ML042660561

Issuance of Amendments Regarding Technical Specification Changes for Physics Test Exceptions and Refueling Operations

ML042660561
Person / Time
Site:	Sequoyah
Issue date:	09/20/2004
From:	Robert Pascarelli NRC/NRR/DLPM/LPD2
To:	Singer K Tennessee Valley Authority
Pascarelli, R J
References
TAC MC2446, TAC MC2447
Download: ML042660561 (15)

Text

September 20, 2004 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 PHYSICS TEST EXCEPTION AND REFUELING OPERATIONS (TAC NOS. MC2446 AND MC2447) (TSC 03-05)

Dear Mr. Singer:

The Commission has issued the enclosed Amendment No. 295 to Facility Operating License No. DPR-77 and Amendment No. 285 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 March 5, 2004 (ADAMS Accession No. ML040760886).

The amendments delete the surveillance requirements to perform a channel functional test within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of core alterations and each power range and intermediate range nuclear instrument within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating physics tests. The associated bases sections have also been revised to reflect these changes. These changes were based on Technical Specification Task Force Traveler 108 and Revision 2 to NUREG-1431.

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/

Robert J. Pascarelli, 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. 295 to License No. DPR-77

2. Amendment No. 285 to License No. DPR-79

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

ML040760886).

The amendments delete the surveillance requirements to perform a channel functional test within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of core alterations and each power range and intermediate range nuclear instrument within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating physics tests. The associated bases sections have also been revised to reflect these changes. These changes were based on Technical Specification Task Force Traveler 108 and Revision 2 to NUREG-1431.

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/

Robert J. Pascarelli, 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. 295 to License No. DPR-77

2. Amendment No. 285 to License No. DPR-79

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

• Concurrence Per Safety Evaluation Input Package No.:

Enclosure:

ADAMS ACCESSION NO. ML042660561 NRR-058 OFFICE PDII-2/PM PDII-2/LA OGC SRXB/SC EEIB/SC NAME RPascarelli EDunnington for BClayton HMcGurren JUhle*

AMarinos*

DATE 09/07/04 9/7/04 08/31/04 06/02/04 07/12/04 OFFICE IROB/SC PDII-2/SC (A)

NAME TBoyce MMarshall DATE 08/23/04 9/20/04

DISTRIBUTION FOR SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 ISSUANCE OF AMENDMENTS REGARDING PHYSICS TEST EXCEPTION AND REFUELING OPERATIONS (TAC NOS. MC2446 AND MC2447) (TSC 03-05)

DISTRIBUTION:

PUBLIC PDII-2 R/F RidsNrrDlpmDpr RidsNrrDlpmpdii (EHackett)

RidsNrrDlpmLpdii2 (MMarshall)

RidsNrrPMRPascarelli RidsNrrLABClayton (Hard Copy)

RidsRgn2MailCenter (SCahill)

RidsAcrsAcnwMailCenter GHill (4 hard copies)

RidsOgcRp GHill (4 Copies)

TBoyce JUhle EMarinos

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. James E. Maddox, Vice President Engineering & Technical Services 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. Mark J. Burzynski, Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Pedro Salas, Manager Licensing and Industry Affairs 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. 295 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 March 5, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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. 295, 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., Acting 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 20, 2004

ATTACHMENT TO LICENSE AMENDMENT NO. 295 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 area of change.

REMOVE INSERT 3/4 9-2 3/4 9-2 3/4 10-3 3/4 10-3 3/4 10-4 3/4 10-4 B 3/4 9-1 B 3/4 9-1 B 3/4 10-1 B 3/4 10-1

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 285 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 March 5, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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. 285, 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., Acting 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 20, 2004

ATTACHMENT TO LICENSE AMENDMENT NO. 285 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 area of change.

REMOVE INSERT 3/4 9-3 3/4 9-3 3/4 10-3 3/4 10-3 3/4 10-4 3/4 10-4 B 3/4 9-1 B 3/4 9-1 B 3/4 10-1 B 3/4 10-1

1 A CHANNEL OPERATIONAL TEST is equivalent to a CHANNEL FUNCTIONAL TEST.

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 295 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO. 285 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 March 5, 2004 (Reference 1), Tennessee Valley Authority (TVA or licensee) requested changes to the Technical Specifications (TSs) of Sequoyah Nuclear Plant Units 1 and 2. TVA requested an amendment to TS 3/4.9.2, Instrumentation, TS 3/4.10.3, Physics Tests, and TS 3/4.10.4, Reactor Coolant Loops. The licensees amendment proposed changes to the surveillance requirements (SRs) associated with the TSs mentioned above.

The proposed changes to TS 3/4.10.3 and TS 3/4.10.4 have been approved by the U.S.

Nuclear Regulatory Commission (NRC) for another TVA facility (Watts Bar Nuclear Plant) and are consistent with Technical Specifications Task Force (TSTF) Traveler-108, Eliminate the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Channel Operational Test (COT)1 on Power Range and Intermediate Range Channels for Physics Test Exceptions.

2.0 REGULATORY EVALUATION

The purpose of the Nuclear Instrumentation System (NIS) is to monitor the power level of the reactor at anytime during operation. It is used primarily for plant protection, providing appropriate alarm functions for various phases of plant operating and shutdown conditions. It provides secondary control function and indicates reactor status during startup and power operation. The NIS consists of three overlapping ranges of instrumentation: Source, Intermediate, and Power. Each range provides overpower trip protection at increasing levels during startup and at power operation.

The NIS provides indication, alarm, control, and trip signals, along with the capability to monitor neutron flux over the complete range from reactor shutdown to 120-percent full power. The system generates permissive and level trip signals, which are then coupled to the logic matrices of the reactor trip system. This interface either allows power changes based upon proper functioning of the next range of measurement instrumentation or shuts down the reactor as unsafe operating limits are approached.

The NIS is designed to initiate nuclear overpower reactor trip signals for the reactor trip system (RTS) as a result of detecting high neutron flux or a high neutron flux rate of change and to monitor the neutron flux during and following an accident. This system offers diverse protection against fuel cladding failure and/or loss of reactor coolant system integrity.

The Power Range, Intermediate Range, and Source Range monitors are part of the NIS excore neutron detectors. The RTS SRs require a CHANNEL FUNCTIONAL TEST be performed on these monitors to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

In Section 50.36(c) of Title 10 of the Code of Federal Regulations (10 CFR 50.36), the Commission established the regulatory requirements related to the content of TSs. Section 50.36(c)(3) requires that the TSs include surveillance requirements. Surveillance requirements relate to test, calibration, or inspection to assure that necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. The NIS system offers diverse protection against fuel cladding failure and/or loss of reactor coolant system integrity.

According to 10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants, Criterion 13, Instrumentation and Controls, instrumentation shall be provided to monitor variables and systems over their operating ranges during normal operation, anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety.

The regulatory basis of Limiting Condition for Operation (LCO) 3.10.3 (TS 3/4.10.3) is to permit relaxation of existing LCOs to allow certain PHYSICS TESTS to be performed in MODE 2. In order to suspend the applicable LCOs during the tests, LCO 3.10.3 requires certain limitations in thermal power, reactor trip setpoints for Intermediate and Power Range channels, and Reactor Coolant System loop temperature. SR 4.10.3.2, which is part of TS 3/4.10.3, requires a CHANNEL FUNCTIONAL TEST for each Intermediate and Power Range channel within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating the PHYSICS TESTS in order to ensure that the RTS is properly aligned and provides the required degree of core protection during the performance of the PHYSICS TESTS.

The regulatory basis of LCO 3.10.4 (TS 3/4.10.4) is to provide an exception to LCO 3.4.1.1 (TS 3/4.4.1, Reactor Coolant Loops and Coolant Circulation) to permit reactor criticality under no flow conditions during certain PHYSICS TESTS performed while at low thermal power levels (below the P-7 interlock setpoint). In order to suspend LCO 3.4.1.1 during the tests, LCO 3.10.4 requires certain limitations in thermal power and reactor trip setpoints for Intermediate and Power Range channels. SR 4.10.4.2, which is part of TS 3/4.10.4, requires a CHANNEL FUNCTIONAL TEST for each Intermediate, Power Range, and P-7 interlock channel within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating startup or PHYSICS TESTS in order to ensure that the RTS is properly functioning and to provide the required degree of core protection during the performance of the PHYSICS TESTS.

On May 2, 1997, the NRC approved TSTF-108 (Reference 2). This TSTF allowed the deletion of the CHANNEL FUNCTIONAL TEST required by SR 3.1.10.1 and SR 3.4.19.2 within 2 SR 3.1.10.1 and SR 3.4.19.2 correspond to Westinghouse Standard Technical Specifications, Revision 1, April 7, 1995. These SRs are equivalent to Sequoyahs SR 4.10.3.2 and SR 4.10.4.2, respectively.

3 Watts Bars SR 3.1.10.1 is equivalent to Sequoyahs SR 4.10.3.2.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to the initiation of PHYSICS TESTS.2 The justification of the proposed change on TSTF-108 relied, mainly, on the fact that a CHANNEL FUNCTIONAL TEST is required for Intermediate Range and Power Range neutron flux monitors by RTSs SR every 92 days. The 92-day frequency has been determined by the staff to be sufficient for verification that the Power Range and Intermediate Range are properly functioning.

By letter dated September 13, 2000 (Reference 3), the NRC approved the adoption of TSTF-108 for another TVA facility, Watts Bar Nuclear Plant Unit 1. TVA requested to eliminate the COT that is required 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to the performance of PHYSICS TESTS from SR 3.1.10.13 (LCO 3.1.10, Physics Tests Exemptions-Mode 2).

The regulatory basis of LCO 3.9.2 (TS 3/4 9.2) is to provide, as a minimum, two OPERABLE and operating source range neutron flux monitors, providing each with continuous visual indication in the control room and audible indication in the containment and control room during MODE 6. SR 4.9.2 currently requires that a CHANNEL FUNCTIONAL TEST be performed on the source range monitors within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to initiation of CORE ALTERATIONS, even though SR 4.3.1.1 has been performed on the required frequency. The licensee proposed to delete the 8-hour requirement so that the testing performed for SR 4.3.1.1 may be used to satisfy SR 4.9.2. Additionally, Revision 1 to NUREG-1431 has deleted SR 4.9.2 to perform a CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to initial start of core alterations.

3.0 TECHNICAL EVALUATION

TVA requested an amendment to TS 3/4.10.3, Physics Tests, and TS 3/4.10.4, Reactor Coolant Loops. TS 3/4.10.3 contains SR 4.10.3.2, which requires a CHANNEL FUNCTIONAL TEST for each Intermediate Range and Power Range channel within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS in MODE 2. Similarly, TS 3/4.10.4 contains SR 4.10.4.2, which requires a CHANNEL FUNCTIONAL TEST for each Intermediate Range and Power Range channel and P-7 interlock within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating startup or PHYSICS TESTS during operation below the P-7 interlock setpoint. The licensee requested the following changes to the TSs mentioned above:

1. Deletion of the within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> requirement from SR 4.10.3.2 to specify that the CHANNEL FUNCTIONAL TEST is only required prior to initiating the PHYSICS TESTS.

2. Deletion of the within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> requirement from SR 4.10.4.2 to specify that the CHANNEL FUNCTIONAL TEST is only required prior to initiating the startup or the PHYSICS TESTS.

In addition, the licensee will revise the associated TS Bases 3/4.10.3 and 3/4.10.4 to reflect the proposed amendment. The licensee states that the proposed changes are consistent with TSTF-108.

TSTF-108 relies on the fact that RTS SRs require the performance of CHANNEL OPERATIONAL TESTS for Power Range and Intermediate Range every 92 days. The NRC staff has determined that the 92-day frequency is sufficient for verification that the Power Range and Intermediate Range are properly functioning. Also, TSTF-108 relied on the fact that initiation of PHYSICS TESTS does not impact the ability of the monitors to perform their required function, does not affect the trip setpoints or RTS trip capability, and does not invalidate previous surveillances.

TVA is requesting the adoption of TSTF-108 for Sequoyah Nuclear Plant Units 1 and 2. TVA states that Sequoyahs RTS SR 4.3.1.1 requires the performance of a CHANNEL OPERATIONAL TEST for the Power Range monitors every 92 days, for the Source Range monitors every 31 days, except when above the P-6 permissive, and during startup for the Intermediate Range monitors if not performed within the previous 31 days. This SR is also performed prior to startup of the reactor and at various points during power escalation or reduction. Therefore, the licensee considers that an additional surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to the Physics Test is an extraneous and unnecessary performance of a surveillance.

The licensee also states that the surveillance is not related to any LCO requirement and has no appropriate action to enter upon failure to meet the surveillance. TVA concludes that the deletion of the within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from the surveillance and reliance on the CHANNEL FUNCTIONAL TEST surveillance specified within the RTS Instrumentation LCO enhances the proper utilization of the TSs.

The NRC staff has reviewed the licensees request and, based on the information provided by the licensee, the NRC staff found that TSTF-108 is applicable to Sequoyah Nuclear Plant. The licensee intends to implement the TSTF without any deviation from the TSTF. The NRC staff agrees with the licensees technical evaluation that the frequencies of Sequoyahs RTS SRs are sufficient to demonstrate that the Intermediate and Power Range monitors are properly functioning. Sequoyahs RTS SRs provide a similar testing approach as the SRs that support the TSTF-108. The NRC staff agrees that the additional testing within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating the physics tests is not necessary for Sequoyah Nuclear Plant Units 1 and 2. The proposed change has no impact on the assumptions of any transient or accident analysis in the Updated Final Safety Analysis Report. Therefore, the NRC staff finds that the deletion of the 12-hour requirement from SR 4.10.3.2 and SR 4.10.4.2 is acceptable and in compliance with the regulations.

Additionally, TVA requested an amendment to TS 3/4.9.2, Instrumentation. TS SR 4.9.2, c.

requires a CHANNEL FUNCTIONAL TEST of the source range channels within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to initial start of CORE ALTERATIONS regardless of whether the CHANNEL FUNCTIONAL TEST has been performed within its required frequency as specified in SR 4.3.1.1. Also, SR 4.9.2 requires a CHANNEL FUNCTIONAL TEST for the source range monitors be performed before entering Mode 6 and at least once per 7 days. Hence, a CHANNEL FUNCTIONAL TEST would have been performed within the previous 7 days of CORE ALTERATIONS. An additional performance of this SR prior to initial start of core alterations is an unnecessary verification that the monitor is operable. Since the monitors provide audible indication in the control room, the operators would know if the monitor became inoperable. Initiation of core alterations does not impact the ability of the source range monitors to perform their required function and does not affect the trip setpoints or RTS trip capability. TS SR 4.9.2, c., A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATION, is an additional and unnecessary test; therefore, the proposed removal of SR 4.9.2, c. is acceptable. The plant continues to meet 10 CFR 50.36 as this change has no impact on the 10 CFR 50.36 requirements.

4.0 STATE CONSULTATION

In accordance with the Commissions 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 the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.

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 19576; April 13, 2004). 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 reviewed the proposed amendment to TS 3/4 9.2, TS 3/4.10.3 and TS 3/4.10.4 at Sequoyah Nuclear Plant and has found them acceptable. The Commission has concluded, based on the nature of the proposed changes, 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 Commissions 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.

7.0 REFERENCES

1. License Amendment Request (TVA-SQN-TS-03-05), Physics Tests Exceptions and Refueling Operations, March 5, 2004, ADAMS Accession No. ML040760886.

2. Industry/TSTF Standard Technical Specification Change Traveler, TSTF-108, Eliminate the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Channel Operational Test (COT) on Power Range and Intermediate Range Channels for Physics Test Exceptions, approved on May 5, 1997, ADAMS Accession No. ML040480061.

3. Letter to J.A. Scalice, Chief Nuclear Officer and Executive Vice President of Tennessee Valley Authority, Issuance of Amendment Regarding Physics Tests Exceptions (TS-00-08)(TAC NO. MA9519), September 13, 2000, ADAMS Accession No. ML0037500040.

Principal Contributors: J. Rivera-Ortiz R. Taylor S. Rhow Date: September 20, 2004