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| {{#Wiki_filter:September 14, 2006Mr. Michael KanslerPresident Entergy Nuclear Operations, Inc. | | {{#Wiki_filter:September 14, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601 | | 440 Hamilton Avenue White Plains, NY 10601 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: RELOCATION OF TECHNICAL SPECIFICATIONS (TAC NO. MC5421) | | PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: |
| | RELOCATION OF TECHNICAL SPECIFICATIONS (TAC NO. MC5421) |
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| ==Dear Mr. Kansler:== | | ==Dear Mr. Kansler:== |
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| The Commission has issued the enclosed Amendment No. 224 to Facility Operating LicenseNo. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 14, 2004, which was subsequently revised by letter dated August 30, 2006. Specifically, this amendment relocates TSs structural integrity requirements to the Pilgrim Final Safety Analysis Report. A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included inthe Commission's biweekly Federal Register Notice. Sincerely,/RA/James J. Shea, Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-293 | | The Commission has issued the enclosed Amendment No. 224 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 14, 2004, which was subsequently revised by letter dated August 30, 2006. Specifically, this amendment relocates TSs structural integrity requirements to the Pilgrim Final Safety Analysis Report. |
| | A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register Notice. |
| | Sincerely, |
| | /RA/ |
| | James J. Shea, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 224 to License No. DPR-35 | | : 1. Amendment No. 224 to License No. DPR-35 |
| : 2. Safety Evaluationcc w/encls: See next page September 14, 2006Mr. Michael KanslerPresident Entergy Nuclear Operations, Inc. | | : 2. Safety Evaluation cc w/encls: See next page |
| 440 Hamilton Avenue White Plains, NY 10601 | | |
| | September 14, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc. |
| | 440 Hamilton Avenue White Plains, NY 10601 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: RELOCATION OF TECHNICAL SPECIFICATIONS (TAC NO. MC5421) | | PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: |
| | RELOCATION OF TECHNICAL SPECIFICATIONS (TAC NO. MC5421) |
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| ==Dear Mr. Kansler:== | | ==Dear Mr. Kansler:== |
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| The Commission has issued the enclosed Amendment No. 224 to Facility Operating LicenseNo. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 14, 2004, which was subsequently revised by letter dated August 30, 2006. Specifically, this amendment relocates TSs structural integrity requirements to the Pilgrim Final Safety Analysis Report. A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included inthe Commission's biweekly Federal Register Notice. Sincerely,/RA/James J. Shea, Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-293 | | The Commission has issued the enclosed Amendment No. 224 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 14, 2004, which was subsequently revised by letter dated August 30, 2006. Specifically, this amendment relocates TSs structural integrity requirements to the Pilgrim Final Safety Analysis Report. |
| | A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register Notice. |
| | Sincerely, |
| | /RA/ |
| | James J. Shea, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 224 to License No. DPR-35 | | : 1. Amendment No. 224 to License No. DPR-35 |
| : 2. Safety Evaluationcc w/encls: See next page DISTRIBUTION | | : 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: |
| :PUBLICRidsNrrDorlLpl1-1RPowell, RIRidsOGC RP CSchulten PDI-I R/FRidsNrrLASLittle RidsNrrPMJSheaGHill (2)
| | PUBLIC RidsNrrDorlLpl1-1 RPowell, RI RidsOGC RP CSchulten PDI-I R/F RidsNrrLASLittle RidsNrrPMJShea GHill (2) |
| RidsAcrsAcnwMailAccession Number: ML062280304OFFICELPL1-1/PMLPL1-1/LAITSB/BCOGCLPL1-1/BCNAMEJSheaSLittleTKobetzSUttalRLauferDATE 8/30/068/31/06 9/01/069/11/069/12/06OFFICIAL RECORD COPY ENTERGY NUCLEAR GENERATION COMPANYENTERGY NUCLEAR OPERATIONS, INC.DOCKET NO. 50-293PILGRIM NUCLEAR POWER STATIONAMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 224 License No. DPR-351.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment filed by Entergy Nuclear Operations, Inc. (thelicensee) dated December 14, 2004, subsequently revised by letter dated August 30, 2006, complies with the standards and requirements of the AtomicEnergy 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance: (I) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.
| | RidsAcrsAcnwMail Accession Number: ML062280304 OFFICE LPL1-1/PM LPL1-1/LA ITSB/BC OGC LPL1-1/BC NAME JShea SLittle TKobetz SUttal RLaufer DATE 8/30/06 8/31/06 9/01/06 9/11/06 9/12/06 OFFICIAL RECORD COPY |
| 2.Accordingly, the license is amended by changes to the license and TechnicalSpecifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:B.Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 224, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.3.This license amendment is effective as of the date of issuance and shall beimplemented within 60 days.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Richard J. Laufer, ChiefPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | |
| | ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC. |
| | DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 224 License No. DPR-35 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment filed by Entergy Nuclear Operations, Inc. (the licensee) dated December 14, 2004, subsequently revised by letter dated August 30, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 license and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows: |
| | B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 224, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications. |
| | : 3. This license amendment is effective as of the date of issuance and shall be implemented within 60 days. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | Richard J. Laufer, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Licenseand Technical SpecificationsDate of Issuance: September 14, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 224FACILITY OPERATING LICENSE NO. DPR-35DOCKET NO. 50-293Replace the following page of the Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change. | | Changes to the License and Technical Specifications Date of Issuance: September 14, 2006 |
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 224 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following page of the Facility Operating License with the attached revised page. |
| | The revised page is identified by amendment number and contains a marginal line indicating the area of change. |
| | Remove Insert 3 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. |
| | Remove Insert ii ii 3/4.6-8 3/4.6-8 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 224 TO FACILITY OPERATING LICENSE NO. DPR-35 ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC. |
| | PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 |
| | |
| | ==1.0 INTRODUCTION== |
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| | By letter dated December 14, 2004 (ADAMS Accession No. ML043560152) Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the Pilgrim Nuclear Power Station (Pilgrim) Technical Specifications (TSs) which was subsequently revised by letter dated August 30, 2006 (ADAMS Accession No. ML062490489). The August 30, 2006, letter reduced the scope of the application as originally noticed. Hence, there is no change to the NRC staffs original proposed no significant hazards consideration determination (70 FR 9991; March 1, 2005). This amendment as revised would remove the TSs associated with the Pilgrim structural integrity requirements and relocates these requirements to the Pilgrim updated final safety analysis report (UFSAR). |
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| RemoveInsert 33Replace the following pages of the Appendix A Technical Specifications with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
| | ==2.0 REGULATORY EVALUATION== |
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| RemoveInsertiiii 3/4.6-83/4.6-8 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 224 TO FACILITY OPERATING LICENSE NO. DPR-35ENTERGY NUCLEAR GENERATION COMPANYENTERGY NUCLEAR OPERATIONS, INC.PILGRIM NUCLEAR POWER STATIONDOCKET NO. 50-29
| | Section 182a of the Atomic Energy Act of 1954, as amended (the Act), requires applicants for nuclear plant operating licenses to include TSs as part of the license. The Commissions regulatory requirements related to the content of TS are set forth in Title 10 of the Code of Federal Regulations (10 CFR 50.36), Technical specifications. The regulation requires that TSs include items in five specific categories, including (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); |
| | (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. |
| | However, the regulation does not specify the particular requirements to be included in a plants TSs. The regulation also specifies four criteria to be used in determining whether a particular item is required to be included in a LCO (10 CFR 50.36(i)(2)(ii)), as follows: Criterion 1 - |
| | Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; Criterion 2 - A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident (DBA) or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; Criterion 3 - A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier, and Criterion 4 - A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. |
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| ==31.0INTRODUCTION==
| | The Nuclear Regulatory Commission (NRC) staff and nuclear steam supply owners groups developed the Standard Technical Specifications (STS) that established models of the Commissions policy for TSs, and improved the format and clarity of the specifications. |
| By letter dated December 14, 2004 (ADAMS Accession No. ML043560152) Entergy NuclearOperations, Inc. (the licensee) submitted a request for changes to the Pilgrim Nuclear Power Station (Pilgrim) Technical Specifications (TSs) which was subsequently revised by letter dated August 30, 2006 (ADAMS Accession No. ML062490489). The August 30, 2006, letter reduced the scope of the application as originally noticed. Hence, there is no change to the NRC staff'soriginal proposed no significant hazards consideration determination (70 FR 9991; March 1, 2005). This amendment as revised would remove the TSs associated with the Pilgrimstructural integrity requirements and relocates these requirements to the Pilgrim updated finalsafety analysis report (UFSAR).
| | NUREG-1433, STS General Electric Plants, BWR/4, Revision 3, was approved and issued for use by the NRC on June 30, 2004. Many Nuclear Power Plants such as Pilgrim have relocated various specifications that are not required explicitly by 10 CFR 50.36 to other licensing basis documents such as a plants Final Safety Analysis Report utilizing the STS as a model. |
| | The NRC staff reviewed the licensee proposed change for compliance with 10 CFR 50.36 and with the precedent as established in the STS. |
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| ==2.0REGULATORY EVALUATION== | | ==3.0 TECHNICAL EVALUATION== |
| Section 182a of the Atomic Energy Act of 1954, as amended (the "Act"), requires applicants fornuclear plant operating licenses to include TSs as part of the license. The Commission's regulatory requirements related to the content of TS are set forth in Title 10 of the Code ofFederal Regulations (10 CFR 50.36), "Technical specifications." The regulation requires thatTSs include items in five specific categories, including (1) safety limits, limiting safety systemsettings, and limiting control settings; (2) limiting conditions for operation (LCOs);
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| (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.
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| However, the regulation does not specify the particular requirements to be included in a plant's TSs. The regulation also specifies four criteria to be used in determining whether a particular item is required to be included in a LCO (10 CFR 50.36(i)(2)(ii)), as follows: Criterion 1 -
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| Installed instrumentation that is used to detect, and indicate in the control room, a significantabnormal degradation of the reactor coolant pressure boundary; Criterion 2 - A process variable, design feature, or operating restriction that is an initial condition of a design-basisaccident (DBA) or transient analysis that either assumes the failure of or presents a challengeto the integrity of a fission product barrier; Criterion 3 - A structure, system, or component thatis part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fissionproduct barrier, and Criterion 4 - A structure, system, or component which operating experienceor probabilistic risk assessment has shown to be significant to public health and safety. The Nuclear Regulatory Commission (NRC) staff and nuclear steam supply owners groupsdeveloped the Standard Technical Specifications (STS) that established models of theCommission's policy for TSs, and improved the format and clarity of the specifications.
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| NUREG-1433, "STS General Electric Plants, BWR/4," Revision 3, was approved and issued foruse by the NRC on June 30, 2004. Many Nuclear Power Plants such as Pilgrim have relocatedvarious specifications that are not required explicitly by 10 CFR 50.36 to other licensing basis documents such as a plants Final Safety Analysis Report utilizing the STS as a model. The NRC staff reviewed the licensee proposed change for compliance with 10 CFR 50.36 andwith the precedent as established in the STS.
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| ==3.0TECHNICAL EVALUATION==
| | 3.1 Current Pilgrim TS Requirements TS 3.6.G.1 and the associated surveillance requirements (SR) 4.6.G provide general programmatic elements for inservice inspections (ISI) of the structural integrity of Pilgrims primary system boundary. The TS requires the primary system boundary to be maintained as required by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Section XI, Rules for ISI of Nuclear Power Plant Components, Articles IWA, IWB, IWC, IWD, IWF, and mandatory appendices as required by 10 CFR50.55a(g), except where specific relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i). The SR simply states that the ISI of components shall be performed in accordance with the Pilgrim ISI program. The results of the inspections shall be evaluated and reviewed with the NRC. |
| 3.1 Current Pilgrim TS RequirementsTS 3.6.G.1 and the associated surveillance requirements (SR) 4.6.G provide generalprogrammatic elements for inservice inspections (ISI) of the structural integrity of Pilgrims' primary system boundary. The TS requires the primary system boundary to be maintained asrequired by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Section XI, "Rules for ISI of Nuclear Power Plant Components," Articles IWA, IWB, IWC, IWD, IWF, and mandatory appendices as required by 10 CFR50.55a(g), except where specific relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i). The SRsimply states that the ISI of components shall be performed in accordance with the Pilgrim ISIprogram. The results of the inspections shall be evaluated and reviewed with the NRC. 3.2 Proposed Changes to the Pilgrim TS RequirementsThe structural integrity requirements of TS 3.6.G and the SR 4.6.G, will be relocated to thePilgrim UFSAR Appendix B.2. Therefore, any changes to these requirements will be strictlycontrolled by the provisions of 10 CFR 50.59, as well as 10 CFR 50.55a(g). 3.3 Staff Evaluation The safety basis for establishing programmatic requirements on structural integrity in TSsrelates to prevention of component degradation and continued long-term maintenance of acceptable structural conditions. Therefore, structural integrity of safe ty systems are notoperational limits that are an initial assumption of any DBA or transient analysis. 10 CFR 50.55a, "Codes and standards" specify the ASME Code requirements for plantoperations, maintenance and testing of ASME Code Class 1, 2, and 3 safety-related components. Each operating license for a boiling or pressurized water-cooled nuclear powerfacility is subject to the conditions in paragraphs (f) and (g) of 10 CRF 50.55a. Pilgrim TS 3.13 establishes the programmatic elements for conducting inservice testing (IST) ofASME Code Class 1, 2, and 3 pumps and valves. This TS provides the required frequencies for performing IST activities which is consistent with the STS Section 5.5.7, "Inservice Testing Program." Testing requirements for ASME Code 1, 2, and 3 pumps and valves are defined in 10 CFR 50.55a(f). 10 CFR 50.55(a)(g) provides the regulatory requirements for performing ISI of ASME Code Class 1, 2, and 3 components. These regulations ensure the structural integrity and continued long term maintenance of ASME Code Class 1, 2, and 3 components, pumpsand valves. The proposed relocated TSs are not required to be in TSs under 10 CFR 50.36 and do notmeet any of the four criteria. They are not needed to obviate the possibility that an abnormalsituation or event will give rise to an immediate threat to the public health and safety. Inaddition, the NRC staff finds that sufficient regulatory controls exist under the regulations citedabove to maintain the effect of the provisions in these specifications. The NRC staff has alsoconcluded that appropriate controls have been established for the specification, information,and requirements that are being relocated to the Pilgrim UFSAR. This is the subject of a licensing commitment established in the licensee's submittal on December 14, 2004, as supplemented on August 30, 2006. Following implementation, the NRC will audit the removedprovisions to ensure that an appropriate level of control has been achieved. The NRC staff has concluded that, in accordance with 10 CFR 50.36, sufficient regulatorycontrols exist under the regulations, particularly 10 CFR 50.59. Accordingly, these specifications, information, and requirements, as described in detail in this SE, may be relocated from Pilgrim TSs and placed in the Pilgrim UFSAR. | | 3.2 Proposed Changes to the Pilgrim TS Requirements The structural integrity requirements of TS 3.6.G and the SR 4.6.G, will be relocated to the Pilgrim UFSAR Appendix B.2. Therefore, any changes to these requirements will be strictly controlled by the provisions of 10 CFR 50.59, as well as 10 CFR 50.55a(g). |
| | 3.3 Staff Evaluation The safety basis for establishing programmatic requirements on structural integrity in TSs relates to prevention of component degradation and continued long-term maintenance of acceptable structural conditions. Therefore, structural integrity of safety systems are not operational limits that are an initial assumption of any DBA or transient analysis. |
| | 10 CFR 50.55a, Codes and standards specify the ASME Code requirements for plant operations, maintenance and testing of ASME Code Class 1, 2, and 3 safety-related components. Each operating license for a boiling or pressurized water-cooled nuclear power facility is subject to the conditions in paragraphs (f) and (g) of 10 CRF 50.55a. |
| | Pilgrim TS 3.13 establishes the programmatic elements for conducting inservice testing (IST) of ASME Code Class 1, 2, and 3 pumps and valves. This TS provides the required frequencies for performing IST activities which is consistent with the STS Section 5.5.7, Inservice Testing Program. Testing requirements for ASME Code 1, 2, and 3 pumps and valves are defined in 10 CFR 50.55a(f). 10 CFR 50.55(a)(g) provides the regulatory requirements for performing ISI of ASME Code Class 1, 2, and 3 components. These regulations ensure the structural integrity |
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| ==4.0STATE CONSULTATION==
| | and continued long term maintenance of ASME Code Class 1, 2, and 3 components, pumps and valves. |
| In accordance with the Commission's regulations, the Massachusetts State official was notifiedof the proposed issuance of the amendment. The State official had no comments. | | The proposed relocated TSs are not required to be in TSs under 10 CFR 50.36 and do not meet any of the four criteria. They are not needed to obviate the possibility that an abnormal situation or event will give rise to an immediate threat to the public health and safety. In addition, the NRC staff finds that sufficient regulatory controls exist under the regulations cited above to maintain the effect of the provisions in these specifications. The NRC staff has also concluded that appropriate controls have been established for the specification, information, and requirements that are being relocated to the Pilgrim UFSAR. This is the subject of a licensing commitment established in the licensees submittal on December 14, 2004, as supplemented on August 30, 2006. Following implementation, the NRC will audit the removed provisions to ensure that an appropriate level of control has been achieved. |
| | The NRC staff has concluded that, in accordance with 10 CFR 50.36, sufficient regulatory controls exist under the regulations, particularly 10 CFR 50.59. Accordingly, these specifications, information, and requirements, as described in detail in this SE, may be relocated from Pilgrim TSs and placed in the Pilgrim UFSAR. |
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| ==5.0ENVIRONMENTAL CONSIDERATION== | | ==4.0 STATE CONSULTATION== |
| The amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff hasdetermined that the amendment involves no significant increase in the amounts, and nosignificant change in the types, of any effluents that may be released offsite, and that there isno significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (70 FR 9991; March 1, 2005). Accordingly, the amendment meets the eligibility criteria forcategorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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| ==6.0CONCLUSION==
| | In accordance with the Commission's regulations, the Massachusetts State official was notified of the proposed issuance of the amendment. The State official had no comments. |
| The Commission has concluded, based on the considerations discussed above, that: (1) thereis reasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical to thecommon defense and security or to the health and safety of the public.Principal Contributor: J. Shea, C. Schulten Date: September 14, 2006 Pilgrim Nuclear Power Station cc:
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| Regional Administrator, Region IU. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415Senior Resident InspectorU. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Post Office Box 867 Plymouth, MA 02360Chairman, Board of Selectmen11 Lincoln Street Plymouth, MA 02360ChairmanNuclear Matters Committee Town Hall 11 Lincoln Street Plymouth, MA 02360Chairman, Duxbury Board of SelectmenTown Hall 878 Tremont Street Duxbury, MA 02332Office of the CommissionerMassachusetts Department of Environmental Protection One Winter Street Boston, MA 02108Office of the Attorney GeneralOne Ashburton Place 20th Floor Boston, MA 02108MA Department of Public HealthRadiation Control Program Schrafft Center, Suite 1M2A 529 Main Street Charlestown, MA 02129Secretary of Public SafetyExecutive Office of Public Safety One Ashburton Place Boston, MA 02108 Director, Massachusetts EmergencyManagement Agency Attn: James Muckerheide 400 Worcester Road Framingham, MA 01702-5399Mr. William D. MeinertNuclear Engineer Massachusetts Municipal Wholesale Electric Company
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| P.O. Box 426 Ludlow, MA 01056-0426Mr. Kevin H. BronsonGeneral Manager, Plant Operations Entergy Nuclear Operations, Inc.
| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| Pilgrim Nuclear Power Station 600 Rocky Hill RoadPlymouth, MA 02360-5508Mr. Michael A. BalduzziSite Vice President Entergy Nuclear Operations, Inc.
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| Pilgrim Nuclear Power Station 600 Rocky Hill RoadPlymouth, MA 02360-5508Mr. Stephen J. BethayDirector, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
| | The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (70 FR 9991; March 1, 2005). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. |
| Pilgrim Nuclear Power Station 600 Rocky Hill RoadPlymouth, MA 02360-5508Mr. Bryan S. FordManager, Licensing Entergy Nuclear Operations, Inc.
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| Pilgrim Nuclear Power Station 600 Rocky Hill RoadPlymouth, MA 02360-5508
| | ==6.0 CONCLUSION== |
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| | 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: J. Shea, C. Schulten Date: September 14, 2006 |
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| Pilgrim Nuclear Power Station cc: | | Pilgrim Nuclear Power Station cc: |
| Mr. Gary J. Taylor Chief Executive Officer Entergy Operations 1340 Echelon Parkway Jackson, MS 39213Mr. John T. HerronSr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
| | Regional Administrator, Region I Secretary of Public Safety U. S. Nuclear Regulatory Commission Executive Office of Public Safety 475 Allendale Road One Ashburton Place King of Prussia, PA 19406-1415 Boston, MA 02108 Senior Resident Inspector Director, Massachusetts Emergency U. S. Nuclear Regulatory Commission Management Agency Pilgrim Nuclear Power Station Attn: James Muckerheide Post Office Box 867 400 Worcester Road Plymouth, MA 02360 Framingham, MA 01702-5399 Chairman, Board of Selectmen Mr. William D. Meinert 11 Lincoln Street Nuclear Engineer Plymouth, MA 02360 Massachusetts Municipal Wholesale Electric Company Chairman P.O. Box 426 Nuclear Matters Committee Ludlow, MA 01056-0426 Town Hall 11 Lincoln Street Mr. Kevin H. Bronson Plymouth, MA 02360 General Manager, Plant Operations Entergy Nuclear Operations, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601Mr. Oscar LimpiasVice President, Engineering Entergy Nuclear Operations, Inc.
| | Chairman, Duxbury Board of Selectmen Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 878 Tremont Street Plymouth, MA 02360-5508 Duxbury, MA 02332 Mr. Michael A. Balduzzi Office of the Commissioner Site Vice President Massachusetts Department of Entergy Nuclear Operations, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601Mr. Christopher SchwarzVice President, Operations Support Entergy Nuclear Operations, Inc.
| | Environmental Protection Pilgrim Nuclear Power Station One Winter Street 600 Rocky Hill Road Boston, MA 02108 Plymouth, MA 02360-5508 Office of the Attorney General Mr. Stephen J. Bethay One Ashburton Place Director, Nuclear Safety Assurance 20th Floor Entergy Nuclear Operations, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601Mr. John F. McCannDirector, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
| | Boston, MA 02108 Pilgrim Nuclear Power Station 600 Rocky Hill Road MA Department of Public Health Plymouth, MA 02360-5508 Radiation Control Program Schrafft Center, Suite 1M2A Mr. Bryan S. Ford 529 Main Street Manager, Licensing Charlestown, MA 02129 Entergy Nuclear Operations, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601
| | Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 |
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| |
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| Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
| | Pilgrim Nuclear Power Station cc: |
| 440 Hamilton Avenue White Plains, NY 10601Mr. Michael J. ColombDirector of Oversight Entergy Nuclear Operations, Inc. | | Mr. Gary J. Taylor Mr. Michael J. Colomb Chief Executive Officer Director of Oversight Entergy Operations Entergy Nuclear Operations, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601Assistant General CounselEntergy Nuclear Operations, Inc.
| | 1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. John T. Herron Assistant General Counsel Sr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc. |
| 440 Hamilton Avenue White Plains, NY 10601Ms. Stacey LousteauTreasury Department Entergy Services, Inc. | | Entergy Nuclear Operations, Inc. 440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Ms. Stacey Lousteau Mr. Oscar Limpias Treasury Department Vice President, Engineering Entergy Services, Inc. |
| 639 Loyola Avenue New Orleans, LA 70113Mr. James Sniezek5486 Nithsdale Drive Salisbury, MD 21801-2490Mr. Michael D. Lyster5931 Barclay Lane Naples, FL 34110-7306Mr. Garrett D. Edwards814 Waverly Road Kennett Square, PA 19348}} | | Entergy Nuclear Operations, Inc. 639 Loyola Avenue 440 Hamilton Avenue New Orleans, LA 70113 White Plains, NY 10601 Mr. James Sniezek Mr. Christopher Schwarz 5486 Nithsdale Drive Vice President, Operations Support Salisbury, MD 21801-2490 Entergy Nuclear Operations, Inc. |
| | 440 Hamilton Avenue Mr. Michael D. Lyster White Plains, NY 10601 5931 Barclay Lane Naples, FL 34110-7306 Mr. John F. McCann Director, Nuclear Safety Assurance Mr. Garrett D. Edwards Entergy Nuclear Operations, Inc. 814 Waverly Road 440 Hamilton Avenue Kennett Square, PA 19348 White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc. |
| | 440 Hamilton Avenue White Plains, NY 10601}} |
Letter Sequence Approval |
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MONTHYEARML0624904892006-08-30030 August 2006 Technical Specification Amendment Request to Relocate Specifications Not Meeting the Criteria of 10 CFR 50.36(c)(2)(ii), Revision 1, Project stage: Meeting ML0622803042006-09-14014 September 2006 Issuance of Amendment Relocation of Technical Specifications Project stage: Approval 2006-08-30
[Table View] |
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Category:Letter
MONTHYEARL-24-002, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2024-02-0202 February 2024 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML23342A1182024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23334A1822023-11-30030 November 2023 Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary November 2021 Through October 2023 L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) L-23-011, 10 CFR 72.48 Biennial Change Summary Report2023-10-27027 October 2023 10 CFR 72.48 Biennial Change Summary Report IR 05000293/20234012023-08-31031 August 2023 NRC Inspection Report No. 05000293/2023401 & 2023001 (Cover Letter Only) IR 05000293/20230022023-08-0404 August 2023 NRC Inspection Report No. 05000293/2023002 L-23-008, Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI)2023-05-23023 May 2023 Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI) ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating Report, January 1 Through December 31, 2022 ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML23069A2782023-03-13013 March 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1 Subsequent License Renewal Application ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000293/20220042023-02-15015 February 2023 NRC Inspection Report No. 05000293/2022004 ML22356A0712023-01-31031 January 2023 Issuance of Exemption for Pilgrim Nuclear Power Station ISFSI Regarding Annual Radioactive Effluent Release Report - Cover Letter ML22347A2782022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 L-22-041, Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension2022-12-0909 December 2022 Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension IR 05000293/20220032022-11-18018 November 2022 NRC Inspection Report No. 05000293/2022003 L-22-036, Decommissioning Trust Fund Agreement2022-11-0808 November 2022 Decommissioning Trust Fund Agreement ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22266A1922022-09-23023 September 2022 and Pilgrim Nuclear Power Station - Request to Withdraw Prior Submissions from NRC Consideration ML22272A0352022-09-22022 September 2022 S. Lynch-Benttinen Letter Regarding U.S. Citizen Intent to Sue U.S. Fish and Wildlife and NOAA Fisheries Representing the Endangered Species (Na Right Whale) Which Will Be Adversely Affected by Holtec International Potential Actions ML22269A4202022-09-22022 September 2022 Citizen Lawsuit ML22241A1122022-08-29029 August 2022 Request for Exemption from 10 CFR 72.212(a)(2), (b)(2), (b)(3), (b)(4), (B)(5)(i), (b)(11), and 72.214 for Pilgrim ISFSI Annual Radioactive Effluent Release Report IR 05000293/20220022022-08-12012 August 2022 NRC Inspection Report No. 05000293/2022002 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22193A1662022-07-28028 July 2022 LTR-22-0154-1 - Heather Govern, VP, Clean Air and Water Program, Et Al., Letter Regarding Radioactive Wastewater Disposal from the Pilgrim Nuclear Power Station (Docket No. 05000293) ML22175A1732022-07-28028 July 2022 LTR-22-0153-1 - Response Letter to D. Turco, Cape Downwinders, from A. Roberts, NRC, Regarding Holtec-Pilgrim Plans to Dump One Million Gallons of Radioactive Waste Into Cape Cod Bay ML22154A4882022-06-0101 June 2022 Letter from Conservation Law Foundation Regarding Irradiated Water Release from Pilgrim ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22136A2602022-05-16016 May 2022 Submittal of Annual Radiological Environmental Operating Report for January 1 Through December 31, 2021 ML22136A2572022-05-16016 May 2022 Submittal of Annual Radioactive Effluent Release Report for January 1 Through December 31, 2021 ML22102A0932022-05-12012 May 2022 LTR-22-0067 Response to Matthew P. Levesque, President, Barnstable Town Council Regarding Irradiated Water Release from Pilgrim IR 05000293/20220012022-05-11011 May 2022 NRC Inspection Report No. 05000293/2022001 ML22104A0542022-04-30030 April 2022 LTR-22-0093 Response to Sheila Lynch-Benttinen, Regarding Irradiated Water Release from Pilgrim L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22152A2592022-04-25025 April 2022 Zaccagnini Letter Dated 04/25/22 ML22152A2642022-04-19019 April 2022 Flynn Letter Dated 04/19/22 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22130A6762022-03-14014 March 2022 Decola Ltr Dtd 03/14/22 Re Potential Discharge of Radioactive Water from Pilgrim Nuclear Power Station ML22041B0762022-03-0707 March 2022 03-07-22 - Letter to the Honorable William R. Keating, Responds to Letter Regarding Proposed Release of Irradiated Water at Pilgrim Nuclear Power Station Into Cape Cod Bay ML22054A2962022-02-23023 February 2022 Annual ISFSI Radioactive Effluent Release Report for 2021 2024-02-02
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML21251A1732021-10-21021 October 2021 Enclosure 1 - Pilgrim Amendment No. 257 ISFSI Only Emergency Plan ML21203A0482021-08-24024 August 2021 License Amendment No. 256 ML21217A1752021-08-0505 August 2021 Amendment No 255 Pilgrim Independent Spent Fuel Storage Installation (ISFSI) Only Physical Security Plan - Public Version ML21103A0562021-05-12012 May 2021 Amendment Pilgrim Ps -Alternative Measures Rev 20 ML20335A1832020-12-0101 December 2020 Amendment Pilgrim Ps ISFSI to Incorporate ISFSI II ML20328A2972020-12-0101 December 2020 Amendment No. 253 - Non-Safeguards Version ML19274C6742020-01-0202 January 2020 Issuance of Amendment No. 251, Revise Emergency Plan and Emergency Action Level Scheme to Address Permanently Defueled Condition ML19276C4202020-01-0202 January 2020 Issuance of Amendment No. 252, Request to Remove Cyber Security Plan Requirements for the Permanently Defueled Condition ML19275E4252019-10-28028 October 2019 Issuance of Amendment No. 250, Revise Technical Specifications to Permanently Defueled TS and Revise Facility License for Permanently Defueled Condition ML19235A0502019-08-27027 August 2019 Issuance of Amendment No. 249 Order Approving Direct Transfer of Renewed Facility Operating License and ISFSI General License and Conforming Amendment ML19170A1012019-08-22022 August 2019 Letter, Order Approving Direct and Indirect Transfer of Renewed Facility Operating License to Holtec Pilgrim, LLC, Owner and Holtec Decommissioning International, LLC, Operator ML18284A3752018-11-30030 November 2018 Issuance of Amendment No. 248, Revise Site Emergency Plan for On-Shift and Emergency Response Organization Staffing to Address Permanently Defueled Condition ML18295A0252018-11-16016 November 2018 Correction to Remove Technical Specification Pages from Authority File Related to Amendment Nos. 169 and 177 ML17066A1302017-07-10010 July 2017 Pilgrim Nuclear Power Station - Issuance of Amendment No. 246, Revise Administrative Controls Section of Technical Specifications to Change Staffing and Training Requirements for Permanently Defueled Condition (CAC No. MF9304) ML16250A2232016-10-28028 October 2016 Issuance of Amendments Proposed Changes to Emergency Plan to Revise Training for the on - Shift Chemistry Technician ML16082A4602016-06-0606 June 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule ML15114A0212015-05-0606 May 2015 Issuance of Amendment Regarding the Minimum Critical Power Ratio License Amendment Request ML14272A0702015-03-12012 March 2015 Issuance of Amendment 242 Re Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open Transient ML14336A6612014-12-11011 December 2014 Issuance of Amendment Regarding Cyber Security Plan Implementation Schedule Milestone 8 (Tac No. MF3482) ML14295A6852014-10-31031 October 2014 Issuance of Amendment Regarding Heavy Loads to Facilitate Dry Storage Handling Operations ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML12261A1302012-11-13013 November 2012 Issuance of Amendments to Renewed Facility Operating License Changes in Cyber Security Plan Implementation Milestone ML1220100482012-08-0707 August 2012 Issuance of Amendment No. 237 Revision to Condensate Storage Tank Low Level Trip Setpoint ML0910404232012-05-29029 May 2012 Issuance of Renewed License for Pilgrim Nuclear Generating Station ML11152A0432011-07-22022 July 2011 License Amendment, Cyber Security Plan ML1106500092011-03-28028 March 2011 Issuance of Amendment No. 235 Revised Technical Specifications for Setpoint and Setpoint Tolerance Increases for Safety Relief Valves and Spring Safety Valves ML0906402242009-03-26026 March 2009 License Amendment, Revised Technical Specifications (TS) Section 2.1.2, Safety Limit Minimum Critical Power Ratio (SLMCPR) for Two-Loop and Single-Loop Operation ML0815703662008-11-20020 November 2008 License Amendment, Issuance of Amendment Adoption of TSTF-448, Revision 3, Control Room Envelope Habitability ML0727503942007-11-0505 November 2007 License Amendment, Issuance of Amendment Control Rod Operability, Scram Insertion Time, and Control Rod Accumulator Requirements ML0723400092007-08-23023 August 2007 Revised License Pages of Facility Operating License DPR-35 B.5.b ML0708711652007-05-14014 May 2007 Issuance of Amendment Adoption of Technical Specification Task Force (TSTF) Change TSTF-372, the Addition of Limiting Condition for Operation (LCO) 3.0.8 on the Inoperability of Snubbers ML0707404192007-04-25025 April 2007 License Amendment, Issuance of Amendment Single Control Rod Withdrawal Allowances ML0705303842007-03-26026 March 2007 License Amendment, Issuance of Amendment Extension of Pressure-Temperature Limits Specified in Technical Specifications ML0705306462007-03-26026 March 2007 Issuance of License Amendment 226 Adoption of Technical Specification Task Force (TSTF) Change TSTF-484 Use of TS 3.10.1 for Scram Time Testing Activities. ML0624303372006-09-20020 September 2006 License Amendment 225 Regarding Revised Reactor Coolant System Leakage Detection Instrumentation Requirements and Actions ML0622803042006-09-14014 September 2006 Issuance of Amendment Relocation of Technical Specifications ML0617200682006-08-0909 August 2006 Issuance of License Amendment 223 Regarding Administrative Changes and Relocation of Certain Technical Specification Responsibilities ML0618400322006-08-0404 August 2006 Issuance of License Amendment 222 Deletion of Requirement Related to NRC Approval of Engineering Evaluation for Elevated Relief Valve Discharge Pipe Temperature ML0606000402006-04-13013 April 2006 Issuance of Amendment Removal of Main Steam Isolation Valve Twice Per Week Testing Surveillance Requirement ML0607402142006-04-13013 April 2006 License Amendment 221 Regarding Revised Rod Worth Minmizer Bypass Allowances ML0601701192006-04-12012 April 2006 Issuance of Amendment Single Recirculation Loop Operation ML0531404332006-04-10010 April 2006 Issuance of Amendment Revised Applicability for Containment Oxygen and Differential Pressure Limits ML0518700032005-08-29029 August 2005 Issuance of License Amendment 217, Surveillance Frequency Improvements ML0518702572005-07-29029 July 2005 License Amendment 216 Revised Action for Scram Discharge Volume Vent and Drain Valves ML0501804932005-03-16016 March 2005 License Amendment No. 211, Revise Reactor Vessel Hydrostatic and Leak Testing Requirements ML0500504862005-02-0202 February 2005 Issuance of Amendment Changes to Technical Specifications Table 3.2.C-1 ML0423001372005-01-0505 January 2005 License Amendment, Revision to the Reactor Pressure Vessel Material Surveillance Program ML0434902432004-12-27027 December 2004 Issuance of Amendment Engineering Evaluation Submitted Pursuant to Technical Specifications Section 3.6.D.3 and 3.6.D.4 ML0419704502004-08-17017 August 2004 License Amendment, Issuance of Amendment Re.: Multiple Control Rod Removal, Limiting Condition for Operation 3/4.10.D ML0411000092004-07-22022 July 2004 License Amendment, Eliminate Requirements for Hydrogen Analyzers 2021-08-05
[Table view] Category:Safety Evaluation
MONTHYEARML21217A1752021-08-0505 August 2021 Amendment No 255 Pilgrim Independent Spent Fuel Storage Installation (ISFSI) Only Physical Security Plan - Public Version ML20328A2972020-12-0101 December 2020 Amendment No. 253 - Non-Safeguards Version ML19276C4202020-01-0202 January 2020 Issuance of Amendment No. 252, Request to Remove Cyber Security Plan Requirements for the Permanently Defueled Condition ML19274C6742020-01-0202 January 2020 Issuance of Amendment No. 251, Revise Emergency Plan and Emergency Action Level Scheme to Address Permanently Defueled Condition ML19142A0432019-12-18018 December 2019 Letter and Safety Evaluation, Exemption to Allow Reduced Emergency Planning Requirements; Revise Radiological Emergency Response Plan Consistent with Permanently Defueled Reactor ML19235A0502019-08-27027 August 2019 Issuance of Amendment No. 249 Order Approving Direct Transfer of Renewed Facility Operating License and ISFSI General License and Conforming Amendment ML19170A2502019-08-22022 August 2019 Enclosure 3, Safety Evaluation for Direct and Indirect Transfer of Renewed Facility Operating License to Holtec Pilgrim, LLC, Owner and Holtec Decommissioning International, LLC, Operator (L-2018-LLO-0003) ML19122A1992019-06-11011 June 2019 Review of Spent Fuel Management Plan ML18284A3752018-11-30030 November 2018 Issuance of Amendment No. 248, Revise Site Emergency Plan for On-Shift and Emergency Response Organization Staffing to Address Permanently Defueled Condition ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML17066A1302017-07-10010 July 2017 Pilgrim Nuclear Power Station - Issuance of Amendment No. 246, Revise Administrative Controls Section of Technical Specifications to Change Staffing and Training Requirements for Permanently Defueled Condition (CAC No. MF9304) ML17093A8942017-05-12012 May 2017 Pilgrim Nuclear Power Station - Relief Requests PNPS-ISI-001 and PNPS-ISI-002, Relief from ASME Code Volumetric Examination Requirements for the Fourth 10-Year Inservice Inspection Interval (CAC Nos. MF8092 and MF8093) ML17058A3252017-04-12012 April 2017 Approval of Certified Fuel Handler Training and Retraining Program ML16250A2232016-10-28028 October 2016 Issuance of Amendments Proposed Changes to Emergency Plan to Revise Training for the on - Shift Chemistry Technician ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16082A4602016-06-0606 June 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16124B0872016-05-0303 May 2016 E-mail Review of Safety Evaluation for Proposed Alternative Relief Request No. PRR-51 ML16042A2912016-03-15015 March 2016 Issuance of Proposed Alternative Relief Request PRR-51, Relief from the Requirements of the ASME Code ML16008B0772016-03-0303 March 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML15338A3092016-01-0505 January 2016 Relief Request PRR-50, Relief from the Requirement of the ASME Code, Implementation of Code Case N-702 ML15166A4012015-06-19019 June 2015 Request for Alternative PRR-26 for the Fifth 10-year Inservice Inspection Interval ML15114A0212015-05-0606 May 2015 Issuance of Amendment Regarding the Minimum Critical Power Ratio License Amendment Request ML15103A0692015-04-21021 April 2015 Relief Request PRR-24 Regarding Nozzle-to-Vessel Welds and Nozzle Inner Radii Examination ML15084A0252015-03-23023 March 2015 Non-Proprietary - Safety Evaluation - Fourth 10-Year Interval Inservice Inspection - Request for Relief PRR-24 ML14272A0702015-03-12012 March 2015 Issuance of Amendment 242 Re Revision to Technical Specification 2.1, Safety Limits to Resolve Pressure Regulator Fail-Open Transient ML14336A6612014-12-11011 December 2014 Issuance of Amendment Regarding Cyber Security Plan Implementation Schedule Milestone 8 (Tac No. MF3482) ML14295A6852014-10-31031 October 2014 Issuance of Amendment Regarding Heavy Loads to Facilitate Dry Storage Handling Operations ML14210A2662014-08-0808 August 2014 Arkansas, Units 1 & 2, Big Rock Point, James A. Fitzpatrick, Grand Gulf, Unit 1, Indian Point, Units 1, 2 & 3, Palisades, Pilgrim, River Bend, Unit 1, Vermont Yankee, Waterford, Safety Evaluation Quality Assurance Program Manual, Rev. 24 & ML14198A1572014-08-0101 August 2014 Relief Requests PR-03 and PR-05 Regarding the Inservice Testing Program (Tac MF0370) ML14083A6312014-03-27027 March 2014 Relief Request PRR-22 Regarding a Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds ML13149A2152013-05-29029 May 2013 Correction to Staff Assessment Letter to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13127A1792013-05-21021 May 2013 Staff Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML12261A1302012-11-13013 November 2012 Issuance of Amendments to Renewed Facility Operating License Changes in Cyber Security Plan Implementation Milestone ML1220100482012-08-0707 August 2012 Issuance of Amendment No. 237 Revision to Condensate Storage Tank Low Level Trip Setpoint ML12174A1472012-07-10010 July 2012 Safety Evaluation for Relief Request PRR-21, Rev 4, to Install a Weld Overlay on RPV-n14-1 Standby Liquid Control Safe-End Nozzle Weld at Pilgrim ML11152A0432011-07-22022 July 2011 License Amendment, Cyber Security Plan ML1106500092011-03-28028 March 2011 Issuance of Amendment No. 235 Revised Technical Specifications for Setpoint and Setpoint Tolerance Increases for Safety Relief Valves and Spring Safety Valves ML1100502982011-01-26026 January 2011 Issuance of Amendment Regarding Revised Pressure and Temperature (P-T) Limit Curves and Relocation of P-T Curves to the PTLR ML1022901632010-08-25025 August 2010 Relief Request PRR-20, Alternative Examination Requirements for Nozzle-To-Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 - Pilgrim Nuclear Power Station ML0936208072010-01-22022 January 2010 Cover Letter, (Non-Proprietary) Order Extending the Effectiveness of the Approval of the Indirect Transfer of Facility Operating Licenses for Big Rock Point, Fitzpatrick, Indian Point, Palisades, Pilgrim, and Vermont Yankee Nuclear Power St ML0936208952010-01-22022 January 2010 Safety Evaluation,(Non-Proprietary) Order Extending the Effectiveness of the Approval of the Indirect Transfer of Facility Operating Licenses for Big Rock Point, Fitzpatrick, Indian Point,Palisades,Pilgrim, and Vermont Yankee Nuclear Power ML0928706472009-10-29029 October 2009 Request for Threshold Determination Under 10 CFR 50.80-Big Rock Point, James A. FitzPatrick Nuclear Power Plant, Indian Point Nuclear Generating Nos. 1, 2 and 3, Palisades, Pilgrim, Vermont Yankee ML0927301372009-10-0909 October 2009 Safety Evaluation by the Office of Nuclear Reactor Regulation Corporate Restructuring Conversion of Companies and Stock Split-Off by Entergy Nuclear Operations, Inc and Subsidiaries ML0923705492009-09-11011 September 2009 Relief Request (PRR)19, Install a Weld Overlay on Jet Pump Instrumentation Nozzle Weld RPV-N9A-1- Pilgrim Nuclear Power Station ML0911304562009-04-30030 April 2009 Relief Request ISI-2008-1, Use of Later ASME Section XI Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Destructive Testing Activities-Pilgrim Nuclear Power Station ML0906402242009-03-26026 March 2009 License Amendment, Revised Technical Specifications (TS) Section 2.1.2, Safety Limit Minimum Critical Power Ratio (SLMCPR) for Two-Loop and Single-Loop Operation ML0815703662008-11-20020 November 2008 License Amendment, Issuance of Amendment Adoption of TSTF-448, Revision 3, Control Room Envelope Habitability 2021-08-05
[Table view] |
Text
September 14, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE:
RELOCATION OF TECHNICAL SPECIFICATIONS (TAC NO. MC5421)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 224 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 14, 2004, which was subsequently revised by letter dated August 30, 2006. Specifically, this amendment relocates TSs structural integrity requirements to the Pilgrim Final Safety Analysis Report.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register Notice.
Sincerely,
/RA/
James J. Shea, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
- 1. Amendment No. 224 to License No. DPR-35
- 2. Safety Evaluation cc w/encls: See next page
September 14, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE:
RELOCATION OF TECHNICAL SPECIFICATIONS (TAC NO. MC5421)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 224 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 14, 2004, which was subsequently revised by letter dated August 30, 2006. Specifically, this amendment relocates TSs structural integrity requirements to the Pilgrim Final Safety Analysis Report.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register Notice.
Sincerely,
/RA/
James J. Shea, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
- 1. Amendment No. 224 to License No. DPR-35
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1-1 RPowell, RI RidsOGC RP CSchulten PDI-I R/F RidsNrrLASLittle RidsNrrPMJShea GHill (2)
RidsAcrsAcnwMail Accession Number: ML062280304 OFFICE LPL1-1/PM LPL1-1/LA ITSB/BC OGC LPL1-1/BC NAME JShea SLittle TKobetz SUttal RLaufer DATE 8/30/06 8/31/06 9/01/06 9/11/06 9/12/06 OFFICIAL RECORD COPY
ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 224 License No. DPR-35
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by Entergy Nuclear Operations, Inc. (the licensee) dated December 14, 2004, subsequently revised by letter dated August 30, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 license and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 224, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: September 14, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 224 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 3 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert ii ii 3/4.6-8 3/4.6-8
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 224 TO FACILITY OPERATING LICENSE NO. DPR-35 ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated December 14, 2004 (ADAMS Accession No. ML043560152) Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the Pilgrim Nuclear Power Station (Pilgrim) Technical Specifications (TSs) which was subsequently revised by letter dated August 30, 2006 (ADAMS Accession No. ML062490489). The August 30, 2006, letter reduced the scope of the application as originally noticed. Hence, there is no change to the NRC staffs original proposed no significant hazards consideration determination (70 FR 9991; March 1, 2005). This amendment as revised would remove the TSs associated with the Pilgrim structural integrity requirements and relocates these requirements to the Pilgrim updated final safety analysis report (UFSAR).
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act of 1954, as amended (the Act), requires applicants for nuclear plant operating licenses to include TSs as part of the license. The Commissions regulatory requirements related to the content of TS are set forth in Title 10 of the Code of Federal Regulations (10 CFR 50.36), Technical specifications. The regulation requires that TSs include items in five specific categories, including (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs);
(3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.
However, the regulation does not specify the particular requirements to be included in a plants TSs. The regulation also specifies four criteria to be used in determining whether a particular item is required to be included in a LCO (10 CFR 50.36(i)(2)(ii)), as follows: Criterion 1 -
Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; Criterion 2 - A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident (DBA) or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; Criterion 3 - A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier, and Criterion 4 - A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
The Nuclear Regulatory Commission (NRC) staff and nuclear steam supply owners groups developed the Standard Technical Specifications (STS) that established models of the Commissions policy for TSs, and improved the format and clarity of the specifications.
NUREG-1433, STS General Electric Plants, BWR/4, Revision 3, was approved and issued for use by the NRC on June 30, 2004. Many Nuclear Power Plants such as Pilgrim have relocated various specifications that are not required explicitly by 10 CFR 50.36 to other licensing basis documents such as a plants Final Safety Analysis Report utilizing the STS as a model.
The NRC staff reviewed the licensee proposed change for compliance with 10 CFR 50.36 and with the precedent as established in the STS.
3.0 TECHNICAL EVALUATION
3.1 Current Pilgrim TS Requirements TS 3.6.G.1 and the associated surveillance requirements (SR) 4.6.G provide general programmatic elements for inservice inspections (ISI) of the structural integrity of Pilgrims primary system boundary. The TS requires the primary system boundary to be maintained as required by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI, Rules for ISI of Nuclear Power Plant Components, Articles IWA, IWB, IWC, IWD, IWF, and mandatory appendices as required by 10 CFR50.55a(g), except where specific relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i). The SR simply states that the ISI of components shall be performed in accordance with the Pilgrim ISI program. The results of the inspections shall be evaluated and reviewed with the NRC.
3.2 Proposed Changes to the Pilgrim TS Requirements The structural integrity requirements of TS 3.6.G and the SR 4.6.G, will be relocated to the Pilgrim UFSAR Appendix B.2. Therefore, any changes to these requirements will be strictly controlled by the provisions of 10 CFR 50.59, as well as 10 CFR 50.55a(g).
3.3 Staff Evaluation The safety basis for establishing programmatic requirements on structural integrity in TSs relates to prevention of component degradation and continued long-term maintenance of acceptable structural conditions. Therefore, structural integrity of safety systems are not operational limits that are an initial assumption of any DBA or transient analysis.
10 CFR 50.55a, Codes and standards specify the ASME Code requirements for plant operations, maintenance and testing of ASME Code Class 1, 2, and 3 safety-related components. Each operating license for a boiling or pressurized water-cooled nuclear power facility is subject to the conditions in paragraphs (f) and (g) of 10 CRF 50.55a.
Pilgrim TS 3.13 establishes the programmatic elements for conducting inservice testing (IST) of ASME Code Class 1, 2, and 3 pumps and valves. This TS provides the required frequencies for performing IST activities which is consistent with the STS Section 5.5.7, Inservice Testing Program. Testing requirements for ASME Code 1, 2, and 3 pumps and valves are defined in 10 CFR 50.55a(f). 10 CFR 50.55(a)(g) provides the regulatory requirements for performing ISI of ASME Code Class 1, 2, and 3 components. These regulations ensure the structural integrity
and continued long term maintenance of ASME Code Class 1, 2, and 3 components, pumps and valves.
The proposed relocated TSs are not required to be in TSs under 10 CFR 50.36 and do not meet any of the four criteria. They are not needed to obviate the possibility that an abnormal situation or event will give rise to an immediate threat to the public health and safety. In addition, the NRC staff finds that sufficient regulatory controls exist under the regulations cited above to maintain the effect of the provisions in these specifications. The NRC staff has also concluded that appropriate controls have been established for the specification, information, and requirements that are being relocated to the Pilgrim UFSAR. This is the subject of a licensing commitment established in the licensees submittal on December 14, 2004, as supplemented on August 30, 2006. Following implementation, the NRC will audit the removed provisions to ensure that an appropriate level of control has been achieved.
The NRC staff has concluded that, in accordance with 10 CFR 50.36, sufficient regulatory controls exist under the regulations, particularly 10 CFR 50.59. Accordingly, these specifications, information, and requirements, as described in detail in this SE, may be relocated from Pilgrim TSs and placed in the Pilgrim UFSAR.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Massachusetts State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (70 FR 9991; March 1, 2005). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The 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: J. Shea, C. Schulten Date: September 14, 2006
Pilgrim Nuclear Power Station cc:
Regional Administrator, Region I Secretary of Public Safety U. S. Nuclear Regulatory Commission Executive Office of Public Safety 475 Allendale Road One Ashburton Place King of Prussia, PA 19406-1415 Boston, MA 02108 Senior Resident Inspector Director, Massachusetts Emergency U. S. Nuclear Regulatory Commission Management Agency Pilgrim Nuclear Power Station Attn: James Muckerheide Post Office Box 867 400 Worcester Road Plymouth, MA 02360 Framingham, MA 01702-5399 Chairman, Board of Selectmen Mr. William D. Meinert 11 Lincoln Street Nuclear Engineer Plymouth, MA 02360 Massachusetts Municipal Wholesale Electric Company Chairman P.O. Box 426 Nuclear Matters Committee Ludlow, MA 01056-0426 Town Hall 11 Lincoln Street Mr. Kevin H. Bronson Plymouth, MA 02360 General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Chairman, Duxbury Board of Selectmen Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 878 Tremont Street Plymouth, MA 02360-5508 Duxbury, MA 02332 Mr. Michael A. Balduzzi Office of the Commissioner Site Vice President Massachusetts Department of Entergy Nuclear Operations, Inc.
Environmental Protection Pilgrim Nuclear Power Station One Winter Street 600 Rocky Hill Road Boston, MA 02108 Plymouth, MA 02360-5508 Office of the Attorney General Mr. Stephen J. Bethay One Ashburton Place Director, Nuclear Safety Assurance 20th Floor Entergy Nuclear Operations, Inc.
Boston, MA 02108 Pilgrim Nuclear Power Station 600 Rocky Hill Road MA Department of Public Health Plymouth, MA 02360-5508 Radiation Control Program Schrafft Center, Suite 1M2A Mr. Bryan S. Ford 529 Main Street Manager, Licensing Charlestown, MA 02129 Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508
Pilgrim Nuclear Power Station cc:
Mr. Gary J. Taylor Mr. Michael J. Colomb Chief Executive Officer Director of Oversight Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. John T. Herron Assistant General Counsel Sr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. 440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Ms. Stacey Lousteau Mr. Oscar Limpias Treasury Department Vice President, Engineering Entergy Services, Inc.
Entergy Nuclear Operations, Inc. 639 Loyola Avenue 440 Hamilton Avenue New Orleans, LA 70113 White Plains, NY 10601 Mr. James Sniezek Mr. Christopher Schwarz 5486 Nithsdale Drive Vice President, Operations Support Salisbury, MD 21801-2490 Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Mr. Michael D. Lyster White Plains, NY 10601 5931 Barclay Lane Naples, FL 34110-7306 Mr. John F. McCann Director, Nuclear Safety Assurance Mr. Garrett D. Edwards Entergy Nuclear Operations, Inc. 814 Waverly Road 440 Hamilton Avenue Kennett Square, PA 19348 White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601