ML080800382
| ML080800382 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/02/2008 |
| From: | Moroney B NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Campbell W Tennessee Valley Authority |
| Mozafari B, NRR/ADRO/DORL, 415-2020 | |
| Shared Package | |
| ML080800504 | List: |
| References | |
| TAC MD5294, TAC MD5295 | |
| Download: ML080800382 (12) | |
Text
April 2, 2008 Mr. William R. Campbell, Jr.
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 - ISSUANCE OF AMENDMENTS REGARDING CHANNEL FUNCTIONAL TEST SURVEILLANCE FREQUENCY FOR REACTOR TRIP SYSTEM TURBINE TRIP (TAC NOS.
MD5294 AND MD5295)
Dear Mr. Campbell,
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 318 to Facility Operating License No. DPR-77 and Amendment No. 310 to Facility Operating License No. DPR-79 for the Sequoyah Nuclear Plant, Units 1 and 2, respectively.
These amendments are in response to your application dated April 5, 2007(TS-07-03).
The amendments revise the surveillance frequency for the turbine trip functions of the reactor trip system instrumentation.
A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
- 1. Amendment No. 318 to License No. DPR-77
- 2. Amendment No. 310 to License No. DPR-79
- 3. Safety Evaluation cc w/enclosures: See next page
April 2, 2008 Mr. William R. Campbell, Jr.
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 - ISSUANCE OF AMENDMENT REGARDING CHANNEL FUNCTIONAL TEST SURVEILLANCE FREQUENCY FOR REACTOR TRIP SYSTEM TURBINE TRIP (TAC NOS.
MD5294 AND MD5295)
Dear Mr. Campbell,
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 318 to Facility Operating License No. DPR-77 and Amendment No. 310 to Facility Operating License No. DPR-79 for the Sequoyah Nuclear Plant, Units 1 and 2, respectively.
These amendments are in response to your application dated April 5, 2007(TS-07-03).
The amendments revise the surveillance frequency for the turbine trip functions of the reactor trip system instrumentation.
A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
- 1. Amendment No. 318 to License No. DPR-77
- 2. Amendment No. 310 to License No. DPR-79
- 3. Safety Evaluation DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsOgcRp RidsNrrrDorlDpr RidsAcrsAcnwMailCenter RidsNrrDorlLpl2-2 RidsNrrLACSola RidsNrrPMBMozafari RidsRgn2MailCenter RidsNrrDirsItsb MHamm, NRR ADAMS Accession Number: Letter: ML080800382 Pkg: ML080800504 TS: ML080810232 NRR-058 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA BC:ITSB:DIRS OGC LPL2-2/BC NAME AObodoako BMoroney RSola GWaig By memo dated CChandler TBoyce DATE 04/02/08 04/02/08 04/02/08 01/28/2008 03/26/08 04/02/08 OFFICIAL RECORD COPY
William R. Campbell, Jr.
SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. James R. Douet Senior Vice President Nuclear Support Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. H. Rick Rogers Vice President Nuclear Engineering & Technical Services Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Timothy P. Cleary, Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902 Mr. John C. Fornicola, Manager Nuclear Assurance Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. James D. Smith, Manager Licensing and Industry Affairs Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Christopher R. Church, 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 TN Dept. of Environment & Conservation Division of Radiological Health Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 County Mayor Hamilton County Courthouse Chattanooga, TN 37402-2801 Mr. Larry E. Nicholson, General Manager Performance Improvement Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael A. Purcell Senior Licensing Manager Nuclear Power Group Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, TN 37854
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 318 License No. DPR-77
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 5, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 318, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance, and shall be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Thomas H. Boyce, Chief Plant Licensing Branch II-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Change to License No. DPR-77 and the Technical Specifications Date of Issuance: April 2, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 318 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace page 3 of License No. DPR-77 with the attached revised page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 310 License No. DPR-79
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 5, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 310, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance, and shall be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Thomas H. Boyce, Chief Plant Licensing Branch II-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Change to License No. DPR-79 and the Technical Specifications Date of Issuance: April 2, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 310 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace page 3 of License No. DPR-79 with the attached revised page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 318 TO FACILITY OPERATING LICENSE NO. DRP-77 AND AMENDMENT NO. 310 TO FACILITY OPERATING LICENSE NO DPR-79 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328
1.0 INTRODUCTION
By letter dated April 5, 2007, Tennessee Valley Authority (TVA, the licensee), submitted a request for changes to the technical specifications (TSs) for Sequoyah Nuclear Plant (SQN)
Units 1 and 2 (Agencywide Documents and Management System (ADAMS) Accession No. ML071080240). The proposed changes would revise the surveillance requirement (SR) frequency for the turbine trip functions of the reactor trip system instrumentation.
The reactor trip systems at SQN Units 1 and 2 are identical and cause automatic rapid control rod insertion, known as a trip, when certain operating conditions are detected in the associated plant. Two of the 18 conditions that lead to a trip are: a drop in turbine auto stop oil pressure when reactor power is above 50 percent and the closure of turbine stop valves when reactor power is above 50 percent. The turbine trip function (Functional Unit 18A and 18B) of the reactor trip system instrumentation causes a trip during these conditions. This trip function is interlocked by P-9, which enables the function above 50 percent power and blocks it below 50 percent power. The turbine trip function is a means to prevent a reactor plant pressure and temperature transient which would otherwise occur if the reactor remained at power upon a large, rapid decrease in steam flow from the steam generators.
TVA is requesting the TS change to eliminate the period of time between when the SR is required to be performed and the time of entry into the mode in which the SR is applicable. On September 2, 2005, the NRC issued Amendment Nos. 304 and 294, which changed the applicability of the trip functions to above 50 percent power. However, the SR was not changed.
This creates confusion regarding the need to perform the SR before reactor startup even though the function is not required to be operable until reactor power reaches 50 percent.
2.0 REGULATORY EVALUATION
10 CFR Part 50, Appendix A, General Design Criteria, provides the design requirements for protection systems associated with reactor operation in General Design Criteria (GDC) 20 through 29.Section II.K.3.12 of Enclosure 3 of NUREG-0737, Clarification of TMI Action Plan Requirements, requires Westinghouse plants to include an anticipatory reactor trip upon turbine trip function in the reactor trip system.
The NRC published a set of Standard Technical Specifications (STS) in NUREG-1431, Revision 3 Standard Technical Specifications, Westinghouse Plants. The STS are a guide to what a plants TSs should contain with regard to format and content. The STS are not requirements in a regulatory sense, but licensees adopting portions of the STS to existing TSs should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency.
The TS changes contained in the licensees amendment request were evaluated by comparing them to the applicable GDC and requirements listed in NUREG-0737. The amendment was also compared to the STS in NUREG-1431 for consistency.
3.0 TECHNICAL EVALUATION
The current surveillance frequency requirements for the turbine trip function of the reactor trip system are found in Table 4.3-1 of TSs for SQN Units 1 and 2. The frequency for the Turbine Trip Channel Functional Test is listed as S/U (1). The S/U means prior to each reactor startup and the (1) refers to a note 1 for the table which reads: if not performed in the previous 31 days. The proposed change would revise the turbine trip surveillance frequency in Table 4.3-1 to be: (1)(12). Note 12 would be added to the table and would read, Prior to exceeding the Permissive P-9 interlock whenever the unit has been in hot standby.
The format of SQN TSs differ from the format of STS. The proposed TS change is similar in content to the change incorporated in NUREG-1431, Revision 3 by TSTF-311.
The proposed changes do not alter the ability of the reactor trip functions to actuate on a valid turbine trip signal. The proposed surveillance frequency is consistent with the function applicability requirements and the SQN design and analysis for the turbine trip safety function.
Therefore, the recommendations of the GDCs continue to be met with the proposed changes.
The requirements of NUREG-0737 also continue to be met. While the format of the SQN TSs does not match that of the STS, the proposed changes bring the content of SQN TS into closer alignment with the content of STS.
Based on the above discussion, the NRC staff finds the proposed changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Tennessee State official, Mr. Bruce House of the Tennessee Bureau of Radiological Health was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (72 FR 29723). Accordingly, the amendm ents meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Matthew E. Hamm Date: April 2, 2008