ML18194A777
| ML18194A777 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/02/2018 |
| From: | Watford M Plant Licensing Branch IV |
| To: | Peters K Vistra Operating Co. (VistraOpCo) |
| Watford M, 301-415-1233 | |
| References | |
| EPID L-2018-LLA-0081 | |
| Download: ML18194A777 (4) | |
Text
August 2, 2018 LICENSEE:
Vistra Operations Company LLC FACILITIES: Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2
SUBJECT:
SUMMARY
OF JULY 9, 2018, PUBLIC TELECONFERENCE WITH VISTRA OPERATIONS COMPANY LLC, REGARDING A LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATION 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION, FOR COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 (EPID L-2018-LLA-0081)
On July 9, 2018, a Category 1 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Vistra Operations Company LLC (Vistra OpCo, the licensee). The purpose of the meeting was to discuss a license amendment request dated March 29, 2018 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML18102A516), which requests NRC approval of a change to Technical Specification (TS) 3.3.2, Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2. The meeting notice and agenda, dated June 28, 2018, are available in ADAMS at Accession No. ML18179A452. In advance of the meeting, the licensee provided presentation slides, which are available under ADAMS Accession No. ML18190A217. The enclosure to this document contains the meeting attendance list.
The NRC staff opened the discussion with a request for the licensee to give an overview of the proposed change, including changes to or introduction of new operator actions. The licensee stated that, currently, TS Table 3.3.2-1 requires automatic auxiliary feedwater (AFW) actuation to be operable in Mode 1 (Power Operation, greater than 5 percent rated thermal power) and Mode 2 (Startup, less than or equal to 5 percent rated thermal power) if there is a trip of all main feedwater pumps. The licensee is proposing to modify the Mode 2 applicability so that the AFW actuation is only required to be operable when one or more main feedwater pump(s) are supplying feedwater to the steam generators. The licensee explained that this proposed change limits the potential for a low power, overcooling transient due to inadvertent AFW actuation before the main feedwater pumps have established sufficient feedwater flow.
The licensee presented information on how the plant procedures for plant startup from hot standby will change as a result of this proposed modification to TS Table 3.3.2-1. The plant procedures will be updated to include steps to restore the automatic AFW actuation after at least one main feedwater pump is operating to feed the steam generators. The NRC staff noted that there will be a period of time when the steam generators are being fed from the main feedwater pumps and the AFW system is not yet aligned for auto start. In addition, the NRC staff questioned if the operators will respond differently if the automatic AFW actuation is not enabled when in Mode 2 and a main feedwater pump is running. In response, the licensee stated that the following will happen if the change is approved. While the AFW system is still feeding the steam generators during startup, the operators will have the opportunity to manually control the flow of the AFW pumps, rather than both AFW pumps automatically starting at full flow if the main feedwater pump(s) trip, which could cause a low power, overcooling transient.
In addition, the licensee stated that if the main feedwater pumps tripped in Mode 2 when it is the only feedwater source (i.e., AFW pumps are secured), the operators would re-establish and control the AFW flow by entering the loss of all feedwater plant abnormal operating procedure.
The NRC staff also requested clarification on the sequence of events and the state of the automatic AFW actuation. The NRC staff noted that if the requested change is approved, the automatic AFW actuation will not be required during the period of time that the AFW is providing feedwater flow and the first main feedwater pump is not yet in service. As a result of the discussion, the NRC staff requested the licensee to review the license amendment request to determine if additional clarification on the proposed change is needed via a supplement.
The NRC project manager informed the licensee of the potential for the NRC staff to request additional information regarding the license amendment request, and stated that it would keep the licensee updated on the projected schedule during routine scheduling discussions with the licensee.
No members of the public attended the meeting via telephone and the NRC did not receive public meeting feedback forms.
If you have any questions, please call me at 301-415-1233 or via e-mail at Margaret.OBanion@nrc.gov.
Sincerely,
/RA/
Margaret W. OBanion, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
List of Attendees cc: Listserv
- concurrence via email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DE/EICB/BC*
NAME MOBanion PBlechman MWaters (RAlvarado for)
DATE 7/13/2018 7/30/2018 7/31/2018 OFFICE NRR/DRA/APHB/BC*
NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME CFong (MMontecalvo for)
RPascarelli MOBanion DATE 8/1/2018 8/2/2018 8/2/2018
Enclosure LIST OF ATTENDEES JULY 9, 2018 PUBLIC TELECONFERENCE WITH VISTRA OPERATIONS COMPANY LLC REGARDING PROPOSED CHANGES TO TECHNICAL SPECIFICATION 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-445 AND 50-446 Name Affiliation Margaret OBanion U.S. Nuclear Regulatory Commission (NRC)
Lisa Regner NRC CJ Fong NRC Michael Montecalvo NRC Norbert Carte NRC Huda Akhavannik NRC Margaret Chernoff NRC Summer Sun NRC Ryan Alexander NRC Jack Hicks Vistra Operations Company LLC (Vistra OpCo)
Garry Struble Vistra OpCo