ML19204A093
| ML19204A093 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/05/2019 |
| From: | Robert Schaaf Plant Licensing Branch II |
| To: | Tennessee Valley Authority |
| Schaaf R, 415-6020 | |
| References | |
| EPID L-2019-LRM-0035 | |
| Download: ML19204A093 (4) | |
Text
August 5, 2019 LICENSEE: Tennessee Valley Authority FACILITY: Watts Bar Nuclear Plant, Unit 2
SUBJECT:
SUMMARY
OF JUNE 11, 2019, PRE-SUBMITTAL MEETING WITH TENNESSEE VALLEY AUTHORITY REGARDING FUTURE LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION CHANGE FOR STEAM GENERATOR TUBE REPAIR (EPID L-2019-LRM-0035)
On June 11, 2019, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of the Tennessee Valley Authority (TVA, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss TVAs planned submittal of a license amendment request to revise the Watts Bar Nuclear Plant (Watts Bar), Unit 2, Technical Specifications (TS).
The proposed change would request approval for use of non-nickel banded tube sleeves to permit steam generator (SG) tubes with certain inspection indications to remain in service. The meeting notice and agenda, dated May 23, 2019, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19144A199. A list of attendees is enclosed.
The licensee presented information on the purpose of the proposed amendment; the SG design, program, and operating and maintenance strategy; the basis for installing the non-nickel banded sleeves; operating experience for the non-nickel banded sleeves; regulatory precedents; and the proposed schedule for submitting the amendment request. The presentation is available in ADAMS at Accession No. ML19161A241.
The NRC staff questioned the licensee about the availability of qualified inspection techniques for the non-nickel banded sleeves, details of the proposed TS changes, and if better than expected performance of the SG tubing material could impact the schedule for replacing the Unit 2 SGs. The staff asked several clarifying questions about the proposed inspection techniques for tubes with non-nickel banded sleeves installed. The staff also asked whether the licensee intended to submit the proposed amendment as a permanent or cycle-limited change.
TVA stated that information would be provided to demonstrate inspection technique compliance with industry standards, that the TS changes would be similar to the cited regulatory precedent, that there are no current plans to modify the planned schedule for SG replacement. TVA provided clarifying information about the planned inspection techniques for tubes with non-nickel banded sleeves installed. Also, TVA stated that it was currently considering submitting the amendment as a permanent TS change.
Based on staff questions and feedback during the meeting, the licensee stated that it would consider submitting the amendment request with a proposed limit on the number of operating cycles and would provide information on qualification methods used to show conformance with industry inspection guidelines.
Two members of the public attended the meeting by teleconference. One person provided comments about SG operating experience at other NRC-licensed facilities that should be taken into consideration by the staff. The other person requested information regarding SG operating experience at other TVA facilities. The NRC staff responded that licensees are required by the TS to submit reports of SG inspection results and that the NRC staff reviews these reports. The staffs review of the first Watts Bar, Unit 2, SG inspection report is available in ADAMS at Accession No. ML18303A213. The second person asked whether SG tube degradation leads to releases of radioactive materials via the secondary steam supply loops. The staff responded that the intent of the SG inspections is to identify SG tube degradation and plug or repair tubes to prevent leakage to the secondary loops. The staff stated that the licensee is also required by the TS to monitor secondary loop radiation levels and take action to shut down the plant in the event that levels exceed conservative threshold values, indicating potential leakage to the secondary loops.
No Public Meeting Feedback forms were received. No regulatory decisions were made during the meeting.
Please direct any inquiries to me at 301-415-6020 or Robert.Schaaf@nrc.gov.
/RA/
Robert G. Schaaf, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
List of Attendees cc: Listserv
ML19204A093 *by e-mail OFFICE NRR/DORL/LPL2-2/PM* NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME RSchaaf LRonewicz UShoop RSchaaf DATE 07/24/2019 07/24/2019 08/02/2019 08/05/2019 LIST OF ATTENDEES JUNE 11, 2019, MEETING WITH TENNESSEE VALLEY AUTHORITY PRE-SUBMITTAL MEETING REGARDING PROPOSED LICENSE AMENDMENT TO TECHNICAL SPECIFICATIONS REGARDING STEAM GENERATOR TUBE SLEEVING NAME ORGANIZATION Robert Schaaf U.S. Nuclear Regulatory Commission (NRC)
Office of Nuclear Reactor Regulation (NRR)
Andrew Johnson NRC/NRR Alan Huynh NRC/NRR Paul Klein NRC/NRR Ravi Grover NRC/NRR Steven Bloom NRC/NRR Joseph Messina NRC/NRR Balwant Singal NRC/NRR Justin Vazquez NRC/RGN-I Jeremy Mayo Tennessee Valley Authority Russell Wells Tennessee Valley Authority Jay Smith Westinghouse Damien Testa Westinghouse Gary White* Westinghouse Ed Kurdziel* Westinghouse Pat Wagner Wolf Creek Nuclear Operating Corp.
Marvin Lewis* Public Don Safer* Public
- by teleconference Enclosure