ML060330048
| ML060330048 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 02/10/2006 |
| From: | Pickett D Plant Licensing Branch III-2 |
| To: | Marshall M Plant Licensing Branch III-2 |
| Pickett , NRR/DLPM, 415-1364 | |
| References | |
| TAC MC4586 | |
| Download: ML060330048 (3) | |
Text
February 10, 2006 MEMORANDUM TO:
Michael L. Marshall, Jr., Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM Douglas V. Pickett, Senior Project Manager /RA/
Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - DOCUMENTATION OF REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MC4586)
On September 23, 2004, the Tennessee Valley Authority, the licensee, submitted license amendment request WBN-TS-04-013 (TAC No. MC4586). As a result of the Nuclear Regulatory Commission (NRC) staffs review, the attached three questions were electronically transmitted to the licensee on February 2, 2005.
On January 27, 2006, a conference call was held with the licensee and the NRC staff to discuss the questions. At that time, it was agreed that the licensee would respond to questions 1 and 2, but question 3 would be deleted. Separate documentation will formally transmit questions 1 and 2 to the licensee.
Pursuant to NRR Office Instruction LIC-101, Revision 3, License Amendment Review Procedures, Section 4.3, this memorandum documents a request for additional information that was electronically transmitted to the licensee and subsequently modified.
Docket No. 50-390
Enclosure:
Request for Additional Information
ML060330048 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME DPickett CSola MMarshall DATE 02/03/06 02/03/06 02/10/06 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390 1.
Explain why the existing Technical Specification (TS) requirement was originally established, and why it was deemed necessary to make it applicable in Mode 1 (below approximately 18 percent power) and in Mode 2, when the turbine-driven main feedwater pumps are not used until the plant exceeds approximately 18 percent power.
2.
Explain why it is not appropriate for the existing TS requirement to also apply to the motor-driven standby main feedwater pump during Modes 1 and 2, when the motor-driven standby main feedwater pump is being used to provide steam generator makeup.
3.
Recognizing that the existing TS requirement applies to an anticipatory circuit which provides early actuation of the auxiliary feedwater system, but it is not a safety-related function and it is not credited for accident mitigation purposes, explain why (pursuant to 10 CFR 50.36 requirements), it is considered appropriate to maintain this function as a TS requirement.