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| | number = ML15167A315 | | | number = ML15167A315 |
| | issue date = 07/08/2015 | | | issue date = 07/08/2015 |
| | title = Nine Mile Point Nuclear Station, Unit Nos. 1 and 2 - Issuance of Amendments Change to TS Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators (TAC Nos. MF4786 and MF4787) | | | title = Issuance of Amendments Change to TS Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators |
| | author name = Mozafari B L | | | author name = Mozafari B |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Orphanos P | | | addressee name = Orphanos P |
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| | docket = 05000220, 05000410 | | | docket = 05000220, 05000410 |
| | license number = DPR-063, NPF-069 | | | license number = DPR-063, NPF-069 |
| | contact person = Mozafari B L, NRR/DORL/LPLI-1 | | | contact person = Mozafari B, NRR/DORL/LPLI-1 |
| | case reference number = TAC MF4786, TAC MF4787 | | | case reference number = TAC MF4786, TAC MF4787 |
| | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation, Technical Specifications | | | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation, Technical Specifications |
| | page count = 15 | | | page count = 15 |
| | project = TAC:MF4786, TAC:MF4787 | | | project = TAC:MF4786, TAC:MF4787 |
| | | stage = Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 8, 2015 SUBJECT: NINE MILE POINT NUCLEAR STATION, UNITS. 1 AND 2 -ISSUANCE OF AMENDMENTS -RE: CHANGE TO TECHNICAL SPECIFICATION REQUIREMENTS REGARDING EDUCATION AND EXPERIENCE ELIGIBILITY REQUIREMENTS FOR LICENSED OPERATORS (TAC NOS. MF4786 AND MF4787) Dear Mr. Orphanos: The Commission has issued the enclosed Amendment No. 218 to Renewed Facility Operating License No. DPR-63 and Amendment No. 148 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 11, 2014. The amendments revise the licensed operator training and qualification education and experience eligibility requirements specified in NMP1 TS 6.3.1 and NMP2 TS 5.3.1 to the eligibility requirements specified in this License Amendment Request. The proposed eligibility requirements correspond to the eligibility requirements contained in the current National Academy for Nuclear Training (NANT) Academy Document, ACAD 10-001, "Guidelines for Initial Training and Qualification of Licensed Operators," dated February 2010. A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice. Docket Nos. 50-220 and 50-410 Enclosures: 1. Amendment No. 218 to DPR-63 2. Amendment No. 148 to NPF-69 3. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, Brenda L. Mozafari, Sr. Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 218 Renewed License No. DPR-63 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee), dated September 1, 2014, 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 1; 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. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 8, 2015 |
| -2 -2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-63 is hereby amended to read as follows: (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 218, are hereby incorporated in the license. Exelon Generation Company, LLC, the licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days. Attachment: Changes to the License and Technical Specifications Date of lssuance:Jul y 8, 2015 FOR THE NUCLEAR REGULA TORY COMMISSION Michael I. Dudek, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ATTACHMENT TO LICENSE AMENDMENT NO. 218 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. Remove Page 3 4 Insert Page 3 4 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove Pages 349 Insert Pages 349
| | |
| -3-(2) Exelon Generation pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40 and 70, to
| | ==SUBJECT:== |
| * receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components. (5) Exelon Generation pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal). (2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. is hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications. (3) Deleted Renewed License No. DPR-63 Amendment No. 191 through 210, 211, 213, 214, 215, 216, 217, 218 Correction Letter Dated August 7, 2012 Correction Letter Dated March 17, 2015 | | NINE MILE POINT NUCLEAR STATION, UNITS. 1 AND 2 - ISSUANCE OF AMENDMENTS - RE: CHANGE TO TECHNICAL SPECIFICATION REQUIREMENTS REGARDING EDUCATION AND EXPERIENCE ELIGIBILITY REQUIREMENTS FOR LICENSED OPERATORS (TAC NOS. MF4786 AND MF4787) |
| * -4-(1) Maximum Power Level Exelon Generation is authorized to operate the facility at reactor core power levels not in excess of 3988 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) Fuel Storage and Handling (Section 9.1, SSER 4)* a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high. b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility. c. The above three fuel assemblies shall maintain a minimum to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations. d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time. (4) Turbine System Maintenance Program (Section 3.5.1.3.10, SER) The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities. (Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, 111). The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed. Renewed License No. NPF-69 Amendment 117 through 140, 141, 143, 144, 146, 147,218 e. As a minimum, either the Manager Operations or the General Supervisor Operations shall hold an SRO license. f. The Shift Technical Advisor (STA) shall provide advisory technical support to the shift supervision in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. 6.3 Unit Staff Qualifications 6.3.1 Each member of the unit staff, with the exception of the operator license applicants and the radiation protection manager, shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed operators shall comply only with the requirements of 10 CFR 55. 6.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of Specification 6.3.1, perform the functions described in 10 CFR 50.54(m). 6.4 Procedures 6.4.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and cover the following activities: a. The applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 3, 1972; AMENDMENT NO. 142. 157. 158. 160. 162. 181. 198. 203, 218 349 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION. LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 148 Renewed License No. NPF-69 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee), dated September 11, 2014. 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 1; 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 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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| -2 -2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2. C. (2) of Renewed Facility Operating License No. NPF-69 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, both of which are attached hereto, as revised through Amendment No. 148 are hereby incorporated into this license. Exelon Generation Company, LLC, shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days. Attachment: Changes to the License and Technical Specifications Date of Issuance: July 8, 2015 FOR THE NUCLEAR REGULATORY COMMISSION Michael I. Dudek, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ATTACHMENT TO LICENSE AMENDMENT NO. 148 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. Remove Page Insert Page Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove Pages 5.3.1 Insert Pages 5.3.1 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff, with the exception of the operator license applicants and the radiation protection manager, shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions. NMP2 The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed operators shall comply only with the requirements of 10 CFR 55. 5.3-1 Amendment 91, 127, 148 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENTS NOS. 218 AND 148 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-63 AND NPF-69 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NOS. 50-220 AND 50-410 NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 1.0 INTRODUCTION By letter dated September 11, 2014, Exelon Generation Company (EGC), requested changes to Nine Mile Point 1 (NMP1) Technical Specifications (TS) Section 6.3.1 and Nine Mile Point 2 (NMP2) Technical Specifications (TS) Section 5.3.1 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 14254A007). The current requirement specifies that operator license applicant's education and experience eligibility requirements and changes thereto shall be reviewed and approved by the U.S. Nuclear Regulatory Commission (NRC) and described in an applicable station training procedure. The proposed amendment would revise NMP1 TS 6.3.1 and NMP2 TS 5.3.1, "Unit Staff Qualifications," to state that Licensed Operators shall comply with Title 10 Part 55 of the Code of Federal Regulations (10 CFR) Part 55. 2.0 REGULATORY EVALUATION In March 1985, the NRC issued the Commission Policy Statement on training and qualification of nuclear power plant personnel which endorsed the training accreditation process and the National Academy for Nuclear Training (NANT) guidelines. In Generic Letter 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing -10 CFR 55 and Conforming Amendments," dated March 19, 1987, and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses," published November 1987, the NRC indicated it would accept a facility's licensed operator training program if the facility certified in writing that the program was accredited and based on a systems approach to training (SAT). This certification would supersede the requirements of American National Standards Institute (ANSI) N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," and ANSl/ANS-3.1-1978, "Selection and Training of Nuclear Power Plant Personnel." Facility
| | ==Dear Mr. Orphanos:== |
| -2 -licensees were advised to submit a request to the NRC for an administrative change to their licensing documents to conform to their accredited program status. In January 1992, the NRC published its proposed rule 10 CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel." The proposed rule stated that, if adopted, the rule would supersede the Commission's Policy Statement on training and qualification of nuclear power plant personnel and would not result in any change to accredited programs. The Commission concluded that accredited programs, implemented consistent with industry objectives and criteria, would be in compliance with this regulation. In April 1993, the NRC published its final rule on training and qualification of nuclear power plant personnel. The rule requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine non-licensed positions. Accreditation of these nine training programs is an acceptable means of meeting the requirements of 1 O CFR 50.120. In January 2001, the NRC published NRC Regulatory Issue Summary (RIS) 2001-1, "Eligibility of Operator License Applicants," to familiarize licensees with the NRC's current guidelines for the qualification and training of reactor operator and senior operator license applicants. The RIS 2001-01 acknowledged that 10 CFR 55.31(a)(4) allows the NRC to accept an application for an operator's license if the facility certifies that the applicant has successfully completed a Commission approved training program that is based on a SAT. In addition, RIS 2001-01 stated that: (1) a training program would be considered approved by the NRC when it receives or renews accreditation from the National Nuclear Accrediting Board (NNAB); (2) accreditation of operator training programs suggests that facilities are implementing the education and experience guidelines endorsed by the NNAB; (3) NANT guidelines for education and experience outline acceptable methods for implementing the Commission's regulations; and (4) the staff encourages all facility licensees to review their requirements and commitments related to licensed operator and senior operator education and experience and to update their documentation (e.g., Updated Final Safety Analysis Report (UFSAR), TSs, and training program descriptions) to enhance consistency and minimize confusion. 3.0 TECHNICAL EVALUATION The licensee has proposed to remove operator license applicant education and experience requirements from the TS. The licensee states in its letter that Nine Mile Point Nuclear Station's (NMNPS) education and experience requirements are administratively controlled through each unit's UFSAR, accredited licensed operator training program, or training procedures that ensure the operation of the facility in a safe manner. The licensee further states that NMPNS Operator Training Programs are designed in accordance with accreditation programs described in the latest approved NANT guidelines and that a station authorized representative will continue to certify that licensed operator applicants meet educational and experience requirements outlined by NANT guidelines. The licensee has proposed to revise TS 5.3.1/6.3.1, "Unit (Facility) Staff Qualifications," to remove operator license applicant education and experience requirements and add the requirement that licensed operators shall comply with 10 CFR Part 55. The licensee states in its letter dated September 11, 2014, that EGC's education and experience requirements for operator license applicants are administratively controlled through each station's updated FSAR. The letter also states that the licensed operator training programs are based on an SAT
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| -3 -and are accredited by the NANT. Since 10 CFR 55.31(a)(4) allows the NRC to accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program, that is based on an SAT in lieu of providing details of the applicant's education and experience, this change meets the 10 CFR 55.31 (a)(4) requirements to apply for an operator's license and ensures the facility licensee maintains administrative controls that assure the operation of the facility in a safe manner by properly qualified licensed operators. Therefore, the staff concludes that the proposed changes to TS 5.3.1/6.3.1 are acceptable. Based on the above discussion, the NRC staff concludes that the proposed revision is consistent with 10 CFR Part 55 and does not affect nuclear safety or plant operations. Therefore, the proposed changes to NMP1 TS 6.3.1 and NMP2 TS 5.3.1 are acceptable. 4.0 STATE CONSULTATION In accordance with the Commission's regulations, the New York State officials were notified of the proposed issuance of the amendment. The State officials had no comments. 5.0 ENVIRONMENTAL CONSIDERATION The amendments change the requirements with respect to TS administrative controls associated with eligibility of licensed operators. As such, the amendments relate to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 1 O CFR 51.22(c)(1 O)(ii). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments. 6.0 CONCLUSION The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor: S. Currie Date: July 8, 2015 Mr. Peter Orphanos Vice President Nine Mile Point Exelon Generation Company, LLC Nine Mile Point Nuclear Station, LLC P. 0. Box 63 Lycoming, NY 13093 July 8, 2015 SUBJECT: NINE MILE POINT NUCLEAR STATION, UNITS. 1 AND 2 -ISSUANCE OF AMENDMENTS -RE: CHANGE TO TECHNICAL SPECIFICATION REQUIREMENTS REGARDING EDUCATION AND EXPERIENCE ELIGIBILITY REQUIREMENTS FOR LICENSED OPERATORS (TAC NOS. MF4786 AND MF4787) Dear Mr. Orphanos: The Commission has issued the enclosed Amendment No. 218 to Renewed Facility Operating License No. DPR-63 and Amendment No. 148 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 11, 2014. The amendments revise the licensed operator training and qualification education and experience eligibility requirements specified in NMP1 TS 6.3.1 and NMP2 TS 5.3.1 to the eligibility requirements specified in this License Amendment Request. The proposed eligibility requirements correspond to the eligibility requirements contained in the current National Academy for Nuclear Training (NANT) Academy Document, ACAD 10-001, "Guidelines for Initial Training and Qualification of Licensed Operators," dated February 201 O. A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice. Docket Nos. 50-220 and 50-410 Enclosures: 1. Amendment No. 218 to DPR-63 2. Amendment No. 148 to NPF-69 Sincerely, IRA/ Brenda L. Mozafari, Sr. Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: PUBLIC LPL 1-1 R/F RidsNRRLAKGoldstein GDentel, RI RidsRgn1 MailCenter RidsNrrDorlDpr RidsAcrsAcnw_MailCTR ADAMS Accession No.: ML 15167A315 RidsDorlLpl1-1 RidsNRRPMNineMilePoint RidsNRR Tech Branches RidsNrrDssStsb Scott Currie . i OFFICE DORL/LPLl-1\PM DORL/LPLl-1\LA NRR/IOLB\BC NRR/DRA/APHB OGC DORL/LPLl-1/BC (A' I NAME BMozafari KGoldstein SS loan Glapinsky SUttal MDudek I DATE 6/16/2015 7/07/2015 5/28/2015 6/24/2015 6/30/2015 7/08/2015 OFFICIAL RECORD COPY
| | The Commission has issued the enclosed Amendment No. 218 to Renewed Facility Operating License No. DPR-63 and Amendment No. 148 to Renewed Facility Operating License No. |
| }} | | NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 11, 2014. |
| | The amendments revise the licensed operator training and qualification education and experience eligibility requirements specified in NMP1 TS 6.3.1 and NMP2 TS 5.3.1 to the eligibility requirements specified in this License Amendment Request. The proposed eligibility requirements correspond to the eligibility requirements contained in the current National Academy for Nuclear Training (NANT) Academy Document, ACAD 10-001, "Guidelines for Initial Training and Qualification of Licensed Operators," dated February 2010. |
| | A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice. |
| | Sincerely, v~~lffixtl~ |
| | Brenda L. Mozafari, Sr. Pr~:<J.J.nager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410 |
| | |
| | ==Enclosures:== |
| | : 1. Amendment No. 218 to DPR-63 |
| | : 2. Amendment No. 148 to NPF-69 |
| | : 3. Safety Evaluation cc w/encls: Distribution via Listserv |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 218 Renewed License No. DPR-63 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee), dated September 1, 2014, 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 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-63 is hereby amended to read as follows: |
| | (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 218, are hereby incorporated in the license. Exelon Generation Company, LLC, the licensee shall operate the facility in accordance with the Technical Specifications. |
| | : 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days. |
| | FOR THE NUCLEAR REGULA TORY COMMISSION |
| | ~~__d Michael I. Dudek, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| | |
| | ==Attachment:== |
| | |
| | Changes to the License and Technical Specifications Date of lssuance:Jul y 8, 2015 |
| | |
| | ATTACHMENT TO LICENSE AMENDMENT NO. 218 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. |
| | Remove Page Insert Page 3 3 4 4 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. |
| | Remove Pages Insert Pages 349 349 |
| | |
| | (2) Exelon Generation pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40 and 70, to |
| | * receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components. |
| | (5) Exelon Generation pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. |
| | C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: |
| | Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below: |
| | (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal). |
| | (2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. is hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications. |
| | (3) Deleted Renewed License No. DPR-63 Amendment No. 191 through 210, 211, 213, 214, 215, 216, 217, 218 Correction Letter Dated August 7, 2012 Correction Letter Dated March 17, 2015 |
| | |
| | (1) Maximum Power Level Exelon Generation is authorized to operate the facility at reactor core power levels not in excess of 3988 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. |
| | (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | (3) Fuel Storage and Handling (Section 9.1, SSER 4)* |
| | : a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high. |
| | : b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility. |
| | : c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations. |
| | : d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time. |
| | (4) Turbine System Maintenance Program (Section 3.5.1.3.10, SER) |
| | The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities. |
| | (Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, 111). |
| | * The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed. |
| | Renewed License No. NPF-69 Amendment 117 through 140, 141, 143, 144, 146, 147,218 |
| | : e. As a minimum, either the Manager Operations or the General Supervisor Operations shall hold an SRO license. |
| | : f. The Shift Technical Advisor (STA) shall provide advisory technical support to the shift supervision in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. |
| | 6.3 Unit Staff Qualifications 6.3.1 Each member of the unit staff, with the exception of the operator license applicants and the radiation protection manager, shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed operators shall comply only with the requirements of 10 CFR 55. |
| | 6.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of Specification 6.3.1, perform the functions described in 10 CFR 50.54(m). |
| | 6.4 Procedures 6.4.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and cover the following activities: |
| | : a. The applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 3, 1972; AMENDMENT NO. 142. 157. 158. 160. 162. 181. 198. 203, 218 349 |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION. LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 148 Renewed License No. NPF-69 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee), dated September 11, 2014. 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 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2. C. (2) of Renewed Facility Operating License No. NPF-69 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, both of which are attached hereto, as revised through Amendment No. 148 are hereby incorporated into this license. |
| | Exelon Generation Company, LLC, shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | : 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days. |
| | FOR THE NUCLEAR REGULATORY COMMISSION Michael I. Dudek, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
| | |
| | ==Attachment:== |
| | |
| | Changes to the License and Technical Specifications Date of Issuance: July 8, 2015 |
| | |
| | ATTACHMENT TO LICENSE AMENDMENT NO. 148 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. |
| | Remove Page Insert Page Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. |
| | Remove Pages Insert Pages 5.3.1 5.3.1 |
| | |
| | Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff, with the exception of the operator license applicants and the radiation protection manager, shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions. |
| | The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed operators shall comply only with the requirements of 10 CFR 55. |
| | NMP2 5.3-1 Amendment 91, 127, 148 |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENTS NOS. 218 AND 148 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-63 AND NPF-69 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NOS. 50-220 AND 50-410 NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 |
| | |
| | ==1.0 INTRODUCTION== |
| | |
| | By letter dated September 11, 2014, Exelon Generation Company (EGC), requested changes to Nine Mile Point 1 (NMP1) Technical Specifications (TS) Section 6.3.1 and Nine Mile Point 2 (NMP2) Technical Specifications (TS) Section 5.3.1 (Agencywide Document Access and Management System (ADAMS) Accession No. ML14254A007). The current requirement specifies that operator license applicant's education and experience eligibility requirements and changes thereto shall be reviewed and approved by the U.S. Nuclear Regulatory Commission (NRC) and described in an applicable station training procedure. The proposed amendment would revise NMP1 TS 6.3.1 and NMP2 TS 5.3.1, "Unit Staff Qualifications," to state that Licensed Operators shall comply with Title 10 Part 55 of the Code of Federal Regulations (10 CFR) Part 55. |
| | |
| | ==2.0 REGULATORY EVALUATION== |
| | |
| | In March 1985, the NRC issued the Commission Policy Statement on training and qualification of nuclear power plant personnel which endorsed the training accreditation process and the National Academy for Nuclear Training (NANT) guidelines. In Generic Letter 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Conforming Amendments," dated March 19, 1987, and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses," published November 1987, the NRC indicated it would accept a facility's licensed operator training program if the facility certified in writing that the program was accredited and based on a systems approach to training (SAT). This certification would supersede the requirements of American National Standards Institute (ANSI) N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," and ANSl/ANS-3.1-1978, "Selection and Training of Nuclear Power Plant Personnel." Facility |
| | |
| | licensees were advised to submit a request to the NRC for an administrative change to their licensing documents to conform to their accredited program status. |
| | In January 1992, the NRC published its proposed rule 10 CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel." The proposed rule stated that, if adopted, the rule would supersede the Commission's Policy Statement on training and qualification of nuclear power plant personnel and would not result in any change to accredited programs. The Commission concluded that accredited programs, implemented consistent with industry objectives and criteria, would be in compliance with this regulation. |
| | In April 1993, the NRC published its final rule on training and qualification of nuclear power plant personnel. The rule requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine non-licensed positions. Accreditation of these nine training programs is an acceptable means of meeting the requirements of 10 CFR 50.120. |
| | In January 2001, the NRC published NRC Regulatory Issue Summary (RIS) 2001-1, "Eligibility of Operator License Applicants," to familiarize licensees with the NRC's current guidelines for the qualification and training of reactor operator and senior operator license applicants. The RIS 2001-01 acknowledged that 10 CFR 55.31(a)(4) allows the NRC to accept an application for an operator's license if the facility certifies that the applicant has successfully completed a Commission approved training program that is based on a SAT. In addition, RIS 2001-01 stated that: (1) a training program would be considered approved by the NRC when it receives or renews accreditation from the National Nuclear Accrediting Board (NNAB); (2) accreditation of operator training programs suggests that facilities are implementing the education and experience guidelines endorsed by the NNAB; (3) NANT guidelines for education and experience outline acceptable methods for implementing the Commission's regulations; and (4) the staff encourages all facility licensees to review their requirements and commitments related to licensed operator and senior operator education and experience and to update their documentation (e.g., Updated Final Safety Analysis Report (UFSAR), TSs, and training program descriptions) to enhance consistency and minimize confusion. |
| | |
| | ==3.0 TECHNICAL EVALUATION== |
| | |
| | The licensee has proposed to remove operator license applicant education and experience requirements from the TS. The licensee states in its letter that Nine Mile Point Nuclear Station's (NMNPS) education and experience requirements are administratively controlled through each unit's UFSAR, accredited licensed operator training program, or training procedures that ensure the operation of the facility in a safe manner. The licensee further states that NMPNS Operator Training Programs are designed in accordance with accreditation programs described in the latest approved NANT guidelines and that a station authorized representative will continue to certify that licensed operator applicants meet educational and experience requirements outlined by NANT guidelines. |
| | The licensee has proposed to revise TS 5.3.1/6.3.1, "Unit (Facility) Staff Qualifications," to remove operator license applicant education and experience requirements and add the requirement that licensed operators shall comply with 10 CFR Part 55. The licensee states in its letter dated September 11, 2014, that EGC's education and experience requirements for operator license applicants are administratively controlled through each station's updated FSAR. The letter also states that the licensed operator training programs are based on an SAT |
| | |
| | and are accredited by the NANT. Since 10 CFR 55.31(a)(4) allows the NRC to accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program, that is based on an SAT in lieu of providing details of the applicant's education and experience, this change meets the 10 CFR 55.31 (a)(4) requirements to apply for an operator's license and ensures the facility licensee maintains administrative controls that assure the operation of the facility in a safe manner by properly qualified licensed operators. Therefore, the staff concludes that the proposed changes to TS 5.3.1/6.3.1 are acceptable. |
| | Based on the above discussion, the NRC staff concludes that the proposed revision is consistent with 10 CFR Part 55 and does not affect nuclear safety or plant operations. |
| | Therefore, the proposed changes to NMP1 TS 6.3.1 and NMP2 TS 5.3.1 are acceptable. |
| | |
| | ==4.0 STATE CONSULTATION== |
| | |
| | In accordance with the Commission's regulations, the New York State officials were notified of the proposed issuance of the amendment. The State officials had no comments. |
| | |
| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| | |
| | The amendments change the requirements with respect to TS administrative controls associated with eligibility of licensed operators. As such, the amendments relate to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 O)(ii). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments. |
| | |
| | ==6.0 CONCLUSION== |
| | |
| | The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| | Principal Contributor: S. Currie Date: July 8, 2015 |
| | |
| | July 8, 2015 Mr. Peter Orphanos Vice President Nine Mile Point Exelon Generation Company, LLC Nine Mile Point Nuclear Station, LLC P. 0. Box 63 Lycoming, NY 13093 |
| | |
| | ==SUBJECT:== |
| | NINE MILE POINT NUCLEAR STATION, UNITS. 1 AND 2 - ISSUANCE OF AMENDMENTS - RE: CHANGE TO TECHNICAL SPECIFICATION REQUIREMENTS REGARDING EDUCATION AND EXPERIENCE ELIGIBILITY REQUIREMENTS FOR LICENSED OPERATORS (TAC NOS. MF4786 AND MF4787) |
| | |
| | ==Dear Mr. Orphanos:== |
| | |
| | The Commission has issued the enclosed Amendment No. 218 to Renewed Facility Operating License No. DPR-63 and Amendment No. 148 to Renewed Facility Operating License No. |
| | NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 11, 2014. |
| | The amendments revise the licensed operator training and qualification education and experience eligibility requirements specified in NMP1 TS 6.3.1 and NMP2 TS 5.3.1 to the eligibility requirements specified in this License Amendment Request. The proposed eligibility requirements correspond to the eligibility requirements contained in the current National Academy for Nuclear Training (NANT) Academy Document, ACAD 10-001, "Guidelines for Initial Training and Qualification of Licensed Operators," dated February 201 O. |
| | A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice. |
| | Sincerely, IRA/ |
| | Brenda L. Mozafari, Sr. Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410 |
| | |
| | ==Enclosures:== |
| | : 1. Amendment No. 218 to DPR-63 |
| | : 2. Amendment No. 148 to NPF-69 |
| | : 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC LPL 1-1 R/F RidsRgn1 MailCenter RidsDorlLpl1-1 RidsNRRPMNineMilePoint RidsNRRLAKGoldstein RidsNrrDorlDpr RidsNRR Tech Branches RidsNrrDssStsb GDentel, RI RidsAcrsAcnw_MailCTR Scott Currie ADAMS |
| | =--~*---*~~~~- . |
| | Accession No.: ML15167A315 i OFFICE DORL/LPLl-1\PM DORL/LPLl-1\LA NRR/IOLB\BC NRR/DRA/APHB OGC DORL/LPLl-1/BC (A' I NAME BMozafari KGoldstein SS loan Glapinsky SUttal MDudek I |
| | DATE 6/16/2015 7/07/2015 5/28/2015 6/24/2015 6/30/2015 7/08/2015 OFFICIAL RECORD COPY}} |
Letter Sequence Approval |
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MONTHYEARML14310A6182014-11-0606 November 2014 TAC Nos. MF4786 & MF4787 - Acceptance of Requested Licensing Action License Amendment Request- Experience Eligibility Requirements for Licensed Operators Project stage: Acceptance Review ML15167A3152015-07-0808 July 2015 Issuance of Amendments Change to TS Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators Project stage: Approval ML15210A0062015-08-0404 August 2015 Correction Letter Regarding Issuance of Amendments - Change to Technical Specification Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators (TAC Nos. MF4786-87) Project stage: Approval 2015-07-08
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Category:Letter
MONTHYEARML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 NMP1L3582, Annual Radioactive Environmental Operating Report2024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines 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 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 2024-08-09
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 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 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 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 ML23082A3502023-04-17017 April 2023 Issuance of Amendment No. 192, Revision of Surveillance Requirements Associated with Emergency Diesel Generator Testing ML23025A4122023-02-28028 February 2023 Issuance of Amendment No. 248 to Revise Alternative Source Term Calculation for Main Steam Isolation Valve Leakage and Non-MSIV Leakage ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) 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 ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21082A2212021-04-29029 April 2021 Issuance of Amendment No. 186, Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21083A1752021-03-24024 March 2021 Correction to License Page for Amendment No. 245 Related to Relaxation of Surveillance Frequency for Instrument Line Flow Check Valve ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21033A9432021-02-0202 February 2021 Correction to Acceptance of Requested License Amendment to Adopt Technical Specification Task Force Traveler 582 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML20241A1902020-10-20020 October 2020 Issuance of Amendment No. 182 to Change Allowable Main Steam Isolation Valve Leak Rates 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 ML19301B0052019-11-25025 November 2019 Issuance of Amendment No. 239 Administrative Edits to the Technical Specifications ML19204A0632019-09-13013 September 2019 Independent Spent Fuel Storage Installation, James A. FitzPatrick, and Nine Mile Point - Issuance of Amendments to Revise the Emergency Response Organization Staff ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19176A0862019-07-30030 July 2019 Issuance of Amendment No. 237 Changes to Containment Oxygen Concentration Requirements RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control2019-06-14014 June 2019 Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control ML19008A4542019-01-22022 January 2019 Issuance of Amendment No. 236 Revising Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18344A4522019-01-11011 January 2019 Issuance of Amendment No. 234 Change to Remove Boraflex Credit from Spent Fuel Racks ML18324A7232018-12-13013 December 2018 Issuance of Amendment No. 233 Relocation of Surveillance Requirement Frequencies to Inservice Testing Program ML18342A0152018-12-0909 December 2018 Issuance of Amendment No. 174 to Revise TS 3.5.1, ECCS-Operating, for One-Time Extension of High Pressure Core Spray Completion Time & Associated Surveillance Requirement (Emergency Circumstances) ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18137A6142018-06-26026 June 2018 Calvert Cliffs Independent Spent Fuel Storage Installation; Nine Mile Point Nuclear Station; and R. E. Ginna Nuclear Power Plant - Issuance of Amendments Revising Emergency Action Level Schemes ML18131A2912018-06-0808 June 2018 Issuance of Amendment No. 170 Removal of Note Associated with Surveillance Requirement 3.5.1.2 (CAC No. MGO148; EPID L-2017-LLA-0294) ML18113A0452018-05-29029 May 2018 Issuance of Amendments to Revise Technical Specification Requirements for Secondary Containment ML18073A3642018-03-28028 March 2018 Issuance of Amendment No. 168 to Revise Technical Specifications to Adopt TS Traveler Force 542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC No. MF9357; EPID L-2017-LLA-0178) ML18060A0162018-03-16016 March 2018 Issuance of Amendment No. 167 to Revise Technical Specifications 2.1.1.2 Safety Limit Minimum Critical Power Ratio ML18032A1772018-03-0606 March 2018 Issuance of Amendment No. 166 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-522 (CAC No. MF9804; EPID L-2017-LLA-0232) ML17324B1782017-12-21021 December 2017 Issuance of Amendment to Allow Greater Flexibility in Performing Surveillance Testing in Modes 1, 2, or 3 of Emergency Diesel Generators(Cac No. MF9579; EPID L-2017-LLA-0203) ML17268A2632017-10-31031 October 2017 Issuance of Amendment to Reduce Steam Dome Pressure in Reactor Core Safety Limits (CAC No. MF8942; EPID L-2016-LLA-0038) 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) ML17152A3202017-06-30030 June 2017 Issuance of Amendments Emergency Plans Emergency Action Level HU1.5 2024-05-23
[Table view] Category:Safety Evaluation
MONTHYEARML24145A1862024-05-30030 May 2024 Authorization and Safety Evaluation of Alternative Relief Request I5R-12 Concerning the Installation of a Full Structural Weld Overlay on RPV Recirculation Inlet Nozzle N2E 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 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 ML23156A6822023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-11 ML23156A6832023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-14 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 ML23103A1912023-04-20020 April 2023 Request for Threshold Determination Under 10 CFR 50.80 ML23082A3502023-04-17017 April 2023 Issuance of Amendment No. 192, Revision of Surveillance Requirements Associated with Emergency Diesel Generator Testing ML23094A1422023-04-0505 April 2023 Approval of Alternative Request I5R-13 to Utilize Specific Provisions of Code Case N-716-3 ML23025A4122023-02-28028 February 2023 Issuance of Amendment No. 248 to Revise Alternative Source Term Calculation for Main Steam Isolation Valve Leakage and Non-MSIV Leakage ML22339A0582022-12-21021 December 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits 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) ML22061A0402022-03-11011 March 2022 Relief Request Associated with Excess Flow Check Valves ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21256A1792021-11-0202 November 2021 Issuance of Amendment No. 246 Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements 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 ML21166A1682021-06-25025 June 2021 ML21140A1532021-06-0303 June 2021 Correction to April 22, 2021 Safety Evaluation for Requests for Alternative to the Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Program Interval ML21082A2212021-04-29029 April 2021 Issuance of Amendment No. 186, Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML21109A2162021-04-22022 April 2021 Proposed Alternative to Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Interval ML21105A3382021-04-22022 April 2021 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Examination Coverage of Certain Class 1 and 2 Component Welds ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21049A0242021-02-23023 February 2021 Alternative Request to the Requirements of the ASME OM Code for the Testing Intervals for the Instrument-Line Flow Check Valves ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 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 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components 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 ML20241A1902020-10-20020 October 2020 Issuance of Amendment No. 182 to Change Allowable Main Steam Isolation Valve Leak Rates 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 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 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 ML20141L0532020-06-0202 June 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19301B0052019-11-25025 November 2019 Issuance of Amendment No. 239 Administrative Edits to the Technical Specifications 2024-05-30
[Table view] Category:Technical Specifications
MONTHYEARML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21077A0142021-03-16016 March 2021 License and Technical Specification Pages for Amendment No. 245, Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems ML19176A0862019-07-30030 July 2019 Issuance of Amendment No. 237 Changes to Containment Oxygen Concentration Requirements ML18344A4522019-01-11011 January 2019 Issuance of Amendment No. 234 Change to Remove Boraflex Credit from Spent Fuel Racks NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. ML18330A0952018-11-30030 November 2018 Correction Duplicate Subparagraph (N) on Technical Specification Page 204 That Occurred in Amendment No. 186 Issued January 25, 2005 RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement ML18032A1772018-03-0606 March 2018 Issuance of Amendment No. 166 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-522 (CAC No. MF9804; EPID L-2017-LLA-0232) NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 ML17324B1782017-12-21021 December 2017 Issuance of Amendment to Allow Greater Flexibility in Performing Surveillance Testing in Modes 1, 2, or 3 of Emergency Diesel Generators(Cac No. MF9579; EPID L-2017-LLA-0203) ML17152A3202017-06-30030 June 2017 Issuance of Amendments Emergency Plans Emergency Action Level HU1.5 ML17055A4512017-03-0909 March 2017 Issuance of Amendment Partial Length Fuel Rod Burnup ML16088A0532016-04-19019 April 2016 Issuance of Amendment License Amendment Request for Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel NMP2L2611, Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-01-0808 January 2016 Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual ML15341A3362016-01-0505 January 2016 Issuance of Amendment Technical Specifications for Safety Limit Minimum Critical Power Ratio NMP1L3064, Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements....2015-12-22022 December 2015 Supplemental Response to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements.... ML15317A3072015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specification Task Force Traveler 425 ML15096A0762015-09-0202 September 2015 Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) ML15167A3152015-07-0808 July 2015 Issuance of Amendments Change to TS Requirements Regarding Education and Experience Eligibility Requirements for Licensed Operators ML15110A0082015-05-26026 May 2015 Issuance of Amendment Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change ML15075A1592015-03-17017 March 2015 Correction Letter to Amendment No. 217 Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change (Tac No. MF1022) ML15043A2702015-03-12012 March 2015 Issuance of Amendment Diesel Generator Initiation - Degraded Voltage Time Delay Setting Change ML14126A0032014-06-30030 June 2014 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14057A5542014-05-29029 May 2014 Issuance of Amendment Regarding Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML1233803362012-11-21021 November 2012 License Amendment Request Pursuant to 10 CFR 50.90: Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML1133000472011-12-22022 December 2011 NMP2 EPU - Operating License and Technical Specification Pages ML1133000412011-12-22022 December 2011 Cover Letter - Nine Mile Point Nuclear Station, Unit No. 2 - Issuance of Amendment Extended Power Uprate ML11208C3952011-07-20020 July 2011 License Amendment Requests Pursuant to 10 CFR 50.90: Revisions to the Technical Specifications Design Features Sections to Reflect Transfer of a Portion of Nine Mile Point Nuclear Station Site Real Property ML1018803332010-07-26026 July 2010 Issuance of Amendment No. 206 Modification of TS Section 3.2.7.1 and 4.2.7.1 ML1008904222010-03-22022 March 2010 License Amendment Request Pursuant to 10 CFR 50.90: Revision to Containment Spray System Nozzle Surveillance Frequency ML0926406812009-09-18018 September 2009 License Amendment Request Pursuant to 10 CFR 50.90: Revisions to Primary Coolant System Pressure Isolation Valve Requirements Consistent with Standard Technical Specifications - Tech. Spec. Sections 3.2.7.1 and 4.2.7.1 ML0919504152009-07-0202 July 2009 License Amendment Request to Remove Position Indication for Relief Valves and Safety Valves from Technical Specifications ML0905605222009-02-11011 February 2009 Units, 1 & 2, License Amendment Request for Adoption of TSTF-511-A Rev. 0 Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. 2023-08-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 8, 2015
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS. 1 AND 2 - ISSUANCE OF AMENDMENTS - RE: CHANGE TO TECHNICAL SPECIFICATION REQUIREMENTS REGARDING EDUCATION AND EXPERIENCE ELIGIBILITY REQUIREMENTS FOR LICENSED OPERATORS (TAC NOS. MF4786 AND MF4787)
Dear Mr. Orphanos:
The Commission has issued the enclosed Amendment No. 218 to Renewed Facility Operating License No. DPR-63 and Amendment No. 148 to Renewed Facility Operating License No.
NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 11, 2014.
The amendments revise the licensed operator training and qualification education and experience eligibility requirements specified in NMP1 TS 6.3.1 and NMP2 TS 5.3.1 to the eligibility requirements specified in this License Amendment Request. The proposed eligibility requirements correspond to the eligibility requirements contained in the current National Academy for Nuclear Training (NANT) Academy Document, ACAD 10-001, "Guidelines for Initial Training and Qualification of Licensed Operators," dated February 2010.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely, v~~lffixtl~
Brenda L. Mozafari, Sr. Pr~:<J.J.nager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410
Enclosures:
- 1. Amendment No. 218 to DPR-63
- 2. Amendment No. 148 to NPF-69
- 3. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 218 Renewed License No. DPR-63
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee), dated September 1, 2014, 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 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-63 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 218, are hereby incorporated in the license. Exelon Generation Company, LLC, the licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULA TORY COMMISSION
~~__d Michael I. Dudek, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of lssuance:Jul y 8, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 218 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 3 3 4 4 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 349 349
(2) Exelon Generation pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40 and 70, to
- receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components.
(5) Exelon Generation pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. is hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications.
(3) Deleted Renewed License No. DPR-63 Amendment No. 191 through 210, 211, 213, 214, 215, 216, 217, 218 Correction Letter Dated August 7, 2012 Correction Letter Dated March 17, 2015
(1) Maximum Power Level Exelon Generation is authorized to operate the facility at reactor core power levels not in excess of 3988 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Fuel Storage and Handling (Section 9.1, SSER 4)*
- a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
- b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.
- c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.
(4) Turbine System Maintenance Program (Section 3.5.1.3.10, SER)
The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.
(Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, 111).
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
Renewed License No. NPF-69 Amendment 117 through 140, 141, 143, 144, 146, 147,218
- e. As a minimum, either the Manager Operations or the General Supervisor Operations shall hold an SRO license.
- f. The Shift Technical Advisor (STA) shall provide advisory technical support to the shift supervision in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
6.3 Unit Staff Qualifications 6.3.1 Each member of the unit staff, with the exception of the operator license applicants and the radiation protection manager, shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed operators shall comply only with the requirements of 10 CFR 55.
6.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of Specification 6.3.1, perform the functions described in 10 CFR 50.54(m).
6.4 Procedures 6.4.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and cover the following activities:
- a. The applicable procedures recommended in Regulatory Guide 1.33, Appendix A, November 3, 1972; AMENDMENT NO. 142. 157. 158. 160. 162. 181. 198. 203, 218 349
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION. LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 148 Renewed License No. NPF-69
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee), dated September 11, 2014. 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 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2. C. (2) of Renewed Facility Operating License No. NPF-69 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, both of which are attached hereto, as revised through Amendment No. 148 are hereby incorporated into this license.
Exelon Generation Company, LLC, shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Michael I. Dudek, Acting Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: July 8, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 148 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 5.3.1 5.3.1
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff, with the exception of the operator license applicants and the radiation protection manager, shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions.
The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed operators shall comply only with the requirements of 10 CFR 55.
NMP2 5.3-1 Amendment 91, 127, 148
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENTS NOS. 218 AND 148 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-63 AND NPF-69 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NOS. 50-220 AND 50-410 NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2
1.0 INTRODUCTION
By letter dated September 11, 2014, Exelon Generation Company (EGC), requested changes to Nine Mile Point 1 (NMP1) Technical Specifications (TS) Section 6.3.1 and Nine Mile Point 2 (NMP2) Technical Specifications (TS) Section 5.3.1 (Agencywide Document Access and Management System (ADAMS) Accession No. ML14254A007). The current requirement specifies that operator license applicant's education and experience eligibility requirements and changes thereto shall be reviewed and approved by the U.S. Nuclear Regulatory Commission (NRC) and described in an applicable station training procedure. The proposed amendment would revise NMP1 TS 6.3.1 and NMP2 TS 5.3.1, "Unit Staff Qualifications," to state that Licensed Operators shall comply with Title 10 Part 55 of the Code of Federal Regulations (10 CFR) Part 55.
2.0 REGULATORY EVALUATION
In March 1985, the NRC issued the Commission Policy Statement on training and qualification of nuclear power plant personnel which endorsed the training accreditation process and the National Academy for Nuclear Training (NANT) guidelines. In Generic Letter 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Conforming Amendments," dated March 19, 1987, and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses," published November 1987, the NRC indicated it would accept a facility's licensed operator training program if the facility certified in writing that the program was accredited and based on a systems approach to training (SAT). This certification would supersede the requirements of American National Standards Institute (ANSI) N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," and ANSl/ANS-3.1-1978, "Selection and Training of Nuclear Power Plant Personnel." Facility
licensees were advised to submit a request to the NRC for an administrative change to their licensing documents to conform to their accredited program status.
In January 1992, the NRC published its proposed rule 10 CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel." The proposed rule stated that, if adopted, the rule would supersede the Commission's Policy Statement on training and qualification of nuclear power plant personnel and would not result in any change to accredited programs. The Commission concluded that accredited programs, implemented consistent with industry objectives and criteria, would be in compliance with this regulation.
In April 1993, the NRC published its final rule on training and qualification of nuclear power plant personnel. The rule requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine non-licensed positions. Accreditation of these nine training programs is an acceptable means of meeting the requirements of 10 CFR 50.120.
In January 2001, the NRC published NRC Regulatory Issue Summary (RIS) 2001-1, "Eligibility of Operator License Applicants," to familiarize licensees with the NRC's current guidelines for the qualification and training of reactor operator and senior operator license applicants. The RIS 2001-01 acknowledged that 10 CFR 55.31(a)(4) allows the NRC to accept an application for an operator's license if the facility certifies that the applicant has successfully completed a Commission approved training program that is based on a SAT. In addition, RIS 2001-01 stated that: (1) a training program would be considered approved by the NRC when it receives or renews accreditation from the National Nuclear Accrediting Board (NNAB); (2) accreditation of operator training programs suggests that facilities are implementing the education and experience guidelines endorsed by the NNAB; (3) NANT guidelines for education and experience outline acceptable methods for implementing the Commission's regulations; and (4) the staff encourages all facility licensees to review their requirements and commitments related to licensed operator and senior operator education and experience and to update their documentation (e.g., Updated Final Safety Analysis Report (UFSAR), TSs, and training program descriptions) to enhance consistency and minimize confusion.
3.0 TECHNICAL EVALUATION
The licensee has proposed to remove operator license applicant education and experience requirements from the TS. The licensee states in its letter that Nine Mile Point Nuclear Station's (NMNPS) education and experience requirements are administratively controlled through each unit's UFSAR, accredited licensed operator training program, or training procedures that ensure the operation of the facility in a safe manner. The licensee further states that NMPNS Operator Training Programs are designed in accordance with accreditation programs described in the latest approved NANT guidelines and that a station authorized representative will continue to certify that licensed operator applicants meet educational and experience requirements outlined by NANT guidelines.
The licensee has proposed to revise TS 5.3.1/6.3.1, "Unit (Facility) Staff Qualifications," to remove operator license applicant education and experience requirements and add the requirement that licensed operators shall comply with 10 CFR Part 55. The licensee states in its letter dated September 11, 2014, that EGC's education and experience requirements for operator license applicants are administratively controlled through each station's updated FSAR. The letter also states that the licensed operator training programs are based on an SAT
and are accredited by the NANT. Since 10 CFR 55.31(a)(4) allows the NRC to accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program, that is based on an SAT in lieu of providing details of the applicant's education and experience, this change meets the 10 CFR 55.31 (a)(4) requirements to apply for an operator's license and ensures the facility licensee maintains administrative controls that assure the operation of the facility in a safe manner by properly qualified licensed operators. Therefore, the staff concludes that the proposed changes to TS 5.3.1/6.3.1 are acceptable.
Based on the above discussion, the NRC staff concludes that the proposed revision is consistent with 10 CFR Part 55 and does not affect nuclear safety or plant operations.
Therefore, the proposed changes to NMP1 TS 6.3.1 and NMP2 TS 5.3.1 are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State officials were notified of the proposed issuance of the amendment. The State officials had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change the requirements with respect to TS administrative controls associated with eligibility of licensed operators. As such, the amendments relate to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 O)(ii). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Currie Date: July 8, 2015
July 8, 2015 Mr. Peter Orphanos Vice President Nine Mile Point Exelon Generation Company, LLC Nine Mile Point Nuclear Station, LLC P. 0. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS. 1 AND 2 - ISSUANCE OF AMENDMENTS - RE: CHANGE TO TECHNICAL SPECIFICATION REQUIREMENTS REGARDING EDUCATION AND EXPERIENCE ELIGIBILITY REQUIREMENTS FOR LICENSED OPERATORS (TAC NOS. MF4786 AND MF4787)
Dear Mr. Orphanos:
The Commission has issued the enclosed Amendment No. 218 to Renewed Facility Operating License No. DPR-63 and Amendment No. 148 to Renewed Facility Operating License No.
NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2 (NMP1 and NMP2). The amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 11, 2014.
The amendments revise the licensed operator training and qualification education and experience eligibility requirements specified in NMP1 TS 6.3.1 and NMP2 TS 5.3.1 to the eligibility requirements specified in this License Amendment Request. The proposed eligibility requirements correspond to the eligibility requirements contained in the current National Academy for Nuclear Training (NANT) Academy Document, ACAD 10-001, "Guidelines for Initial Training and Qualification of Licensed Operators," dated February 201 O.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely, IRA/
Brenda L. Mozafari, Sr. Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410
Enclosures:
- 1. Amendment No. 218 to DPR-63
- 2. Amendment No. 148 to NPF-69
- 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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