ML24347A029
| ML24347A029 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/12/2024 |
| From: | Perry Buckberg NRC/NRR/DORL/LPL2-2 |
| To: | Baron J Tennessee Valley Authority |
| Buckberg P | |
| References | |
| L-2024-LLA-0117 | |
| Download: ML24347A029 (3) | |
Text
From:
Perry Buckberg Sent:
Thursday, December 12, 2024 9:18 AM To:
Taylor, Andrew Charles; Baron, Jesse Shawn
Subject:
Request for Confirmatory Information - LAR to modify the FHA Analysis, delete TS 3.9.4 and to modify TS 3.3.6 - L-2024-LLA-0117 Attachments:
SQN LAR - FHA TSs L-2024-LLA- 0117 SFNB-RCI-10463-R1 12-12-2024.docx Andy /Jesse, By letter dated August 28, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24247A185), the Tennessee Valley Authority (TVA) submitted a license amendment request to the U.S. Nuclear Regulatory Commission (NRC). The request is to revise the Fuel Handling Accident Analysis, to delete Technical Specification 3.9.4, and to modify Technical Specification 3.3.6 for Sequoyah Nuclear Plant, Unit 1 and 2.
The U.S. Nuclear Regulatory Commission staff is reviewing the request and has identified an area where confirmatory information is needed to complete its review. Attached, please find a request for confirmatory information (RCI).
As discussed, response to the attached RCIs is requested no later than 30 business days from todays date. If circumstances result in the need to revise the requested response date, please contact me.
- Thanks, Perry Buckberg Senior Project Manager / Agency 2.206 Petition Coordinator U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation office: (301)415-1383 perry.buckberg@nrc.gov Mail Stop O-8B1a, Washington, DC, 20555-0001
Hearing Identifier:
NRR_DRMA Email Number:
2666 Mail Envelope Properties (PH0PR09MB767471F682D47889EA22700E9A3F2)
Subject:
Request for Confirmatory Information - LAR to modify the FHA Analysis, delete TS 3.9.4 and to modify TS 3.3.6 - L-2024-LLA-0117 Sent Date:
12/12/2024 9:18:12 AM Received Date:
12/12/2024 9:18:00 AM From:
Perry Buckberg Created By:
Perry.Buckberg@nrc.gov Recipients:
"Taylor, Andrew Charles" <actaylor@tva.gov>
Tracking Status: None "Baron, Jesse Shawn" <jsbaron@tva.gov>
Tracking Status: None Post Office:
PH0PR09MB7674.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1231 12/12/2024 9:18:00 AM SQN LAR - FHA TSs L-2024-LLA- 0117 SFNB-RCI-10463-R1 12-12-2024.docx 24876 Options Priority:
Normal Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
1 REQUEST FOR CONFIRMATORY INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SEQUOYAH 1&2 - REVISE FHA ANALYSIS, DELETE TS 3.9.4 AND TO MODIFY TS 3.3.6 LAR to TENNESSEE VALLEY AUTHORITY SEQUOYAH, UNITS 1, 2 DOCKET NO. 05000327, 05000328 EPID L-2024-LLA-0117 ISSUE DATE: 12/12/2024
Background
By letter dated August 28, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24247A185), the Tennessee Valley Authority submitted a license amendment request to the U.S. Nuclear Regulatory Commission. The request is to revise the Fuel Handling Accident Analysis, to delete Technical Specification 3.9.4, and to modify Technical Specification 3.3.6 for Sequoyah Nuclear Plant, Unit 1 and 2.
Question 1 RG 1.183, Revision 0, Footnote 11 states that the non-LOCA gap release fractions in Table 3 of RG 1.183 Rev. 0 are acceptable for fuel with a peak rod-average burnup up to 62 GWd/MTU, provided the maximum linear heat generation rate does not exceed 6.3 kW/ft peak rod average power for burnups exceeding 54 GWd/MTU.
Table 3.1.1-1 of Enclosure 1 of the license amendment request indicates that the RG 1.183 Rev.
0 non-LOCA gap release fractions are used in the updated fuel handling accident dose analysis, but does not clarify that the Footnote 11 range of applicability is met. Please confirm that the RG 1.183 Rev. 0 Footnote 11 burnup and linear heat generation rate range of applicability will be met.