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| | issue date = 02/06/2007 | | | issue date = 02/06/2007 |
| | title = Amendment, Low Pressure Coolant Injection Crosstie Valve Surveillance Requirement (TAC No. MD3544) (TS-458) | | | title = Amendment, Low Pressure Coolant Injection Crosstie Valve Surveillance Requirement (TAC No. MD3544) (TS-458) |
| | author name = Chernoff M H | | | author name = Chernoff M |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 |
| | addressee name = Singer K W | | | addressee name = Singer K |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000259 | | | docket = 05000259 |
| | license number = DPR-033 | | | license number = DPR-033 |
| | contact person = Chernoff M H, NRR/DORL, 415-4041 | | | contact person = Chernoff M, NRR/DORL, 415-4041 |
| | case reference number = TAC MD3544, TS-458 | | | case reference number = TAC MD3544, TS-458 |
| | package number = ML070300436 | | | package number = ML070300436 |
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| =Text= | | =Text= |
| {{#Wiki_filter:February 6, 2007Mr. Karl W. SingerChief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | | {{#Wiki_filter:February 6, 2007 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BROWNS FERRY NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENTREGARDING LOW PRESSURE COOLANT INJECTION CROSSTIE VALVE SURVEILLANCE REQUIREMENT (TAC NO. MD3544) (TS-458) | | BROWNS FERRY NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT REGARDING LOW PRESSURE COOLANT INJECTION CROSSTIE VALVE SURVEILLANCE REQUIREMENT (TAC NO. MD3544) (TS-458) |
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| ==Dear Mr. Singer:== | | ==Dear Mr. Singer:== |
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| The Commission has issued the enclosed Amendment No. 268 to Renewed Facility OperatingLicense No. DPR-33 for the Browns Ferry Nuclear Plant, Unit 1. This amendment is in response to your application dated November 9, 2006. This amendment deletes the Technical Specification Surveillance Requirement to verify the position of a low pressure coolant injection crosstie valve.A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in theCommission's biweekly Federal Register notice.Sincerely, | | The Commission has issued the enclosed Amendment No. 268 to Renewed Facility Operating License No. DPR-33 for the Browns Ferry Nuclear Plant, Unit 1. This amendment is in response to your application dated November 9, 2006. This amendment deletes the Technical Specification Surveillance Requirement to verify the position of a low pressure coolant injection crosstie valve. |
| /RA/ | | A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice. |
| Margaret H. Chernoff, Senior Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-259 | | Sincerely, |
| | /RA/ |
| | Margaret H. Chernoff, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 268 to DPR-33 | | : 1. Amendment No. 268 to DPR-33 |
| : 2. Safety Evaluationcc w/enclosures: See next page | | : 2. Safety Evaluation cc w/enclosures: See next page |
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| ML070300427NRR-058OFFICELPL2-2/PMLPL2-2/LASBWB/BC ITSB/BCOGCLPL2-2/BCNAMEMChernoffBClaytonGCranstonby Memo dtdTKobetzMZoblerPMilano forLRaghavanDATE 1/29/071/26/0712/21/06/21/072/5/072/6/07 TENNESSEE VALLEY AUTHORITYDOCKET NO. 50-259BROWNS FERRY NUCLEAR PLANT UNIT 1AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 268 Renewed License No. DPR-331.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Tennessee Valley Authority (the licensee)dated November 9, 2006, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment 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 andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-33 is hereby amended to read as follows:(2)Technical SpecificationsThe Technical Specifications contained in Appendices A and B, as revised throughAmendment No. 268, 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 implementedwithin 30 days from the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION/RA Patrick D. Milano for/
| | ML070300427 NRR-058 OFFICE LPL2-2/PM LPL2-2/LA SBWB/BC ITSB/BC OGC LPL2-2/BC NAME MChernoff BClayton GCranston TKobetz MZobler PMilano for by Memo dtd LRaghavan DATE 1/29/07 1/26/07 12/21/06 /21/07 2/5/07 2/6/07 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 268 Renewed License No. DPR-33 |
| L. Raghavan, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Tennessee Valley Authority (the licensee) dated November 9, 2006, 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 Renewed Facility Operating License No. DPR-33 is hereby amended to read as follows: |
| | (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 268, 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 30 days from the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA Patrick D. Milano for/ |
| | L. Raghavan, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Operating License and Technical Specifications Date of Issuance: February 6, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 268TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33DOCKET NO. 50-259Replace Page 3 of Renewed Operating License DPR-33 with the attached Page 3.Revise the Appendix A Technical Specifications by removing the pages identified below andinserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. REMOVE INSERT3.5-43.5-4 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33TENNESSEE VALLEY AUTHORITYBROWNS FERRY NUCLEAR PLANT, UNIT 1DOCKET NO. 50-25 | | Changes to the Operating License and Technical Specifications Date of Issuance: February 6, 2007 |
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| ==91.0 INTRODUCTION==
| | ATTACHMENT TO LICENSE AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Replace Page 3 of Renewed Operating License DPR-33 with the attached Page 3. |
| By letter to the U.S. Nuclear Regulatory Commission (NRC), dated November 6, 2006, theTennessee Valley Authority (the licensee) submitted a request for changes to the Browns Ferry Nuclear Plant, Unit 1, Technical Specifications (TS). The requested change would delete TS Surveillance Requirement (SR) 3.5.1.4, which requires monthly verification that the Low Pressure Coolant Injection (LPCI) Crosstie valve is in the closed position with its motive power removed.
| | Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. |
| | REMOVE INSERT 3.5-4 3.5-4 |
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| ==2.0 REGULATORY EVALUATION==
| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 |
| The LPCI is one of the systems that comprise the Emergency Core Cooling System (ECCS). Itis provided to automatically reflood the reactor core in time to limit cladding temperatures after a nuclear system loss-of-coolant accident (LOCA) when the reactor vessel pressure is below the shutoff head of the pumps. The LPCI system provides cooling by flooding, which differs from the Core Spray System that provides cooling by spraying. When the nuclear system pressure decreases to the pumping head of LPCI system, the check valve in the injection line opens and LPCI water is pumped into the reactor vessel to reflood the core. As stated in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46, the purposeof the ECCSs is to remove the residual and decay heat from the reactor core so that fuel clad melting is prevented and fuel clad damage is acceptably minimized. The criterion against which the ECCS System performance is measured is that ECCS systems shall limit cladding peak temperature to 2200 °F.
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| ==3.0 TECHNICAL EVALUATION== | | ==1.0 INTRODUCTION== |
| Description of ChangeThe change removes an SR that verifies that the LPCI loop discharge crosstie valve is in theclosed position with its motive power removed. The LPCI loop discharge crosstie valve has been physically removed and the associated piping has been capped or closed with a blind flange. The LPCI loop crosstie valve was physically removed and the associated piping capped orclosed with a blind flange as part of the Unit 1 restart effort. The removal of the crosstie valve also reduces the maintenance in a high-radiation area and, in turn, reduces ALARA (as low as reasonably achievable) concerns. Crosstie capability is not required for the mitigation of design basis events. EvaluationThe LPCI system previously had the ability to crosstie the redundant loops. This configurationprovided the LPCI system the flexibility to provide make-up flow into either of the loops. During normal operation the loops were isolated from one another through the use of a normally closed LPCI loop crosstie valve with the motive power removed.The purpose for the LPCI loop crosstie was for both LPCI loops to be able to provide reactormake-up flow into either of the two reactor recirculation loops under various LOCA pipe break scenarios. Subsequent to plant construction and licensing, analyses determined that the crosstie capability, under certain accident and single-failure scenarios, could result in the loss of injection from both LPCI loops. Additionally, analyses determined that the crosstie capability was not required for the mitigation of any design-basis events.The existence of the LPCI loop crosstie line was determined to be a liability in plant design andan SR was placed in TS Section 3.5.1, ECCS (Emergency Core Cooling System) - Operating.
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| SR 3.5.1.4 states, "Verify the LPCI cross tie valve is closed and power is removed from the valve operator." The frequency of this requirement is once every 31 days. This SR was intended to ensure the plant was in an analyzed condition.The LPCI system design has been changed to eliminate the crosstie ability. In this change, theLPCI loop crosstie valve has been physically removed and the associated piping has been capped or closed with a blind flange. This change was made as part of the Unit 1 restart effort.
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| The crosstie valve was not required for mitigation of design basis accidents. This design change makes it physically impossible for flow to occur between the two LPCI loops. The proposed change eliminates SR 3.5.1.4. With the removal of the LPCI loop crosstie valve,SR 3.5.1.4 is no longer necessary. The NRC staff reviewed the information supplied by the applicant and the Updated Final SafetyAnalysis Report, and concludes that the change in the mechanical separation inline from an isolation valve to a capped pipe does not affect adversely any safety function of the LPCI system. Therefore, the proposed TS change associated with this modification is acceptable.The licensee also provided its marked up changes to the affected TS Bases. The NRC staffhas no objection to the proposed TS Bases changes.
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| ==4.0 STATE CONSULTATION==
| | By letter to the U.S. Nuclear Regulatory Commission (NRC), dated November 6, 2006, the Tennessee Valley Authority (the licensee) submitted a request for changes to the Browns Ferry Nuclear Plant, Unit 1, Technical Specifications (TS). The requested change would delete TS Surveillance Requirement (SR) 3.5.1.4, which requires monthly verification that the Low Pressure Coolant Injection (LPCI) Crosstie valve is in the closed position with its motive power removed. |
| In accordance with the Commission's regulations, the Alabama State official was notified of theproposed issuance of the amendment. The State official had no comments.
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| ==5.0 ENVIRONMENTAL CONSIDERATION== | | ==2.0 REGULATORY EVALUATION== |
| The amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes SRs. | | |
| | The LPCI is one of the systems that comprise the Emergency Core Cooling System (ECCS). It is provided to automatically reflood the reactor core in time to limit cladding temperatures after a nuclear system loss-of-coolant accident (LOCA) when the reactor vessel pressure is below the shutoff head of the pumps. The LPCI system provides cooling by flooding, which differs from the Core Spray System that provides cooling by spraying. When the nuclear system pressure decreases to the pumping head of LPCI system, the check valve in the injection line opens and LPCI water is pumped into the reactor vessel to reflood the core. |
| | As stated in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46, the purpose of the ECCSs is to remove the residual and decay heat from the reactor core so that fuel clad melting is prevented and fuel clad damage is acceptably minimized. The criterion against which the ECCS System performance is measured is that ECCS systems shall limit cladding peak temperature to 2200 °F. |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | Description of Change The change removes an SR that verifies that the LPCI loop discharge crosstie valve is in the closed position with its motive power removed. The LPCI loop discharge crosstie valve has been physically removed and the associated piping has been capped or closed with a blind flange. |
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| | The LPCI loop crosstie valve was physically removed and the associated piping capped or closed with a blind flange as part of the Unit 1 restart effort. The removal of the crosstie valve also reduces the maintenance in a high-radiation area and, in turn, reduces ALARA (as low as reasonably achievable) concerns. Crosstie capability is not required for the mitigation of design basis events. |
| | Evaluation The LPCI system previously had the ability to crosstie the redundant loops. This configuration provided the LPCI system the flexibility to provide make-up flow into either of the loops. During normal operation the loops were isolated from one another through the use of a normally closed LPCI loop crosstie valve with the motive power removed. |
| | The purpose for the LPCI loop crosstie was for both LPCI loops to be able to provide reactor make-up flow into either of the two reactor recirculation loops under various LOCA pipe break scenarios. Subsequent to plant construction and licensing, analyses determined that the crosstie capability, under certain accident and single-failure scenarios, could result in the loss of injection from both LPCI loops. Additionally, analyses determined that the crosstie capability was not required for the mitigation of any design-basis events. |
| | The existence of the LPCI loop crosstie line was determined to be a liability in plant design and an SR was placed in TS Section 3.5.1, ECCS (Emergency Core Cooling System) - Operating. |
| | SR 3.5.1.4 states, Verify the LPCI cross tie valve is closed and power is removed from the valve operator. The frequency of this requirement is once every 31 days. This SR was intended to ensure the plant was in an analyzed condition. |
| | The LPCI system design has been changed to eliminate the crosstie ability. In this change, the LPCI loop crosstie valve has been physically removed and the associated piping has been capped or closed with a blind flange. This change was made as part of the Unit 1 restart effort. |
| | The crosstie valve was not required for mitigation of design basis accidents. This design change makes it physically impossible for flow to occur between the two LPCI loops. |
| | The proposed change eliminates SR 3.5.1.4. With the removal of the LPCI loop crosstie valve, SR 3.5.1.4 is no longer necessary. |
| | The NRC staff reviewed the information supplied by the applicant and the Updated Final Safety Analysis Report, and concludes that the change in the mechanical separation inline from an isolation valve to a capped pipe does not affect adversely any safety function of the LPCI system. Therefore, the proposed TS change associated with this modification is acceptable. |
| | The licensee also provided its marked up changes to the affected TS Bases. The NRC staff has no objection to the proposed TS Bases changes. |
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| | ==4.0 STATE CONSULTATION== |
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| | In accordance with the Commission's regulations, the Alabama State official was notified of the proposed issuance of the amendment. The State official had no comments. |
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| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
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| | The amendment changes 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 SRs. |
| The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (71 FR 67166). Accordingly, the amendment meets 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 amendment. | | The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (71 FR 67166). Accordingly, the amendment meets 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 amendment. |
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| ==6.0 CONCLUSION== | | ==6.0 CONCLUSION== |
| The Commission has concluded, based on the considerations discussed above, that: (1) thereis reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.Principal Contributor: Diana Woodyatt Date: February 6, 2007 Mr. Karl W. SingerBROWNS FERRY NUCLEAR PLANTTennessee 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, Vice PresidentNuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Brian O'Grady, Site Vice PresidentBrowns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Preston D. Swafford, Senior Vice PresidentNuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 General CounselTennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902Mr. John C. Fornicola, General ManagerNuclear Assurance Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Bruce Aukland, Plant ManagerBrowns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Masoud Bajestani, Vice PresidentBrowns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Robert G. Jones, General ManagerBrowns Ferry Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Larry S. MellenBrowns Ferry Unit 1 Project Engineer Division of Reactor Projects, Branch 6 U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW. | | |
| Suite 23T85 Atlanta, GA 30303-8931 Ms. Beth A. Wetzel, ManagerCorporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Mr. William D. Crouch, ManagerLicensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Senior Resident InspectorU.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970State Health OfficerAlabama Dept. of Public Health RSA Tower - Administration
| | The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| | Principal Contributor: Diana Woodyatt Date: February 6, 2007 |
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| Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017ChairmanLimestone County Commission 310 West Washington Street Athens, AL 35611Mr. Robert H. Bryan, Jr., General ManagerLicensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801}} | | Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc: |
| | Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW. |
| | Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Ms. Beth A. Wetzel, Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Preston D. Swafford, Senior Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, General Manager 10833 Shaw Road Nuclear Assurance Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Mr. Robert H. Bryan, Jr., General Manager Tennessee Valley Authority Licensing and Industry Affairs P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801}} |
Letter Sequence Other |
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MONTHYEARML0631800372006-11-14014 November 2006
Individual Notice, Low Pressure Coolant Injection Loop Crosstie Valve Position Verification
Project stage: Other
ML0703004272007-02-0606 February 2007
Amendment, Low Pressure Coolant Injection Crosstie Valve Surveillance Requirement (TAC No. MD3544) (TS-458)
Project stage: Other
2006-11-14
[Table View] |
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Category:Letter
MONTHYEARIR 05000259/20240102024-11-12012 November 2024
Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010
IR 05000259/20240032024-11-0404 November 2024
Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003
CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024
Application for Subsequent Renewed Operating Licenses, Second Safety Supplement
ML24305A1692024-10-31031 October 2024
Site Emergency Plan Implementing Procedure Revision
05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024
Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators
05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024
Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure
ML24299A2632024-10-25025 October 2024
Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075
ML24289A1232024-10-24024 October 2024
Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry
CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24308A0042024-10-16016 October 2024
Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County
CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024
Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1
ML24270A2162024-09-27027 September 2024
Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075
ML24262A1502024-09-24024 September 2024
Requalification Program Inspection - Browns Ferry Nuclear Plant
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024
Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
ML24262A0602024-09-23023 September 2024
Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan
ML24263A2952024-09-19019 September 2024
Site Emergency Plan Implementing Procedure Revision
CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024
Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000260/20240902024-09-17017 September 2024
NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1
CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024
Cycle 16 Reload Analysis Report
ML24255A8862024-09-10010 September 2024
Core Operating Limits Report for Cycle 16 Operation, Revision 0
IR 05000259/20244042024-09-0303 September 2024
Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter
ML24239A3332024-09-0303 September 2024
Full Audit Plan
IR 05000259/20240052024-08-26026 August 2024
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005
ML24225A1682024-08-16016 August 2024
– Notification of Inspection and Request
ML24219A0272024-08-0606 August 2024
Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000259/20244022024-08-0606 August 2024
Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402
IR 05000259/20240022024-08-0202 August 2024
Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002
ML24199A0012024-07-22022 July 2024
Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
ML24183A4142024-07-10010 July 2024
– License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296)
05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024
Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints
05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024
Inoperability of Unit 3 Diesel Generator Due to Relay Failure
ML24184A1142024-07-0202 July 2024
Site Emergency Plan Implementing Procedure Revision
ML24183A3842024-07-0101 July 2024
Registration of Use of Cask to Store Spent Fuel (MPC-364, -365)
ML24179A0282024-06-26026 June 2024
Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a)
05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024
Reactor Scram Due to Generator Step-Up Transformer Failure
ML24175A0042024-06-23023 June 2024
Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System
ML24176A1132024-06-23023 June 2024
American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper
ML24089A1152024-06-21021 June 2024
Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2)
ML24155A0042024-06-18018 June 2024
Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47)
ML24158A5312024-06-0606 June 2024
Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363)
ML24071A0292024-06-0505 June 2024
Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter
ML24068A2612024-06-0505 June 2024
SLRA Fluence Methodology Report - Proprietary Determination Letter
ML24151A6322024-05-30030 May 2024
Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report
IR 05000259/20244032024-05-22022 May 2024
– Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403
05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024
High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation
ML24141A0482024-05-17017 May 2024
EN 56958_1 Ametek Solidstate Controls, Inc
ML24136A0702024-05-15015 May 2024
2023 Annual Radiological Environmental Operating Report
IR 05000259/20240012024-05-14014 May 2024
Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001
CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
2024-09-03
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24043A0462024-02-16016 February 2024
Summary of Meeting with TVA to Discuss Use of Risk-Informed Process Evaluation (RIPE) for a Proposed LAR Regarding Elimination of Limiting Condition for Operation Actions for Rod Worth Minimizers
ML23319A1992024-01-0303 January 2024
Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves
ML23257A1232023-09-22022 September 2023
Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315
ML23205A2132023-09-0808 September 2023
Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1
ML23171A8862023-07-24024 July 2023
Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML23116A2472023-05-23023 May 2023
Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control
ML23101A1102023-05-16016 May 2023
Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications
ML23073A2902023-05-0202 May 2023
Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times
ML22348A0052023-01-25025 January 2023
Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements
ML22349A6472023-01-20020 January 2023
Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules
ML22348A0662023-01-13013 January 2023
Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary
ML22271A9142022-12-0707 December 2022
Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme
ML22327A0182022-12-0101 December 2022
Correction of Error Incurred During Issuance of License Amendment No. 322
ML22273A1032022-11-22022 November 2022
Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification
ML22220A2602022-11-21021 November 2022
Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A
ML22138A3252022-06-24024 June 2022
Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis
ML22161A9292022-06-10010 June 2022
Bf 2022-301 Exam Report Items, SRO Written Exam
ML22020A2282022-03-16016 March 2022
Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2
ML21285A0682021-10-28028 October 2021
Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2
ML21214A1392021-08-30030 August 2021
Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters
ML21173A1772021-07-27027 July 2021
Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components
ML21075A0762021-04-30030 April 2021
Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis
ML21041A4892021-04-0808 April 2021
Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3
ML20268A0822021-01-12012 January 2021
Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications
ML20282A3452020-11-19019 November 2020
Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements
ML20190A1052020-08-11011 August 2020
Correction to Amendment No. 319 Regarding Revisions to Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation
ML20085G8962020-06-26026 June 2020
Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times
ML19294A0112019-12-26026 December 2019
Issuance of Amendment Nos. 311, 334, and 294 Adopt Technical Specifications Task Force Traveler, TSTF-542, Revision 2
ML18277A1102019-08-27027 August 2019
Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection
ML19198A0012019-08-13013 August 2019
Issuance of Amendment Nos. 308, 331, and 291 to Extend Implementation Due Date for Modifications 102 and 106 Related to NFPA 805 (Eid L-2019-LLA-0140)
ML19037A1372019-04-0202 April 2019
Revisions to Modifications 85, 102 and 106 Related to National Fire Protection Association 805 Performance-based Standard for Fire Protection of Light Water Reactor Electric Generating Plants
ML18241A3192018-10-0909 October 2018
Issuance of Amendment Nos. 306, 329, and 289 to Revise Approved NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants-Revision
ML18251A0032018-09-27027 September 2018
Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292)
ML18138A4522018-05-29029 May 2018
Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20
ML17289A0322017-12-22022 December 2017
Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160)
ML17215A2432017-10-0202 October 2017
Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566)
ML17032A1202017-08-14014 August 2017
Non-Proprietary Issuance of Amendments Regarding Extended Power Uprate
ML17034A3602017-03-27027 March 2017
Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ...
ML17052A1362017-03-16016 March 2017
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendment Nos. 297, 321, and 281 to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 (CAC Nos. MF8125, MF8126, and MF8127)
ML16330A1582017-01-17017 January 2017
Issuance of Amendments Regarding Revisions to Technical Specification 4.3.1.2, Fuel Storage Criticality
ML16028A4142016-04-26026 April 2016
Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio
ML15317A4782016-02-0909 February 2016
Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio
ML15344A3212016-01-0707 January 2016
Issuance of Amendment Regarding Modification of Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits
ML15321A4722015-12-23023 December 2015
Issuance of Amendments Regarding Revision to Table 3.3.6.1-1, Primary Containment Isolation Instrumentation
ML15287A2132015-12-16016 December 2015
Issuance of Amendments Regarding Technical Specification Changes to Reactor Core Safety Limits
ML15324A2472015-12-14014 December 2015
Issuance of Amendment to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Valves to Licensee Control
ML15287A3712015-12-0404 December 2015
Issuance of Amendments for the Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-535 (CNL-15-029)
ML15212A7962015-10-28028 October 2015
Issuance of Amendments to Transition to Fire Protection Program NFPA-805
ML15251A5402015-09-29029 September 2015
Issuance of Amendment Regarding Control Rod Scram Time Testing Frequency Per TSTF-460, Revision 0
ML15065A0492015-06-0202 June 2015
Issuance of Amendment Revising Pressure and Temperature Limit Curves
2024-02-16
[Table view]
Category:Safety Evaluation
MONTHYEARML23319A1992024-01-0303 January 2024
Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves
ML23205A2132023-09-0808 September 2023
Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1
ML23219A1542023-08-17017 August 2023
Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program
ML23171A8862023-07-24024 July 2023
Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML23116A2472023-05-23023 May 2023
Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control
ML23101A1102023-05-16016 May 2023
Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications
ML23073A2902023-05-0202 May 2023
Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times
ML23054A2902023-03-13013 March 2023
Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage
ML23048A3042023-03-0808 March 2023
Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047)
ML22348A0052023-01-25025 January 2023
Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements
ML22349A6472023-01-20020 January 2023
Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules
ML22348A0662023-01-13013 January 2023
Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary
ML22271A9142022-12-0707 December 2022
Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme
ML22273A1032022-11-22022 November 2022
Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification
ML22220A2602022-11-21021 November 2022
Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A
ML22298A2852022-11-14014 November 2022
Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526
ML22138A3252022-06-24024 June 2022
Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis
ML22084A0012022-04-0505 April 2022
Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes
ML22020A2282022-03-16016 March 2022
Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2
ML22010A1952022-01-12012 January 2022
Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants
ML21285A0682021-10-28028 October 2021
Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2
ML21214A1392021-08-30030 August 2021
Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters
ML21173A1772021-07-27027 July 2021
Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components
ML21075A0762021-04-30030 April 2021
Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis
ML21041A4892021-04-0808 April 2021
Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3
ML20268A0822021-01-12012 January 2021
Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications
ML20282A3452020-11-19019 November 2020
Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements
ML20253A1812020-09-23023 September 2020
Proposed Alternative to the Requirements of the American Society of Mechanical Engineers Code
ML20085G8962020-06-26026 June 2020
Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times
ML19329E3192020-01-0202 January 2020
SE Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC Nos. MF4540, MF4541 and MF4542; EPID No. L-2014-JLD-0044)
ML19294A0112019-12-26026 December 2019
Issuance of Amendment Nos. 311, 334, and 294 Adopt Technical Specifications Task Force Traveler, TSTF-542, Revision 2
ML18277A1102019-08-27027 August 2019
Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection
ML19198A0012019-08-13013 August 2019
Issuance of Amendment Nos. 308, 331, and 291 to Extend Implementation Due Date for Modifications 102 and 106 Related to NFPA 805 (Eid L-2019-LLA-0140)
ML19037A1372019-04-0202 April 2019
Revisions to Modifications 85, 102 and 106 Related to National Fire Protection Association 805 Performance-based Standard for Fire Protection of Light Water Reactor Electric Generating Plants
ML19010A2742019-03-18018 March 2019
Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority
ML19016A2152019-02-28028 February 2019
Relief from the Requirements of American Association of Mechanical Engineers Code Section XI Inservice Inspection Program, Request for an Alternative ISI-46
ML18323A1722018-12-31031 December 2018
Relief Request No. 1 ISI 29 Regarding Second 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Welds
ML18323A0262018-12-0404 December 2018
Relief Request No. 1-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Reactor Vessel Welds
ML18241A3192018-10-0909 October 2018
Issuance of Amendment Nos. 306, 329, and 289 to Revise Approved NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants-Revision
ML18251A0032018-09-27027 September 2018
Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292)
ML18236A3312018-09-24024 September 2018
Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML18197A3072018-08-30030 August 2018
Issuance of Amendments Regarding Request to Change Technical Specification 3.3.1 and Surveillance Requirement 3.2.4
ML18171A3372018-07-10010 July 2018
Issuance of Amendment to Revise License Condition 2.C(18)(a)3
ML18138A4522018-05-29029 May 2018
Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20
ML17289A0322017-12-22022 December 2017
Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160)
ML17261A0362017-10-0606 October 2017
Request for Request 3-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Examination Coverage of Inside Radius and Nozzle-to-Vessel Welds
ML17215A2432017-10-0202 October 2017
Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566)
ML17032A1202017-08-14014 August 2017
Non-Proprietary Issuance of Amendments Regarding Extended Power Uprate
ML17145A5522017-08-11011 August 2017
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Alternative Request IST-RR-1 for the Fourth 10-Year Inservice Testing Interval (CAC Nos. MF9087, MF9088, and MF9089)
ML17034A3602017-03-27027 March 2017
Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ...
2024-01-03
[Table view] |
Text
February 6, 2007 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:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT REGARDING LOW PRESSURE COOLANT INJECTION CROSSTIE VALVE SURVEILLANCE REQUIREMENT (TAC NO. MD3544) (TS-458)
Dear Mr. Singer:
The Commission has issued the enclosed Amendment No. 268 to Renewed Facility Operating License No. DPR-33 for the Browns Ferry Nuclear Plant, Unit 1. This amendment is in response to your application dated November 9, 2006. This amendment deletes the Technical Specification Surveillance Requirement to verify the position of a low pressure coolant injection crosstie valve.
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/
Margaret H. Chernoff, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosures:
- 1. Amendment No. 268 to DPR-33
- 2. Safety Evaluation cc w/enclosures: See next page
ML070300427 NRR-058 OFFICE LPL2-2/PM LPL2-2/LA SBWB/BC ITSB/BC OGC LPL2-2/BC NAME MChernoff BClayton GCranston TKobetz MZobler PMilano for by Memo dtd LRaghavan DATE 1/29/07 1/26/07 12/21/06 /21/07 2/5/07 2/6/07 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 268 Renewed License No. DPR-33
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Tennessee Valley Authority (the licensee) dated November 9, 2006, 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 Renewed Facility Operating License No. DPR-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 268, 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 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA Patrick D. Milano for/
L. Raghavan, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: February 6, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Replace Page 3 of Renewed Operating License DPR-33 with the attached Page 3.
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.5-4 3.5-4
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-33 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC), dated November 6, 2006, the Tennessee Valley Authority (the licensee) submitted a request for changes to the Browns Ferry Nuclear Plant, Unit 1, Technical Specifications (TS). The requested change would delete TS Surveillance Requirement (SR) 3.5.1.4, which requires monthly verification that the Low Pressure Coolant Injection (LPCI) Crosstie valve is in the closed position with its motive power removed.
2.0 REGULATORY EVALUATION
The LPCI is one of the systems that comprise the Emergency Core Cooling System (ECCS). It is provided to automatically reflood the reactor core in time to limit cladding temperatures after a nuclear system loss-of-coolant accident (LOCA) when the reactor vessel pressure is below the shutoff head of the pumps. The LPCI system provides cooling by flooding, which differs from the Core Spray System that provides cooling by spraying. When the nuclear system pressure decreases to the pumping head of LPCI system, the check valve in the injection line opens and LPCI water is pumped into the reactor vessel to reflood the core.
As stated in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46, the purpose of the ECCSs is to remove the residual and decay heat from the reactor core so that fuel clad melting is prevented and fuel clad damage is acceptably minimized. The criterion against which the ECCS System performance is measured is that ECCS systems shall limit cladding peak temperature to 2200 °F.
3.0 TECHNICAL EVALUATION
Description of Change The change removes an SR that verifies that the LPCI loop discharge crosstie valve is in the closed position with its motive power removed. The LPCI loop discharge crosstie valve has been physically removed and the associated piping has been capped or closed with a blind flange.
The LPCI loop crosstie valve was physically removed and the associated piping capped or closed with a blind flange as part of the Unit 1 restart effort. The removal of the crosstie valve also reduces the maintenance in a high-radiation area and, in turn, reduces ALARA (as low as reasonably achievable) concerns. Crosstie capability is not required for the mitigation of design basis events.
Evaluation The LPCI system previously had the ability to crosstie the redundant loops. This configuration provided the LPCI system the flexibility to provide make-up flow into either of the loops. During normal operation the loops were isolated from one another through the use of a normally closed LPCI loop crosstie valve with the motive power removed.
The purpose for the LPCI loop crosstie was for both LPCI loops to be able to provide reactor make-up flow into either of the two reactor recirculation loops under various LOCA pipe break scenarios. Subsequent to plant construction and licensing, analyses determined that the crosstie capability, under certain accident and single-failure scenarios, could result in the loss of injection from both LPCI loops. Additionally, analyses determined that the crosstie capability was not required for the mitigation of any design-basis events.
The existence of the LPCI loop crosstie line was determined to be a liability in plant design and an SR was placed in TS Section 3.5.1, ECCS (Emergency Core Cooling System) - Operating.
SR 3.5.1.4 states, Verify the LPCI cross tie valve is closed and power is removed from the valve operator. The frequency of this requirement is once every 31 days. This SR was intended to ensure the plant was in an analyzed condition.
The LPCI system design has been changed to eliminate the crosstie ability. In this change, the LPCI loop crosstie valve has been physically removed and the associated piping has been capped or closed with a blind flange. This change was made as part of the Unit 1 restart effort.
The crosstie valve was not required for mitigation of design basis accidents. This design change makes it physically impossible for flow to occur between the two LPCI loops.
The proposed change eliminates SR 3.5.1.4. With the removal of the LPCI loop crosstie valve, SR 3.5.1.4 is no longer necessary.
The NRC staff reviewed the information supplied by the applicant and the Updated Final Safety Analysis Report, and concludes that the change in the mechanical separation inline from an isolation valve to a capped pipe does not affect adversely any safety function of the LPCI system. Therefore, the proposed TS change associated with this modification is acceptable.
The licensee also provided its marked up changes to the affected TS Bases. The NRC staff has no objection to the proposed TS Bases changes.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Alabama State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes 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 SRs.
The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (71 FR 67166). Accordingly, the amendment meets 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 amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Diana Woodyatt Date: February 6, 2007
Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW.
Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Ms. Beth A. Wetzel, Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Preston D. Swafford, Senior Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, General Manager 10833 Shaw Road Nuclear Assurance Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Mr. Robert H. Bryan, Jr., General Manager Tennessee Valley Authority Licensing and Industry Affairs P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
