ML050480669

License Amendments 299 and 288, RCS & ECCS Enhancements

ML050480669
Person / Time
Site:	Sequoyah
Issue date:	03/09/2005
From:	Pickett D NRC/NRR/DLPM/LPD2
To:	Singer K Tennessee Valley Authority
Pickett D, NRR/DLPM, 415-1364
Shared Package
ML050480671	List: ML050480669
References
TAC MC4199, TAC MC4200
Download: ML050480669 (14)

Text

March 9, 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 REACTOR COOLANT SYSTEM AND EMERGENCY CORE COOLING SYSTEM ENHANCEMENTS (TAC NOS.

MC4199 AND MC4200)

Dear Mr. Singer:

The Commission has issued the enclosed Amendment No. 299 to Facility Operating License No. DPR-77 and Amendment No. 288 to Facility Operating License No. DPR-79 for the Sequoyah Nuclear Plant (SQN), Units 1 and 2, respectively. These amendments are in response to your application dated August 18, 2004 (TVA-SQN-04-03).

The amendments revise Technical Specification (TS) 3/4.4.2, Safety Valves - Shutdown, TS 3/4.4.3, Safety and Relief Valves - Operating, and TS 3/4.5.2, ECCS Subsystems - Tavg Greater Than or Equal to 350EF. TS 3/4.4.2 is eliminated because overpressure protection of the reactor coolant system does not rely upon the pressurizer safety valves during plant operation in Modes 4 and 5. TS 3/4.4.3 is revised to remove redundancy and add improvements consistent with NUREG-1431, Revision 3, Standard Technical Specifications for Westinghouse Plants. TS 3/4.5.2 is revised by adding a note to the Limiting Condition for Operation (LCO) supporting transition to and from LCO 3.4.12, Low Temperature Overpressure Protection (LTOP) System. These changes are improvements to the current SQN TSs and are consistent with the safety analyses and NUREG-1431, Revision 3.

K. Singer March 9, 2005 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. 299 to License No. DPR-77

2. Amendment No. 288 to License No. DPR-79

3. Safety Evaluation cc w/enclosures: See next page

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. 299 to License No. DPR-77

2. Amendment No. 288 to License No. DPR-79

3. Safety Evaluation cc w/enclosures: See next page DISTRIBUTION:

PUBLIC PDII-2 R/F KDesai DCoe TBoyce OGC ACRS GHill (2) MMarshall DLPM DPR BClayton DPickett SCahill, R2 CHarbuck EHackett Package No.: ML050480671 TS: ML050730303 ADAMS ACCESSION NO.: ML050480669 *No Legal Objection NRR-058 OFFICE PM:LPD2-2 LA:LPD2-2 SC:SRXB SC:IROB OGC SC:LPD2-2 NAME DPickett BClayton DCoe TBoyce Tsmith NLO w/ edits MMarshall DATE 02 / 24 /05 02 / 24 /05 02 / 14 /05 03/ 4 /05 03 / 7 /05 03 / 09 /05 OFFICIAL RECORD COPY

Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:

Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Paul L. Pace, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority ATTN: James D. Smith 6A Lookout Place Sequoyah Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Larry S. Bryant, General Manager Nuclear Engineering Mr. David A. Kulisek, Plant Manager Tennessee Valley Authority Sequoyah Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Soddy Daisy, TN 37384-2000 Mr. Randy Douet Senior Resident Inspector Site Vice President Sequoyah Nuclear Plant Sequoyah Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road P.O. Box 2000 Soddy Daisy, TN 37379 Soddy Daisy, TN 37384-2000 Mr. Lawrence E. Nanney, Director General Counsel Division of Radiological Health Tennessee Valley Authority Dept. of Environment & Conservation ET 11A Third Floor, L and C Annex 400 West Summit Hill Drive 401 Church Street Knoxville, TN 37902 Nashville, TN 37243-1532 Mr. John C. Fornicola, Manager County Mayor Nuclear Assurance and Licensing Hamilton County Courthouse Tennessee Valley Authority Chattanooga, TN 37402-2801 6A Lookout Place 1101 Market Street Ms. Ann P. Harris Chattanooga, TN 37402-2801 341 Swing Loop Road Rockwood, Tennessee 37854 Mr. Fredrick C. Mashburn Senior Program Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 299 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 August 18, 2004, 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. 299, 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 by May 15, 2005.

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: March 9, 2005

ATTACHMENT TO LICENSE AMENDMENT NO. 299 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 VI VI 3/4 4-3 3/4 4-3 3/4 4-4 3/4 4-4 3/4 4-4a 3/4 4-4a 3/4 5-4 3/4 5-4

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 288 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 August 18, 2004, 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. 288, 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 by the completion of the 2005 Sequoyah Unit 2 Cycle 13 Refueling Outage.

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: March 9, 2005

ATTACHMENT TO LICENSE AMENDMENT NO. 288 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 VI VI 3/4 4-6 3/4 4-6 3/4 4-7 3/4 4-7 3/4 4-8 3/4 4-8 3/4 5-4 3/4 5-4

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 288 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO. 299 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 August 18, 2004 (Agencywide Documents Access and Management Systems Accession No. ML042430463), the Tennessee Valley Authority (the licensee) proposed amendments to the Technical Specifications (TSs) for Sequoyah Nuclear Plant (SQN)

Units 1 and 2.

The proposed TS changes will revise TS 3/4.4.2, Safety Valves - Shutdown, 3/4.4.3, Safety and Relief Valves - Operating, and 3/4.5.2, ECCS [Emergency Core Cooling System]

Subsystems - Tavg Greater Than or Equal to 350 EF. TS 3/4.4.2 will be eliminated because overpressure protection of the reactor coolant system does not rely upon the pressurizer safety valves during plant operation in Modes 4 and 5. TS 3/4.4.3 will be revised to remove redundancy and add improvements consistent with NUREG-1431, Revision 3, Standard Technical Specifications for Westinghouse Plants. TS 3/4.5.2 will be revised by adding a note to the Limiting Condition for Operation (LCO) supporting transition to and from LCO 3.4.12, Low Temperature Overpressure Protection (LTOP) System. These changes are improvements to the current SQN TSs and are consistent with the safety analyses and NUREG-1431, Revision 3.

2.0 REGULATORY EVALUATION

The Commissions regulatory requirements related to the contents of TSs are set forth in Title 10, Code of Federal Regulations (10 CFR) Section 50.36, which ensures that the TS-specified LCO is consistent with assumed values of the initial conditions in the licensees safety analyses. In accordance with 10 CFR 50.36, the NRC staff and the Nuclear Steam System Supplier Owners Groups developed improved standard technical specifications which meets 10 CFR 50.36(c)(2)(ii) and 10 CFR 50.36(c)(3) requirements. The licensee is using the NRC staff approved NUREG-1431, Revision 3, Standard Technical Specifications for Westinghouse Plants.

General Design Criterion (GDC) 15, Reactor Coolant System Design, of Appendix A, General Design Criteria, to 10 CFR Part 50, provides design considerations for the reactor coolant system (RCS). TS 3/4.4.2 and TS 3/4.4.3 involve the RCS.

GDC 35, Emergency Core Cooling, of Appendix A to 10 CFR Part 50, provides design considerations for the ECCS. TS 3/4.5.2 involves the ECCS.

3.0 TECHNICAL EVALUATION

3.1 TS 3/4.4.2, Safety Valves - Shutdown Each SQN unit is equipped with three safety valves and two power operated relief valves (PORVs) which are connected to the pressurizer and provide overpressure protection, in conjunction with the reactor protection system for the RCS. TS 3/4.4.3, Safety and Relief Valves - Operating, requires that the pressurizer safety valves be operable during Modes 1, 2, and 3 with a lift setting of 2485 psig, +/- 3 percent. This ensures that RCS overpressure protection is provided during power operation. The pressurizer PORVs provide protection during the lower Modes of operation (Modes 4, 5, and 6) as part of the LTOP. The proposed changes are as follows:

TS 3/4.4.2, Safety Valves - Shutdown, is proposed to be deleted from the SQN TSs. The LCO currently states : A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2485 psig +/- 3 %. This TS is applicable to lower Modes of operation (Modes 4 and 5).

TS 3/4.4.3.1 requires that safety valves be operable during Modes 1, 2, and 3 with a lift setting of 2485 psig, +/- 3 percent. Below Mode 3, the RCS temperature is below 350 oF and the RCS pressure is significantly lower than the safety valve setpoint. The pressurizer safety valves are not credited for overpressure protection during Modes 4 and 5. For SQN, the pressure temperature limits report provides LTOP arming temperature of 350 oF. This temperature coincides with the Mode 3/Mode 4 transition temperature. The SQN LTOP system is armed during plant shutdown immediately following entry into Mode 4 when RCS temperature reaches less than 350 oF. The LTOP system is enabled and designed to protect the RCS from any overpressure condition during low temperature plant conditions. TS 3/4.4.12, Low Temperature Over Pressure Protection (LTOP) System, governs the operability requirements for the LTOP system during Modes 4, 5, and Mode 6 with the reactor vessel head on. Thus, RCS overpressure protection will be maintained during the lower Modes of operation and, therefore, there is no need to require one pressurizer safety valve to be OPERABLE during Modes 4 and 5. Therefore, the proposed change to delete TS 3/4.4.2 is acceptable.

3.2 TS 3/4.4.3, Safety and Relief Valves - Operating 3.2.1 TS 3.4.3.1, Safety Valves - Operating The proposed change revises the current action requirements to incorporate improved standard TS action requirements. The current Action statement for TS 3.4.3.1 is as follows:

With one pressurizer code safety valve inoperable, either restore the inoperable valve to operable status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The licensee proposes to revise the Action statement to become:

a) With one pressurizer safety valve inoperable, restore the inoperable valve to OPERABLE within 15 minutes.

b) With two or more pressurizer safety valves inoperable or with ACTION (a) above not completed within 15 minutes, be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in MODE 4 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The staff finds the proposed change acceptable because it provides better clarity and it will be consistent with NUREG-1431, Revision 3 requirements.

3.2.2 TS 3.4.3.2, Relief Valves - Operating TS 3.4.3.2 demonstrates operability of the PORVs during Modes 1, 2, and 3. Surveillance Requirement (SR) 4.4.3.2.1.a requires performance of a channel calibration of PORV actuation circuitry once every 18 months. However, SR 4.4.12.1.b (from TS 3/4.4.12, which is applicable in Modes 4, 5, and 6) also requires performance of a channel calibration of PORV actuation circuitry once every 18 months. In order to eliminate duplicity, the licensee has proposed to delete SR 4.4.3.2.1.a. The staff agrees that PORV actuation circuitry will be ensured through performance of SR 4.4.12.1.b. Therefore, the staff finds it acceptable to eliminate SR 4.4.3.2.1.a.

3.3. TS 3/4.5.2, ECCS Subsystems - Tavg Greater Than or Equal to 350 oF The proposed change will add a standard notation from NUREG-1431, Revision 3, to this LCO which states as follows:

In MODE 3, ECCS pumps may be made incapable of injecting to support transition into or from the APPLICABILITY of LCO 3.4.12, Low Temperature Overpressure Protection (LTOP)

System, for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or until the temperature of all RCS cold legs exceed LTOP arming temperature specified in the pressure temperature limits report (PTLR) plus 25 oF, whichever comes first.

For SQN, LTOP arming temperature is near the Mode 3 boundary temperature of 350 oF.

TS 3/4.4.12- LTOP, requires that certain ECCS pumps be rendered incapable of injecting at and below the LTOP arming temperature. When RCS temperature is at or near the Mode 3 boundary temperature, time is needed to make the pumps incapable of injecting prior to entering the LTOP applicability, and provide time to restore the inoperable pumps to operable status on exiting the LTOP applicability. The 4-hour time allowance is based on a reasonable time for the operator to perform this task under controlled plant conditions. The temperature 375 oF is based on a 25 oF margin above the 350 oF LTOP arming temperature. This provision is intended to minimize the chances of a cold overpressurization event.

This notation is consistent with the NUREG-1431, Revision 3. The staff finds the proposed change reasonable and necessary for operational flexibility. Therefore, the staff finds the proposed change acceptable.

3.4 Summary The NRC staff has reviewed the proposed TS changes and finds these changes in compliance with 10 CFR 50.36 criteria. Also these TS changes are consistent with the safety analyses and conform to NUREG-1431, Revision 3 guidelines. We find these changes are an improvement to the SQN TSs. The NRC staff concludes that the proposed TS changes are acceptable.

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 and changes 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 (69 FR 64991). 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: K. Desai Dated: March 9, 2005