ML060180186
| ML060180186 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/27/2006 |
| From: | Pickett D Plant Licensing Branch III-2 |
| To: | Singer K Tennessee Valley Authority |
| DOUGLAS PICKET, NRR/DORL, 41501364 | |
| References | |
| TAC MC8246, TAC MC8247 | |
| Download: ML060180186 (6) | |
Text
January 27, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISION OF ALLOWABLE VALUE FOR REACTOR TRIP SYSTEM - TURBINE TRIP ON LOW TRIP SYSTEM PRESSURE (TAC NOS. MC8246 AND MC8247)
Dear Mr. Singer:
By letter dated September 1, 2005, Tennessee Valley Authority (TVA, the licensee) requested an amendment to the operating license for the Sequoyah Nuclear Plant, Units 1 and 2, to revise the reactor protection system turbine trip allowable value for low trip system pressure (TVA-SQN-TS-05-04). This change affects Functional Unit 17.A of Technical Specification 2.2.1, "Reactor Trip System Instrumentation Setpoints," in Table 2.2-1.
In order for the staff to complete its review of the reports, we request that the licensee provide responses to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you intend to respond to this RAI within 60 days of receipt of this letter.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosure:
Request for Additional Information cc w/encl: See next page
ML060180186 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA EICB/BC LPL2-2/BC NAME DPickett RSola AHowe By memo dated BMozafari for MMarshall DATE 1/26/06 1/26/06 01/ 09 /06 1/27/06
Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Robert J. Beecken, Vice President Nuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Randy Douet Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 General Counsel Tennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Paul L. Pace, Manager Licensing and Industry Affairs ATTN: Mr. James D. Smith Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. David A. Kulisek, Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 Senior Resident Inspector Sequoyah Nuclear Plant U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, TN 37379 Mr. Lawrence E. Nanney, Director Division of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 County Mayor Hamilton County Courthouse Chattanooga, TN 37402-2801 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS CHANGES FOR ALLOWABLE VALUE FOR REACTOR TRIP SYSTEM - TURBINE TRIP ON LOW TRIP SYSTEM PRESSURE TAC NOS. MC8246 AND MC8247 The license amendment request (LAR) proposes Technical Specification (TS) change to revise the reactor protection system turbine trip allowable value for low trip system pressure from greater than or equal to 43 pounds per square inch gauge (psig) to 39.5 psig. This change affects Functional Unit 17.A of TS 2.2.1, Reactor Trip System Instrumentation Setpoint, in TS Table 2.2-1.
To assess the acceptability of the LAR related to setpoint changes, please provide the following information:
1.
Setpoint Calculation Methodology: Provide documentation (including sample calculations) of the methodology used for establishing the limiting nominal setpoint and the limiting acceptable values for the As-Found and As-Left setpoints as measured in periodic surveillance testing as described below. Indicate the related Analytical Limits and other limiting design values (and the sources of these values) for each setpoint.
2.
Safety Limit-Related Determination: Provide a statement as to whether or not the setpoint is a limiting safety system setting for a variable on which a safety limit (SL) has been placed as discussed in Title 10, Code of Federal Regulations (10 CFR),
Section 50.36(c)(ii)(A). Such setpoints are described as SL-related, in the discussions that follow. For each setpoint that you determined not to be SL-Related, explain the basis for this determination.
3.
For setpoints that are determined to be SL-related: The Nuclear Regulatory Commission (NRC) letter to the Nuclear Energy Institute (NEI) Setpoint Methods Task Force dated September 7, 2005 (ML052500004), described setpoint-related TS (SRTS) requirements that are acceptable to the NRC for instrument settings associated with SL-related setpoints. Specifically: Part A of the enclosure to the letter provides Limiting Condition for Operation notes to be added to the TS, and Part B includes a checklist of the information to be provided in the TS Bases related to the proposed TS changes.
a.
Describe whether and how you plan to implement the SRTS requirements suggested in the September 7 letter. If you do not plan to adopt the suggested SRTS, then explain how you will ensure compliance with 10 CFR 50.36 by addressing items 3b and 3c, below.
b.
As-Found Setpoint Evaluation: Describe how surveillance test results and associated TS limits are used to establish operability of the safety system. Show that this evaluation is consistent with the assumptions and results of the setpoint calculation methodology. Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be inoperable, or operable but degraded. If the requirements for determining operability of the instrument being tested are located in a document other than the TSs (e.g., plant test procedure) explain how the requirements of 10 CFR 50.36 are met.
c.
As-Left Setpoint Control: Describe the controls employed to ensure that the instrument setpoint, upon completion of surveillance testing, is consistent with the assumptions of the associated analyses. If the controls are located in a document other than the TSs (e.g., plant test procedure), explain how the requirements of 10 CFR 50.36 are met.
4.
For setpoints that are not determined to be SL-related setpoints in response to question 2: Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion, information on the controls you employ to ensure that the as-left trip setting, after completion of periodic surveillance, is consistent with your setpoint methodology. If the controls are located in a document other than the TSs (e.g., plant test procedure),
describe how it is ensured that the controls will be implemented to satisfy operability requirements.