ML22207B830
| ML22207B830 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/28/2022 |
| From: | Luke Haeg Plant Licensing Branch II |
| To: | Tennessee Valley Authority |
| Haeg, L. | |
| References | |
| EPID L-2022-LRM-0055 | |
| Download: ML22207B830 (4) | |
Text
July 28, 2022 LICENSEE: Tennessee Valley Authority FACILITY: Sequoyah Nuclear Plant, Unit No. 1
SUBJECT:
SUMMARY
OF JULY 20, 2022, OBSERVATION PUBLIC MEETING WITH THE TENNESSEE VALLEY AUTHORITY TO DISCUSS PLANNED ALTERNATIVE REQUEST RP-12 TO ASME OM CODE TESTING FOR THE 1B-B CENTRIFUGAL CHARGING PUMP AT THE SEQUOYAH NUCLEAR PLANT, UNIT NO. 1 (EPID L-2022-LRM-0055)
On July 20, 2022, an observation public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of the Tennessee Valley Authority (TVA, the licensee) via teleconference. The purpose of the meeting was to discuss the licensees planned submittal of an alternative request to American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants, Section IST, Rules for Inservice Testing of Light-Water Reactor Power Plants (OM Code), 2004 Edition through 2006 Addenda, for testing of the 1B-B centrifugal charging pump (CCP) at the Sequoyah Nuclear Plant, Unit No. 1 (Sequoyah). The proposed alternative request was associated with return-to-service testing of the 1B-B CCP following replacement of the pump rotating element with Sequoyah, Unit 1, in Mode 1. The meeting notice and agenda dated July 20, 2022, are available in the Agencywide Documents Access and Management System (ADAMS) Accession No. ML22201A029. A list of attendees is provided as an enclosure.
The licensee presented slides (ML22201A126) involving the reason for the planned request, applicable ASME OM Code and Technical Specification requirements, and the proposed alternative basis and duration. Specifically, Sequoyah, Unit 1, declared the 1B-B CCP inoperable on July 18, 2022, and identified that the pump rotating element needed to be replaced. Based on the needed repairs, prior to returning the 1B-B CCP to operable status, ASME OM Code required a comprehensive or preservice test to be performed. However, the licensee considered this required testing as representing a hardship or unusual difficulty without a compensating increase in the level of quality and safety due to performance of required preservice or comprehensive test not being possible in Mode 1. Therefore, TVA proposed to conduct a Group A pump test, and defer the required comprehensive or preservice test until the Sequoyah, Unit 1, refueling outage in October 2022.
The NRC staff inquired whether referencing the 2020 Edition of the ASME OM Code was appropriate considering that the code of record for Sequoyah, Unit 1, was the 2004 Edition through the 2006 Addenda. The licensee acknowledged the inquiry and planned to submit the alternative request in relation to the Sequoyah, Unit 1, code of record. The NRC staff inquired whether the 1B-B CCP comprehensive test would be performed if there was an unplanned outage prior to the Sequoyah, Unit 1, refueling outage in October 2022. The licensee responded that if an unplanned outage occurred, an evaluation would be conducted to determine whether
plant conditions were favorable to performing the comprehensive or preservice test considering removal of the reactor vessel head. Further, the NRC staff made general inquiries involving the level of confidence the licensee had regarding the cause of the 1B-B CCP inoperability, whether the licensee confirmed that the 1B-B CCP motor was not impacted, and the level of data gathering that would be conducted during the Group A return-to-service testing. The licensee provided preliminary causal information that supported failure of the pump rotating element, that motor testing of the 1B-B CCP was conducted and did not indicate any impact to the motor, and that data gathered during the Group A test would be used to establish a reference curve for the range of flow rates achievable in Mode 1. Further, the licensee stated that the differential pressure, flow rate, and vibration data gathered during the Group A test of the 1B-B CCP would be compared with reference values from the reference curve.
No members of the public were in attendance. No regulatory decisions were made at this meeting.
Please direct any inquiries to me at 301-415-0272, or Lucas.Haeg@nrc.gov.
Sincerely,
/RA/
Luke Haeg, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-327
Enclosure:
List of Attendees cc: Listserv
LIST OF ATTENDEES JULY 20, 2022, OBSERVATION PUBLIC MEETING WITH THE TENNESSEE VALLEY AUTHORITY TO DISCUSS PLANNED ALTERNATIVE REQUEST RP-12 TO ASME OM CODE TESTING FOR THE 1B-B CENTRIFUGAL CHARGING PUMP AT THE SEQUOYAH NUCLEAR PLANT, UNIT NO. 1 (EPID L-2022-LRM-0055)
Nuclear Regulatory Commission Stewart Bailey Tom Scarbrough James Baptist Lou McKown David Wrona Binoy Desai Shane Sandal Andy Rosebrook Yuken Wong Hanry Wagage Son Ninh Ian Tseng Robert Beaton Geoffrey Ottenberg Ed Miller David Hardage Luke Haeg Tennessee Valley Authority Russell Wells Robert Shaler Jeffrey Sowa Mannon Wills Kevin Groom Stuart Rymer William Victor Earl Ridgell Gordon Williams Robert Smith Duke Dang Luke Green Rob Snow John Alexander Andrew Taylor William Ivey Enclosure
ML22207B830 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DEX/EMIB/BC NAME LHaeg RButler SBailey DATE 07/26/2022 07/28/2022 07/28/2022 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona LHaeg DATE 07/28/2022 07/28/2022