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| {{#Wiki_filter:May 4, 2006Mr. Bruce H. HamiltonVice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672 | | {{#Wiki_filter:May 4, 2006 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| OCONEE NUCLEAR STATION, UNIT 3, ISSUANCE OF AMENDMENTS RE:REPLACEMENT OF REACTOR BUILDING EMERGENCY SUMP SUCTION INLET TRASH RACKS AND SCREENS WITH STRAINERS (TAC NO. MC8127) | | OCONEE NUCLEAR STATION, UNIT 3, ISSUANCE OF AMENDMENTS RE: |
| | REPLACEMENT OF REACTOR BUILDING EMERGENCY SUMP SUCTION INLET TRASH RACKS AND SCREENS WITH STRAINERS (TAC NO. MC8127) |
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| ==Dear Mr. Hamilton:== | | ==Dear Mr. Hamilton:== |
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| The Nuclear Regulatory Commission has issued the enclosed Amendment No. 350 to RenewedFacility Operating License DPR-55 for the Oconee Nuclear Station, Unit 3. The amendmentconsists of changes to the Technical Specifications (TS) in response to your application dated August 18, 2005, as supplemented by letters dated September 15, 2005, and January 5 andApril 6, 2006.The amendment revises TS 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactorbuilding emergency sump suction inlet trash racks and screens with strainers. Similaramendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of theimpact of pipe whip, jet impingement and internally-generated missiles for Unit 3.A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be incl udedin the Commission's biweekly Federal Register notice. Sincerely,/RA/Leonard N. Olshan, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-287 | | The Nuclear Regulatory Commission has issued the enclosed Amendment No. 350 to Renewed Facility Operating License DPR-55 for the Oconee Nuclear Station, Unit 3. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated August 18, 2005, as supplemented by letters dated September 15, 2005, and January 5 and April 6, 2006. |
| | The amendment revises TS 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally-generated missiles for Unit 3. |
| | A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Leonard N. Olshan, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 350 to DPR-55 | | : 1. Amendment No. 350 to DPR-55 |
| : 2. Safety Evaluationcc w/encls: See next page May 4, 2006Mr. Bruce H. HamiltonVice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672 | | : 2. Safety Evaluation cc w/encls: See next page |
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| | May 4, 2006 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| OCONEE NUCLEAR STATION, UNIT 3, ISSUANCE OF AMENDMENTS RE:REPLACEMENT OF REACTOR BUILDING EMERGENCY SUMP SUCTION INLET TRASH RACKS AND SCREENS WITH STRAINERS (TAC NO. MC8127) | | OCONEE NUCLEAR STATION, UNIT 3, ISSUANCE OF AMENDMENTS RE: |
| | REPLACEMENT OF REACTOR BUILDING EMERGENCY SUMP SUCTION INLET TRASH RACKS AND SCREENS WITH STRAINERS (TAC NO. MC8127) |
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| ==Dear Mr. Hamilton:== | | ==Dear Mr. Hamilton:== |
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| The Nuclear Regulatory Commission has issued the enclosed Amendment No. to RenewedFacility Operating License DPR-55 for the Oconee Nuclear Station, Unit 3. The amendmentconsists of changes to the Technical Specifications (TS) in response to your application dated August 18, 2005, as supplemented by letters dated September 15, 2005, and January 5 andApril 6, 2006.The amendment revises TS 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactorbuilding emergency sump suction inlet trash racks and screens with strainers. Similaramendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of theimpact of pipe whip, jet impingement and internally-generated missiles for Unit 3.A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be incl udedin the Commission's biweekly Federal Register notice. Sincerely,/RA/Leonard N. Olshan, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-287 | | The Nuclear Regulatory Commission has issued the enclosed Amendment No. to Renewed Facility Operating License DPR-55 for the Oconee Nuclear Station, Unit 3. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated August 18, 2005, as supplemented by letters dated September 15, 2005, and January 5 and April 6, 2006. |
| | The amendment revises TS 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally-generated missiles for Unit 3. |
| | A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Leonard N. Olshan, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 350 to DPR-55 | | : 1. Amendment No. 350 to DPR-55 |
| : 2. Safety Evaluationcc w/encls: See next page DISTRIBUTION: | | : 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public RidsAcrsAcnwMailCenter LPL2-1 R/F GHill(6 hard copies) |
| PublicRidsAcrsAcnwMailCenter LPL2-1 R/FGHill(6 hard copies)RidsNrrDorlLplc(EMarinos)RidsNrrDirsItsb(TBoyce)RidsNrrPMLOlshan(hard copy)Princ Contr of SE/Tech BrRidsNrrLAMO'Brien(hard copy)RidsRgn2MailCenter(MErnstes)RidsOgcRpBSingal (DORL DPR)Package No.: ML061150507License Amendment No. ML061140442Tech Spec No.: ML061160014 NRR-058OFFICENRR/LPL2-1/PMNRR/LPL2-1/LAOGCBGCB/BDNRR/LPL2-1/BCNAMELOlshanMO'BrienSHamrickRKaras CM forEMarinosDATE4/13/065/4/064/25/064/17/065/4/06 OFFICIAL RECORD COPY DUKE POWER COMPANY LLCDOCKET NO. 50-287OCONEE NUCLEAR STATION, UNIT 3AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 350Renewed License No. DPR-551.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment to the Oconee Nuclear Station, Unit 3 (thefacility) Renewed Facility Operating License No. DPR-55 filed by the Duke PowerCompany LLC, (the licensee) dated August 18, 2005, supplemented September 15, 2005, and January 5 and April 6, 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 as 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 theCommission's regulations set forth in 10 CFR Chapter I;D.The issuance of this amendment will not be inimical to the common defense andsecurity 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 theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is hereby amended by page changes to the TechnicalSpecifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read asfollows:B. Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 350, 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 60 days of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
| | RidsNrrDorlLplc(EMarinos) RidsNrrDirsItsb(TBoyce) |
| | RidsNrrPMLOlshan(hard copy) Princ Contr of SE/Tech Br RidsNrrLAMOBrien(hard copy) RidsRgn2MailCenter(MErnstes) |
| | RidsOgcRp BSingal (DORL DPR) |
| | Package No.: ML061150507 License Amendment No. ML061140442 Tech Spec No.: ML061160014 NRR-058 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA OGC BGCB/BD NRR/LPL2-1/BC NAME LOlshan MOBrien SHamrick RKaras CM for EMarinos DATE 4/13/06 5/4/06 4/25/06 4/17/06 5/4/06 |
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| | OFFICIAL RECORD COPY DUKE POWER COMPANY LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 350 Renewed License No. DPR-55 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Renewed Facility Operating License No. DPR-55 filed by the Duke Power Company LLC, (the licensee) dated August 18, 2005, supplemented September 15, 2005, and January 5 and April 6, 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 as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows: |
| | B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 350, 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 |
| | /RA/ |
| | Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Technical Specification ChangesDate of Issuance: May 4, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 350RENEWED FACILITY OPERATING LICENSE NO. DPR-55DOCKET NO. 50-287Replace the following pages of the Appendix A Technical Specifications with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. RemoveInsert3.5.2-5a3.5.2-53.5.2-5b3.5.3-3 3.5.3-3a 3.5.3-3b SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TOAMENDMENT NO. 350 TO RENEWED FACILITY OPERATING LICENSE DPR-55DUKE POWER COMPANY LLCOCONEE NUCLEAR STATION, UNIT 3DOCKET NO. 50-28
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| ==71.0 INTRODUCTION== | | Technical Specification Changes Date of Issuance: May 4, 2006 |
| By letter dated August 18, 2005, as supplemented September 15, 2005, and January 5 andApril 6, 2006, Duke Power Company LLC (the licensee), submitted a request for changes to the Oconee Nuclear Station, Unit 3, Technical Specifications (TSs). The requested changes would revise TSs 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor buildingemergency sump (RBES) suction inlet trash racks and screens with strainers. Similaramendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of theimpact of pipe whip, jet impingement and internally generated missiles for Unit 3.The supplements dated September 15, 2005, and January 5 and April 6, 2006, providedclarifying information that did not change the scope of the original application and the initialproposed no significant hazards consideration determination. | | |
| | ATTACHMENT TO LICENSE AMENDMENT NO. 350 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. |
| | Remove Insert 3.5.2-5a 3.5.2-5 3.5.2-5b 3.5.3-3 3.5.3-3a 3.5.3-3b |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 350 TO RENEWED FACILITY OPERATING LICENSE DPR-55 DUKE POWER COMPANY LLC OCONEE NUCLEAR STATION, UNIT 3 DOCKET NO. 50-287 |
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| | ==1.0 INTRODUCTION== |
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| | By letter dated August 18, 2005, as supplemented September 15, 2005, and January 5 and April 6, 2006, Duke Power Company LLC (the licensee), submitted a request for changes to the Oconee Nuclear Station, Unit 3, Technical Specifications (TSs). The requested changes would revise TSs 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump (RBES) suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally generated missiles for Unit 3. |
| | The supplements dated September 15, 2005, and January 5 and April 6, 2006, provided clarifying information that did not change the scope of the original application and the initial proposed no significant hazards consideration determination. |
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| | ==2.0 REGULATORY EVALUATION== |
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| | Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents and Pressurized Water Reactors, is part of the regulatory framework the NRC staff is using to address issues associated with Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on PWR Sump Performance, for requirements to improve evaluation of plant capability to meet Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.46(b)(5). |
| | The new strainers are functionally equivalent to the existing trash racks and screens for meeting requirements of 10 CFR 50.46(b)(5) for long-term cooling and 10 CFR Part 50, Appendix A, Criterion 35 for emergency core cooling. |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | The proposed change involves revising TS Surveillance Requirements 3.5.2.6 and 3.5.3.6 to use the term "strainers" to replace the terms "trash racks and screens. This change is needed to reflect the replacement of RBES suction inlet trash racks and screens with strainer |
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| | assemblies in response to NRC Generic Letter 2004-02. The new strainers are functionally equivalent to the existing trash racks and screens for meeting the requirements of 10 CFR 50.46(b)(5) for long-term cooling and 10 CFR Part 50, Appendix A, Criterion 35 for emergency core cooling. The use of the generic term "strainers" can be used for both the existing and new designs, will not affect implementation of Surveillance Requirements 3.5.2.6 and 3.5.3.6, and can be used for implementation of corrective actions to address GSI-191. |
| | GSI-191 was established by the NRC to determine whether transport and accumulation of debris in pressurized-water reactor (PWR) containments following a loss-of-coolant accident (LOCA) would impede the long-term operation of the emergency core cooling system or containment spray system. The NRC is currently implementing its plan to have all PWR licensees evaluate the potential for excessive head loss across the containment sump screen and implement necessary actions to resolve concerns associated with GSI-191. This action plan includes review of all licensee responses to GL 2004-02 and plant audits as needed to confirm proper evaluation and corrective actions to address all technical issues associated with proper sump performance. The information that was provided by the licensee regarding jet impingement and pipe whip effects, and missile protection, will be reviewed as part of this action plan. |
| | The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment, which are described in Attachments 3, 4, and 5 of the licensees August 18, 2005, submittal and finds these justifications acceptable. |
| | On November 1, 2005, similar amendments were issued for Units 1 and 2; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement, and internally-generated missiles for Unit 3. By letter dated April 6, 2006, the licensee provided the results of these evaluations. |
| | The NRC staff has reviewed Dukes evaluation of pipe whip, jet impingement and internally generated missile impact on the emergency sump strainer. The sources and targets were identified by a walkdown of Unit 1 and applied to Unit 3 on the basis of similarity. Duke Calculations S-005 "Missile Evaluation for the Emergency Sump Strainer," and S-006, "Jet Impingement and Pipe Whip Evaluation for the Emergency Sump Strainer," document the walkdown results and perform the analysis of the findings. The calculations document that Unit 3 piping arrangement in the area of the RBES is similar to that of Unit 1 & Unit 2. The NRC staff concurs with the conclusions of these calculations. Based on this evaluation, the licensee concludes that the emergency strainer operability will not be compromised during a LOCA by missiles, jet impingement or pipe whip. The NRC staff concludes that there are no credible missiles nor credible high-energy line break jets or pipe whips that could damage the strainer when needed during a LOCA. |
| | Based on the review of the calculations provided by the licensee, the NRC staff grants approval of the proposed TS changes with regard to the evaluation for jet impingement, pipe whip and internally-generated missile impact of the RBES for Unit 3. |
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| | ==4.0 STATE CONSULTATION== |
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| ==2.0 REGULATORY EVALUATION==
| | In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments. |
| Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of DebrisBlockage on Emergency Recirculation During Design Basis Accidents and Pressurized Water Reactors, is part of the regulatory framework the NRC staff is using to address issuesassociated with Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on PWRSump Performance, for requirements to improve evaluation of plant capability to meet Title 10of the Code of Federal Regulations (10 CFR), Part 50, Section 50.46(b)(5). The new strainers are functionally equivalent to the existing trash racks and screens formeeting requirements of 10 CFR 50.46(b)(5) for long-term cooling and 10 CFR Part 50, Appendix A, Criterion 35 for emergency core cooling.
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| ==3.0 TECHNICAL EVALUATION== | | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| The proposed change involves revising TS Surveillance Requirements 3.
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| 5.2.6 and 3.5.3.6 touse the term "strainers" to replace the terms "trash racks and screens." This change is neededto reflect the replacement of RBES suction inlet trash racks and screens with strainer assemblies in response to NRC Generic Letter 2004-02. The new strainers are functionallyequivalent to the existing trash racks and screens for meeting the requirements of 10 CFR50.46(b)(5) for long-term cooling and 10 CFR Part 50, Appendix A, Criterion 35 for emergency core cooling. The use of the generic term "strainers" can be used for both the existing and new designs, will not affect implementation of Surveillance Requirements 3.5.2.
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| 6 and 3.5.3.6, andcan be used for implementation of corrective actions to address GSI-191.GSI-191 was established by the NRC to determine whether transport and accumulation ofdebris in pressurized-water reactor (PWR) containments following a loss-of-coolant accident (LOCA) would impede the long-term operation of the emergency core cooling system orcontainment spray system. The NRC is currently implementing its plan to have all PWR licensees evaluate the potential for excessive head loss across the containment sump screenand implement necessary actions to resolve concerns associated with GSI-191. This action plan includes review of all licensee responses to GL 2004-02 and plant audits as needed to confirm proper evaluation and corrective actions to address all technical issues associated with proper sump performance. The information that was provided by the licensee regarding jet impingement and pipe whip effects, and missile protection, will be reviewed as part of thisaction plan.The NRC staff has reviewed the licensee's regulatory and technical analyses in support of itsproposed license amendment, which are described in Attachments 3, 4, and 5 of the licensee's August 18, 2005, submittal and finds these justifications acceptable.On November 1, 2005, similar amendments were issued for Units 1 and 2; however, theamendment for Unit 3 was not issued at that time since the licensee had not completed itsevaluation of the impact of pipe whip, jet impingement, and internally-generated missiles for Unit 3. By letter dated April 6, 2006, the licensee provided the results of these evaluations. The NRC staff has reviewed Duke's evaluation of pipe whip, jet impingement and internallygenerated missile impact on the emergency sump strainer. The sources and targets were identified by a walkdown of Unit 1 and applied to Unit 3 on the basis of similarity. Duke Calculations S-005 "Missile Evaluation for the Emergency Sump Strainer," and S-006, "Jet Impingement and Pipe Whip Evaluation for the Emergency Sump Strainer," document the walkdown results and perform the analysis of the findings. The calculations document that Unit 3 piping arrangement in the area of the RBES is similar to that of Unit 1 & Unit 2. The NRC staff concurs with the conclusions of these calculations. Based on this evaluation, the licensee concludes that the emergency strainer operability will not be compromised during aLOCA by missiles, jet impingement or pipe whip. The NRC staff concludes that there are nocredible missiles nor credible high-energy line break jets or pipe whips that could damage the strainer when needed during a LOCA.Based on the review of the calculations provided by the licensee, the NRC staff grants approvalof the proposed TS changes with regard to the evaluation for jet impingement, pipe whip and internally-generated missile impact of the RBES for Unit 3.
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| ==4.0 STATE CONSULTATION==
| | The amendment changes requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the 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 (70 FR 51852). 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. |
| In accordance with the Commission's regulations, the South Carolina State official was notifiedof the proposed issuance of the amendments. The State official had no comments.
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| ==5.0 ENVIRONMENTAL CONSIDERATION== | | ==6.0 CONCLUSION== |
| The amendment changes requirements with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves nosignificant increase in the amounts and no significant change in the types of any effluents thatmay 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 nopublic comment on such finding (70 FR 51852). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR51.22(b), no environmental impact statement or environmental assessment need be preparedin connection with the issuance of the amendment.
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| ==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. |
| 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 byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical to thecommon defense and security or to the health and safety of the public.Principal Contributors: T. Hafera S. Samaddar Date: May 4, 2006Oconee Nuclear Station, Units 1, 2, and 3 cc:Ms. Lisa F. VaughnDuke Power Company, LLC 526 South Church Street P. O. Box 1006 Mail Code = EC07H Charlotte, North Carolina 28201-1006Manager, LISNUS Corporation 2650 McCormick Dr., 3rd Floor Clearwater, FL 34619-1035Senior Resident InspectorU.S. Nuclear Regulatory Commission 7812B Rochester Highway Seneca, SC 29672Mr. Henry Porter, DirectorDivision of Radioactive Waste Management Bureau of Land and Waste Management Dept. of Health and Env. Control 2600 Bull St. | | Principal Contributors: T. Hafera S. Samaddar Date: May 4, 2006 Oconee Nuclear Station, Units 1, 2, and 3 |
| Columbia, SC 29201-1708Mr. Michael A. SchoppmanFramatome ANP 1911 North Ft. Myer Dr.
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| Suite 705 Rosslyn, VA 22209Mr. B. G. DavenportRegulatory Compliance Manager Oconee Nuclear Site Duke Power Company, LLC ON03RC 7800 Rochester Highway Seneca, SC 29672Ms. Karen E. LongAssistant Attorney General NC Department of Justice
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| P.O. Box 629 Raleigh, NC 27602Mr. R. L. Gill, Jr.Manager - Nuclear Regulatory Issues and Industry Affairs Duke Power Company, LLC 526 S. Church St.
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| Mail Stop EC05P Charlotte, NC 28202Division of Radiation ProtectionNC Dept of Environment, Health, & Natural Resources 3825 Barrett Dr. | | Ms. Lisa F. Vaughn Manager - Nuclear Regulatory Duke Power Company, LLC Issues and Industry Affairs 526 South Church Street Duke Power Company, LLC P. O. Box 1006 526 S. Church St. |
| Raleigh, NC 27609-7721Mr. Peter R. Harden, IVVP-Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road 12th Floor Charlotte, NC 28210Mr. Henry BarronGroup Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006}} | | Mail Code = EC07H Mail Stop EC05P Charlotte, North Carolina 28201-1006 Charlotte, NC 28202 Manager, LIS Division of Radiation Protection NUS Corporation NC Dept of Environment, Health, & Natural 2650 McCormick Dr., 3rd Floor Resources Clearwater, FL 34619-1035 3825 Barrett Dr. |
| | Raleigh, NC 27609-7721 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. Peter R. Harden, IV 7812B Rochester Highway VP-Customer Relations and Sales Seneca, SC 29672 Westinghouse Electric Company 6000 Fairview Road Mr. Henry Porter, Director 12th Floor Division of Radioactive Waste Management Charlotte, NC 28210 Bureau of Land and Waste Management Dept. of Health and Env. Control Mr. Henry Barron 2600 Bull St. Group Vice President, Nuclear Generation Columbia, SC 29201-1708 and Chief Nuclear Officer P.O. Box 1006-EC07H Mr. Michael A. Schoppman Charlotte, NC 28201-1006 Framatome ANP 1911 North Ft. Myer Dr. |
| | Suite 705 Rosslyn, VA 22209 Mr. B. G. Davenport Regulatory Compliance Manager Oconee Nuclear Site Duke Power Company, LLC ON03RC 7800 Rochester Highway Seneca, SC 29672 Ms. Karen E. Long Assistant Attorney General NC Department of Justice P.O. Box 629 Raleigh, NC 27602 Mr. R. L. Gill, Jr.}} |
Letter Sequence Approval |
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MONTHYEARML0523105582005-08-24024 August 2005
FRN, Notice of Consideration of Issuance of Amendments Revising the Technical Specifications to Accommodate Replacement of the Reactor Building Emergency Sump Suction Inlet Trash..
Project stage: Other
ML0611800782006-03-27027 March 2006
Unit 3 Calculations for Oconee TAC MC8127
Project stage: Other
ML0611600142006-05-0404 May 2006
Tech Spec Pages for Amendment 350 Replacement of Reactor Building Emergency Sump Suction Inlet Trash Racks and Screens with Strainers
Project stage: Other
ML0611404422006-05-0404 May 2006
License Amendment 350 Replacement of Reactor Building Emergency Sump Suction Inlet Trash Racks and Screens with Strainers
Project stage: Approval
2006-03-27
[Table View] |
|
|---|
Category:Letter
MONTHYEARML23304A1422024-02-0101 February 2024
Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application
ML24005A2492024-01-24024 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)
IR 05000269/20243012024-01-11011 January 2024
Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301
ML23331A7982023-12-14014 December 2023
Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32)
ML23262A9672023-12-13013 December 2023
Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1
ML23317A3462023-11-14014 November 2023
Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
IR 05000269/20230032023-11-14014 November 2023
Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion
ML23219A1402023-10-10010 October 2023
Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1
ML23269A1102023-10-0606 October 2023
Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application
ML23256A0882023-09-25025 September 2023
Issuance of Alternative to Steam Generator Welds
ML23195A0782023-08-29029 August 2023
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
IR 05000269/20230112023-08-25025 August 2023
Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011
IR 05000269/20230052023-08-25025 August 2023
Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005)
IR 05000269/20230022023-07-28028 July 2023
Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002
ML23208A0972023-07-27027 July 2023
Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected
IR 05000269/20230102023-07-19019 July 2023
Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation
ML23178A0682023-07-0303 July 2023
Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1
ML23132A2392023-06-0101 June 2023
Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application
ML23144A0192023-05-25025 May 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31)
IR 05000269/20230012023-05-12012 May 2023
Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001
ML23121A0552023-05-0303 May 2023
Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program
ML23118A0762023-05-0101 May 2023
Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML23117A0432023-04-20020 April 2023
Framatome, Inc., Part 21 Notification of Existence of a Defect
ML23075A0732023-04-0505 April 2023
License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002)
ML23045A1332023-03-15015 March 2023
Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter
ML23045A1402023-03-15015 March 2023
Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter
ML23045A1432023-03-15015 March 2023
Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter
ML22332A4932023-03-10010 March 2023
William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility
ML23069A1102023-03-10010 March 2023
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
ML23061A1772023-03-0303 March 2023
Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011
IR 05000269/20220062023-03-0101 March 2023
Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006)
ML23039A1632023-02-0808 February 2023
Requalification Program Inspection
ML23037A0772023-02-0606 February 2023
402 Cyber Notification and RFI Letter Final
IR 05000269/20220042023-02-0202 February 2023
Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004
ML22363A3942023-01-12012 January 2023
Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule
ML22356A0512022-12-14014 December 2022
Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl
ML22321A0492022-12-0808 December 2022
Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints
ML22329A1042022-11-29029 November 2022
Review of the Fall 2021 Steam Generator Tube Inspection Report
ML22321A1582022-11-22022 November 2022
Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections
ML22096A0032022-11-18018 November 2022
McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations
ML22256A2532022-11-14014 November 2022
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2
IR 05000269/20220032022-11-0707 November 2022
Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003
ML22301A0112022-11-0303 November 2022
Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022
ML22298A0752022-10-27027 October 2022
Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022
ML22264A0322022-10-20020 October 2022
_Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022
IR 05000269/20220112022-09-26026 September 2022
NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011
ML22258A0302022-09-15015 September 2022
Evacuation Time Estimate Reports
ML22222A0072022-09-14014 September 2022
Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application
ML22231B1362022-09-0101 September 2022
Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi
ML22234A0062022-08-30030 August 2022
SLRA - Closed Public Meeting Summary - August 18, 2022
2024-02-01
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23195A0782023-08-29029 August 2023
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
ML22332A4932023-03-10010 March 2023
William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility
ML22321A0492022-12-0808 December 2022
Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints
ML22256A2532022-11-14014 November 2022
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2
ML22096A1872022-07-15015 July 2022
Issuance of Amendment Nos. 424, 426, and 425 Revise TS 3.7.7, Low Pressure Service Water (LPSW) System to Extend the Completion Time for One Required Inoperable LPSW Pump
ML22046A0222022-06-14014 June 2022
Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
ML21362A7532022-01-0606 January 2022
Regulatory Audit in Support of the License Amendment Request for One-Time Note to Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System
ML21155A2132021-08-26026 August 2021
Plant
ML21158A1952021-06-0707 June 2021
Application for Subsequent Renewed Operating Licenses. Part 2 of 8
ML21158A1982021-06-0707 June 2021
Application for Subsequent Renewed Operating Licenses. Part 5 of 8
ML21158A1962021-06-0707 June 2021
Application for Subsequent Renewed Operating Licenses. Part 3 of 8
ML21158A1992021-06-0707 June 2021
Application for Subsequent Renewed Operating Licenses. Part 6 of 8
ML21158A1972021-06-0707 June 2021
Application for Subsequent Renewed Operating Licenses. Part 4 of 8
RA-21-0132, Application for Subsequent Renewed Operating Licenses. Part 7 of 82021-06-0707 June 2021
Application for Subsequent Renewed Operating Licenses. Part 7 of 8
ML21006A0982021-03-15015 March 2021
Issuance of Amendment Nos. 421, 423, and 422 Revision of Licensing Basis for High Energy Line Breaks Outside of Containment (EPID L-2019-LLA-0184) (Public Version)
ML20335A0012021-01-26026 January 2021
Issuance of Amendment Nos. 420, 422, and 421 Measurement Uncertainty Recapture Power Uprate
ML20303A0242020-12-0909 December 2020
Issuance of Amendments 419, 421, 420 TSTF-272, Refueling Boron Concentration Clarification
ML20296A2812020-11-25025 November 2020
Issuance of Amendment Nos. 418, 420 and 419 TSTF-421, Revision to RCP Flywheel Inspection Program
ML20258A2712020-09-21021 September 2020
Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268
ML20237F4352020-09-0404 September 2020
Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations
ML20083F9272020-08-12012 August 2020
Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description
ML19260E0842019-10-31031 October 2019
Issuance of Amendments 415, 417, and 416, Regarding the Updated Final Safety Analysis Report Description of Tornado Mitigation
ML19056A0862019-09-30030 September 2019
Issuance of Amendments Nos. 414, 416 and 415 Regarding the Physical Security Plan
ML19183A3172019-07-17017 July 2019
Issuance of Amendments Regarding the Updated Final Safety Analysis Report Section for Fission Gas Gap Release Rates
ML19140A0262019-06-14014 June 2019
Issuance of Amendments Regarding the Technical Specifications for Electrical Power Systems
ML18311A1342018-12-17017 December 2018
Non Proprietary - Issuance of Amendments Regarding the Updated Final Safety Analysis Report Section for the Standby Shutdown Facility
ML18172A1722018-08-15015 August 2018
Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application
ML18040A1942018-04-12012 April 2018
Issuance of Amendments Regarding the Technical Specifications for Control Room Habitability (CAC Nos. MF9555, MF9556, and MF9557; EPID L-2017-LLA-0219)
ML17124A6082017-11-20020 November 2017
Issuance of Amendments Regarding the Technical Specifications for Electrical Power Systems (CAC Nos. MF7417, MF7418, and MF7419; EPID L-2016-LLA-0002)
ML17188A3872017-08-21021 August 2017
Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660)
ML17167A2652017-07-12012 July 2017
Issuance of Amendments Regarding the Technical Specifications for Dry Spent Fuel Storage Cask Loading and Unloading (CAC Nos. MF8161, MF8162, and MF8163)
ML17103A5092017-05-11011 May 2017
Issuance of Amendments Allowing the Use of the Copernic Fuel Performance Code
ML17066A3742017-04-26026 April 2017
Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049)
ML16159A3362016-07-19019 July 2016
Issuance of Amendments Regarding Request to Use an Alternate Fission Gas Gap Release Fraction (CAC Nos. MF6480 Through MF6486)
ML16174A0722016-06-27027 June 2016
Correction to License Pages Issuance of Amendments Regarding Adoption of TSTF-523 (Cac Nos. MF6413 Through MF6422)
ML16138A3322016-06-0606 June 2016
Issuance of Amendments to Correct Usage Problem with Technical Specification 3.8.1
ML16109A0932016-05-26026 May 2016
Issuance of License Amendments Regarding Emergency Action Level Scheme Change
ML16088A3302016-04-29029 April 2016
Issuance of Amendments to Add High Flux Trip for Three Reactor Coolant Pump Operation
ML16085A1132016-04-29029 April 2016
1 & 2; Shearon Harris Nuclear Power Plant 1; Catawba Nuclear Station 1 & 2; Mcguire Nuclear Station 1 & 2; and Oconee Nuclear Station 1, 2, & 3: Issuance of Amendments Regarding Adoption of TSTF-523 (CAC Nos. MF6413-MF6422)
ML16075A3012016-04-26026 April 2016
Issuance of Amendments Regarding the Revision of the Steam Generator Technical Specifications to Reflect the Adoption of TSTF-510(CAC Nos. MF6139,MF6140,MF6141,MF6142,MF6143,MF6144.
ML15166A3872015-09-24024 September 2015
Issuance of Amendments Regarding Allowed Maximum Rated Thermal Power
ML15170A0552015-07-27027 July 2015
Issuance of Amendments Regarding Adoption of TSTF-513
ML15174A2672015-07-0707 July 2015
Issuance of Amendments Regarding the Inservice Testing Program
ML15050A6712015-06-19019 June 2015
Issuance of Amendments Regarding Inspection Plan for Reactor Vessel Internals
ML15133A4532015-06-11011 June 2015
McGuire Nuclear Station, Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Cyber Security Plan Implementation Schedule Milestone 8
ML15093A3492015-04-23023 April 2015
Issuance of Amendments Regarding Keowee Hydro Unit (Khu) Steady State Frequency Requirements
ML15002A3242015-02-12012 February 2015
McGuire Nuclear Station, and Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Areas
ML14195A3552014-10-21021 October 2014
Issuance of Amendments
ML14254A2462014-09-25025 September 2014
Issuance of Amendments Regarding Quality Assurance Requirements for the Standby Shutdown Facility Equipment
ML14206A7902014-08-13013 August 2014
Issuance of Amendments Regarding Implementation of the Protected Service Water System
2023-08-29
[Table view]
Category:Safety Evaluation
MONTHYEARML23262A9672023-12-13013 December 2023
Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1
ML23256A0882023-09-25025 September 2023
Issuance of Alternative to Steam Generator Welds
ML23195A0782023-08-29029 August 2023
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
ML23118A0762023-05-0101 May 2023
Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML22332A4932023-03-10010 March 2023
William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility
ML22349A1452022-12-19019 December 2022
Non-Proprietary Safety Evaluation Related to the SLRA of Oconee Nuclear Station, Units 1, 2, and 3
ML22321A0492022-12-0808 December 2022
Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints
ML22096A0032022-11-18018 November 2022
McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations
ML22256A2532022-11-14014 November 2022
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2
ML22096A1872022-07-15015 July 2022
Issuance of Amendment Nos. 424, 426, and 425 Revise TS 3.7.7, Low Pressure Service Water (LPSW) System to Extend the Completion Time for One Required Inoperable LPSW Pump
ML22046A0222022-06-14014 June 2022
Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
ML22068A0252022-03-15015 March 2022
Code Case OMN-28 - Alternative Valve Position Verification Approach to Satisfy ISTC-3700 for Valves Not Susceptible to Stem-Disk Separation
ML22046A2802022-02-23023 February 2022
Relief from ASME Code Paragraph ISTP-3540(b) Related to High Pressure Injection Pumps Vibration Measurements
ML22046A2452022-02-18018 February 2022
Regarding Alternative to Implement Code Case OMN-22, Smooth Running Pumps
ML22019A1352022-01-21021 January 2022
Proposed Alternative to Implement ASME Code Case OMN-24
ML21347A0102021-12-20020 December 2021
Proposed Alternative to Implement ASME Code Case OMN-26
ML21335A1062021-12-0707 December 2021
Proposed Alternative to ASME Code W, Section XI, Subsection Iwl Regarding Containment Post-Tensioning System Inservice Inspection Requirements
ML21281A1412021-11-19019 November 2021
Authorization and Safety Evaluation for Alternative Reactor Pressure Vessel Inservice Inspection Intervals
ML21155A2132021-08-26026 August 2021
Plant
ML21113A0132021-05-0606 May 2021
Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities
ML21006A0982021-03-15015 March 2021
Issuance of Amendment Nos. 421, 423, and 422 Revision of Licensing Basis for High Energy Line Breaks Outside of Containment (EPID L-2019-LLA-0184) (Public Version)
ML21029A3352021-02-16016 February 2021
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20335A0012021-01-26026 January 2021
Issuance of Amendment Nos. 420, 422, and 421 Measurement Uncertainty Recapture Power Uprate
ML20303A0242020-12-0909 December 2020
Issuance of Amendments 419, 421, 420 TSTF-272, Refueling Boron Concentration Clarification
ML20296A2812020-11-25025 November 2020
Issuance of Amendment Nos. 418, 420 and 419 TSTF-421, Revision to RCP Flywheel Inspection Program
ML20300A2062020-11-0909 November 2020
Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20258A2712020-09-21021 September 2020
Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268
ML20237F4352020-09-0404 September 2020
Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations
ML20083F9272020-08-12012 August 2020
Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description
ML20055F5712020-02-26026 February 2020
Proposed Alternative Request 19-ON-001 to Use Modified American Society of Mechanical Engineer'S Boiler and Pressure Vessel Code Case N-853
ML20042D7142020-02-13013 February 2020
Relief Request 19-ON-002 for Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in ASME Code Case N-770-2
ML19260E0842019-10-31031 October 2019
Issuance of Amendments 415, 417, and 416, Regarding the Updated Final Safety Analysis Report Description of Tornado Mitigation
ML19056A0862019-09-30030 September 2019
Issuance of Amendments Nos. 414, 416 and 415 Regarding the Physical Security Plan
ML19254A6202019-09-17017 September 2019
Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography
ML19183A3172019-07-17017 July 2019
Issuance of Amendments Regarding the Updated Final Safety Analysis Report Section for Fission Gas Gap Release Rates
ML19058A6322019-07-0101 July 2019
Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs
ML19128A3262019-06-20020 June 2019
Alternative to Depth Sizing Qualification Examination of Welds
ML18311A1342018-12-17017 December 2018
Non Proprietary - Issuance of Amendments Regarding the Updated Final Safety Analysis Report Section for the Standby Shutdown Facility
ML18172A1722018-08-15015 August 2018
Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application
ML18040A1942018-04-12012 April 2018
Issuance of Amendments Regarding the Technical Specifications for Control Room Habitability (CAC Nos. MF9555, MF9556, and MF9557; EPID L-2017-LLA-0219)
ML18051B2572018-02-28028 February 2018
Safety Evaluation for Alternative to Codes and Standards Requirements Associated with Bronze Tape Wrapped Emergency Power Cables (CAC Nos. MF7365, MF7366, and MF7367; EPID L-2016-LLR-0001)
ML17331A0862017-12-26026 December 2017
Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads
ML17335A0252017-12-0505 December 2017
Correction to Safety Evaluation for Amendment Nos. 406, 408, and 407 (CAC Nos. MF7417, MF7418, and MF7419; EPID L-2016-LLA-0002)
ML17124A6082017-11-20020 November 2017
Issuance of Amendments Regarding the Technical Specifications for Electrical Power Systems (CAC Nos. MF7417, MF7418, and MF7419; EPID L-2016-LLA-0002)
ML17202U7912017-08-30030 August 2017
Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML17188A3872017-08-21021 August 2017
Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660)
ML17167A2652017-07-12012 July 2017
Issuance of Amendments Regarding the Technical Specifications for Dry Spent Fuel Storage Cask Loading and Unloading (CAC Nos. MF8161, MF8162, and MF8163)
ML17103A5092017-05-11011 May 2017
Issuance of Amendments Allowing the Use of the Copernic Fuel Performance Code
ML17066A3742017-04-26026 April 2017
Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049)
ML16197A0112016-07-22022 July 2016
Relief Request Nos. 15-ON-002 and 15-ON-003, Fourth 10-Year Inservice Inspection Interval
2023-09-25
[Table view] |
Text
May 4, 2006 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672
SUBJECT:
OCONEE NUCLEAR STATION, UNIT 3, ISSUANCE OF AMENDMENTS RE:
REPLACEMENT OF REACTOR BUILDING EMERGENCY SUMP SUCTION INLET TRASH RACKS AND SCREENS WITH STRAINERS (TAC NO. MC8127)
Dear Mr. Hamilton:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 350 to Renewed Facility Operating License DPR-55 for the Oconee Nuclear Station, Unit 3. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated August 18, 2005, as supplemented by letters dated September 15, 2005, and January 5 and April 6, 2006.
The amendment revises TS 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally-generated missiles for Unit 3.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Leonard N. Olshan, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287
Enclosures:
- 1. Amendment No. 350 to DPR-55
- 2. Safety Evaluation cc w/encls: See next page
May 4, 2006 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672
SUBJECT:
OCONEE NUCLEAR STATION, UNIT 3, ISSUANCE OF AMENDMENTS RE:
REPLACEMENT OF REACTOR BUILDING EMERGENCY SUMP SUCTION INLET TRASH RACKS AND SCREENS WITH STRAINERS (TAC NO. MC8127)
Dear Mr. Hamilton:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. to Renewed Facility Operating License DPR-55 for the Oconee Nuclear Station, Unit 3. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated August 18, 2005, as supplemented by letters dated September 15, 2005, and January 5 and April 6, 2006.
The amendment revises TS 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally-generated missiles for Unit 3.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Leonard N. Olshan, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287
Enclosures:
- 1. Amendment No. 350 to DPR-55
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public RidsAcrsAcnwMailCenter LPL2-1 R/F GHill(6 hard copies)
RidsNrrDorlLplc(EMarinos) RidsNrrDirsItsb(TBoyce)
RidsNrrPMLOlshan(hard copy) Princ Contr of SE/Tech Br RidsNrrLAMOBrien(hard copy) RidsRgn2MailCenter(MErnstes)
RidsOgcRp BSingal (DORL DPR)
Package No.: ML061150507 License Amendment No. ML061140442 Tech Spec No.: ML061160014 NRR-058 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA OGC BGCB/BD NRR/LPL2-1/BC NAME LOlshan MOBrien SHamrick RKaras CM for EMarinos DATE 4/13/06 5/4/06 4/25/06 4/17/06 5/4/06
OFFICIAL RECORD COPY DUKE POWER COMPANY LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 350 Renewed License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Renewed Facility Operating License No. DPR-55 filed by the Duke Power Company LLC, (the licensee) dated August 18, 2005, supplemented September 15, 2005, and January 5 and April 6, 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 as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 350, 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
/RA/
Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: May 4, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 350 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.5.2-5a 3.5.2-5 3.5.2-5b 3.5.3-3 3.5.3-3a 3.5.3-3b
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 350 TO RENEWED FACILITY OPERATING LICENSE DPR-55 DUKE POWER COMPANY LLC OCONEE NUCLEAR STATION, UNIT 3 DOCKET NO. 50-287
1.0 INTRODUCTION
By letter dated August 18, 2005, as supplemented September 15, 2005, and January 5 and April 6, 2006, Duke Power Company LLC (the licensee), submitted a request for changes to the Oconee Nuclear Station, Unit 3, Technical Specifications (TSs). The requested changes would revise TSs 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump (RBES) suction inlet trash racks and screens with strainers. Similar amendments were issued for Units 1 and 2 on November 1, 2005; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement and internally generated missiles for Unit 3.
The supplements dated September 15, 2005, and January 5 and April 6, 2006, provided clarifying information that did not change the scope of the original application and the initial proposed no significant hazards consideration determination.
2.0 REGULATORY EVALUATION
Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents and Pressurized Water Reactors, is part of the regulatory framework the NRC staff is using to address issues associated with Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on PWR Sump Performance, for requirements to improve evaluation of plant capability to meet Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.46(b)(5).
The new strainers are functionally equivalent to the existing trash racks and screens for meeting requirements of 10 CFR 50.46(b)(5) for long-term cooling and 10 CFR Part 50, Appendix A, Criterion 35 for emergency core cooling.
3.0 TECHNICAL EVALUATION
The proposed change involves revising TS Surveillance Requirements 3.5.2.6 and 3.5.3.6 to use the term "strainers" to replace the terms "trash racks and screens. This change is needed to reflect the replacement of RBES suction inlet trash racks and screens with strainer
assemblies in response to NRC Generic Letter 2004-02. The new strainers are functionally equivalent to the existing trash racks and screens for meeting the requirements of 10 CFR 50.46(b)(5) for long-term cooling and 10 CFR Part 50, Appendix A, Criterion 35 for emergency core cooling. The use of the generic term "strainers" can be used for both the existing and new designs, will not affect implementation of Surveillance Requirements 3.5.2.6 and 3.5.3.6, and can be used for implementation of corrective actions to address GSI-191.
GSI-191 was established by the NRC to determine whether transport and accumulation of debris in pressurized-water reactor (PWR) containments following a loss-of-coolant accident (LOCA) would impede the long-term operation of the emergency core cooling system or containment spray system. The NRC is currently implementing its plan to have all PWR licensees evaluate the potential for excessive head loss across the containment sump screen and implement necessary actions to resolve concerns associated with GSI-191. This action plan includes review of all licensee responses to GL 2004-02 and plant audits as needed to confirm proper evaluation and corrective actions to address all technical issues associated with proper sump performance. The information that was provided by the licensee regarding jet impingement and pipe whip effects, and missile protection, will be reviewed as part of this action plan.
The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment, which are described in Attachments 3, 4, and 5 of the licensees August 18, 2005, submittal and finds these justifications acceptable.
On November 1, 2005, similar amendments were issued for Units 1 and 2; however, the amendment for Unit 3 was not issued at that time since the licensee had not completed its evaluation of the impact of pipe whip, jet impingement, and internally-generated missiles for Unit 3. By letter dated April 6, 2006, the licensee provided the results of these evaluations.
The NRC staff has reviewed Dukes evaluation of pipe whip, jet impingement and internally generated missile impact on the emergency sump strainer. The sources and targets were identified by a walkdown of Unit 1 and applied to Unit 3 on the basis of similarity. Duke Calculations S-005 "Missile Evaluation for the Emergency Sump Strainer," and S-006, "Jet Impingement and Pipe Whip Evaluation for the Emergency Sump Strainer," document the walkdown results and perform the analysis of the findings. The calculations document that Unit 3 piping arrangement in the area of the RBES is similar to that of Unit 1 & Unit 2. The NRC staff concurs with the conclusions of these calculations. Based on this evaluation, the licensee concludes that the emergency strainer operability will not be compromised during a LOCA by missiles, jet impingement or pipe whip. The NRC staff concludes that there are no credible missiles nor credible high-energy line break jets or pipe whips that could damage the strainer when needed during a LOCA.
Based on the review of the calculations provided by the licensee, the NRC staff grants approval of the proposed TS changes with regard to the evaluation for jet impingement, pipe whip and internally-generated missile impact of the RBES for Unit 3.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the 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 (70 FR 51852). 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 Contributors: T. Hafera S. Samaddar Date: May 4, 2006 Oconee Nuclear Station, Units 1, 2, and 3
cc:
Ms. Lisa F. Vaughn Manager - Nuclear Regulatory Duke Power Company, LLC Issues and Industry Affairs 526 South Church Street Duke Power Company, LLC P. O. Box 1006 526 S. Church St.
Mail Code = EC07H Mail Stop EC05P Charlotte, North Carolina 28201-1006 Charlotte, NC 28202 Manager, LIS Division of Radiation Protection NUS Corporation NC Dept of Environment, Health, & Natural 2650 McCormick Dr., 3rd Floor Resources Clearwater, FL 34619-1035 3825 Barrett Dr.
Raleigh, NC 27609-7721 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. Peter R. Harden, IV 7812B Rochester Highway VP-Customer Relations and Sales Seneca, SC 29672 Westinghouse Electric Company 6000 Fairview Road Mr. Henry Porter, Director 12th Floor Division of Radioactive Waste Management Charlotte, NC 28210 Bureau of Land and Waste Management Dept. of Health and Env. Control Mr. Henry Barron 2600 Bull St. Group Vice President, Nuclear Generation Columbia, SC 29201-1708 and Chief Nuclear Officer P.O. Box 1006-EC07H Mr. Michael A. Schoppman Charlotte, NC 28201-1006 Framatome ANP 1911 North Ft. Myer Dr.
Suite 705 Rosslyn, VA 22209 Mr. B. G. Davenport Regulatory Compliance Manager Oconee Nuclear Site Duke Power Company, LLC ON03RC 7800 Rochester Highway Seneca, SC 29672 Ms. Karen E. Long Assistant Attorney General NC Department of Justice P.O. Box 629 Raleigh, NC 27602 Mr. R. L. Gill, Jr.
