Tennessee Valley Authority FACILITY: Sequoyah Nuclear Plant, Unit 2

SUBJECT:

SUMMARY

OF AUGUST 5, 2021, PUBLIC PREAPPLICATION MEETING WITH TENNESSEE VALLEY AUTHORITY REGARDING A FUTURE SUBMITTAL OF A RELIEF REQUEST RELATED TO THE INSERVICE INSPECTION OF THE UPPER HEAD INJECTION NOZZLES (EPID L-2021-LRM-0070)

On August 5, 2021, the U.S. Nuclear Regulatory Commission (NRC) staff held a virtual public meeting with representatives from Tennessee Valley Authority (TVA). The purpose of the meeting was to discuss the licensees plans to submit a relief request for the Sequoyah Nuclear Plant, Unit 2 (Sequoyah Unit 2), to allow an alternative to the specified requirements of the American Society of Mechanical Engineers Code Case N-729-6. The meeting notice and agenda, dated July 21, 2021, are available in the NRCs Agencywide Documents Access and Management System (ADAMS) under Accession No. ML21202A060.

A list of attendees is provided in the enclosure.

During the meeting, the licensee presented information (ADAMS Accession No. ML21197A002) regarding the Sequoyah Unit 2 reactor vessel Upper Head Injection (UHI) nozzles for the abandoned UHI systems and discussed the penetration diameters and how the currently endorsed Code Case will require a different examination than the previous Code Case (N-729-

1) leading to the need. TVA is not sure it can qualify an ultrasonic testing procedure for the UHI exams in time to support the October 2, 2021, Sequoyah Unit 2 refueling outage (U2R24). As TVA continues to pursue qualification, it has chosen to ensure that the NRC is aware of this potential expedited Relief Request to support U2R24.

In response to the TVA presentation, the NRC staff discussed with TVA the following elements that would help ensure a comprehensive Relief Request submittal:

1. Discuss how complexities in geometry, flaw location, etc., in addition to diameter caused difficulties in generating the mock-ups and qualification.
2. Discuss how minimum wall thickness of the nozzle wall excluding the weld material was or was not a concern in the previous (2014) inspection.
3. Identify all known limitations and differences of the new techniques.
4. Consider submitting the previous Technical Justification with the relief request.
5. Explain what the differences in probes are and how significant are they?
6. Explain what the timing of the head move is in relation to the fabrication timeline.
7. Provide discussion of the radiological dose hardship in performing the surface examination option. Discuss how surface prep time is limiting because the surface beneath the head was left in an as-welded condition.
8. Fully describe the plan for inspection, including the use of the previous technique and probe and the new technique and probe.
9. Explain what actions will be taken if the technique qualification fails (e.g., supplemental inspections, reinspect next outage, etc.).

The NRC and TVA staffs agreed that TVA providing the NRC progress update regarding the fabrication of the mockups and the qualification of the inspection procedures would be beneficial.

The NRC staff did not make any regulatory decisions or commitments at the meeting. One member of the public identified themselves at the meeting and there were no public comments or questions.

Please direct any inquiries to me at 301-415-1383 or by e-mail to Perry.Buckberg@nrc.gov.

/RA/

Perry H. Buckberg, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-328

Enclosure:

List of Attendees cc: Listserv

LIST OF ATTENDEES AUGUST 5, 2021, VIRTUAL PUBLIC MEETING WITH TENNESSEE VALLEY AUTHORITY, ET AL.

SEQUOYAH NUCLEAR PLANT, UNIT 2 PRE-APPLICATION MEETING REGARDING CODE CASE N-729-6 EXAMINATIONS U.S. Nuclear Regulatory Commission Perry Buckberg, NRR1 /DORL2 /LPLII-23 Jay Collins, NRR/DNRL4 /NPHP5 Tennessee Valley Authority Tracy Orf Jeffrey Sowa Jason Barrick Ryan Spencer Donna Stevens Anne Robinson-Givens Matt McCallum Dylan Merrill Damon Priestly Adam Keyser Electric Power Research Institute (EPRI)

Carl Latiolais Leif Esp Derrick Moreau Members of the Public Maria Garcia-Heras 1

Office of Nuclear Reactor Regulation 2

Division of Operating Reactor Licensing 3

Plant Licensing Branch II-2 4

Division of New and Renewed Licenses 5

Piping and Head Penetrations Branch Enclosure

ML21218A158 (Package)

ML21218A147(Summary)

ML21197A002 (Presentation)

ML21202A060 (Meeting Notice)

OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DNRL/NPHP/BC NRR/DORL/LPL2-2/BC NAME PBuckberg RButler MMitchell DWrona DATE 8/10/2021 8/9/2021 8/11/2021 8/11/2021 OFFICE NRR/DORL/LPL2-2/PM NAME PBuckberg DATE 8/11/2021