ML11271A135
| ML11271A135 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/14/2011 |
| From: | Siva Lingam Plant Licensing Branch II |
| To: | Krich R Tennessee Valley Authority |
| Lingam S | |
| References | |
| TAC ME6707 | |
| Download: ML11271A135 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 14, 2011 Mr. Rodney M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOPSED TECHNICAL SPECIFICATION CHANGES FOR REPLACEMENT STEAM GENERATOR TUBE INSPECTION REQUIREMENTS (TAC NO. ME6707)
Dear Mr. Krich:
By letter dated July 15, 2011, you submitted an application for a license amendment to revise the Sequoyah Nuclear Plant, Unit 2, technical specifications requirements for steam generator tube inspections to reflect the replacement steam generators to be installed during fall 2012 refueling outage.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Green of your staff on September 28, 2011, and it was agreed that a response would be provided within 30 days from the date of this letter.
If you have any questions regarding this matter, I can be reached at 301-415-1564.
Sincerely,
~
<J'~
Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket No. 50-328
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES FOR REPLACEMENT STEAM GENERATORS TUBE INSPECTION REQUIREMENTS SEQUOYAH NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-328 By letter dated July 15, 2011 (Agencywide Documents Access and Management System Accession No. ML11199A212), Tennessee Valley Authority (the licensee), submitted a license amendment request regarding proposed changes to the technical specifications (TSs) to reflect steam generator (SG) replacement for Sequoyah Nuclear Plant, Unit 2. In order to complete its review, the Nuclear Regulatory Commission (NRC) staff needs the following additional information:
- 1. The proposed modification to TS 6.8.4.k.b.2 does not match the wording in TSTF-449, since the proposal indicates that accident-induced leakage is not to exceed 1.0 gpm for the faulted steam generator (emphasis added), whereas TSTF-449 simply indicates that the accident-induced leakage is not to exceed 1.0 gpm per steam generator. Please justify this discrepancy or modify your proposal to remove this discrepancy. The reason for this limit is discussed in Regulatory Issue Summary 2007-20, "Implementation of Primary-to-Secondary Leakage Performance Criteria."
- 2. Changes to the Technical SpeCification Bases were provided for information only, however, the NRC staff noticed that several of the changes appear to go beyond what would be needed to reflect the replacement of the steam generators. In fact, some of the changes appear to remove changes made during the NRC staffs review of your submittal adopting TSTF-449. Please clarify these changes, which include the following:
- a. Bases page B 3/4 4-3a: deletion of "or the NRC approved licensing basis"
- b. Bases page B 3/4 4-3i: deletion of "(Mode 4)"
- c.
Bases page B 3/44-3j: deletion of "(i.e., prior to HOT SHUTDOWN following a SG tube inspection)"
- d. Bases page B 3/44-4f: deletion of "the expected leak rate following a steam line rupture is limited to below 3.7 gpm at atmospheric conditions and 70 degrees F in the faulted loop, which will limit the calculated offsite doses to within 10 percent of the 10 CFR 100 guidelines" Enclosure
- transmitted by memo dated OFFICE LPL2-2/PM LPL2-2/LA DCI/CSGB/BC (A)
LPL2-2/BC LPL2-2/PM NAME SLingam CSoia MMurphy (VCusumano for)
DBroaddus (FSaba for)
SLingam 9/29/11 09/28/11 09/20/11*
10/13/11 10/14/11