ML090930330

Issuance of Amendment Regarding Removal of Main Steam Isolation Valve Closure Times (TS 08-04)

ML090930330
Person / Time
Site:	Sequoyah
Issue date:	06/12/2009
From:	Siva Lingam Plant Licensing Branch II
To:	Swafford P Tennessee Valley Authority
Orf, Tracy J.; NRR/DORL 415-2788
References
TAC ME0006, TAC ME0007
Download: ML090930330 (10)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 12, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT REGARDING REMOVAL OF MAIN STEAM ISOLATION VALVE CLOSURE TIMES (TS 08-04) (TAC NOS. ME0006 AND ME0007)

Dear Mr. Swafford:

The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 324 to Facility Operating License No. DPR-77 and Amendment No. 316 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 October 23, 2008. The amendments remove the main steam isolation valve closure times from the Technical Specifications and relocate them to the Technical Specification Bases.

A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in NRC's biweekly Federal Register notice.

Sincerely,

~(f'~

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328

Enclosures:

1. Amendment No. 324 to License No. DPR-77

2. Amendment No. 316 to License No. DPR-79

3. Safety Evaluation cc w/enclosures: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 324 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 October 23, 2008, 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, 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

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. 324 ,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci"fications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Thomas H. Boyce, Chie Plant Licensing Branch 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the license and Technical Specifications Date of Issuance: June 12, 2009

ATTACHMENT TO LICENSE AMENDMENT NO. 324 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace Page 3 of Operating License DPR-77 with the attached page.

Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by amendment number and contains a marginal line indicating the area of change.

REMOVE INSERT 3/47-10 3/47-10

- 3 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30,40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 324 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

b. Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

c. Performance of any test at power level different from there described; and Facility Operating License No. DPR-77 Amendment No. 324

PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATIOI'J 3.7.1.5 Four main steam line isolation valves shall be OPERABLE.

APPLICABIl ITY: MODES 1, 2, and 3 ACTION:

MODE 1 - With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; Otherwise, be in MODE 2 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 2 - With one or more main steam line isolation valves inoperable, and 3 subsequent operation in MODES 2 or 3 may proceed provided:

a. The isolation valve is restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />;

b. The inoperable isolation valve is verified closed once per 7 days;

c. Separate entry into this action is allowed for each isolation valve.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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 />.

SURVEILLANCE REQUIREMENTS 4.7.1.5.1 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within limits when tested pursuant to Specification 4.0.5.

4.7.1.5.2 At least once per 18 months, verify each main steam isolation valve closes on an actual or simulated automatic actuation signal.

SEQUOYAH - UNIT 1 3/47-10 Amendment 114, 236, 301, 324

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 316 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 October 23, 2008, 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, 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

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. 316 ,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 within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Thomas H. Boyce, C Plant Licensing Branc 11-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the license and Technical Specifications Date of Issuance: June 12, 2009

ATTACHMENT TO LICENSE AMENDMENT NO. 316 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace Page 3 of Operating License DPR-79 with the attached page.

Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by amendment number and contains a marginal line indicating the area of change.

REMOVE INSERT 3/47-10 3/47-10

-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 316 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

b. Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

c. Performance of any test at power level different from there described; and Facility Operating License No. DPR-79 Amendment No. 316

PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Four main steam line isolation valves shall be OPERABLE.

APPLICABILITY: MODE 1, 2, and 3 ACTION:

MODE 1 - With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; Otherwise, be in MODE 2 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 2 - With one or more main steam line isolation valves inoperable, and 3 subsequent operation in MODES 2 or 3 may proceed provided:

a. The isolation valve is restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />;

b. The inoperable isolation valve is verified closed once per 7 days;

c. Separate entry into this action is allowed for each isolation valve.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in 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 />.

SURVEILLANCE REQUIREMENTS 4.7.1.5.1 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within limits when tested pursuant to Specification 4.0.5.

4.7.1.5.2 At least once per 18 months, verify each main steam isolation valve closes on an actual or simulated automatic actuation signal.

SEQUOYAH - UNIT;~ 3/47-10 Amendment 104, 226, 290,316

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 324 TO FACILITY OPERATING LICENSE NO. DPR-77 AND AMENDMENT NO. 316 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 October 23, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083030397), Tennessee Valley Authority (the licensee), submitted a request for changes to the Technical Specifications (TS) for Sequoyah Nuclear Plant, Units 1 and 2 (SQN). The requested changes are the partial adoption of Technical Specifications Task Force (TSTF) Traveler, TSTF-491, Revision 2, "Removal of Main Steam and Feedwater Valve Isolation Times," which was proposed by the TSTF by letter on May 18, 2006. The proposed changes would revise TS 3.7.1.5, "Main Steam Line Isolation Valves," by relocating the main steam line isolation valve (MSIV) closure times to the TS Bases. The Nuclear Regulatory Commission (NRC or the Commission) announced the availability of TSTF-491 in the Federal Register on December 29, 2006, as part of the consolidated line item improvement process (CLlIP).

The licensee proposed partial adoption of TSTF-491 changes. TSTF-491 changed the technical specifications for MSIVs, main feedwater isolation, regulating, and bypass valves contained in NUREG-1431, Revision 3, "Standard Technical Specifications [STS], Westinghouse Plants," by removing the required closure times from STS. The licensee proposed adopting TSTF-491 for only the MSIV's, as the SQN TSs do not contain closure times for the main feedwater isolation, regulating, and bypass valves. Those times are established by the plant transient and accident analyses and verified in accordance with the Inservice Testing Program requirements.

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TS as part of the license. The TS ensure the operational capability of structures, systems and components that are required to protect the health and safety of the public.

The Commission's regulatory requirements related to the content of the TS are contained in Section 50.36 of Title 10 of the Code of Federal Regulations (10 CFR). That regulation requires that the TS include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings (50.36(c)(1>>; (2) Limiting Conditions for

-2 Operation (50.36(c)(2)); (3) Surveillance Requirements (SRs) (50.36(c)(3)); (4) design features (50.34(c)(4)); and (5) administrative controls (50.36(c)(5)).

In general, there are two classes of changes to TS: (1) changes needed to reflect modifications to the design basis (TS are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TS over time. This amendment deals with the second class of changes.

In determining the acceptability of revising SON TS 3.7.1.5, the staff used the accumulation of generically approved guidance in NUREG-1431, Revision 3. Licensees may revise the TS to adopt current improved STS format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (Le., no requirements are materially altered), (2) the change is more restrictive than the licensee's current requirement, or (3) the change is less restrictive than the licensee's current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.

3.0 TECHNICAL EVALUATION

One MSIV is located in each main steam line outside of the containment. Closing the MSIVs isolates each steam generator from the others and isolates the turbine, steam bypass system and other auxiliary steam supplies from the steam generator. By isolating the steam flow from the secondary side of the steam generator, the MSIVs prevent over cooling the reactor core following a high energy line break. By preventing core overcooling, the MSIVs protect the reactor core from being damaged.

The NRC staff reviewed the justification for TSTF-491 as described in the industry submittal dated September 13, 2005 (ADAMS Accession No. ML052590343). The licensee stated in their application dated October 23, 2008, that the information presented in the TSTF-491 proposal and the model SE prepared by the NRC staff are applicable to SON for the incorporation of the changes to SON TS 3.7.1.5.

SON SR 4.7.1.5.1 currently states "Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5."

The licensee proposed replacing the "5 seconds" in the sentence above with the word "limits."

The licensee also proposed modifying the final sentences in the TS Bases for TS 3.7.1.5 to state:

The OPERABILITY of the main steam isolation valves within the closure time of 5 seconds is consistent with the assumptions used in the accident analyses. Surveillance Requirements 4.7.1.5.1 verifies the closure time is in accordance with the Inservice Testing Program.

TSTF-491 relocated the required closure times to a Licensee Controlled Document (LCD) that is referenced in the STS Bases. The staff approved TSTF-491 on the basis that changes to LCDs are subject to the 10 CFR 50.59 process. This provides adequate assurance that prior staff review and approval will be requested by a licensee for changes to the LCD with the potential to

-3 affect the safe operation of the plant. The licensee proposed relocating the required closure times for the MSIVs to the SON TS Bases. SON has a TS Bases Control Program that requires that proposed changes to the Bases be subject to the 10 CFR 50.59 process. The staff reviewed the SON TS Bases Control Program and determined that the SON TS Bases Control Program provides adequate assurance that prior staff review and approval will be requested by the licensee for changes to the TS Bases with the potential to affect the safe operation of the plant.

Furthermore, the MSIVs are subject to periodic testing and acceptance criteria in accordance with the Inservice Testing (1ST) Program. Compliance with the 1ST Program is required by SR 4.0.5 and 10 CFR 50.55a. The 1ST Program includes specific reference value baseline operating times for valves that are not subject to arbitrary changes.

Section 50.36 of 10 CFR requires the inclusion of the periodic testing of the MSIVs in the Surveillance Requirements not the actual closure time of the valves. The licensee's partial adoption of TSTF-491 changes maintains the periodic testing requirements for MSIVs in accordance with 10 CFR 50.36.

Based on the requirements of 10 CFR 50.36, 10 CFR 50.59, and the 1ST Program, the staff concludes that relocating the MSIV closure time to the SON TS Bases is acceptable.

The licensee included in its application the revised TS Bases to be implemented with the TS change. The NRC staff finds that the TS Bases Control Program is the appropriate process for updating the affected TS Bases pages and has, therefore, not included the affected Bases pages with this amendment.

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 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 (74 FR 1716; January 13, 2009). 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.

-4

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 Contributors: Y. S. Huang M. E. Hamm Dated: June 12, 2009

June 12, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB..IECT: SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENT REGARDING REMOVAL OF MAIN STEAM ISOLATION VALVE CLOSURE TIMES (TS 08-04) (TAC NOS. ME0006 AND ME0007)

Dear Mr. Swafford:

The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 324 to Facility Operating License !'lo. DPR-77 and Amendment No. 316 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 October 23, 2008. The amendments remove the main steam isolation valve closure times from the Technical Specifications and relocate them to the Technical Specification Bases.

A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in NRC's biweekly Federal Register notice.

Sincerely, IRA!

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328

Enclosures:

1. Amendment No. 324 to License No. DPR-77

2. Amendment No. 316 to License No. DPR-79

3. Safety Evaluation cc w/enclosures: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrLACSola RidsRgn2MailCenter LPL2-2 R/F RidsOgcRp RidsN rrDciCptb RidsNrrDorlLpl2-2 RidsNrrDorlDpr MHamm, NRR RidsAcrsAcnw_MailCTR RidsNrrDirsltsb YHuang, NRR RidsNrrPMSequoyah ADAMS Accession No ML090930330 NRR-058 OGC NLO OFFICE LPL2-2/PM LPL2-2/LA ITSB/BC CPTB/BC LPL2-2/BC w/comment NAME Sling am CSoia RElliott* ..IMcHale* MSmith TBoyce DATE 06/08/09 06/08/09 5/28/09 3/17/09 06/11/09 06/12/09

• By memo OFFICIAL RECORD COpy