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| {{#Wiki_filter:March 21, 2006Mr. Christopher M. Crane, President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 | | {{#Wiki_filter:March 21, 2006 Mr. Christopher M. Crane, President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| CLINTON POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT - RE: REVISION OF SECONDARY CONTAINMENT BYPASS LEAKAGE SURVEILLANCE REQUIREMENT (TAC NO. MC6488) | | CLINTON POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT - |
| | RE: REVISION OF SECONDARY CONTAINMENT BYPASS LEAKAGE SURVEILLANCE REQUIREMENT (TAC NO. MC6488) |
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| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
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| The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 173 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit 1. Theamendment is in response to your application dated March 25, 2005.The amendment revises Technical Specification Surveillance Requirement (SR) 3.6.1.3.8 to exclude the containment purge valve leakage rates from the summation of secondary containment bypass leakage rates.A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in theCommission's next biweekly Federal Register notice.Sincerely,/RA/Kahtan N. Jabbour, Senior Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-461 | | The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 173 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit 1. The amendment is in response to your application dated March 25, 2005. |
| | The amendment revises Technical Specification Surveillance Requirement (SR) 3.6.1.3.8 to exclude the containment purge valve leakage rates from the summation of secondary containment bypass leakage rates. |
| | A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Kahtan N. Jabbour, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 173 to NPF-62 | | : 1. Amendment No. 173 to NPF-62 |
| : 2. Safety Evaluationcc w/encls: See next page Mr. Christopher M. Crane, PresidentMarch 21, 2006 and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 | | : 2. Safety Evaluation cc w/encls: See next page |
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| | Mr. Christopher M. Crane, President March 21, 2006 and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, Illinois 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| CLINTON POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT - RE: REVISION OF SECONDARY CONTAINMENT BYPASS LEAKAGE SURVEILLANCE REQUIREMENT (TAC NO. MC6488) | | CLINTON POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT - |
| | RE: REVISION OF SECONDARY CONTAINMENT BYPASS LEAKAGE SURVEILLANCE REQUIREMENT (TAC NO. MC6488) |
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| ==Dear Mr. Crane:== | | ==Dear Mr. Crane:== |
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| The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 173 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit 1. Theamendment is in response to your application dated March 25, 2005.The amendment revises Technical Specification Surveillance Requirement (SR) 3.6.1.3.8 to exclude the containment purge valve leakage rates from the summation of secondary containment bypass leakage rates.A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in theCommission's next biweekly Federal Register notice.Sincerely,/RA/Kahtan N. Jabbour, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-461 | | The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 173 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit 1. The amendment is in response to your application dated March 25, 2005. |
| | The amendment revises Technical Specification Surveillance Requirement (SR) 3.6.1.3.8 to exclude the containment purge valve leakage rates from the summation of secondary containment bypass leakage rates. |
| | A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Kahtan N. Jabbour, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 173 to NPF-62 | | : 1. Amendment No. 173 to NPF-62 |
| : 2. Safety Evaluationcc w/encls: See next page DISTRIBUTION | | : 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: |
| :PUBLICLPLIII-2 R/FGHill (2) RidsAcrsAcnwMailCenterRidsOgcRpRidsNrrLADClarke RidsNrrPMKJabbourRidsRgn3MailCenterRidsNrrDirsItsbDORL DPRRidsNrrDorlLplfRidsNrrDraAcvb JPulsipherRidsNrrCHarbuck TWengertRidsNRRMHartPackage: ML060610305Amendment: ML060610286 Tech Spec Page: ML061040207OFFICELPLIII-2/PMLPLIII-2/PELPLIII-2/LADRA/ACVB/BCNAMEKJabbourTWengertDClarkeRDennigDATE3/13/063/13/063/13/063/20/06OFFICEITSB/BCOGCLPLIII-2/BC(A)NAMETBoyceAHodgdonDCollins(EHackett for)DATE3/17/063/17/063/20/06OFFICIAL RECORD COPY AMERGEN ENERGY COMPANY, LLCDOCKET NO. 50-461CLINTON POWER STATION, UNIT 1AMENDMENT TO FACILITY OPERATING LICENSEAmendment No.173License No. NPF-621.The U.S. Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by AmerGen Energy Company, LLC (thelicensee), dated March 25, 2005, 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 theCommission'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 FacilityOperating License No. NPF-62 is hereby amended to read as follows: (2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A and the EnvironmentalProtection Plan contained in Appendix B, as revised through Amendment No.173 are hereby incorporated into this license. The licensee shall operate the facilityin accordance with the Technical Specifications and the Environmental Protection Plan.3.This license amendment is effective as of its date of issuance and shall be implementedwithin 60 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA by E.Hackett for/Daniel S. Collins, ChiefPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
| | PUBLIC LPLIII-2 R/F GHill (2) |
| | RidsAcrsAcnwMailCenter RidsOgcRp RidsNrrLADClarke RidsNrrPMKJabbour RidsRgn3MailCenter RidsNrrDirsItsb DORL DPR RidsNrrDorlLplf RidsNrrDraAcvb JPulsipher RidsNrrCHarbuck TWengert RidsNRRMHart Package: ML060610305 Amendment: ML060610286 Tech Spec Page: ML061040207 OFFICE LPLIII-2/PM LPLIII-2/PE LPLIII-2/LA DRA/ACVB/BC NAME KJabbour TWengert DClarke RDennig DATE 3/13/06 3/13/06 3/13/06 3/20/06 OFFICE ITSB/BC OGC LPLIII-2/BC(A) |
| | NAME TBoyce AHodgdon DCollins (EHackett for) |
| | DATE 3/17/06 3/17/06 3/20/06 OFFICIAL RECORD COPY |
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| | AMERGEN ENERGY COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.173 License No. NPF-62 |
| | : 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by AmerGen Energy Company, LLC (the licensee), dated March 25, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows: |
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| | (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.173 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | : 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA by E.Hackett for/ |
| | Daniel S. Collins, Chief Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Technical SpecificationsDate of Issuance: March 21, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 173 FACILITY OPERATING LICENSE NO. NPF-62DOCKET NO. 50-461Replace the following page of Appendix "A," Technical Specifications, with the attached revisedpage. The revised page is identified by an amendment number and contains a marginal line indicating the area of change. Remove PageInsert Page3.6-193.6-19 Clinton Power Station, Unit 1 cc: | | Changes to the Technical Specifications Date of Issuance: March 21, 2006 |
| Senior Vice President of OperationsAmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Illinois Emergency Management Agency Division of Disaster Assistance & | | |
| Preparedness 110 East Adams Street Springfield, IL 62701-1109Vice President - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Manager Licensing - Dresden, Quad Cities, and ClintonAmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Regulatory Assurance Manager - ClintonAmerGen Energy Company, LLC Clinton Power Station RR3, Box 228 Clinton, IL 61727-9351Director - Licensing and Regulatory AffairsAmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Document Control Desk - LicensingAmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Site Vice President - Clinton Power StationAmerGen Energy Company, LLC Clinton Power Station RR 3, Box 228 Clinton, IL 61727-9351Clinton Power Station Plant M anagerAmerGen Energy Company, LLC Clinton Power Station RR 3, Box 228 Clinton, IL 61727-9351Resident InspectorU.S. Nuclear Regulatory Commission RR #3, Box 229A Clinton, IL 61727Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville RoadLisle, IL 60532-4351Assistant General CounselExelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348R. T. HillLicensing Services Manager General Electric Company 175 Curtner Avenue, M/C 481 San Jose, CA 95125Chairman of DeWitt Countyc/o County Clerk's Office DeWitt County Courthouse Clinton, IL 61727J. W. BlattnerProject Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago, IL 60603 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 173 TO FACILITY OPERATING LICENSE NO. NPF-62AMERGEN ENERGY COMPANY, LLCCLINTON POWER STATION, UNIT 1DOCKET NO. 50-46 | | ATTACHMENT TO LICENSE AMENDMENT NO. 173 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following page of Appendix "A," Technical Specifications, with the attached revised page. The revised page is identified by an amendment number and contains a marginal line indicating the area of change. |
| | Remove Page Insert Page 3.6-19 3.6-19 |
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| | Clinton Power Station, Unit 1 cc: |
| | Senior Vice President of Operations Clinton Power Station Plant Manager AmerGen Energy Company, LLC AmerGen Energy Company, LLC 4300 Winfield Road Clinton Power Station Warrenville, IL 60555 RR 3, Box 228 Clinton, IL 61727-9351 Illinois Emergency Management Agency Resident Inspector Division of Disaster Assistance & U.S. Nuclear Regulatory Commission Preparedness RR #3, Box 229A 110 East Adams Street Clinton, IL 61727 Springfield, IL 62701-1109 Regional Administrator, Region III Vice President - Licensing and U.S. Nuclear Regulatory Commission Regulatory Affairs Suite 210 AmerGen Energy Company, LLC 2443 Warrenville Road 4300 Winfield Road Lisle, IL 60532-4351 Warrenville, IL 60555 Assistant General Counsel Manager Licensing - Dresden, Quad Cities, Exelon Generation Company, LLC and Clinton 200 Exelon Way AmerGen Energy Company, LLC Kennett Square, PA 19348 4300 Winfield Road Warrenville, IL 60555 R. T. Hill Licensing Services Manager Regulatory Assurance Manager - Clinton General Electric Company AmerGen Energy Company, LLC 175 Curtner Avenue, M/C 481 Clinton Power Station San Jose, CA 95125 RR3, Box 228 Clinton, IL 61727-9351 Chairman of DeWitt County c/o County Clerks Office Director - Licensing and Regulatory Affairs DeWitt County Courthouse AmerGen Energy Company, LLC Clinton, IL 61727 4300 Winfield Road Warrenville, IL 60555 J. W. Blattner Project Manager Document Control Desk - Licensing Sargent & Lundy Engineers AmerGen Energy Company, LLC 55 East Monroe Street 4300 Winfield Road Chicago, IL 60603 Warrenville, IL 60555 Site Vice President - Clinton Power Station AmerGen Energy Company, LLC Clinton Power Station RR 3, Box 228 Clinton, IL 61727-9351 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 173 TO FACILITY OPERATING LICENSE NO. NPF-62 AMERGEN ENERGY COMPANY, LLC CLINTON POWER STATION, UNIT 1 DOCKET NO. 50-461 |
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| | ==1.0 INTRODUCTION== |
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| | By letter to the Nuclear Regulatory Commission (NRC, Commission) dated March 25, 2005, (Agencywide Documents Access and Management System Accession Number ML050870603) |
| | AmerGen Energy Company, LLC (the licensee), requested a technical specification (TS) change for Clinton Power Station, Unit 1 (Clinton). Specifically, the change would exclude the primary containment purge valve leakage rates from the summation of secondary containment bypass leakage rates. |
| | TS Surveillance Requirement (SR) 3.6.1.3.8 states: |
| | Verify the combined leakage rate for all secondary containment bypass leakage paths is # 0.08 La when pressurized to $ Pa. |
| | La is the maximum allowable primary containment leakage rate at pressure Pa. Pa is the calculated peak primary containment internal pressure related to the design basis loss-of-coolant accident (LOCA). |
| | The licensee proposes to add a note which states: |
| | Leakage through penetrations 1MC-101 and 1MC-102 is excluded. |
| | Penetrations 1MC-101 and 1MC-102 are the primary containment purge valve penetrations. |
| | In addition, by this letter, the licensee requested withdrawal of its July 1, 2004, request for exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, which was submitted in support of its application for the alternative source term (AST). The NRC staff had no objection to the withdrawal. |
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| | ==2.0 BACKGROUND== |
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| | The Clinton plant has a secondary containment, which encloses the primary containment. Its function is to capture radioactive material leaking from the primary containment during an accident, and to reduce the radiological consequences of this leakage by hold-up, recirculation, and filtration before release. However, a small amount of primary containment leakage will |
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| | bypass the secondary containment during an accident and be released directly to the environment. The licensee assumes a total secondary containment bypass leakage rate amount in its radiological consequences analysis, and then establishes a TS to verify and maintain that limit during plant operation. |
| | Licensees identify primary containment penetrations, which are potential secondary containment bypass leakage pathways, in accordance with the guidelines in Standard Review Plan, Section 6.2.3, Secondary Containment Functional Design, and Branch Technical Position CSB [Containment Systems Branch] 6-3, Determination of Bypass Leakage Paths in Dual Containment Plants. The leakage rates through these penetrations are periodically measured and their sum must not exceed the TS limit for the total secondary containment bypass leakage rate. |
| | The leakage rate through a potential secondary containment bypass leakage pathway is typically measured by performing local leakage rate tests on the primary containment isolation valves (PCIVs) in the pathway. |
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| | ==2.0 REGULATORY EVALUATION== |
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| | 10 CFR Part 50, Appendix J, contains requirements for performing local leakage rate tests on certain penetrations (Type B tests) and PCIVs (Type C tests). In addition, it requires that the sum of the leakage rates from Types B and C tests not exceed a limit specified in TS 5.5.13.a. |
| | (i.e., 0.6 La). However, Appendix J does not directly address secondary containment bypass leakage rates or their limits. The PCIVs in potential secondary containment bypass leakage pathways are a subset of the PCIVs that are Type C tested. |
| | TS SR 3.6.1.3.8 specifies a limit of 0.08 La for the sum of the leakage rates through the potential secondary containment bypass leakage pathways. The Type C test results for the PCIVs are used to calculate the sum, which is then compared to the TS SR 3.6.1.3.8 limit of 0.08 La for the total secondary containment bypass leakage rate. However, neither Appendix J nor any other regulation controls which PCIVs are to be tested as potential secondary containment bypass leakage pathways. Further, no regulation specifies the TS limit for the sum of potential secondary containment bypass leakage rates. |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | Clinton has requested full implementation of the AST in accordance with 10 CFR 50.67, Accident Source Term. License Amendment No. 167, dated September 19, 2005, approved the revised radiological consequence analysis for LOCAs associated with this request. In the revised analysis, the contribution to dose from the primary containment purge valves is calculated separately from the other potential secondary containment bypass leakage pathways. All of the doses calculated from the various release terms (primary containment, main steam isolation valves, feedwater isolation valves, primary containment purge valves, and emergency core cooling system leakage outside primary containment) are added together and shown to be within the applicable regulatory limits (10 CFR 50.67, as supplemented in Regulatory Position 4.4 of Regulatory Guide 1.183 and 10 CFR Part 50, Appendix A, General Design Criterion 19, Control Room). |
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| ==11.0INTRODUCTION==
| | Based on its review, the NRC staff finds that: |
| By letter to the Nuclear Regulatory Commission (NRC, Commission) dated March 25, 2005,(Agencywide Documents Access and Management System Accession Number ML050870603)
| | : 1. The current TS combines primary containment purge valve leakage rates with the leakage rates of the other secondary containment bypass leakage pathways, in accordance with the pre-AST radiological consequence analysis for LOCA; |
| AmerGen Energy Company, LLC (the licensee), requested a technical specification (TS) change for Clinton Power Station, Unit 1 (Clinton). Specifically, the change would exclude theprimary containment purge valve leakage rates from the summation of secondary containment bypass leakage rates.TS Surveillance Requirement (SR) 3.6.1.3.8 states:Verify the combined leakage rate for all secondary containment bypass leakagepaths is 0.08 L a when pressurized to P a.L a is the maximum allowable primary containment leakage rate at pressure P
| | : 2. The dose contribution of the primary containment purge valves is calculated separately from the other potential secondary containment bypass leakage pathways in the AST analysis; |
| : a. P a is thecalculated peak primary containment internal pressure related to the design basis loss-of-coolant accident (LOCA).The licensee proposes to add a note which states:Leakage through penetrations 1MC-101 and 1MC-102 is excluded.Penetrations 1MC-101 and 1MC-102 are the primary containment purge valve penetrations. | | : 3. The total calculated LOCA dose is within regulatory limits; |
| In addition, by this letter, the licensee requested withdrawal of its July 1, 2004, request forexemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix J,"Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," which was submitted in support of its application for the alternative source term (AST). The NRC staff hadno objection to the withdrawal.
| | : 4. The primary containment purge valves have their own separate TS leakage rate limit; and |
| | : 5. There is no regulatory requirement, other than the current Clinton TS, to sum the primary containment purge valve leakage rates with other potential secondary containment bypass pathway leakage rates. |
| | Therefore, the NRC staff finds that the primary containment purge valve leakage rates may be excluded from the combined leakage rate of the other potential secondary containment bypass leakage pathways, in TS SR 3.6.1.3.8. |
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| ==2.0BACKGROUND== | | ==4.0 STATE CONSULTATION== |
| The Clinton plant has a secondary containment, which encloses the primary containment. Itsfunction is to capture radioactive material leaking from the primary containment during an accident, and to reduce the radiological consequences of this leakage by hold-up, recirculation, and filtration before release. However, a small amount of primary containment leakage will bypass the secondary containment during an accident and be released directly to theenvironment. The licensee assumes a total secondary containment bypass leakage rate amount in its radiological consequences analysis, and then establishes a TS to verify and maintain that limit during plant operation.Licensees identify primary containment penetrations, which are potential secondarycontainment bypass leakage pathways, in accordance with the guidelines in Standard Review Plan, Section 6.2.3, "Secondary Containment Functional Design," and Branch TechnicalPosition CSB [Containment Systems Branch] 6-3, "Determination of Bypass Leakage Paths in Dual Containment Plants." The leakage rates through these penetrations are periodically measured and their sum must not exceed the TS limit for the total secondary containment bypass leakage rate.The leakage rate through a potential secondary containment bypass leakage pathway istypically measured by performing local leakage rate tests on the primary containment isolation valves (PCIVs) in the pathway.
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| ==2.0REGULATORY EVALUATION==
| | In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendment. The State official had no comments. |
| 10 CFR Part 50, Appendix J, contains requirements for performing local leakage rate tests oncertain penetrations (Type B tests) and PCIVs (Type C tests). In addition, it requires that the sum of the leakage rates from Types B and C tests not exceed a limit specified in TS 5.5.13.a.
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| (i.e., 0.6 L a). However, Appendix J does not directly address secondary containment bypassleakage rates or their limits. The PCIVs in potential secondary containment bypass leakage pathways are a subset of the PCIVs that are Type C tested.TS SR 3.6.1.3.8 specifies a limit of 0.08 L a for the sum of the leakage rates through thepotential secondary containment bypass leakage pathways. The Type C test results for the PCIVs are used to calculate the sum, which is then compared to the TS SR 3.6.1.3.8 limit of 0.08 L a for the total secondary containment bypass leakage rate. However, neither Appendix Jnor any other regulation controls which PCIVs are to be tested as potential secondary containment bypass leakage pathways. Further, no regulation specifies the TS limit for the sumof potential secondary containment bypass leakage rates.
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| ==3.0 TECHNICAL EVALUATION== | | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| Clinton has requested full implementation of the AST in accordance with 10 CFR 50.67,"Accident Source Term." License Amendment No. 167, dated September 19, 2005, approvedthe revised radiological consequence analysis for LOCAs associated with this request. In the revised analysis, the contribution to dose from the primary containment purge valves iscalculated separately from the other potential secondary containment bypass leakagepathways. All of the doses calculated from the various release terms (primary containment,main steam isolation valves, feedwater isolation valves, primary containment purge valves, and emergency core cooli ng system leakage outside primary containment) are added together andshown to be within the applicable regulatory limits (10 CFR 50.67, as supplemented in Regulatory Position 4.4 of Regulatory Guide 1.183 and 10 CFR Part 50, Appendix A, GeneralDesign Criterion 19, "Control Room"). Based on its review, the NRC staff finds that:1.The current TS combines primary containment purge valve leakage rates with theleakage rates of the other secondary containment bypass leakage pathways, in accordance with the pre-AST radiological consequence analysis for LOCA;2.The dose contribution of the primary containment purge valves is calculated separatelyfrom the other potential secondary containment bypass leakage pathways in the ASTanalysis;3.The total calculated LOCA dose is within regulatory limits; 4.The primary containment purge valves have their own separate TS leakage rate limit; and5.There is no regulatory requirement, other than the current Clinton TS, to sum theprimary containment purge valve leakage rates with other potential secondary containment bypass pathway leakage rates.Therefore, the NRC staff finds that the primary containment purge valve leakage rates may beexcluded from the combined leakage rate of the other potential secondary containment bypassleakage pathways, in TS SR 3.6.1.3.8.
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| ==4.0STATE CONSULTATION==
| | 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, or changes a surveillance requirement. 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (70 FR 21451; April 26, 2005). |
| In accordance with the Commission's regulations, the Illinois State official was notified of theproposed issuance of the amendment. The State official had no comments.
| | 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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| ==5.0ENVIRONMENTAL CONSIDERATION== | | ==6.0 CONCLUSION== |
| 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, or changes a surveillance requirement. 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 amendments involve no significant hazards consideration, and there has been nopublic comment on such finding (70 FR 21451; April 26, 2005).Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in10 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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| ==6.0CONCLUSION==
| | The NRC staff 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 amendments will not be inimical to the common defense and security or to the health and safety of the public. |
| The NRC staff has concluded, based on the considerations discussed above, that: (1) there isreasonable 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 amendments will not be inimical to thecommon defense and security or to the health and safety of the public.Principal Contributor: J. Pulsipher Date: March 21, 2006}} | | Principal Contributor: J. Pulsipher Date: March 21, 2006}} |
Letter Sequence Approval |
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MONTHYEARML0602605522006-01-25025 January 2006 Technical Specifications Pages- Reactor Coolant System Pressure and Temperature Curves Project stage: Other ML0610402072006-03-21021 March 2006 Tech Spec Page for Amendment 17 Regarding Revision of Secondary Containment Bypass Leakage Surveillance Requirement Project stage: Other ML0606102862006-03-21021 March 2006 License Amendment 17 Regarding Revision of Secondary Containment Bypass Leakage Surveillance Requirement Project stage: Approval 2006-01-25
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Category:Letter
MONTHYEARIR 05000461/20230042024-02-0202 February 2024 Integrated Inspection Report 05000461/2023004 ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation ML24004A0792024-01-18018 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0041 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000461/20230032023-11-0808 November 2023 Integrated Inspection Report 05000461/2023003 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000461/20233012023-09-12012 September 2023 NRC Initial License Examination Report 05000461/2023301 RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000461/20234202023-08-29029 August 2023 Security Baseline Inspection Report 05000461/2023420 RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20230022023-08-0404 August 2023 Integrated Inspection Report 05000461/2023002 RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release ML23209A8102023-07-28028 July 2023 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23198A0152023-07-27027 July 2023 License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23202A0992023-07-24024 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000461/2023004 ML23200A2592023-07-24024 July 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary IR 05000461/20234012023-07-19019 July 2023 Cyber Security Inspection Report 05000461/2023401 ML23194A1662023-07-19019 July 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Partial Site Release ML23191A8772023-07-11011 July 2023 Operator Licensing Examination Approval Clinton Power Station July 2023 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release IR 05000461/20230102023-05-26026 May 2023 Triennial Fire Protection Inspection Report 05000461/2023010 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23143A3182023-05-23023 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 IR 05000461/20230012023-05-0404 May 2023 Integrated Inspection Report 05000461/2023001 ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000461/20220062023-03-0101 March 2023 Annual Assessment Letter for Clinton Power Station, Unit 1 (Report 05000461/2022006) RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 ML23039A1852023-02-10010 February 2023 Integrated Inspection Report 05000461/2022004 07201046/2022001 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 IR 05000461/20220112023-01-27027 January 2023 Biennial Problem Identification and Resolution Inspection Report 05000461/2022011 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing ML23005A0682023-01-0505 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000461/2023010 ML22341A6042022-12-0808 December 2022 Confirmation of Initial License Examination IR 05000461/20224022022-12-0606 December 2022 Security Baseline Inspection Report 05000461/2022402 RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI 2024-02-02
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 ML22263A4732022-11-10010 November 2022 Issuance of Amendment No. 247 Adoption of TSTF-230, Revision 1 ML22292A0352022-11-10010 November 2022 Issuance of Amendment No. 246 Secondary Containment and the Fuel Building Railroad Airlock (EPID L-2022- LLA-0055) ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21306A0002021-12-21021 December 2021 License Amendment to Revise Degraded Voltage Relay Allowable Values ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21132A2882021-06-28028 June 2021 Issuance of Amendment No. 238, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21090A1932021-05-19019 May 2021 Issuance of Amendment No. 237 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20266G3432020-10-14014 October 2020 Issuance of Amendment No. 235 Regarding Operation of the Emergency Auxiliary Reserve Transformer Load Tap Changer ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19266A5272019-10-0808 October 2019 Issuance of Amendments to Eliminate Second Completion Times from Technical Specifications ML19238A3082019-09-30030 September 2019 Issuance of Amendment - Regarding Adoption of TSTF-476, Improved Banked Position Withdrawal Sequence Control Rod Insertion Process ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19109A0012019-06-12012 June 2019 Issuance of Amendment Regarding Recapture of Low-Power Testing Time ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18303A3132019-01-0303 January 2019 Issuance of Amendment 221 Regarding Revised Alternative Source Term Dose Calculation ML18254A3672018-10-29029 October 2018 County 1 & 2; and Quad Cities 1 & 2 - Issuance of Amendments 220, 259, 252, 231, 217, 271 and 266 to Revise Technical Specification Requirements for Inoperable Snubbers ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18113A0452018-05-29029 May 2018 Issuance of Amendments to Revise Technical Specification Requirements for Secondary Containment ML18072A0502018-04-30030 April 2018 Issuance of Amendment Regarding the Spent Fuel Pool Level (CAC No. MF9962; EPID L-2017-LLA-0258) ML18110A3542018-04-24024 April 2018 Correction to Facility Operating License ML18043A5052018-03-22022 March 2018 Issuance of Amendment to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC No. MF9666; EPID L-2017-LLA-0223) ML17324A3542018-01-22022 January 2018 Issuance of Amendment Regarding Residual Heat Removal Subsystem Operability Requirements During Decay Heat Removal Operations (CAC No. MF9684; EPID L-2017-LLA-0225) ML17237A0102017-09-26026 September 2017 Issuance of Amendment Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) ML17027A0382017-02-22022 February 2017 Issuance of Amendment Regarding Inservice Leak and Hydrostatic Testing Operations ML16217A3322016-08-17017 August 2016 Issuance of Amendment Concerning Incorporation of Revised Alternative Source Term (CAC No. MF7336) (RS-16-019) RS-16-132, Certification of Permanent Cessation of Power Operations2016-06-20020 June 2016 Certification of Permanent Cessation of Power Operations ML16111A1042016-05-11011 May 2016 Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644) ML15251A5842015-12-18018 December 2015 Issuance of Amendment Concerning Revision to Integrated Leak Test Intervals (TAC No. MF5291)(RS-14-308) ML15280A2582015-10-22022 October 2015 Issuance of Amendment Related to One-Time Extension of Completion Time for Shutdown Service Water (TAC No. MF6705)(RS-15-264) ML15153A2822015-07-30030 July 2015 Issuance of Amendments Revising the Completion Date for Milestone 8 of the Cyber Security Plan (TAC Nos. MF4728, MF4729, MF4730, MF4731, MF4732, MF4733, MF4734, MF4735, MF4736, MF4737, MF4738, MF4739, MF4740 ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML15114A1882015-06-19019 June 2015 Issuance of Amendments Adoption of Technical Specification Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation 2023-05-01
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22292A0352022-11-10010 November 2022 Issuance of Amendment No. 246 Secondary Containment and the Fuel Building Railroad Airlock (EPID L-2022- LLA-0055) ML22263A4732022-11-10010 November 2022 Issuance of Amendment No. 247 Adoption of TSTF-230, Revision 1 ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22047A1272022-02-22022 February 2022 Relief from the Requirements of the American Society of Mechanical Engineers Code ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21306A0002021-12-21021 December 2021 License Amendment to Revise Degraded Voltage Relay Allowable Values ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21132A2882021-06-28028 June 2021 Issuance of Amendment No. 238, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21166A1682021-06-25025 June 2021 ML21090A1932021-05-19019 May 2021 Issuance of Amendment No. 237 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20268C2322020-11-0404 November 2020 Proposed Alternative I4R-06 to the Requirements of the ASME Code ML20266G3432020-10-14014 October 2020 Issuance of Amendment No. 235 Regarding Operation of the Emergency Auxiliary Reserve Transformer Load Tap Changer ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20218A6602020-09-0202 September 2020 Proposed Alternative I4R-01 to the Requirements of the ASME Code ML20232A1882020-09-0101 September 2020 Proposed Alternative I4R-02 to the Requirements of the ASME Code ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20219A2022020-09-0101 September 2020 Proposed Alternative I4R-05 to the Requirements of the American Society of Mechanical Engineers Code ML20212L3902020-08-31031 August 2020 Proposed Alternative I4r-03 to the Requirements of the Asme Code (Epid L-2019-Llr-0114) ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20163A7172020-06-26026 June 2020 Proposed Alternative to the Requirements of the ASME Code ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML20010E8702020-01-27027 January 2020 Proposed Alternative to the Requirements of the ASME Code ML19238A3082019-09-30030 September 2019 Issuance of Amendment - Regarding Adoption of TSTF-476, Improved Banked Position Withdrawal Sequence Control Rod Insertion Process ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19109A0012019-06-12012 June 2019 Issuance of Amendment Regarding Recapture of Low-Power Testing Time ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18303A3132019-01-0303 January 2019 Issuance of Amendment 221 Regarding Revised Alternative Source Term Dose Calculation 2023-04-28
[Table view] |
Text
March 21, 2006 Mr. Christopher M. Crane, President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, Illinois 60555
SUBJECT:
CLINTON POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT -
RE: REVISION OF SECONDARY CONTAINMENT BYPASS LEAKAGE SURVEILLANCE REQUIREMENT (TAC NO. MC6488)
Dear Mr. Crane:
The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 173 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit 1. The amendment is in response to your application dated March 25, 2005.
The amendment revises Technical Specification Surveillance Requirement (SR) 3.6.1.3.8 to exclude the containment purge valve leakage rates from the summation of secondary containment bypass leakage rates.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Kahtan N. Jabbour, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosures:
- 1. Amendment No. 173 to NPF-62
- 2. Safety Evaluation cc w/encls: See next page
Mr. Christopher M. Crane, President March 21, 2006 and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, Illinois 60555
SUBJECT:
CLINTON POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT -
RE: REVISION OF SECONDARY CONTAINMENT BYPASS LEAKAGE SURVEILLANCE REQUIREMENT (TAC NO. MC6488)
Dear Mr. Crane:
The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 173 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit 1. The amendment is in response to your application dated March 25, 2005.
The amendment revises Technical Specification Surveillance Requirement (SR) 3.6.1.3.8 to exclude the containment purge valve leakage rates from the summation of secondary containment bypass leakage rates.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Kahtan N. Jabbour, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosures:
- 1. Amendment No. 173 to NPF-62
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC LPLIII-2 R/F GHill (2)
RidsAcrsAcnwMailCenter RidsOgcRp RidsNrrLADClarke RidsNrrPMKJabbour RidsRgn3MailCenter RidsNrrDirsItsb DORL DPR RidsNrrDorlLplf RidsNrrDraAcvb JPulsipher RidsNrrCHarbuck TWengert RidsNRRMHart Package: ML060610305 Amendment: ML060610286 Tech Spec Page: ML061040207 OFFICE LPLIII-2/PM LPLIII-2/PE LPLIII-2/LA DRA/ACVB/BC NAME KJabbour TWengert DClarke RDennig DATE 3/13/06 3/13/06 3/13/06 3/20/06 OFFICE ITSB/BC OGC LPLIII-2/BC(A)
NAME TBoyce AHodgdon DCollins (EHackett for)
DATE 3/17/06 3/17/06 3/20/06 OFFICIAL RECORD COPY
AMERGEN ENERGY COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.173 License No. NPF-62
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by AmerGen Energy Company, LLC (the licensee), dated March 25, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.173 are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by E.Hackett for/
Daniel S. Collins, Chief Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 21, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 173 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following page of Appendix "A," Technical Specifications, with the attached revised page. The revised page is identified by an amendment number and contains a marginal line indicating the area of change.
Remove Page Insert Page 3.6-19 3.6-19
Clinton Power Station, Unit 1 cc:
Senior Vice President of Operations Clinton Power Station Plant Manager AmerGen Energy Company, LLC AmerGen Energy Company, LLC 4300 Winfield Road Clinton Power Station Warrenville, IL 60555 RR 3, Box 228 Clinton, IL 61727-9351 Illinois Emergency Management Agency Resident Inspector Division of Disaster Assistance & U.S. Nuclear Regulatory Commission Preparedness RR #3, Box 229A 110 East Adams Street Clinton, IL 61727 Springfield, IL 62701-1109 Regional Administrator, Region III Vice President - Licensing and U.S. Nuclear Regulatory Commission Regulatory Affairs Suite 210 AmerGen Energy Company, LLC 2443 Warrenville Road 4300 Winfield Road Lisle, IL 60532-4351 Warrenville, IL 60555 Assistant General Counsel Manager Licensing - Dresden, Quad Cities, Exelon Generation Company, LLC and Clinton 200 Exelon Way AmerGen Energy Company, LLC Kennett Square, PA 19348 4300 Winfield Road Warrenville, IL 60555 R. T. Hill Licensing Services Manager Regulatory Assurance Manager - Clinton General Electric Company AmerGen Energy Company, LLC 175 Curtner Avenue, M/C 481 Clinton Power Station San Jose, CA 95125 RR3, Box 228 Clinton, IL 61727-9351 Chairman of DeWitt County c/o County Clerks Office Director - Licensing and Regulatory Affairs DeWitt County Courthouse AmerGen Energy Company, LLC Clinton, IL 61727 4300 Winfield Road Warrenville, IL 60555 J. W. Blattner Project Manager Document Control Desk - Licensing Sargent & Lundy Engineers AmerGen Energy Company, LLC 55 East Monroe Street 4300 Winfield Road Chicago, IL 60603 Warrenville, IL 60555 Site Vice President - Clinton Power Station AmerGen Energy Company, LLC Clinton Power Station RR 3, Box 228 Clinton, IL 61727-9351
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 173 TO FACILITY OPERATING LICENSE NO. NPF-62 AMERGEN ENERGY COMPANY, LLC CLINTON POWER STATION, UNIT 1 DOCKET NO. 50-461
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC, Commission) dated March 25, 2005, (Agencywide Documents Access and Management System Accession Number ML050870603)
AmerGen Energy Company, LLC (the licensee), requested a technical specification (TS) change for Clinton Power Station, Unit 1 (Clinton). Specifically, the change would exclude the primary containment purge valve leakage rates from the summation of secondary containment bypass leakage rates.
TS Surveillance Requirement (SR) 3.6.1.3.8 states:
Verify the combined leakage rate for all secondary containment bypass leakage paths is # 0.08 La when pressurized to $ Pa.
La is the maximum allowable primary containment leakage rate at pressure Pa. Pa is the calculated peak primary containment internal pressure related to the design basis loss-of-coolant accident (LOCA).
The licensee proposes to add a note which states:
Leakage through penetrations 1MC-101 and 1MC-102 is excluded.
Penetrations 1MC-101 and 1MC-102 are the primary containment purge valve penetrations.
In addition, by this letter, the licensee requested withdrawal of its July 1, 2004, request for exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, which was submitted in support of its application for the alternative source term (AST). The NRC staff had no objection to the withdrawal.
2.0 BACKGROUND
The Clinton plant has a secondary containment, which encloses the primary containment. Its function is to capture radioactive material leaking from the primary containment during an accident, and to reduce the radiological consequences of this leakage by hold-up, recirculation, and filtration before release. However, a small amount of primary containment leakage will
bypass the secondary containment during an accident and be released directly to the environment. The licensee assumes a total secondary containment bypass leakage rate amount in its radiological consequences analysis, and then establishes a TS to verify and maintain that limit during plant operation.
Licensees identify primary containment penetrations, which are potential secondary containment bypass leakage pathways, in accordance with the guidelines in Standard Review Plan, Section 6.2.3, Secondary Containment Functional Design, and Branch Technical Position CSB [Containment Systems Branch] 6-3, Determination of Bypass Leakage Paths in Dual Containment Plants. The leakage rates through these penetrations are periodically measured and their sum must not exceed the TS limit for the total secondary containment bypass leakage rate.
The leakage rate through a potential secondary containment bypass leakage pathway is typically measured by performing local leakage rate tests on the primary containment isolation valves (PCIVs) in the pathway.
2.0 REGULATORY EVALUATION
10 CFR Part 50, Appendix J, contains requirements for performing local leakage rate tests on certain penetrations (Type B tests) and PCIVs (Type C tests). In addition, it requires that the sum of the leakage rates from Types B and C tests not exceed a limit specified in TS 5.5.13.a.
(i.e., 0.6 La). However, Appendix J does not directly address secondary containment bypass leakage rates or their limits. The PCIVs in potential secondary containment bypass leakage pathways are a subset of the PCIVs that are Type C tested.
TS SR 3.6.1.3.8 specifies a limit of 0.08 La for the sum of the leakage rates through the potential secondary containment bypass leakage pathways. The Type C test results for the PCIVs are used to calculate the sum, which is then compared to the TS SR 3.6.1.3.8 limit of 0.08 La for the total secondary containment bypass leakage rate. However, neither Appendix J nor any other regulation controls which PCIVs are to be tested as potential secondary containment bypass leakage pathways. Further, no regulation specifies the TS limit for the sum of potential secondary containment bypass leakage rates.
3.0 TECHNICAL EVALUATION
Clinton has requested full implementation of the AST in accordance with 10 CFR 50.67, Accident Source Term. License Amendment No. 167, dated September 19, 2005, approved the revised radiological consequence analysis for LOCAs associated with this request. In the revised analysis, the contribution to dose from the primary containment purge valves is calculated separately from the other potential secondary containment bypass leakage pathways. All of the doses calculated from the various release terms (primary containment, main steam isolation valves, feedwater isolation valves, primary containment purge valves, and emergency core cooling system leakage outside primary containment) are added together and shown to be within the applicable regulatory limits (10 CFR 50.67, as supplemented in Regulatory Position 4.4 of Regulatory Guide 1.183 and 10 CFR Part 50, Appendix A, General Design Criterion 19, Control Room).
Based on its review, the NRC staff finds that:
- 1. The current TS combines primary containment purge valve leakage rates with the leakage rates of the other secondary containment bypass leakage pathways, in accordance with the pre-AST radiological consequence analysis for LOCA;
- 2. The dose contribution of the primary containment purge valves is calculated separately from the other potential secondary containment bypass leakage pathways in the AST analysis;
- 3. The total calculated LOCA dose is within regulatory limits;
- 4. The primary containment purge valves have their own separate TS leakage rate limit; and
- 5. There is no regulatory requirement, other than the current Clinton TS, to sum the primary containment purge valve leakage rates with other potential secondary containment bypass pathway leakage rates.
Therefore, the NRC staff finds that the primary containment purge valve leakage rates may be excluded from the combined leakage rate of the other potential secondary containment bypass leakage pathways, in TS SR 3.6.1.3.8.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois 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, or changes a surveillance requirement. 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (70 FR 21451; April 26, 2005).
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 NRC staff 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: J. Pulsipher Date: March 21, 2006