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| {{#Wiki_filter:October 27, 2006Mr. Richard AndersonVice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant, Unit 1 Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 | | {{#Wiki_filter:October 27, 2006 Mr. Richard Anderson Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant, Unit 1 Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PERRY NUCLEAR POWER PLANT, UNIT 1 - ISSUANCE OF AMENDMENTRE: CLARIFY WORDING OF EMERGENCY CLOSED COOLING WATER SURVEILLANCE REQUIREMENT 3.7.10.2 (TAC NO. MC8970) | | PERRY NUCLEAR POWER PLANT, UNIT 1 - ISSUANCE OF AMENDMENT RE: CLARIFY WORDING OF EMERGENCY CLOSED COOLING WATER SURVEILLANCE REQUIREMENT 3.7.10.2 (TAC NO. MC8970) |
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| ==Dear Mr. Pearce:== | | ==Dear Mr. Pearce:== |
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| The Commission has issued the enclosed Amendment No. 139 to Facility Operating LicenseNo. NPF-58 for the Perry Nuclear Power Plant, Unit 1. The amendment is in response to your application dated November 15, 2005.The amendment modifies the technical specifications to clarify the wording of emergencyclosed cooling water (ECCW) Surveillance Requirement (SR) 3.7.10.2. The SR verifies actuation of the entire ECCW system rather than just verifying "valve" actuation. 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/Thomas J. Wengert, Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-440 | | The Commission has issued the enclosed Amendment No. 139 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit 1. The amendment is in response to your application dated November 15, 2005. |
| | The amendment modifies the technical specifications to clarify the wording of emergency closed cooling water (ECCW) Surveillance Requirement (SR) 3.7.10.2. The SR verifies actuation of the entire ECCW system rather than just verifying valve actuation. |
| | A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 139 to NPF-58 | | : 1. Amendment No. 139 to NPF-58 |
| : 2. Safety Evaluationcc w/encls: See next page Mr. Richard AndersonOctober 27, 2006Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant, Unit 1 Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 | | : 2. Safety Evaluation cc w/encls: See next page |
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| | Mr. Richard Anderson October 27, 2006 Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant, Unit 1 Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PERRY NUCLEAR POWER PLANT, UNIT 1 - ISSUANCE OF AMENDMENTRE: CLARIFY WORDING OF EMERGENCY CLOSED COOLING WATER SURVEILLANCE REQUIREMENT 3.7.10.2 (TAC NO. MC8970) | | PERRY NUCLEAR POWER PLANT, UNIT 1 - ISSUANCE OF AMENDMENT RE: CLARIFY WORDING OF EMERGENCY CLOSED COOLING WATER SURVEILLANCE REQUIREMENT 3.7.10.2 (TAC NO. MC8970) |
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| ==Dear Mr. Pearce:== | | ==Dear Mr. Pearce:== |
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| The Commission has issued the enclosed Amendment No. 139 to Facility Operating LicenseNo. NPF-58 for the Perry Nuclear Power Plant, Unit 1. The amendment is in response to your application dated November 15, 2005.The amendment modifies the technical specifications to clarify the wording of emergencyclosed cooling water (ECCW) Surveillance Requirement (SR) 3.7.10.2. The SR verifies actuation of the entire ECCW system rather than just verifying "valve" actuation. 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/Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-440 | | The Commission has issued the enclosed Amendment No. 139 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit 1. The amendment is in response to your application dated November 15, 2005. |
| | The amendment modifies the technical specifications to clarify the wording of emergency closed cooling water (ECCW) Surveillance Requirement (SR) 3.7.10.2. The SR verifies actuation of the entire ECCW system rather than just verifying valve actuation. |
| | A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 139 to NPF-58 | | : 1. Amendment No. 139 to NPF-58 |
| : 2. Safety Evaluationcc w/encls: See next pageDISTRIBUTION | | : 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: |
| :PUBLICRidsNrrLADClarkeGHill, OIS (2)
| | PUBLIC RidsNrrLADClarke GHill, OIS (2) |
| LPL3-2 R/FRidsOgcRpRidsRgn3MailCenter RidsNrrDorlLpl3-2RidsAcrsAcnwMailCenterRidsNrrDorlDpr RidsNrrPMTWengertRidsNrrDirsItsbPHearn, NRRPackage Accession Number: ML062220662Amendment Accession Number: ML062220654 TS Accession Number: MLOFFICELPL3-2/PMLPL3-2/LADIRS/ITSBOGCLPL3-2/BCNAMETWengert:mwDClarkeTKobetzTCampbellDCollinsDATE10/18/0610/18/06 10/23/0610/24/0610/27/06OFFICIAL RECORD COPY FIRSTENERGY NUCLEAR OPERATING COMPANYFIRSTENERGY NUCLEAR GENERATION CORP.OHIO EDISON COMPANYDOCKET NO. 50-440PERRY NUCLEAR POWER PLANT, UNIT 1FACILITY OPERATING LICENSEAmendment No. 139License No. NPF-581.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for license filed by FirstEnergy Nuclear Operating Company,et al., (the licensee) dated November 15, 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 the Commission's regulations;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows: (2)Technical SpecificationsThe Technical Specifications contained in Appendix A and the EnvironmentalProtection Plan contained in Appendix B, as revised through Amendment No. 139, are hereby incorporated into this license. FENOC 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 its issuance and shall beimplemented within 90 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Daniel S. Collins, ChiefPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | LPL3-2 R/F RidsOgcRp RidsRgn3MailCenter RidsNrrDorlLpl3-2 RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrPMTWengert RidsNrrDirsItsb PHearn, NRR Package Accession Number: ML062220662 Amendment Accession Number: ML062220654 TS Accession Number: ML OFFICE LPL3-2/PM LPL3-2/LA DIRS/ITSB OGC LPL3-2/BC NAME TWengert:mw DClarke TKobetz TCampbell DCollins DATE 10/18/06 10/18/06 10/23/06 10/24/06 10/27/06 OFFICIAL RECORD COPY |
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| | FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP. |
| | OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT 1 FACILITY OPERATING LICENSE Amendment No. 139 License No. NPF-58 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for license filed by FirstEnergy Nuclear Operating Company, et al., (the licensee) dated November 15, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows: |
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| | (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 139, are hereby incorporated into this license. FENOC 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 its issuance and shall be implemented within 90 days of the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | 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 Specifications and Facility Operating LicenseDate of Issuance: October 27, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 139FACILITY OPERATING LICENSE NO. NPF-58DOCKET NO. 50-440Replace the following pages of the Facility Operating License and Appendix A TechnicalSpecifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. RemoveInsertLicense Page 4License Page 43.7-20 3.7-20 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 139 TO FACILITY OPERATING LICENSE NO. NPF-58FIRSTENERGY NUCLEAR OPERATING COMPANYFIRSTENERGY NUCLEAR GENERATION CORP.OHIO EDISON COMPANYPERRY NUCLEAR POWER PLANT, UNIT 1DOCKET NO. 50-44 | | Changes to the Technical Specifications and Facility Operating License Date of Issuance: October 27, 2006 |
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 139 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Facility Operating License and 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 License Page 4 License Page 4 3.7-20 3.7-20 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 139 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP. |
| | OHIO EDISON COMPANY PERRY NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-440 |
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| | ==1.0 INTRODUCTION== |
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| | By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated November 15, 2005 (Agencywide Documents Access and Management System Accession No. |
| | ML053260443), FirstEnergy Nuclear Operating Company, et al. (the licensee) requested changes to the technical specifications (TSs) for the Perry Nuclear Power Plant, Unit 1 (Perry). |
| | The proposed changes would modify the TSs to clarify the wording of emergency closed cooling water (ECCW) surveillance requirement (SR) 3.7.10.2. |
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| | ==2.0 REGULATORY EVALUATION== |
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| | Section 182a of the Atomic Energy Act of 1954, as amended (the Act), requires applicants for nuclear power plant operating licenses to include TSs as part of the license. TSs specify the requirements for operation of nuclear reactors. Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications, states that TSs are to be derived from the analyses and evaluations of the safety analysis report (the design basis). Additionally, 10 CFR 50.36(c)(3) requires TSs to include SRs, which are requirements relating to the test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that the facility operation will be within the safety limits, and that the limiting conditions for operation will be met. |
| | General Design Criterion 44, Cooling water, to 10 CFR Part 50, Appendix A, requires a system be provided to transfer heat from structures, systems, and components (SSCs) important to safety, to an ultimate heat sink. The criterion further states that the system safety function shall transfer the combined heat load of these SSCs under normal operating and accident conditions. The Perry ECCW system is a closed loop system designed to provide a heat sink, during a design-basis accident or transient, for safety-related components in systems such as subsystems for the low-pressure emergency core cooling system. ECCW then transfers that heat to the emergency service water system, which transports the heat to Lake Erie. |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | The NRC staff reviewed the proposed change for compliance with 10 CFR 50.36 and for consistency with the precedent established in NUREG-1434, Standard Technical Specifications [STSs] General Electric Plants, BWR/6. The change would make the SR 3.7.10.2 wording consistent with the more standard wording of the system actuation SRs in TS 3.7.1, [Standby Service Water (SSW)] System and [Ultimate Heat Sink (UHS)]; |
| | TS 3.7.2, High Pressure Core Spray (HPCS) Service Water System (SWS); and TS 3.7.3, |
| | [Control Room Fresh Air (CRFA)] System, of NUREG-1434. In the licensees amendment request dated November 15, 2005, the licensee noted that an ECCW specification is not included in NUREG-1434 because the ECCW system is a Perry-specific plant design. |
| | The current wording of SR 3.7.10.2 requires that automatic valves in ECCW actuate on an actuation signal. However, the TS Bases for the SR identify that more than just valves are tested. The TS Bases state, This Surveillance also verifies the automatic start capability of the ECCW pump in each subsystem. During development of the Perry improved STSs, no direct template existed for the wording of SR 3.7.10.2, since NUREG-1434 did not include an ECCW specification. Therefore, wording similar to the original Perry TS SR was incorporated. The non-standard wording focused on valve actuation, since the original ECCW system design required several valves to close after an accident to isolate the safety-related ECCW system from a non-safety cooling water system. The overall system actuation was only addressed in the TS Bases. Since that time, the physical boundary for the safety-related ECCW subsystems has been made passive, by adding check valves. It is therefore appropriate to revise the SR wording to reflect actuation of the total system, consistent with the standard wording of SRs in TS 3.7.1, 3.7.2, and 3.7.3 of NUREG-1434. This is accomplished by revising SR 3.7.10.2 to read, Verify each ECCW subsystem actuates on an actual or simulated initiation signal. |
| | The licensees amendment request rewords SR 3.7.10.2 to more clearly state that the actuation capability of the entire ECCW system must continue to be tested. This change also ensures consistency with the standard wording in SRs for TSs 3.7.1, 3.7.2, and 3.7.3 as described in NUREG-1434 and for verifying the overall system actuation as described in the Perry TS Bases. The NRC staff determined that this is an administrative clarification and the rewording of SR 3.7.10.2 does not change the technical content of the specification. |
| | The NRC staffs position, in general, is that there are two classes of TS changes: (1) changes needed to reflect contents of the design basis (as mentioned above, TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TSs over time. |
| | The NRC staff concludes that this amendment involves the second class of changes; namely, administrative changes that reflect the current configuration of the plant and consistency with the TS Bases. Furthermore, the licensees proposed changes are acceptable since they conform to the standard wording in NUREG-1434 and continue to meet the requirements of 10 CFR 50.36, and 10 CFR Part 50, Appendix A, Criterion 44. |
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| | ==4.0 STATE CONSULTATION== |
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| | In accordance with the Commissions regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments. |
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| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
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| ==01.0INTRODUCTION==
| | This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes an SR. |
| By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated November 15,2005 (Agencywide Documents Access and Management System Accession No.
| | The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 5081; dated January 31, 2006). Accordingly, this 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 this amendment. |
| ML053260443), FirstEnergy Nuclear Operating Company, et al. (the licensee) requested changes to the technical specifications (TSs) for the Perry Nuclear Power Plant, Unit 1 (Perry). The proposed changes would modify the TSs to clarify the wording of emergency closed cooling water (ECCW) surveillance requirement (SR) 3.7.10.2.
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| ==2.0REGULATORY EVALUATION== | | ==6.0 CONCLUSION== |
| Section 182a of the Atomic Energy Act of 1954, as amended (the Act), requires applicants fornuclear power plant operating licenses to include TSs as part of the license. TSs specify the requirements for operation of nuclear reactors. Title 10 of the Code of Federal Regulations(10 CFR) Section 50.36, "Technical specifications," states that TSs are to be derived from the analyses and evaluations of the safety analysis report (the design basis). Additionally, 10 CFR 50.36(c)(3) requires TSs to include SRs, which are requirements relating to the test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that the facility operation will be within the safety limits, and that the limiting conditions for operation will be met.General Design Criterion 44, "Cooling water," to 10 CFR Part 50, Appendix A, requires asystem be provided to transfer heat from structures, systems, and components (SSCs) important to safety, to an ultimate heat sink. The criterion further states that the system safety function shall transfer the combined heat load of these SSCs under normal operating and accident conditions. The Perry ECCW system is a closed loop system designed to provide a heat sink, during a design-basis accident or transient, for safety-related components in systems such as subsystems for the low-pressure emergency core cooling system. ECCW then transfers that heat to the emergency service water system, which transports the heat to Lake Erie.
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| ==3.0TECHNICAL EVALUATION==
| | 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 Commissions regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| The NRC staff reviewed the proposed change for compliance with 10 CFR 50.36 and forconsistency with the precedent established in NUREG-1434, "Standard Technical Specifications [STSs] General Electric Plants, BWR/6." The change would make the SR 3.7.10.2 wording consistent with the more "standard" wording of the system actuation SRs in TS 3.7.1, "[Standby Service Water (SSW)] System and [Ultimate Heat Sink (UHS)]"; | | Principal Contributor: P. Hearn Date: October 27, 2006 |
| TS 3.7.2, "High Pressure Core Spray (HPCS) Service Water System (SWS)"; and TS 3.7.3,
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| "[Control Room Fresh Air (CRFA)] System," of NUREG-1434. In the licensee's amendment request dated November 15, 2005, the licensee noted that an ECCW specification is not included in NUREG-1434 because the ECCW system is a Perry-specific plant design. The current wording of SR 3.7.10.2 requires that automatic valves in ECCW actuate on anactuation signal. However, the TS Bases for the SR identify that more than just valves are tested. The TS Bases state, "This Surveillance also verifies the automatic start capability of the ECCW pump in each subsystem." During development of the Perry improved STSs, no direct template existed for the wording of SR 3.7.10.2, since NUREG-1434 did not include an ECCW specification. Therefore, wording similar to the original Perry TS SR was incorporated. The non-standard wording focused on valve actuation, since the original ECCW system design required several valves to close after an accident to isolate the safety-related ECCW system from a non-safety cooling water system. The overall system actuation was only addressed in the TS Bases. Since that time, the physical boundary for the safety-related ECCW subsystems has been made passive, by adding check valves. It is therefore appropriate to revise the SR wording to reflect actuation of the total system, consistent with the standard wording of SRs in TS 3.7.1, 3.7.2, and 3.7.3 of NUREG-1434. This is accomplished by revising SR 3.7.10.2 to read, "Verify each ECCW subsystem actuates on an actual or simulated initiation signal."The licensee's amendment request rewords SR 3.7.10.2 to more clearly state that the actuationcapability of the entire ECCW system must continue to be tested. This change also ensures consistency with the standard wording in SRs for TSs 3.7.1, 3.7.2, and 3.7.3 as described in NUREG-1434 and for verifying the overall system actuation as described in the Perry TS Bases. The NRC staff determined that this is an administrative clarification and the rewording of SR 3.7.10.2 does not change the technical content of the specification. The NRC staff's position, in general, is that there are two classes of TS changes: (1) changesneeded to reflect contents of the design basis (as mentioned above, TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TSs over time. The NRC staff concludes that this amendment involves the second class of changes; namely,administrative changes that reflect the current configuration of the plant and consistency with the TS Bases. Furthermore, the licensee's proposed changes are acceptable since they conform to the standard wording in NUREG-1434 and continue to meet the requirements of 10 CFR 50.36, and 10 CFR Part 50, Appendix A, Criterion 44.
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| ==4.0STATE CONSULTATION==
| | Perry Nuclear Power Plant, Unit 1 cc: |
| In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
| | David W. Jenkins, Attorney Dennis Clum FirstEnergy Corporation Radiological Assistance Section Supervisor Mail Stop A-GO-18 Bureau of Radiation Protection 76 South Main Street Ohio Department of Health Akron, OH 44308 P.O. Box 118 Columbus, OH 43266-0118 Resident Inspector's Office U.S. Nuclear Regulatory Commission Zack A. Clayton P.O. Box 331 DERR Perry, OH 44081-0331 Ohio Environmental Protection Agency ATTN: Mr. Zack A. Clayton Regional Administrator, Region III P.O. Box 1049 U.S. Nuclear Regulatory Commission Columbus, OH 43266-0149 2443 Warrenville Road Lisle, IL 60532-4531 Chairman Perry Township Board of Trustees Sue Hiatt 3750 Center Road, Box 65 OCRE Interim Representative Perry, OH 44081 8275 Munson Mentor, OH 44060 Daniel Z. Fisher Transportation Department Manager - Regulatory Compliance Public Utilities Commission FirstEnergy Nuclear Operating Company 180 East Broad Street Perry Nuclear Power Plant Columbus, OH 43215-3793 P.O. Box 97, A210 10 Center Road Joseph J. Hagan Perry, OH 44081 Senior Vice President of Operations and Chief Operating Officer Mayor, Village of North Perry First Energy Nuclear Operating Company North Perry Village Hall Mail Stop A-GO-14 4449 Lockwood Road 76 South Main Street North Perry Village, OH 44081 Akron, OH 44308 Donna Owens, Director Director, Regulatory Affairs Ohio Department of Commerce FirstEnergy Nuclear Operating Company Division of Industrial Compliance 395 Ghent Road Bureau of Operations & Maintenance Akron, OH 44333 6606 Tussing Road P.O. Box 4009 Gary R. Leidich Reynoldsburg, OH 43068-9009 President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Carol OClaire, Chief, Radiological Branch Mail Stop A-GO-19 Ohio Emergency Management Agency 76 South Main Street 2855 West Dublin Granville Road Akron, OH 44308 Columbus, OH 43235-7150 Mayor, Village of Perry P.O. Box 100 Perry, OH 44081-0100 |
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| ==5.0ENVIRONMENTAL CONSIDERATION==
| | Perry Nuclear Power Plant, Unit 1 cc: |
| This amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes an SR.
| | Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GHE-107 395 Ghent Road Akron, OH 44333 L. W. Pearce Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A200 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 |
| The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 5081; dated January 31, 2006). Accordingly, this 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 this amendment.
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| ==6.0CONCLUSION==
| | renewal. Such sale and leaseback transactions are subject to the representations and conditions set forth in the above mentioned application of January 23, 1987, as supplemented on March 3, 1987, as well as the letter of the Director of the Office of Nuclear Reactor Regulation dated March 16, 1987, consenting to such transactions. Specifically, a lessor and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over the licenses of PNPP Unit 1. For purposes of this condition the limitations of 10 CFR 50.81, as now in effect and as may be subsequently amended, are fully applicable to the lessor and any successor in interest to that lessor as long as the license for PNPP Unit 1 remains in effect; these financial transactions shall have no effect on the license for the Perry Nuclear facility throughout the term of the license. |
| The Commission has concluded, based on the considerations discussed above, that: (1) thereis reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.Principal Contributor: P. Hearn Date: October 27, 2006 Perry Nuclear Power Plant, Unit 1 cc:David W. Jenkins, AttorneyFirstEnergy CorporationMail Stop A-GO-1876 South Main StreetAkron, OH 44308Resident Inspector's OfficeU.S. Nuclear Regulatory CommissionP.O. Box 331Perry, OH 44081-0331Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission2443 Warrenville RoadLisle, IL 60532-4531Sue HiattOCRE Interim Representative8275 MunsonMentor, OH 44060Manager - Regulatory ComplianceFirstEnergy Nuclear Operating CompanyPerry Nuclear Power PlantP.O. Box 97, A21010 Center RoadPerry, OH 44081Mayor, Village of North PerryNorth Perry Village Hall4449 Lockwood RoadNorth Perry Village, OH 44081Donna Owens, DirectorOhio Department of CommerceDivision of Industrial ComplianceBureau of Operations & Maintenance6606 Tussing RoadP.O. Box 4009Reynoldsburg, OH 43068-9009Carol O'Claire, Chief, Radiological BranchOhio Emergency Management Agency2855 West Dublin Granville RoadColumbus, OH 43235-7150Mayor, Village of PerryP.O. Box 100Perry, OH 44081-0100 Dennis ClumRadiological Assistance Section SupervisorBureau of Radiation ProtectionOhio Department of HealthP.O. Box 118Columbus, OH 43266-0118Zack A. Clayton DERROhio Environmental Protection AgencyATTN: Mr. Zack A. ClaytonP.O. Box 1049Columbus, OH 43266-0149ChairmanPerry Township Board of Trustees3750 Center Road, Box 65Perry, OH 44081Daniel Z. FisherTransportation DepartmentPublic Utilities Commission180 East Broad StreetColumbus, OH 43215-3793Joseph J. HaganSenior Vice President of Operations and Chief Operating OfficerFirst Energy Nuclear Operating CompanyMail Stop A-GO-1476 South Main StreetAkron, OH 44308Director, Regulatory AffairsFirstEnergy Nuclear Operating Company395 Ghent Road Akron, OH 44333Gary R. LeidichPresident and Chief Nuclear OfficerFirstEnergy Nuclear Operating CompanyMail Stop A-GO-1976 South Main StreetAkron, OH 44308 Perry Nuclear Power Plant, Unit 1 cc:
| | (b) Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the terms or conditions of any lease agreements executed as part of these transactions; (ii) the PNPP Operating Agreement; (iii) the existing property insurance coverage for PNPP Unit 1; and (iv) any action by a lessor or others that may have an adverse effect on the safe operation of the facility. |
| Danny L. Pace Senior Vice President, Fleet EngineeringFirstEnergy Nuclear Operating CompanyMail Stop A-GO-1476 South Main StreetAkron, OH 44308Jeannie M. RinckelVice President, Fleet OversightFirstEnergy Nuclear Operating CompanyMail Stop A-GO-1476 South Main StreetAkron, OH 44308Manager, Fleet LicensingFirstEnergy Nuclear Operating CompanyMail Stop A-GHE-107395 Ghent RoadAkron, OH 44333L. W. PearceVice PresidentFirstEnergy Nuclear Operating CompanyPerry Nuclear Power PlantMail Stop A-PY-A290P.O. Box 97, 10 Center RoadPerry, OH 44081-0097Manager, Site Regulatory ComplianceFirstEnergy Nuclear Operating CompanyPerry Nuclear Power PlantMail Stop A-PY-A200P.O. Box 97, 10 Center RoadPerry, OH 44081-0097 renewal. Such sale and leaseback transactions are subject to therepresentations and conditions set forth in the above mentioned application ofJanuary 23, 1987, as supplemented on March 3, 1987, as well as the letter of theDirector of the Office of Nuclear Reactor Regulation dated March 16, 1987,consenting to such transactions. Specifically, a lessor and anyone else who mayacquire an interest under these transactions are prohibited from exercisingdirectly or indirectly any control over the licenses of PNPP Unit 1. For purposesof this condition the limitations of 10 CFR 50.81, as now in effect and as may besubsequently amended, are fully applicable to the lessor and any successor ininterest to that lessor as long as the license for PNPP Unit 1 remains in effect;these financial transactions shall have no effect on the license for the PerryNuclear facility throughout the term of the license. (b)Further, the licensees are also required to notify the NRC in writing prior to anychange in: (i) the terms or conditions of any lease agreements executed as partof these transactions; (ii) the PNPP Operating Agreement; (iii) the existingproperty insurance coverage for PNPP Unit 1; and (iv) any action by a lessor orothers that may have an adverse effect on the safe operation of the facility.C.This license shall be deemed to contain and is subject to the conditions specified inthe Commission's regulations set forth in 10 CFR Chapter I and is subject to allapplicable provisions of the Act and to the rules, regulations, and orders of theCommission now and hereafter in effect; and is subject to the additional conditionsspecified or incorporated below:(1)Maximum Power LevelFENOC is authorized to operate the facility at reactor core power levels not inexcess of 3758 megawatts thermal (100% power) in accordance with theconditions specified herein.(2)Technical SpecificationsThe Technical Specifications contained in Appendix A and the EnvironmentalProtection Plan contained in Appendix B, as revised through AmendmentNo.139, are hereby incorporated into the license. FENOC shall operate the lfacility in accordance with the Technical Specifications and the Environmental Protection Plan.(3)Antitrust Conditionsa. FirstEnergy Nuclear Generation Corp. and Ohio Edison CompanyAmendment No. 139}}
| | C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now and hereafter in effect; and is subject to the additional conditions specified or incorporated below: |
| | (1) Maximum Power Level FENOC is authorized to operate the facility at reactor core power levels not in excess of 3758 megawatts thermal (100% power) in accordance with the conditions specified herein. |
| | (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.139, are hereby incorporated into the license. FENOC shall operate the l facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | (3) Antitrust Conditions |
| | : a. FirstEnergy Nuclear Generation Corp. and Ohio Edison Company Amendment No. 139}} |
Letter Sequence Approval |
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MONTHYEARML0630502502006-10-27027 October 2006 Issuance of Technical Specification Page Clarify Wording of Emergency Closed Cooling Water SR 3.7.10.2 Project stage: Approval ML0622206542006-10-27027 October 2006 Issuance of Amendment Clarify Wording of Emergency Closed Cooling Water SR 3.7.10.2 Project stage: Approval ML0632501272006-11-30030 November 2006 Correction of Safety Evaluation for Amendment Dated October 27, 2006 Project stage: Approval 2006-10-27
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[Table view] Category:Safety Evaluation
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L-2021-LLR-0097) ML21322A2602022-01-10010 January 2022 Issuance of Amendment No. 197 Regarding the Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Oper ML21270A1122021-11-16016 November 2021 Issuance of Amendment No. 196 Regarding Changes to the Emergency Plan ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21123A2172021-05-0505 May 2021 Issuance of Relief Requests Vr 4, Revision 0, Vr 6, Revision 0, and Vr 8, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L 2021 Llr 0010, L 2021 Llr 0011, L 2021 Llr 0012 COVID-19 ML21123A2892021-05-0404 May 2021 Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML21081A0702021-04-27027 April 2021 Issuance of Amendment No. 193 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML21063A2532021-03-0505 March 2021 Issuance of Relief Request SR-2, Revision 0, from Certain Requirements of the ASME OM Code (EPID L-2021-LLR-0005 (COVID-19)) ML21063A1572021-03-0404 March 2021 Safety Evaluation for Alternative Request SR-2, Revision 0 Related to one-time Extension Snubbers Testing to ASME OM Code for the Fourth 10-year Inservice Interval at Perry Nuclear Power Plant Unit 1, Docket Nos. 50-440 ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20363A0062021-01-29029 January 2021 Issuance of Relief Proposed Alternative Request Associated with Fourth 10-Year Inservice Inspection Interval ML20311A6582020-11-10010 November 2020 Issuance of Relief Proposed Alternative Request Associated with Fourth Ten Year Interval Inservice Inspection Interval ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20266G2652020-09-24024 September 2020 Correction Letter for Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20252A0262020-09-18018 September 2020 Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20189A0032020-07-10010 July 2020 Relief Request PR-3 for Fourth 10-Year Pump and Valve Inservice Testing Program ML20154K7002020-07-0909 July 2020 Issuance of Amendment No. 190 Regarding Fire Protection Program Licensing Basis ML20118C1672020-05-22022 May 2020 Issuance of Amendment No. 189, Regarding Special Heavy Lifting Device Nondestructive Examination Frequency ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19163A0232019-08-14014 August 2019 Issuance of Amendment No. 186 Concerning Changes to Emergency Response Organization ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML19072A0122019-03-15015 March 2019 Correction to License Amendment No. 184 Related to Adoption of Technical Specification Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ML19072A0852019-03-15015 March 2019 Correction to Request for Alternatives Related to Inservice Testing Program for the Fourth 10 Year Inservice Testing Interval ML19029A0902019-02-25025 February 2019 Request for Alternatives Related to Inservice Testing Program for the Fourth 10-Year Inservice Testing Interval (EPID Nos. L-2018-LLR-0092, 0093, 0094, 0095, and 0096) ML19022A3242019-02-25025 February 2019 Issuance of Amendment No. 185 Concerning Extension of Containment Leakage Test Frequency ML19037A0412019-02-25025 February 2019 Request for Alternative to Use ASME Code Case N-831 ML18292A8162018-12-12012 December 2018 Issuance of Amendment No. 184 Concerning Adoption of Technical Specification Task Force Traveler 542, Rev. 2, Reactor Pressure Vessel Water Inventory Control ML18199A2802018-08-23023 August 2018 Issuance of Amendment No. 183, Adopt Technical Specification Task Force Traveler TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18157A0842018-06-25025 June 2018 Issuance of Amendment No. 181 Concerning Adoption of TS Task Force Traveler TSTF-306-A, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration (CAC No. MG0150; EPID L-2017-LLA-0286) ML18110A1332018-05-16016 May 2018 Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241) ML18023A6252018-01-29029 January 2018 Approval of Alternative to Use BWRVIP Guidelines in Lieu of Certain ASME Code Requirements (CAC No. MG0149; EPID 2017-LLR-0112) (L-17-183) ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17257A0982017-10-19019 October 2017 Issuance of Amendment Concerning Revisions to the Environmental Protection Plan (CAC No. MF9652; EPID L-7017-LLA-0226) (L-17-043) ML17270A0302017-10-16016 October 2017 Approval of Alternative to Use ASME Code Case N-513-4 for Repair of Emergency Service Water System Piping (CAC No. MG0130; EPID L-2017-LLR-0080)(L-17-278) ML17193A3822017-07-18018 July 2017 Correction to Safety Evaluation for License Amendment No. 177 ML17163A3542017-06-29029 June 2017 Issuance of Amendment Concerning Adoption of Tstf-501, Revision 1, Relocation of Diesel Fuel and Lube Oil Volume Values to Licensee Control (CAC No. MF8693) (L-16-236) ML17139C3722017-06-19019 June 2017 Issuance of Amendment Concerning Reduction of Steam Dome Pressure Value Specified in Technical Specification 2.1.1 (CAC No. MF8760) (L-16-179) 2023-09-28
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October 27, 2006 Mr. Richard Anderson Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant, Unit 1 Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT 1 - ISSUANCE OF AMENDMENT RE: CLARIFY WORDING OF EMERGENCY CLOSED COOLING WATER SURVEILLANCE REQUIREMENT 3.7.10.2 (TAC NO. MC8970)
Dear Mr. Pearce:
The Commission has issued the enclosed Amendment No. 139 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit 1. The amendment is in response to your application dated November 15, 2005.
The amendment modifies the technical specifications to clarify the wording of emergency closed cooling water (ECCW) Surveillance Requirement (SR) 3.7.10.2. The SR verifies actuation of the entire ECCW system rather than just verifying valve actuation.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 139 to NPF-58
- 2. Safety Evaluation cc w/encls: See next page
Mr. Richard Anderson October 27, 2006 Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant, Unit 1 Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT 1 - ISSUANCE OF AMENDMENT RE: CLARIFY WORDING OF EMERGENCY CLOSED COOLING WATER SURVEILLANCE REQUIREMENT 3.7.10.2 (TAC NO. MC8970)
Dear Mr. Pearce:
The Commission has issued the enclosed Amendment No. 139 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant, Unit 1. The amendment is in response to your application dated November 15, 2005.
The amendment modifies the technical specifications to clarify the wording of emergency closed cooling water (ECCW) Surveillance Requirement (SR) 3.7.10.2. The SR verifies actuation of the entire ECCW system rather than just verifying valve actuation.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosures:
- 1. Amendment No. 139 to NPF-58
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrLADClarke GHill, OIS (2)
LPL3-2 R/F RidsOgcRp RidsRgn3MailCenter RidsNrrDorlLpl3-2 RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrPMTWengert RidsNrrDirsItsb PHearn, NRR Package Accession Number: ML062220662 Amendment Accession Number: ML062220654 TS Accession Number: ML OFFICE LPL3-2/PM LPL3-2/LA DIRS/ITSB OGC LPL3-2/BC NAME TWengert:mw DClarke TKobetz TCampbell DCollins DATE 10/18/06 10/18/06 10/23/06 10/24/06 10/27/06 OFFICIAL RECORD COPY
FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT 1 FACILITY OPERATING LICENSE Amendment No. 139 License No. NPF-58
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for license filed by FirstEnergy Nuclear Operating Company, et al., (the licensee) dated November 15, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 139, are hereby incorporated into this license. FENOC 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 its issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
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 and Facility Operating License Date of Issuance: October 27, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 139 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following pages of the Facility Operating License and 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 License Page 4 License Page 4 3.7-20 3.7-20
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 139 TO FACILITY OPERATING LICENSE NO. NPF-58 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY PERRY NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated November 15, 2005 (Agencywide Documents Access and Management System Accession No.
ML053260443), FirstEnergy Nuclear Operating Company, et al. (the licensee) requested changes to the technical specifications (TSs) for the Perry Nuclear Power Plant, Unit 1 (Perry).
The proposed changes would modify the TSs to clarify the wording of emergency closed cooling water (ECCW) surveillance requirement (SR) 3.7.10.2.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act of 1954, as amended (the Act), requires applicants for nuclear power plant operating licenses to include TSs as part of the license. TSs specify the requirements for operation of nuclear reactors. Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications, states that TSs are to be derived from the analyses and evaluations of the safety analysis report (the design basis). Additionally, 10 CFR 50.36(c)(3) requires TSs to include SRs, which are requirements relating to the test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that the facility operation will be within the safety limits, and that the limiting conditions for operation will be met.
General Design Criterion 44, Cooling water, to 10 CFR Part 50, Appendix A, requires a system be provided to transfer heat from structures, systems, and components (SSCs) important to safety, to an ultimate heat sink. The criterion further states that the system safety function shall transfer the combined heat load of these SSCs under normal operating and accident conditions. The Perry ECCW system is a closed loop system designed to provide a heat sink, during a design-basis accident or transient, for safety-related components in systems such as subsystems for the low-pressure emergency core cooling system. ECCW then transfers that heat to the emergency service water system, which transports the heat to Lake Erie.
3.0 TECHNICAL EVALUATION
The NRC staff reviewed the proposed change for compliance with 10 CFR 50.36 and for consistency with the precedent established in NUREG-1434, Standard Technical Specifications [STSs] General Electric Plants, BWR/6. The change would make the SR 3.7.10.2 wording consistent with the more standard wording of the system actuation SRs in TS 3.7.1, [Standby Service Water (SSW)] System and [Ultimate Heat Sink (UHS)];
TS 3.7.2, High Pressure Core Spray (HPCS) Service Water System (SWS); and TS 3.7.3,
[Control Room Fresh Air (CRFA)] System, of NUREG-1434. In the licensees amendment request dated November 15, 2005, the licensee noted that an ECCW specification is not included in NUREG-1434 because the ECCW system is a Perry-specific plant design.
The current wording of SR 3.7.10.2 requires that automatic valves in ECCW actuate on an actuation signal. However, the TS Bases for the SR identify that more than just valves are tested. The TS Bases state, This Surveillance also verifies the automatic start capability of the ECCW pump in each subsystem. During development of the Perry improved STSs, no direct template existed for the wording of SR 3.7.10.2, since NUREG-1434 did not include an ECCW specification. Therefore, wording similar to the original Perry TS SR was incorporated. The non-standard wording focused on valve actuation, since the original ECCW system design required several valves to close after an accident to isolate the safety-related ECCW system from a non-safety cooling water system. The overall system actuation was only addressed in the TS Bases. Since that time, the physical boundary for the safety-related ECCW subsystems has been made passive, by adding check valves. It is therefore appropriate to revise the SR wording to reflect actuation of the total system, consistent with the standard wording of SRs in TS 3.7.1, 3.7.2, and 3.7.3 of NUREG-1434. This is accomplished by revising SR 3.7.10.2 to read, Verify each ECCW subsystem actuates on an actual or simulated initiation signal.
The licensees amendment request rewords SR 3.7.10.2 to more clearly state that the actuation capability of the entire ECCW system must continue to be tested. This change also ensures consistency with the standard wording in SRs for TSs 3.7.1, 3.7.2, and 3.7.3 as described in NUREG-1434 and for verifying the overall system actuation as described in the Perry TS Bases. The NRC staff determined that this is an administrative clarification and the rewording of SR 3.7.10.2 does not change the technical content of the specification.
The NRC staffs position, in general, is that there are two classes of TS changes: (1) changes needed to reflect contents of the design basis (as mentioned above, TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TSs over time.
The NRC staff concludes that this amendment involves the second class of changes; namely, administrative changes that reflect the current configuration of the plant and consistency with the TS Bases. Furthermore, the licensees proposed changes are acceptable since they conform to the standard wording in NUREG-1434 and continue to meet the requirements of 10 CFR 50.36, and 10 CFR Part 50, Appendix A, Criterion 44.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes an SR.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 5081; dated January 31, 2006). Accordingly, this 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 this 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 Commissions regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: P. Hearn Date: October 27, 2006
Perry Nuclear Power Plant, Unit 1 cc:
David W. Jenkins, Attorney Dennis Clum FirstEnergy Corporation Radiological Assistance Section Supervisor Mail Stop A-GO-18 Bureau of Radiation Protection 76 South Main Street Ohio Department of Health Akron, OH 44308 P.O. Box 118 Columbus, OH 43266-0118 Resident Inspector's Office U.S. Nuclear Regulatory Commission Zack A. Clayton P.O. Box 331 DERR Perry, OH 44081-0331 Ohio Environmental Protection Agency ATTN: Mr. Zack A. Clayton Regional Administrator, Region III P.O. Box 1049 U.S. Nuclear Regulatory Commission Columbus, OH 43266-0149 2443 Warrenville Road Lisle, IL 60532-4531 Chairman Perry Township Board of Trustees Sue Hiatt 3750 Center Road, Box 65 OCRE Interim Representative Perry, OH 44081 8275 Munson Mentor, OH 44060 Daniel Z. Fisher Transportation Department Manager - Regulatory Compliance Public Utilities Commission FirstEnergy Nuclear Operating Company 180 East Broad Street Perry Nuclear Power Plant Columbus, OH 43215-3793 P.O. Box 97, A210 10 Center Road Joseph J. Hagan Perry, OH 44081 Senior Vice President of Operations and Chief Operating Officer Mayor, Village of North Perry First Energy Nuclear Operating Company North Perry Village Hall Mail Stop A-GO-14 4449 Lockwood Road 76 South Main Street North Perry Village, OH 44081 Akron, OH 44308 Donna Owens, Director Director, Regulatory Affairs Ohio Department of Commerce FirstEnergy Nuclear Operating Company Division of Industrial Compliance 395 Ghent Road Bureau of Operations & Maintenance Akron, OH 44333 6606 Tussing Road P.O. Box 4009 Gary R. Leidich Reynoldsburg, OH 43068-9009 President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Carol OClaire, Chief, Radiological Branch Mail Stop A-GO-19 Ohio Emergency Management Agency 76 South Main Street 2855 West Dublin Granville Road Akron, OH 44308 Columbus, OH 43235-7150 Mayor, Village of Perry P.O. Box 100 Perry, OH 44081-0100
Perry Nuclear Power Plant, Unit 1 cc:
Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GHE-107 395 Ghent Road Akron, OH 44333 L. W. Pearce Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A200 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
renewal. Such sale and leaseback transactions are subject to the representations and conditions set forth in the above mentioned application of January 23, 1987, as supplemented on March 3, 1987, as well as the letter of the Director of the Office of Nuclear Reactor Regulation dated March 16, 1987, consenting to such transactions. Specifically, a lessor and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over the licenses of PNPP Unit 1. For purposes of this condition the limitations of 10 CFR 50.81, as now in effect and as may be subsequently amended, are fully applicable to the lessor and any successor in interest to that lessor as long as the license for PNPP Unit 1 remains in effect; these financial transactions shall have no effect on the license for the Perry Nuclear facility throughout the term of the license.
(b) Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the terms or conditions of any lease agreements executed as part of these transactions; (ii) the PNPP Operating Agreement; (iii) the existing property insurance coverage for PNPP Unit 1; and (iv) any action by a lessor or others that may have an adverse effect on the safe operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now and hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level FENOC is authorized to operate the facility at reactor core power levels not in excess of 3758 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.139, are hereby incorporated into the license. FENOC shall operate the l facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions
- a. FirstEnergy Nuclear Generation Corp. and Ohio Edison Company Amendment No. 139