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| | number = ML092260127 | | | number = ML092260127 |
| | issue date = 08/19/2009 | | | issue date = 08/19/2009 |
| | title = Nine Mile Point, Unit 2, Issuance of Amendment Regarding Implementation of TSTF-460, Rev 0, Control Rod Scram Time Testing Frequency, Using the Consolidated Line Item Improvement Process | | | title = Issuance of Amendment Regarding Implementation of TSTF-460, Rev 0, Control Rod Scram Time Testing Frequency, Using the Consolidated Line Item Improvement Process |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Belcher S L | | | addressee name = Belcher S |
| | addressee affiliation = Nine Mile Point Nuclear Station, LLC | | | addressee affiliation = Nine Mile Point Nuclear Station, LLC |
| | docket = 05000410 | | | docket = 05000410 |
| | license number = NPF-069 | | | license number = NPF-069 |
| | contact person = Guzman R V, NRR/DORL, 415-1030 | | | contact person = Guzman R, NRR/DORL, 415-1030 |
| | case reference number = TAC ME0898 | | | case reference number = TAC ME0898 |
| | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation | | | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August; 19, 2009 Mr. Samuel L. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August; 19, 2009 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 |
| Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -ISSUANCE OF AMENDMENT REGARDING IMPLEMENTATION OF TECHNICAL SPECIFICATION TASK FORCE (TSTF)-460, REVISION 0, "CONTROL ROD SCRAM TIME TESTING FREQUENCY," USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. ME0898) | | |
| | ==SUBJECT:== |
| | NINE MILE POINT NUCLEAR STATION, UNIT NO.2 - ISSUANCE OF AMENDMENT REGARDING IMPLEMENTATION OF TECHNICAL SPECIFICATION TASK FORCE (TSTF)-460, REVISION 0, "CONTROL ROD SCRAM TIME TESTING FREQUENCY," USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. ME0898) |
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| ==Dear Mr. Belcher:== | | ==Dear Mr. Belcher:== |
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| The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 132 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station (I\lMPNS), Unit NO.2 (NMP2), in response to your application dated March 9, 2009, (Agencywide Documents Access Management System Accession Number ML090780250). | | The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 132 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station (I\lMPNS), Unit NO.2 (NMP2), in response to your application dated March 9, 2009, (Agencywide Documents Access Management System Accession Number ML090780250). |
| The amendment revises the Technical Specification (TS) testing frequency for the Surveillance Requirement (SR) in TS 3.1.4, "Control Rod Scram Times," by extending the frequency of SR 3.1.4.2, from "120 days cumulative operation in Mode 1" to "200 days cumulative operation in Mode 1." This change is based on NRC-approved TSTF Change Traveler, TSTF-460-A, Revision 0, "Control Rod Scram Time Testing Frequency." 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, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 | | The amendment revises the Technical Specification (TS) testing frequency for the Surveillance Requirement (SR) in TS 3.1.4, "Control Rod Scram Times," by extending the frequency of SR 3.1.4.2, from "120 days cumulative operation in Mode 1" to "200 days cumulative operation in Mode 1." This change is based on NRC-approved TSTF Change Traveler, TSTF-460-A, Revision 0, "Control Rod Scram Time Testing Frequency." |
| | 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, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 132 to NPF-69 | | : 1. Amendment No. 132 to NPF-69 |
| : 2. Safety Evaluation cc w/encls: Distribution via Listserv UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION, LLC (NMPNS) DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 132 Renewed License No. NPF-69 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Nine Mile Point Nuclear Station, LLC (the licensee) dated March 9, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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. 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: Technical Specifications 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. 132 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. | | : 2. Safety Evaluation cc w/encls: Distribution via Listserv |
| -2This license amendment is effective as of the date of its issuance and shall be implemented within 60 days from the date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief 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 (NMPNS) |
| | DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 132 Renewed License No. NPF-69 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Nine Mile Point Nuclear Station, LLC (the licensee) dated March 9, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-69 is hereby amended to read as follows: |
| | (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 132 are hereby incorporated into this license. |
| | Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
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| | : 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days from the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the License and Technical Specifications Date of Issuance: | | |
| August 1 q, 2009 ATTACHMENT TO LICENSE AMENDMENT NO. TO RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. 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 4 4 Replace the following page of Appendix A, Technical Specifications, 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 3.1.4-2 3.1.4-2 Maximum Power Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor core power levels not in excess of 3467 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. 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. 132 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. Fuel Storage and Handling (Section 9.1, SSER 4)* Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high. 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. 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. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at anyone time. (4) Turbine System Maintenance Program (Section 3.5.1.3.10, SER) | | Changes to the License and Technical Specifications Date of Issuance: August 1q, 2009 |
| 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 3D, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III). | | |
| | ATTACHMENT TO LICENSE AMENDMENT NO. 132 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 4 4 Replace the following page of Appendix A, Technical Specifications, 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 3.1.4-2 3.1.4-2 |
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| | -4 (1) Maximum Power Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor core power levels not in excess of 3467 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. 132 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC 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 anyone 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 3D, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III). |
| 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. | | 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 125, 126, 127, 128, 129, 130, 131 132 Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued) | | Renewed License No. NPF 69 Amendment 117 through 125, 126, 127, 128, 129, 130, 131 132 |
| SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each tested control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure 800 pslq.
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| 200 days cumulative operation in MODE 1 SR 3.1.4.3 Verify each affected control rod scram time is within the limits of Table 3.1.4-1 with any reactor steam dome pressure.
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| Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure 800 psig. Prior to exceeding 40% RTP after fuel movement within the affected core cell Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time NMP2 3.1.4-2 Amendment , 132 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 132 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO.2 DOCKET NO. 50-410
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| ==1.0 INTRODUCTION==
| | Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued) |
| By letter dated March 9, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090780250), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for changes to the Nine Mile Point Nuclear Station, Unit NO.2 (NMP2) Technical Specifications (TSs). The proposed amendment would revise the Technical Specification (TS) testing frequency for the Surveillance Requirement (SR) in TS 3.1.4, "Control Rod Scram Times," by extending the frequency of SR 3.1.4.2 from "120 days cumulative operation in Mode 1" to "200 days cumulative operation in Mode 1." This change is based on TS Task Force (TSTF) Change Traveler, 460-A, Revision 0, "Control Rod Scram Time Testing Frequency," which has been approved by the Nuclear Regulatory Commission (NRC) generically for the Boiling-Water Reactor (BWR) Standard TS, NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6). The changes were described in a Notice of Availability for Consolidated Line Item Improvement Process (CLlIP) TSTF-460, published in the Federal Register on August 23,2004 (69 FR 51864). NMP2 is a BWR/5 plant. The NMP2 SR 3.1.4.2 is identical to Standard TS, NUREG-1433 (BWR/4) SR 3.1.4.2. The licensee stated in its application that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to NMP2.
| | SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each 200 days tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam operation in dome pressure ~ 800 pslq. MODE 1 SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor steam dome pressure. control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure ~ 800 psig. 40% RTP after fuel movement within the affected core cell Prior to exceeding 40% |
| | RTP after work on control rod or CRD System that could affect scram time NMP2 3.1.4-2 Amendment ~ , 132 |
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| ==2.0 REGULATORY EVALUATION==
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 132 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO.2 DOCKET NO. 50-410 |
| Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(c)(3), states that TSs shall contain SRs "relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." The TS requirement governing the control rod scram time surveillance is intended to assure proper function of control rod insertion. Following each refueling outage, all control rod scram times are verified. In addition, periodically during power operation, a representative sample of
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| -2control rods is selected to be inserted to verify the insertion speed. A representative sample is defined as a sample containing at least 10 percent of the total number of control rods. The current TS stipulates that no more than 20 percent of the control rods in this representative sample can be "slow" during the post outage testing. With more than 20 percent of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 20 percent criterion (e.g., 20 percent of the entire sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all surveillances) exceeds the Limiting Condition for Operation limit. For planned testing, the control rods selected for the sample should be different for each test. The acceptance criterion for at-power surveillance testing will be redefined from 20 percent to 7.5 percent. This tightened acceptance criterion for at-power surveillance aligns with the TS 3.1.4 requirement for the total control rods allowed to have scram times exceeding the specified limit. The proposed change does not affect any current operability requirements and the test frequency being revised is not specified in the regulations. As a result, no regulatory requirements or criteria are affected.
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| ===3.0 TECHNICAL=== | | ==1.0 INTRODUCTION== |
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| EVALUATION
| | By letter dated March 9, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090780250), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for changes to the Nine Mile Point Nuclear Station, Unit NO.2 (NMP2) Technical Specifications (TSs). |
| | The proposed amendment would revise the Technical Specification (TS) testing frequency for the Surveillance Requirement (SR) in TS 3.1.4, "Control Rod Scram Times," by extending the frequency of SR 3.1.4.2 from "120 days cumulative operation in Mode 1" to "200 days cumulative operation in Mode 1." This change is based on TS Task Force (TSTF) Change Traveler, TSTF 460-A, Revision 0, "Control Rod Scram Time Testing Frequency," which has been approved by the Nuclear Regulatory Commission (NRC) generically for the Boiling-Water Reactor (BWR) |
| | Standard TS, NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6). The changes were described in a Notice of Availability for Consolidated Line Item Improvement Process (CLlIP) |
| | TSTF-460, published in the Federal Register on August 23,2004 (69 FR 51864). |
| | NMP2 is a BWR/5 plant. The NMP2 SR 3.1.4.2 is identical to Standard TS, NUREG-1433 (BWR/4) SR 3.1.4.2. The licensee stated in its application that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to NMP2. |
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| ===3.1 Statement=== | | ==2.0 REGULATORY EVALUATION== |
| of Proposed Changes NMP2 SR 3.1.4.2 states, "Verify, for a representative sample, each tested control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure 800 psig." SR 3.1.4.2 has a frequency of "120 days cumulative operation in MODE 1." The proposed change revises the frequency to "200 days cumulative operation in MODE 1." The TS Bases are revised to reference the new frequency and to reduce the percentage of the tested rods which can be "slow" from 20 percent to 7.5 percent.
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| ===3.2 Evaluation===
| | Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(c)(3), states that TSs shall contain SRs "relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." |
| of Proposed Change The control rod insertion (scram) time test results at NMP2 have shown the control rod scram rates to be highly reliable. During the most recent 7 years of operation, out of more than 1340 control rod insertion tests, no control rods have been slower than the insertion time limit. As stated in NMPNS's application: Improved Technical Specifications (ITS) were implemented at NMP2 in December, 2000 and Scram Time Testing (STT) for all Control Rod Drives (CRDs) from then up to present met the ITS acceptance criteria with no 'Slow Rods'identified. Prior to ITS, custom Technical Specifications (CTS) had different criteria using maximum and average scram times for detecting slow CRDs. Scram Time Testing conducted between 1998 and 2000 using CTS criteria were reviewed. No instance of slow scram times were identified during the period. The extensive historical database substantiates the claim of high reliability of the NMP2 control drive system. The current TS requires that 10 percent of the 185 control rods, or 18 rods, be tested via sampling every 120 cumulative days of operation in Mode 1. | | The TS requirement governing the control rod scram time surveillance is intended to assure proper function of control rod insertion. Following each refueling outage, all control rod scram times are verified. In addition, periodically during power operation, a representative sample of |
| -3The NMP2 current TS states that the acceptance criteria have been met if 20 percent or fewer of the sample control rods that are tested are found to be slow. The acceptance criterion is being redefined for at-power surveillance testing from 20 percent to 7.5 percent when the surveillance period is extended to 200 cumulative days of operation in Mode 1. This tightened acceptance criterion for at-power surveillance aligns with the TS 3.1.4 requirement for the total control rods allowed to have scram times exceeding the specified limit. NMPNS has committed to incorporate the revised acceptance criterion value of 7.5 percent into TS Bases in accordance with their Bases Control Program and as a condition of this license amendment. The NRC staff considers the extended surveillance interval to be justified by the demonstrated reliability of the control rod insertion system, based on historical control rod scram time test data, and by the more restrictive acceptance criterion for the number of slow rods allowed during power surveillance testing. The NRC staff finds the proposed TS change acceptable.
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| ==4.0 STATE CONSULTATION==
| | -2 control rods is selected to be inserted to verify the insertion speed. A representative sample is defined as a sample containing at least 10 percent of the total number of control rods. The current TS stipulates that no more than 20 percent of the control rods in this representative sample can be "slow" during the post outage testing. With more than 20 percent of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 20 percent criterion (e.g., 20 percent of the entire sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all surveillances) exceeds the Limiting Condition for Operation limit. For planned testing, the control rods selected for the sample should be different for each test. The acceptance criterion for at-power surveillance testing will be redefined from 20 percent to 7.5 percent. This tightened acceptance criterion for at-power surveillance aligns with the TS 3.1.4 requirement for the total control rods allowed to have scram times exceeding the specified limit. |
| | The proposed change does not affect any current operability requirements and the test frequency being revised is not specified in the regulations. As a result, no regulatory requirements or criteria are affected. |
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| In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
| | ==3.0 TECHNICAL EVALUATION== |
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| ===5.0 ENVIRONMENTAL===
| | 3.1 Statement of Proposed Changes NMP2 SR 3.1.4.2 states, "Verify, for a representative sample, each tested control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure ~ 800 psig." SR 3.1.4.2 has a frequency of "120 days cumulative operation in MODE 1." The proposed change revises the frequency to "200 days cumulative operation in MODE 1." The TS Bases are revised to reference the new frequency and to reduce the percentage of the tested rods which can be "slow" from 20 percent to 7.5 percent. |
| | 3.2 Evaluation of Proposed Change The control rod insertion (scram) time test results at NMP2 have shown the control rod scram rates to be highly reliable. During the most recent 7 years of operation, out of more than 1340 control rod insertion tests, no control rods have been slower than the insertion time limit. As stated in NMPNS's application: |
| | Improved Technical Specifications (ITS) were implemented at NMP2 in December, 2000 and Scram Time Testing (STT) for all Control Rod Drives (CRDs) from then up to present met the ITS acceptance criteria with no 'Slow Rods'identified. Prior to ITS, custom Technical Specifications (CTS) had different criteria using maximum and average scram times for detecting slow CRDs. Scram Time Testing conducted between 1998 and 2000 using CTS criteria were reviewed. No instance of slow scram times were identified during the period. |
| | The extensive historical database substantiates the claim of high reliability of the NMP2 control drive system. The current TS requires that 10 percent of the 185 control rods, or 18 rods, be tested via sampling every 120 cumulative days of operation in Mode 1. |
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| CONSIDERATION The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change the surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant changes in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (74 FR 23447). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
| | -3 The NMP2 current TS states that the acceptance criteria have been met if 20 percent or fewer of the sample control rods that are tested are found to be slow. The acceptance criterion is being redefined for at-power surveillance testing from 20 percent to 7.5 percent when the surveillance period is extended to 200 cumulative days of operation in Mode 1. This tightened acceptance criterion for at-power surveillance aligns with the TS 3.1.4 requirement for the total control rods allowed to have scram times exceeding the specified limit. |
| | NMPNS has committed to incorporate the revised acceptance criterion value of 7.5 percent into TS Bases in accordance with their Bases Control Program and as a condition of this license amendment. |
| | The NRC staff considers the extended surveillance interval to be justified by the demonstrated reliability of the control rod insertion system, based on historical control rod scram time test data, and by the more restrictive acceptance criterion for the number of slow rods allowed during at power surveillance testing. The NRC staff finds the proposed TS change acceptable. |
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| ==6.0 CONCLUSION== | | ==4.0 STATE CONSULTATION== |
| 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 amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributors:
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| K. Bucholtz R. Grover Date: August 19, 2009 August 19, 2009 Mr. Samuel L.
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| Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 NINE MILE POINT NUCLEAR STATION, UNIT NO.2 -ISSUANCE OF AMENDMENT REGARDING IMPLEMENTATION OF TECHNICAL SPECIFICATION TASK FORCE (TSTF)-460, REVISION 0, "CONTROL ROD SCRAM TIME TESTING FREQUENCY," USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. ME0898)
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| ==Dear Mr. Belcher:== | | In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments. |
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| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| | |
| | The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change the surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant changes in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (74 FR 23447). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), |
| | no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. |
|
| |
|
| The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 132 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station (NMPNS), Unit NO.2 (NMP2), in response to your application dated March 9, 2009, (Agencywide Documents Access Management System Accession Number ML090780250).
| | ==6.0 CONCLUSION== |
| The amendment revises the Technical Specification (TS) testing frequency for the Surveillance Requirement (SR) in TS 3.1.4, "Control Rod Scram Times," by extending the frequency of SR 3.1.4.2, from "120 days cumulative operation in Mode 1" to "200 days cumulative operation in Mode 1." This change is based on NRC-approved TSTF Change Traveler, TSTF-460-A, Revision 0, "Control Rod Scram Time Testing Frequency." 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, IRAI Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
| |
|
| |
|
| ==Enclosures:==
| | 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 amendments will not be inimical to the common defense and security or to the health and safety of the public. |
| : 1. Amendment No. 132 to N2. Safety Evaluation PF-69 cc wtencls: | | Principal Contributors: K. Bucholtz R. Grover Date: August 19, 2009 |
| Distribution via Listserv Distribution:
| |
| PUBLIC LPL1-1 RtF RidsAcrsAcnw MailCenter RGrover, NRR RidsOgcRp
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| RidsNrrDorlLPL 1-1 RidsNrrDirsltsb RidsNrrPMRGuzman RidsNrrLASLittle RidsNrrDorlDpr KBucholtz, NRR RidsRgn'1 MailCenter RidsOGCMailCenter L09226012 *SE pravi e lY memo. o su bstantial ch de. NRR 106 ADAMS Accession No.: M 7 id db N s an ra c anoes rna OFFICE NAME DATE LPL1-1/PM LPL1-1/LA SUttle RGuzman 8/17/09 8/17/09 DIRS/ITSB/BC LPL1-1/BC RElliott* DPickett for NSalgado 07/28/09*
| | ML092260127 *SE praviidedblY memo. No su bstantial c anoes rnade. NRR106 s an ra ch OFFICE LPL1-1/PM LPL1-1/LA DIRS/ITSB/BC LPL1-1/BC NAME RGuzman SUttle RElliott* DPickett for NSalgado DATE 8/17/09 8/17/09 07/28/09* 8/18/09}} |
| 8/18/09 OFFICIAL RECORD}} | |
Letter Sequence Approval |
|---|
TAC:ME0898, Control Rod SCRAM Time Testing Frequency (Approved, Closed) |
|
MONTHYEARML0907802502009-03-0909 March 2009
Submittal of Amendment Request for Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency
Project stage: Request
ML0922601272009-08-19019 August 2009
Issuance of Amendment Regarding Implementation of TSTF-460, Rev 0, Control Rod Scram Time Testing Frequency, Using the Consolidated Line Item Improvement Process
Project stage: Approval
2009-03-09
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - 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
NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 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
ML24158A2052024-05-15015 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
05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
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
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
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
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)
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
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
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))
05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023
Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
IR 05000410/20243012023-12-14014 December 2023
Initial Operator Licensing Examination Report 05000410/2024301
2024-09-04
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
ML24079A0762024-05-23023 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
ML22021B6602022-02-0101 February 2022
Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1
ML22021B6592022-02-0101 February 2022
Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter)
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)
2024-05-23
[Table view]
Category:Safety Evaluation
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
ML24145A1862024-05-30030 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
ML23156A6832023-06-22022 June 2023
Authorization and Safety Evaluation of Alternative Relief Request I5R-14
ML23156A6822023-06-22022 June 2023
Authorization and Safety Evaluation of Alternative Relief Request I5R-11
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
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2024-09-26
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August; 19, 2009 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.2 - ISSUANCE OF AMENDMENT REGARDING IMPLEMENTATION OF TECHNICAL SPECIFICATION TASK FORCE (TSTF)-460, REVISION 0, "CONTROL ROD SCRAM TIME TESTING FREQUENCY," USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. ME0898)
Dear Mr. Belcher:
The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 132 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station (I\lMPNS), Unit NO.2 (NMP2), in response to your application dated March 9, 2009, (Agencywide Documents Access Management System Accession Number ML090780250).
The amendment revises the Technical Specification (TS) testing frequency for the Surveillance Requirement (SR) in TS 3.1.4, "Control Rod Scram Times," by extending the frequency of SR 3.1.4.2, from "120 days cumulative operation in Mode 1" to "200 days cumulative operation in Mode 1." This change is based on NRC-approved TSTF Change Traveler, TSTF-460-A, Revision 0, "Control Rod Scram Time Testing Frequency."
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, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosures:
- 1. Amendment No. 132 to NPF-69
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION, LLC (NMPNS)
DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 132 Renewed License No. NPF-69
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nine Mile Point Nuclear Station, LLC (the licensee) dated March 9, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-69 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 132 are hereby incorporated into this license.
Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
-2
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, 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: August 1q, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 132 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 4 4 Replace the following page of Appendix A, Technical Specifications, 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 3.1.4-2 3.1.4-2
-4 (1) Maximum Power Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor core power levels not in excess of 3467 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. 132 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC 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 anyone 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 3D, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III).
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 125, 126, 127, 128, 129, 130, 131 132
Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each 200 days tested control rod scram time is within the cumulative limits of Table 3.1.4-1 with reactor steam operation in dome pressure ~ 800 pslq. MODE 1 SR 3.1.4.3 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with declaring any reactor steam dome pressure. control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time Prior to is within the limits of Table 3.1.4-1 with exceeding reactor steam dome pressure ~ 800 psig. 40% RTP after fuel movement within the affected core cell Prior to exceeding 40%
RTP after work on control rod or CRD System that could affect scram time NMP2 3.1.4-2 Amendment ~ , 132
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 132 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO.2 DOCKET NO. 50-410
1.0 INTRODUCTION
By letter dated March 9, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090780250), Nine Mile Point Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for changes to the Nine Mile Point Nuclear Station, Unit NO.2 (NMP2) Technical Specifications (TSs).
The proposed amendment would revise the Technical Specification (TS) testing frequency for the Surveillance Requirement (SR) in TS 3.1.4, "Control Rod Scram Times," by extending the frequency of SR 3.1.4.2 from "120 days cumulative operation in Mode 1" to "200 days cumulative operation in Mode 1." This change is based on TS Task Force (TSTF) Change Traveler, TSTF 460-A, Revision 0, "Control Rod Scram Time Testing Frequency," which has been approved by the Nuclear Regulatory Commission (NRC) generically for the Boiling-Water Reactor (BWR)
Standard TS, NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6). The changes were described in a Notice of Availability for Consolidated Line Item Improvement Process (CLlIP)
TSTF-460, published in the Federal Register on August 23,2004 (69 FR 51864).
NMP2 is a BWR/5 plant. The NMP2 SR 3.1.4.2 is identical to Standard TS, NUREG-1433 (BWR/4) SR 3.1.4.2. The licensee stated in its application that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to NMP2.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(c)(3), states that TSs shall contain SRs "relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."
The TS requirement governing the control rod scram time surveillance is intended to assure proper function of control rod insertion. Following each refueling outage, all control rod scram times are verified. In addition, periodically during power operation, a representative sample of
-2 control rods is selected to be inserted to verify the insertion speed. A representative sample is defined as a sample containing at least 10 percent of the total number of control rods. The current TS stipulates that no more than 20 percent of the control rods in this representative sample can be "slow" during the post outage testing. With more than 20 percent of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 20 percent criterion (e.g., 20 percent of the entire sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all surveillances) exceeds the Limiting Condition for Operation limit. For planned testing, the control rods selected for the sample should be different for each test. The acceptance criterion for at-power surveillance testing will be redefined from 20 percent to 7.5 percent. This tightened acceptance criterion for at-power surveillance aligns with the TS 3.1.4 requirement for the total control rods allowed to have scram times exceeding the specified limit.
The proposed change does not affect any current operability requirements and the test frequency being revised is not specified in the regulations. As a result, no regulatory requirements or criteria are affected.
3.0 TECHNICAL EVALUATION
3.1 Statement of Proposed Changes NMP2 SR 3.1.4.2 states, "Verify, for a representative sample, each tested control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure ~ 800 psig." SR 3.1.4.2 has a frequency of "120 days cumulative operation in MODE 1." The proposed change revises the frequency to "200 days cumulative operation in MODE 1." The TS Bases are revised to reference the new frequency and to reduce the percentage of the tested rods which can be "slow" from 20 percent to 7.5 percent.
3.2 Evaluation of Proposed Change The control rod insertion (scram) time test results at NMP2 have shown the control rod scram rates to be highly reliable. During the most recent 7 years of operation, out of more than 1340 control rod insertion tests, no control rods have been slower than the insertion time limit. As stated in NMPNS's application:
Improved Technical Specifications (ITS) were implemented at NMP2 in December, 2000 and Scram Time Testing (STT) for all Control Rod Drives (CRDs) from then up to present met the ITS acceptance criteria with no 'Slow Rods'identified. Prior to ITS, custom Technical Specifications (CTS) had different criteria using maximum and average scram times for detecting slow CRDs. Scram Time Testing conducted between 1998 and 2000 using CTS criteria were reviewed. No instance of slow scram times were identified during the period.
The extensive historical database substantiates the claim of high reliability of the NMP2 control drive system. The current TS requires that 10 percent of the 185 control rods, or 18 rods, be tested via sampling every 120 cumulative days of operation in Mode 1.
-3 The NMP2 current TS states that the acceptance criteria have been met if 20 percent or fewer of the sample control rods that are tested are found to be slow. The acceptance criterion is being redefined for at-power surveillance testing from 20 percent to 7.5 percent when the surveillance period is extended to 200 cumulative days of operation in Mode 1. This tightened acceptance criterion for at-power surveillance aligns with the TS 3.1.4 requirement for the total control rods allowed to have scram times exceeding the specified limit.
NMPNS has committed to incorporate the revised acceptance criterion value of 7.5 percent into TS Bases in accordance with their Bases Control Program and as a condition of this license amendment.
The NRC staff considers the extended surveillance interval to be justified by the demonstrated reliability of the control rod insertion system, based on historical control rod scram time test data, and by the more restrictive acceptance criterion for the number of slow rods allowed during at power surveillance testing. The NRC staff finds the proposed TS change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change the surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant changes in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (74 FR 23447). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: K. Bucholtz R. Grover Date: August 19, 2009
ML092260127 *SE praviidedblY memo. No su bstantial c anoes rnade. NRR106 s an ra ch OFFICE LPL1-1/PM LPL1-1/LA DIRS/ITSB/BC LPL1-1/BC NAME RGuzman SUttle RElliott* DPickett for NSalgado DATE 8/17/09 8/17/09 07/28/09* 8/18/09
