ML25330A018
| ML25330A018 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 12/08/2025 |
| From: | Kimberly Green NRC/NRR/DORL/LPL2-2 |
| To: | Erb D Tennessee Valley Authority |
| Green K, NRR/DORL/LPL2-2 | |
| References | |
| EPID L-2020-LLA-0133 | |
| Download: ML25330A018 (0) | |
Text
December 8, 2025 Mr. Delson Erb Vice President, OPS Support Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - CORRECTION TO AMENDMENT NO. 141 REGARDING THE ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER, TSTF-569, REVISION 2, REVISE RESPONSE TIME TESTING DEFINITION (EPID L-2020-LLA-0133)
Dear Mr. Erb:
During the issuance of Amendment No. 141 to Facility Operating License (FOL) No. NPF-90 on January 25, 2021 (ADAMS Accession No. ML20350B493), the U.S. Nuclear Regulatory Commission (NRC) staff inadvertently omitted a portion of the definition for SHUTDOWN MARGIN (SDM) in the Watts Bar Nuclear Plant, Unit 1, technical specifications (TSs).
The purpose of this letter is to issue corrected TS page 1.1-5 for FOL No. NPF-90. The NRC concludes that this omission does not change the staffs previous conclusion in the safety evaluation for issuance of Amendment No. 141, nor does it affect the NRC staffs no significant hazards consideration determination.
Enclosed, please find corrected TS page 1.1-5 for FOL No. NPF-90 for Amendment No. 141.
If you have any questions regarding this matter, please contact me at (301) 415-1627 or by email at Kimberly.Green@nrc.gov.
Sincerely,
/RA/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
Corrected TS page 1.1-5 for FOL NPF-90 cc: Listserv
ENCLOSURE WATTS BAR NUCLEAR PLANT, UNIT NO. 1 DOCKET NO. 50-390 CORRECTED TECHNICAL SPECIFICATION PAGE 1.1-5 FOR FACILITY OPERATING LICENSE NO. NPF-90
Definitions 1.1 1.1 Definitions (continued)
(continued)
Watts Bar - Unit 1 1.1-5 Amendment 24, 31, 141 PHYSICS TESTS a.
Described in Chapter 14, Initial Test Program of the (continued)
FSAR; b.
Authorized under the provisions of 10 CFR 50.59; or c.
Otherwise approved by the Nuclear Regulatory Commission.
PRESSURE AND TEMPERATURE LIMITS REPORT QUADRANT POWER TILT RATIO (QPTR)
RATED THERMAL POWER (RTP)
REACTOR TRIP SYSTEM (RTS) RESPONSE TIME SHUTDOWN MARGIN (SDM)
The PTLR is the unit specific document that provides the RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.9.6. Plant operation within these operating limits is addressed in LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits," and LCO 3.4.12, "Cold Overpressure Mitigation System (COMS)."
QPTR shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.
RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3459 MWt.
The RTS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC, or the components have been evaluated in accordance with an NRC approved methodology.
SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:
ML25330A018 NRR-106 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME KGreen ABaxter DWrona KGreen DATE 11/25/2025 12/8/2025 12/8/2025 12/8/2025