ML14175B286
| ML14175B286 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/03/2014 |
| From: | Andrew Hon Plant Licensing Branch II |
| To: | |
| Hon A DORL/LPL2-2 301-415-8480 | |
| References | |
| TAC MF3128, TAC MF3129 | |
| Download: ML14175B286 (4) | |
Text
LICENSEE:
Tennessee Valley Authority FACILITY:
Sequoyah Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF May 22, 2014, MEETING WITH TENNESSEE VALLEY AUTHORITY REGARDING IMPROVED TECHNICAL SPECIFICATIONS CONVERSIONS FOR SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. MF3128 AND MF3129)
On May 22, 2014, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of the Tennessee Valley Authority (TVA) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland.
The purpose of this public meetings was to discuss the ongoing review of the license amendment request for Sequoyah Nuclear Plant, Units 1 and 2 (SQN), to convert the current technical specifications (CTS) to the improved technical specifications (ITS) format. The focus of the discussion was on controlling the outage time of the shutdown board for maintenance in a shutdown unit while the other unit is at power and the applicable section of the ITS. TVA's presentation from the March 13, 2014, public meeting (ML14071A152) was used to facilitate the discussion. Key points of the discussion are summarized as follow:
Action c. of the Limiting Condition for Operations (LCO) 3.8.1.1 of the CTS requires power to be restored to a 6.9 kilovolt (kV) Shutdown Board within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if both offsite power and onsite power (emergency diesel generator (EDG)) are lost to the 6.9 kV Shutdown Board, or go to dual unit shutdown, because of certain TS required systems of the operating unit are powered by the de-energized Shutdown Board.
The proposed ITS will allow power to be restored to the inoperable 6.9 kV Shutdown Board within 7 days [either offsite power or onsite power (EDG)] without requiring dual unit shutdown. Only one unit is required to be shutdown associated with the 6.9 kV Shutdown Board with no offsite and onsite power. This is assuming the approval of a separate license amendment request that will allow operation with only one essential raw cooling water pump per loop.
During a prior meeting with NRC on March 13, 2014, TVA stated it intended to use the ITS LCO 3.8.1, Condition I, which allows up to 7 days to restore power to one of the Shutdown Boards under maintenance (with one unit in shutdown mode and other unit in operation). Based on response to NRC Question GMW-004, Part D, posted on Excel Services website, it appeared that TVA believed they could do the shutdown board maintenance while in Mode 5 or Mode 6 on the shutdown unit. The NRC staff requested additional information (GMW-006) about the risk during the 7 day Shutdown Board outage in Mode 5 or Mode 6. During that time one train of the residual heat removal is already unavailable, a single failure on the remaining train could result in a loss of all residual heat removal capability and possible fuel damage.
During the meeting with NRC on May 22, 2014, TVA stated that it will evaluate the licensing control options so that they could do maintenance on one of the Shutdown Boards with the associated unit's core offloaded completely or in Mode 6 with the reactor cavity filled with 23 feet of water, subsequent to complete core offload. This control can be either Actions in the TS or a license condition. TVA also stated that they will have a calculation or backup document justifying that the reactor will remain safely shutdown during Mode 6 with the reactor cavity filled with 23 feet of water, subsequent to core offloaded completely, with no power available to both the 6.9 kV switchgears associated with the shutdown unit (during the latter part of 7 days of switchgear maintenance).
No regulatory decisions were made at the meeting. Members of the public were not in attendance. No Public Meeting Feedback forms were received.
Please direct any inquiries to me by phone at 301-415-8480, or e-mail at Andrew.Hon@nrc.gov.
Docket Nos. 50-327 and 50-328
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
LIST OF ATTENDEES MAY 22,2014 MEETING WITH TENNESSEE VALLEY AUTHORITY IMPROVED TECHNICAL SPECIFICATIONS CONVERSIONS SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 Tennessee Valley Authority and Contractors N. Mynatt R. Shiele S. Bowman M. Conner Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation A. Hon G. Singh J. Purciarello PUBLIC None V. Goel R. Elliott M. Hamm K. Hemphill G. Curran J. Zimmerman M. McBrearty L. Regner N. Otto Enclosure
PKG ML141758327 Notice ML14131A004 S
ML141758286 urn mary OFFICE DORL/LPL2-2/PM DORLILPL2-2/LA DORL/LPL2-2/BC DORLILPL2-2/PM NAME AHon BCiayton LRegner (A)
AHon DATE 6/25/14 6/25/14 7/2/14 7/2/14