ML051920164
| ML051920164 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/02/2005 |
| From: | Pickett D NRC/NRR/DLPM/LPD2 |
| To: | Singer K Tennessee Valley Authority |
| Pickett D, NRR/DLPM, 415-1364 | |
| Shared Package | |
| ML052520073 | List: |
| References | |
| TAC MC6879, TAC MC6880 | |
| Download: ML051920164 (13) | |
Text
September 2, 2005 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 ISSUANCE OF AMENDMENTS REGARDING TURBINE TRIP IN REACTOR TRIP SYSTEM INSTRUMENTATION (TAC NOS. MC6879 AND MC6880)
Dear Mr. Singer:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 304 to Facility Operating License No. DPR-77 and Amendment No. 294 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 27, 2005 (TVA-SQN-05-03).
The amendments revise the applicability of Technical Specifications (TS) 3.4.3, Functional Unit 18.A, Turbine Trip, Low Fluid Oil Pressure, and TS Functional Unit 18.B, Turbine Trip, Turbine Stop Valve Closure, in Table 3.3-1, Reactor Trip System Instrumentation, and Table 4.3-1, Reactor Trip System Instrumentation Surveillance Requirements. The change (1) adds a footnote to limit applicability of Functional Units 18.A and 18.B above the P-9 (50 percent rated thermal power) interlock setpoint and (2) replaces the current Action 6 with a new Action 7 for Functional Unit 18.B. These changes are consistent with the latest version of NUREG-1431, Revision 3, Standard Technical Specifications for Westinghouse Plants and constitute improvements to the current Sequoyah Nuclear Plant TSs.
K. Singer A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
- 1. Amendment No. 304 to License No. DPR-77
- 2. Amendment No. 294 to License No. DPR-79
- 3. Safety Evaluation cc w/enclosures: See next page
ML051920164 TS: ML052510061 NRR-058 OFFICE LPD2-2 PM: LPD2-2 LA: LPD2-2 SC: EEIB SC: IROB OGC SC: LPD2-2 NAME MVaaler DPickett BClayton AHowe by memo dtd TBoyce MDuffy MMarshall DATE 07/ 15/ 05 07/ 18 /05 07/ 15 /05 06 / 09 / 05 07/ 22 /05 08/ 04 /05 09/ 02 /05
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, General Manager Nuclear Engineering 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: 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
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 304 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 27, 2005, 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 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. 304, 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, to be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Michael L. Marshall, Jr., Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 2, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 304 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 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 3-3 3/4 3-3 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 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. 294 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 27, 2005, 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 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. 294, 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, to be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Michael L. Marshall, Jr., Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 2, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 294 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 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 3-3a 3/4 3-3a 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 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. 304 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO. 294 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 application dated April 27, 2005, the Tennessee Valley Authority (the licensee) proposed amendments to the Technical Specifications (TSs) for Sequoyah Nuclear Plant (SQN)
Units 1 and 2. The requested changes would revise the applicability of TS Functional Unit 18.A, Turbine Trip, Low Fluid Oil Pressure, and TS Functional Unit 18.B, Turbine Trip, Turbine Stop Valve Closure, in Table 3.3-1, Reactor Trip System Instrumentation, and Table 4.3-1, Reactor Trip System Instrumentation Surveillance Requirements. The proposed change will (1) add a footnote ** to limit applicability of Functional Units 18.A and 18.B above the P-9 (50-percent rated thermal power) interlock setpoint and (2) replace the current Action 6 with a new Action 7 for Functional Unit 18.B.
The current TS specifies 1" in Applicable Modes column for these instrument channels in TS Tables 3.3-1 and 4.3-1. The new footnote ** states, Above the P-9 (Power Range Neutron Flux) interlock.
The current TS specifies Action 6 in TS Table 3.3-1 for Functional Unit 18.B instrument channels. Action 6 states:
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.1.
The new Action 7 reads:
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or THERMAL POWER is reduced to less than P-9 within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
2.0 REGULATORY EVALUATION
The staff used the Commissions regulatory requirements for TS changes set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 for this evaluation. Specifically, 10 CFR 50.36(c)(2) specifies the requirements for limiting conditions for operation, and 10 CFR 50.36(c)(3) specifies the surveillance requirements. The staff also used General Design Criterion 20, Protection System Functions, and General Design Criterion 21, Protection System Reliability and Testability, of Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50. In addition, the staff considered guidance and information in NUREG-1431, Revision 3, "Standard Technical Specifications for Westinghouse Plants," Chapter 7 of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," and the Sequoyah Nuclear Plant, Units 1 and 2, Updated Final Safety Analysis Report (UFSAR) in its evaluation.
3.0 TECHNICAL EVALUATION
The first change will add a footnote to limit applicability of Functional Units 18.A, Turbine Trip, Low Fluid Oil Pressure, and 18.B, Turbine Trip, Turbine Stop Valve Closure, in TS Tables 3.3-1 and 4.3-1 above the P-9 (50 percent rated thermal power) interlock setpoint. The current TS states that Functional Units 18.A, and 18.B, are applicable in Mode 1. As explained in Chapters 7.2.1.1.2 and 7.2.1.1.3 of Sequoyah Nuclear Plant, Units 1 and 2, UFSAR, Functional Units 18.A and 18.B are used to trip the reactor in the event of a turbine trip while operating above the P-9 interlock setpoint. This reactor trip on turbine trip is an anticipatory reactor trip on loss of heat removal capabilities of the secondary system following a turbine trip. When the turbine trips, the turbine auto stop oil pressure drops, which trips the reactor while operating above the P-9 interlock setpoint. Below the P-9 interlock setpoint, the turbine trip will not actuate a reactor trip (the P-9 interlock blocks turbine trip) and the reactor control system and the steam dump system will automatically bring the reactor to zero power condition. In Modes 2, 3, 4, 5, or 6, there is no potential for a turbine trip, and therefore, the Functional Units 18.A and 18.B do not need to be OPERABLE. The addition of the footnote **, which reads, Above the P-9 (Power Range Neutron Flux) interlock will make the Applicable Mode more specific for Functional Units 18.A and 18.B. This change is consistent with the latest version of NUREG-1431, Revision 3, Standard Technical Specifications for Westinghouse Plants, dated March 2004, therefore, the staff finds the proposed TS change acceptable.
The second TS request replaces Action 6 by Action 7 for Functional Unit 18.B, Turbine Stop Valve Closure. Functional Unit 18.B requires actuation of all four channels to generate the trip signal. Part b of Action 6, which allows one channel to be inoperable, contradicts the minimum channel operable requirement of Functional Unit 18.B. The new Action 7 eliminates this contradiction and is consistent with NUREG-1431, Revision 3. The proposed Action 7 will also eliminate the allowance to bypass a channel for surveillance testing. To meet the requirement that all four channels be available for the reactor trip, a channel cannot be placed in the bypass condition for the surveillance test. This change is also consistent with NUREG-1431, Revision 3. The third difference between Action 6 and Action 7 is the addition of a 10-hour time period to reduce the thermal power below the P-9 interlock setpoint for continued operation if the inoperable channel cannot be placed in trip condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This time period of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for power reduction below the P-9 interlock setpoint is more conservative than the current TS 3.0.3 requirement of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, which includes 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to place the channel in trip condition, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to initiate actions to proceed to a nonapplicable condition, and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to be in hot shutdown. Because this change is more conservative, the staff finds this change acceptable.
The NRC staff has reviewed the proposed TS changes to Functional Units 18.A and 18.B of Tables 3.3-1 and 4.3-1 and finds these changes in compliance with 10 CFR 50.36 criteria.
Also, revising the current statements to conform with the NUREG-1431, Revision 3, is more conservative, eliminates contradictions and is, therefore, acceptable to the staff.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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 (70 FR 38722). Accordingly, the amendments 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 these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Mazumdar Dated: September 2, 2005