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| | number = ML061430135 | | | number = ML061430135 |
| | issue date = 10/04/2006 | | | issue date = 10/04/2006 |
| | title = Millstone, Unit No. 3, Issuance of License Amendment 234 Deleting Section 2.F to Facility Operating License No. NPF-49 | | | title = Issuance of License Amendment 234 Deleting Section 2.F to Facility Operating License No. NPF-49 |
| | author name = Nerses V | | | author name = Nerses V |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 |
| | addressee name = Christian D A | | | addressee name = Christian D |
| | addressee affiliation = Dominion Nuclear Connecticut, Inc | | | addressee affiliation = Dominion Nuclear Connecticut, Inc |
| | docket = 05000423 | | | docket = 05000423 |
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| =Text= | | =Text= |
| {{#Wiki_filter:October 4, 2006Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. | | {{#Wiki_filter:October 4, 2006 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. |
| Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 | | Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENTRE: DELETING SECTION 2.F TO FACILITY OPERATING LICENSE NO. | | MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: DELETING SECTION 2.F TO FACILITY OPERATING LICENSE NO. |
| NPF-49 (TAC NO. MD1056) | | NPF-49 (TAC NO. MD1056) |
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| ==Dear Mr. Christian:== | | ==Dear Mr. Christian:== |
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| The Commission has issued the enclosed Amendment No. 234 to Facility Operating LicenseNo. NPF-49 for the Millstone Power Station, Unit No. 3., in response to your application datedMarch 28, 2006. This amendment revises Facility Operating License No. NPF-49 by deletingSection 2.F, which specifies reporting of violations of the requirements of Section 2.C of the renewed operating license.A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in theCommission's biweekly Federal Register notice. Sincerely,/RA/Victor Nerses, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-423 | | The Commission has issued the enclosed Amendment No. 234 to Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3., in response to your application dated March 28, 2006. This amendment revises Facility Operating License No. NPF-49 by deleting Section 2.F, which specifies reporting of violations of the requirements of Section 2.C of the renewed operating license. |
| | A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Victor Nerses, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 234 to License No. NPF-49 | | : 1. Amendment No. 234 to License No. NPF-49 |
| : 2. Safety Evaluationcc w/encls: See next page October 4, 2006Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. | | : 2. Safety Evaluation cc w/encls: See next page |
| Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 | | |
| | October 4, 2006 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. |
| | Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENTRE: DELETING SECTION 2.F TO FACILITY OPERATING LICENSE NO. | | MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: DELETING SECTION 2.F TO FACILITY OPERATING LICENSE NO. |
| NPF-49 (TAC NO. MD1056) | | NPF-49 (TAC NO. MD1056) |
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| ==Dear Mr. Christian:== | | ==Dear Mr. Christian:== |
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| The Commission has issued the enclosed Amendment No. 234 to Facility Operating LicenseNo. NPF-49 for the Millstone Power Station, Unit No. 3., in response to your application datedMarch 28, 2006. This amendment revises Facility Operating License No. NPF-49 by deletingSection 2.F, which specifies reporting of violations of the requirements of Section 2.C of the renewed operating license.A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in theCommission's biweekly Federal Register notice. Sincerely,/RA/Victor Nerses, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-423 | | The Commission has issued the enclosed Amendment No. 234 to Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3., in response to your application dated March 28, 2006. This amendment revises Facility Operating License No. NPF-49 by deleting Section 2.F, which specifies reporting of violations of the requirements of Section 2.C of the renewed operating license. |
| | A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | Victor Nerses, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No. 234 to License No. NPF-49 | | : 1. Amendment No. 234 to License No. NPF-49 |
| : 2. Safety Evaluationcc w/encls: See next page DISTRIBUTION | | : 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: |
| :RidsNrrLpl1-2RidsOgcRpRidsRgn1MailCenterPUBLICRidsNrrPMVNersesRidsAcrs AcnwMailCenter LPL1-2 R/FRidsNrrLACRaynorTKobetz RidsNrrDorlGHill (2)Package Accession Number: ML061930080Amendment Accession Number: ML061430135 Tech Specs. Accession Number: ML062790492OFFICELPL1-2/PMLPL1-2/LAITSB/BCOGC/NLOLPL1-2/BC (A)NAMEVNerses:rsaCRaynorTKobetzMZoblerBPooleDATE7/26/067/25/065/18/068/2/068/3/06OFFICIAL RECORD COPY DOMINION NUCLEAR CONNECTICUT, INC.DOCKET NO. 50-423MILLSTONE POWER STATION, UNIT NO. 3AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 234License No. NPF-491.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment filed by Dominion Nuclear Connecticut, Inc. (thelicensee) dated March 28, 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 Title 10 of the Code of FederalRegulations (10 CFR), Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the rules and regulations of the Commission;C.There is reasonable assurance: (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations set forth in 10 CFR Chapter I;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by deleting paragraph 2.F of Facility OperatingLicense No. NPF-49 as indicated in the attachment to this license amendment.3.This license amendment is effective as of its date of issuance and shall be implementedwithin 60 days.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Brooke D. Poole, Acting ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
| | RidsNrrLpl1-2 RidsOgcRp RidsRgn1MailCenter PUBLIC RidsNrrPMVNerses RidsAcrs AcnwMailCenter LPL1-2 R/F RidsNrrLACRaynor TKobetz RidsNrrDorl GHill (2) |
| | Package Accession Number: ML061930080 Amendment Accession Number: ML061430135 Tech Specs. Accession Number: ML062790492 OFFICE LPL1-2/PM LPL1-2/LA ITSB/BC OGC/NLO LPL1-2/BC (A) |
| | NAME VNerses:rsa CRaynor TKobetz MZobler BPoole DATE 7/26/06 7/25/06 5/18/06 8/2/06 8/3/06 OFFICIAL RECORD COPY |
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| | DOMINION NUCLEAR CONNECTICUT, INC. |
| | DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 234 License No. NPF-49 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment filed by Dominion Nuclear Connecticut, Inc. (the licensee) dated March 28, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by deleting paragraph 2.F of Facility Operating License No. NPF-49 as indicated in the attachment to this license amendment. |
| | : 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | Brooke D. Poole, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Changes to the Renewed Operating LicenseDate of Issuance: October 4, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 234 FACILITY OPERATING LICENSE NO. NPF-49DOCKET NO. 50-423Replace the following page of Facility Operating License No. NPF-49 as indicated. The revisedpage is identified by amendment number and contains a marginal line indicating the area of change.Remove PageInsert Page SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO.234 TO FACILITY OPERATINGLICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 | | Changes to the Renewed Operating License Date of Issuance: October 4, 2006 |
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 234 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of Facility Operating License No. NPF-49 as indicated. The revised page is identified by amendment number and contains a marginal line indicating the area of change. |
| | Remove Page Insert Page SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.234 TO FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC. |
| | MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 |
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| | ==1.0 INTRODUCTION== |
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| | By letter dated March 28, 2006, Dominion Nuclear Connecticut, Inc. (DNC or the licensee) requested a license amendment for Millstone Power Station, Unit No. 3 (MPS3). The licensee requested to delete Section 2.F of Facility Operating License No. NPF-49, which specifies reporting of violations of the requirements in Section 2.C. A notice announcing the availability of this proposed change using the consolidated line item improvement process (CLIIP) was published in the Federal Register on November 4, 2005 (70 FR 67202). |
| | The Nuclear Regulatory Commission (NRC or the Commission) staffs proposed no significant hazards consideration determination of the licensees proposed amendment was published in the Federal Register on May 9, 2006 (71 FR 26997). |
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| | ==2.0 REGULATORY EVALUATION== |
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| | A section or condition was included in the facility operating licenses issued to some nuclear power plants requiring the licensee to make reports to the NRC regarding violations of other sections of the operating license (typically Section 2.C). In the case of MPS3, Section 2.F of the Facility Operating License reads as follows: |
| | Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, [DNC] shall report any violations of the requirements contained in Section 2.C. of this renewed operating license in the following manner: initial notification shall be made within 24 hours to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in [Title 10 of the Code of Federal Regulations (10 CFR)] |
| | 10 CFR Sections 50.73(b), (c) and (e). |
| | In addition to the information provided to support licensing decisions, the NRC obtains information about plant operation, licensee programs, and other matters using a combination of inspections and reporting requirements. Routine or scheduled reports that are required to be submitted to the NRC are defined in the related regulations, specific license condition, technical specification, or an NRC-approved program document. The reporting of emergencies, |
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| | unplanned events or conditions, and other special cases may also be addressed within such documents by the inclusion of reporting thresholds and are also the focus of the reporting requirements in 10 CFR 50.72, Immediate notification requirements for operating nuclear power reactors, and 10 CFR 50.73, Licensee event report system. Changes to the reporting regulations in 10 CFR Sections 50.72 and 50.73 became effective in January 2001 (see Federal Register notice on October 25, 2000 (65 FR 63769) and included extending the allowable reporting times for licensee event reports (LERs) from 30 days to 60 days. |
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| ==1.0INTRODUCTION== | | ==3.0 TECHNICAL EVALUATION== |
| By letter dated March 28, 2006, Dominion Nuclear Connecticut, Inc. (DNC or the licensee)requested a license amendment for Millstone Power Station, Unit No. 3 (MPS3). The licenseerequested to delete Section 2.F of Facility Operating License No. NPF-49, which specifies reporting of violations of the requirements in Section 2.C. A notice announcing the availabilityof this proposed change using the consolidated line item improvement process (CLIIP) was published in the Federal Register on November 4, 2005 (70 FR 67202). The Nuclear Regulatory Commission (NRC or the Commission) staff's proposed no significanthazards consideration determination of the licensee's proposed amendment was published in
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| the Federal Register on May 9, 2006 (71 FR 26997). | | Section 2.F of the MPS3 Facility Operating License requires the licensee to report any violations of the requirements of Section 2.C of the Facility Operating License and defines the method and allowable time periods for such reports. The reporting threshold (i.e., a violation) for the conditions included in Section 2.C of the Facility Operating License duplicate those defined in 10 CFR 50.72 and 10 CFR 50.73. However, the requirements in the Facility Operating License have different deadlines than those defined in the regulations following a rule change in 2001. This difference in reporting requirements has led to variations in reporting since many facility operating licenses do not contain the subject condition. For those licensees with a 30-day reporting requirement in the Facility Operating License, the condition has decreased the benefits of the rulemaking. For those cases where the current Facility Operating License requirement to report violations is also reportable in accordance with the regulations defined in 10 CFR 50.72 and 10 CFR 50.73, the NRC staff finds that the regulations adequately address this issue and the elimination of the duplicative requirement in the Facility Operating License is acceptable. |
| | Some of the conditions addressed in Section 2.C of the Facility Operating License may address the maintenance of particular programs, administrative requirements, or other matters where a violation of the requirement would not result in a report to the NRC in accordance with 10 CFR 50.72 or 10 CFR 50.73. In most cases, there are requirements for reports to the NRC related to these conditions in other regulations, the specific license condition or technical specification, or an NRC-approved program document. In other cases, there are reports to other agencies or news releases that would prompt a report to the NRC (in accordance with 10 CFR 50.72(b)(2)(xi)). The NRC staff also assessed violations of administrative requirements that could be reportable under the current License Condition but that may not have a duplicative requirement in a regulation or other regulatory requirement. The NRC staff finds that the requirements to report such problems within 24 hours with written reports to follow using the LER process is not needed. The NRC staff is confident that the information related to such violations that is actually important to the NRCs regulatory functions would come to light in a time frame comparable to the 60-day LER requirements. The information would become available to the appropriate NRC staff through the inspection program, updates to program documents, resultant licensing actions, public announcements, or some other reliable mechanism. |
| | The NRC staff finds that the elimination of Section 2.F in the MPS3 Facility Operating License will not result in a loss of information to the NRC that would adversely affect either its goal to protect public health and safety or its ability to carry out its various other regulatory responsibilities. Therefore, the elimination of Section 2.F of the Facility Operating License is acceptable. |
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| ==2.0REGULATORY EVALUATION== | | ==4.0 STATE CONSULTATION== |
| A section or condition was included in the facility operating licenses issued to somenuclear power plants requiring the licensee to make reports to the NRC regarding violations ofother sections of the operating license (typically Section 2.C). In the case of MPS3, Section 2.F of the Facility Operating License reads as follows:Except as otherwise provided in the Technical Specifications or EnvironmentalProtection Plan, [DNC] shall report any violations of the requirements contained inSection 2.C. of this renewed operating license in the following manner: initial notification shall be made within 24 hours to the NRC Operations Center via the EmergencyNotification System with written followup within thirty days in accordance with the procedures described in [Title 10 of the Code of Federal Regulations (10 CFR)]10 CFR Sections 50.73(b), (c) and (e).In addition to the information provided to support licensing decisions, the NRC obtainsinformation about plant operation, licensee programs, and other matters using a combination of inspections and reporting requirements. Routine or scheduled reports that are required to be submitted to the NRC are defined in the related regulations, specific license condition, technicalspecification, or an NRC-approved program document. The reporting of emergencies, unplanned events or conditions, and other special cases may also be addressed within suchdocuments by the inclusion of reporting thresholds and are also the focus of the reporting requirements in 10 CFR 50.72, "Immediate notification requirements for operating nuclearpower reactors," and 10 CFR 50.73, "Licensee event report system." Changes to the reportingregulations in 10 CFR Sections 50.72 and 50.73 became effective in January 2001 (see Federal Register notice on October 25, 2000 (65 FR 63769) and included extending theallowable reporting times for licensee event reports (LERs) from 30 days to 60 days.
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| ==3.0TECHNICAL EVALUATION==
| | In accordance with the Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The State official had no comments. |
| Section 2.F of the MPS3 Facility Operating License requires the licensee to report anyviolations of the requirements of Section 2.C of the Facility Operating License and defines themethod and allowable time periods for such reports. The reporting threshold (i.e., a violation) for the conditions included in Section 2.C of the Facility Operating License duplicate thosedefined in 10 CFR 50.72 and 10 CFR 50.73. However, the requirements in the FacilityOperating License have different deadlines than those defined in the regulations following a rulechange in 2001. This difference in reporting requirements has led to variations in reporting since many facility operating licenses do not contain the subject condition. For those licenseeswith a 30-day reporting requirement in the Facility Operating License, the condition hasdecreased the benefits of the rulemaking. For those cases where the current Facility OperatingLicense requirement to report violations is also reportable in accordance with the regulations defined in 10 CFR 50.72 and 10 CFR 50.73, the NRC staff finds that the regulations adequatelyaddress this issue and the elimination of the duplicative requirement in the Facility OperatingLicense is acceptable.Some of the conditions addressed in Section 2.C of the Facility Operating License mayaddress the maintenance of particular programs, administrative requirements, or other matters where a violation of the requirement would not result in a report to the NRC in accordance with10 CFR 50.72 or 10 CFR 50.73. In most cases, there are requirements for reports to the NRC related to these conditions in other regulations, the specific license condition or technical specification, or an NRC-approved program document. In other cases, there are reports toother agencies or news releases that would prompt a report to the NRC (in accordance with10 CFR 50.72(b)(2)(xi)). The NRC staff also assessed violations of administrative requirementsthat could be reportable under the current License Condition but that may not have a duplicativerequirement in a regulation or other regulatory requirement. The NRC staff finds that therequirements to report such problems within 24 hours with written reports to follow using the LER process is not needed. The NRC staff is confident that the information related to suchviolations that is actually important to the NRC's regulatory functions would come to light in atime frame comparable to the 60-day LER requirements. The information would become available to the appropriate NRC staff through the inspection program, updates to programdocuments, resultant licensing actions, public announcements, or some other reliable mechanism.The NRC staff finds that the elimination of Section 2.F in the MPS3 Facility Operating Licensewill not result in a loss of information to the NRC that would adversely affect either its goal toprotect public health and safety or its ability to carry out its various other regulatoryresponsibilities. Therefore, the elimination of Section 2.F of the Facility Operating License isacceptable.
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| ==4.0STATE CONSULTATION== | | ==5.0 ENVIRONMENTAL CONSIDERATION== |
| In accordance with the Commission's regulations, the Connecticut State official was notified ofthe proposed issuance of the amendment. The State official had no comments.
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| ==5.0ENVIRONMENTAL CONSIDERATION==
| | The amendment changes recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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 amendment changes recordkeeping, reporting, or administrative procedures orrequirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusionset forth in 10 CFR 51.22(c)(10). 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== | | ==6.0 CONCLUSION== |
| The Commission has concluded, based on the considerations discussed above, that (1) there isreasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical to thecommon defense and security or to the health and safety of the public. Principal Contributor: E. Thomas Date: October 4, 2006 Millstone Power Station, Unit No. 3 cc:
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| Lillilan M. Cuoco, EsquireSenior Counsel Dominion Resources Services, Inc.
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| Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385Edward L. Wilds, Jr., Ph.D.Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406First SelectmenTown of Waterford 15 Rope Ferry Road Waterford, CT 06385Mr. J. W. "Bill" S heehan Co-Chair NEAC 19 Laurel Crest Drive Waterford, CT 06385Mr. Evan W. WoollacottCo-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070Senior Resident InspectorMillstone Power Stationc/o U.S. Nuclear Regulatory Commission
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| P. O. Box 513 Niantic, CT 06357Ms. Nancy Burton147 Cross Highway Redding Ridge, CT 00870Mr. Joseph Roy, Director of Operations Massachusetts Municipal Wholesale Electric Company Moody Street
| | The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| | Principal Contributor: E. Thomas Date: October 4, 2006 |
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| P.O. Box 426 Ludlow, MA 01056Mr. J. Alan PriceSite Vice President Dominion Nuclear Connecticut, Inc. | | Millstone Power Station, Unit No. 3 cc: |
| Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385Mr. Chris FunderburkDirector, Nuclear Licensing and Operations Support Dominion Resources Services, Inc. | | Lillilan M. Cuoco, Esquire Mr. Joseph Roy, Senior Counsel Director of Operations Dominion Resources Services, Inc. Massachusetts Municipal Wholesale Building 475, 5th Floor Electric Company Rope Ferry Road Moody Street Waterford, CT 06385 P.O. Box 426 Ludlow, MA 01056 Edward L. Wilds, Jr., Ph.D. |
| 5000 Dominion Boulevard Glen Allen, VA 23060-6711Mr. David W. DodsonLicensing Supervisor Dominion Nuclear Connecticut, Inc. | | Director, Division of Radiation Mr. J. Alan Price Department of Environmental Protection Site Vice President 79 Elm Street Dominion Nuclear Connecticut, Inc. |
| Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385}} | | Hartford, CT 06106-5127 Building 475, 5th Floor Rope Ferry Road Regional Administrator, Region I Waterford, CT 06385 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Chris Funderburk King of Prussia, PA 19406 Director, Nuclear Licensing and Operations Support First Selectmen Dominion Resources Services, Inc. |
| | Town of Waterford 5000 Dominion Boulevard 15 Rope Ferry Road Glen Allen, VA 23060-6711 Waterford, CT 06385 Mr. David W. Dodson Mr. J. W. "Bill" Sheehan Licensing Supervisor Co-Chair NEAC Dominion Nuclear Connecticut, Inc. |
| | 19 Laurel Crest Drive Building 475, 5th Floor Waterford, CT 06385 Rope Ferry Road Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870}} |
Letter Sequence Approval |
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MONTHYEARML0627904922006-10-0404 October 2006
Tech Spec Pages for Amendment 234 Deleting Section 2.F to Facility Operating License No. NPF-49
Project stage: Other
ML0614301352006-10-0404 October 2006
Issuance of License Amendment 234 Deleting Section 2.F to Facility Operating License No. NPF-49
Project stage: Approval
2006-10-04
[Table View] |
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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024
Technical Specification Bases Pages
IR 05000336/20234022024-01-30030 January 2024
Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only)
ML23341A0172024-01-12012 January 2024
Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures
IR 05000336/20234402024-01-11011 January 2024
Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only)
ML24004A1052024-01-0404 January 2024
Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010
ML23361A0942023-12-21021 December 2023
Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report .
ML23283A3052023-12-20020 December 2023
Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary)
ML23361A0312023-12-20020 December 2023
Intent to Pursue Subsequent License Renewal
ML23352A0202023-12-18018 December 2023
Senior Reactor and Reactor Operator Initial License Examinations
ML23334A2242023-11-30030 November 2023
Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation
ML23324A4222023-11-20020 November 2023
Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13
ML23324A4302023-11-20020 November 2023
Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15
ML23317A2702023-11-13013 November 2023
Core Operating Limits Report, Cycle 23
IR 05000336/20230032023-11-0606 November 2023
Integrated Inspection Report 05000336/2023003 and 05000423/2023003
ML23298A1652023-10-26026 October 2023
Requalification Program Inspection
IR 05000336/20234202023-10-0404 October 2023
Security Inspection Report 05000336/2023420 and 05000423/2023420
ML23230A0502023-10-0202 October 2023
5 of the Quality Assurance Topical Report - Review of Program Changes
ML23226A0052023-09-26026 September 2023
Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis
IR 05000245/20230012023-09-19019 September 2023
Safstor Inspection Report 05000245/2023001
IR 05000336/20230102023-09-0808 September 2023
Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010
IR 05000336/20230052023-08-31031 August 2023
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005)
ML23248A2132023-08-30030 August 2023
Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature.
ML23242A0142023-08-30030 August 2023
Operator Licensing Examination Approval
ML23223A0552023-08-18018 August 2023
Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel
ML23223A0482023-08-18018 August 2023
Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits
IR 05000336/20230022023-08-0909 August 2023
Integrated Inspection Report 05000336/2023002 and 05000423/2023002
ML23188A0432023-07-31031 July 2023
Authorization and Safety Evaluation for Alternative Request No. IR-04-11
ML23208A0922023-07-26026 July 2023
Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response
ML23188A0202023-07-26026 July 2023
Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML23207A1102023-07-26026 July 2023
NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
IR 05000336/20234012023-07-17017 July 2023
Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only)
ML23175A0052023-07-12012 July 2023
Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps
ML23193A8562023-06-28028 June 2023
Submittal of Updates to the Final Safety Analysis Reports
ML23178A1682023-06-26026 June 2023
2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46
ML23153A1732023-06-16016 June 2023
Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement
ML23151A0742023-06-12012 June 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
ML23159A2202023-06-0808 June 2023
Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes
IR 07200047/20234012023-06-0808 June 2023
NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401
2024-01-04
[Table view]
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23341A0172024-01-12012 January 2024
Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures
ML23072A0892023-05-0101 May 2023
(Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements
ML23058A4542023-03-16016 March 2023
Issuance of Amendment Nos. 345 and 285 Regarding Adoption of Technical Specification Task Force-359, Increase Flexibility in Mode Restraints
ML23005A1702023-01-17017 January 2023
Correction to Issuance of Amendment No. 283 to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definition
ML22095A1072022-07-11011 July 2022
Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD
ML22041A0102022-03-0101 March 2022
V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition
ML22007A1512022-02-16016 February 2022
Issuance of Amendment No. 282 Regarding Shutdown Bank Technical Specification Requirements and Alternate Control Rod Position Monitoring Requirements
ML21326A0992022-01-0707 January 2022
Issuance of Amendment No. 281 Regarding Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1
ML21262A0012021-11-0909 November 2021
Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate
ML21227A0002021-10-0505 October 2021
Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident
ML21222A2302021-09-0909 September 2021
Issuance of Amendment No. 343 Revision to Technical Specifications for Steam Generator Inspection Frequency (L-2020-LLA-0227)
ML21043A1622021-03-25025 March 2021
Issuance of Amendment No. 278 Regarding Revision to Battery Surveillance Requirements
ML21026A1422021-02-23023 February 2021
Issuance of Amendment No. 342 Revision to Technical Specification Table 3.3-11, Accident Monitoring Instrumentation
ML20275A0002020-10-14014 October 2020
Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections
ML20237H9952020-09-29029 September 2020
Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program
ML20191A0042020-08-0707 August 2020
Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity
ML20161A0002020-07-15015 July 2020
Issuance of Amendment No. 276 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals
ML20140A3692020-06-24024 June 2020
Issuance of Amendment No. 339 Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time
ML19340A0252020-01-30030 January 2020
Issuance of Amendment No. 337 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components of Nuclear Power Reactors
ML19305D2482019-12-31031 December 2019
Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6
ML19150A3672019-05-30030 May 2019
Current Facility Operating License No. DPR-21, Tech Specs, Revised 5/30/2019
ML19126A0002019-05-28028 May 2019
Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage
ML19042A2772019-03-21021 March 2019
Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels
ML18246A0072018-09-25025 September 2018
Issuance of Amendment No. 335 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals
ML18038B2002018-02-26026 February 2018
Issuance of Amendment Nos. 118, 334, and 271 to Revise Licensee'S Name (CAC Nos. MF9844, MF9845, and MF9848; EPID L-2017-LLA-0245 and EPID L-2017-LLA-0346)
ML17025A2182017-01-24024 January 2017
Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis
ML16308A4852016-12-22022 December 2016
Issuance of Amendment No. 331 Revision to Emergency Core Cooling System Technical Specification and Final Safety Analysis Report Ch. 14 to Remove Charging
ML16249A0012016-09-30030 September 2016
Issuance of Amendments Small Break Loss of Coolant Accident Reanalysis
ML16206A0012016-08-0404 August 2016
Issuance of Amendment No. 270 to Revise Technical Specification 5.6.3, Fuel Storage Capacity
ML16131A7282016-07-28028 July 2016
Issuance of Amendment 268 Adopting Dominion Core Design and Safety Analysis Methods and Addressing the Issues Identified in Three Westinghouse Communication Documents
ML16193A0012016-07-28028 July 2016
Issuance of Amendments Removal of Severe Line Outage Detection from the Offsite Power System
ML16189A0762016-06-29029 June 2016
Supplement to Information Regarding License Amendment Request for Removal of Severe Line Outage Detection from the Offsite Power System
ML16003A0082016-06-23023 June 2016
Issuance of Amendment No. 327 Proposed Technical Specification Changes for Spent Fuel Storage
ML16068A3122016-03-31031 March 2016
Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing
ML16011A4002016-01-29029 January 2016
Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation
ML15288A0042015-11-30030 November 2015
Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times
ML15280A2422015-10-29029 October 2015
Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3
ML15245A4822015-10-0707 October 2015
Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses
ML15225A0102015-08-28028 August 2015
Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves
ML15246A1422015-08-27027 August 2015
Connecticut, Inc. Millstone Power Station Unit 3 Supplement to License Amendment Request to Revise Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves
ML15225A0082015-08-26026 August 2015
Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds
ML15187A3262015-07-29029 July 2015
Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C
ML15187A1862015-07-28028 July 2015
Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692)
ML15187A0112015-07-27027 July 2015
Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures
ML15093A0022015-05-20020 May 2015
Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes
ML15098A0342015-05-20020 May 2015
Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes
ML15093A4412015-05-18018 May 2015
Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies
ML14178A5992014-07-11011 July 2014
Issuance of Amendment Proposed Changes to Technical Specification 3/4 7.5, Ultimate Heat Sink (Tac MF1780)
ML14037A4082014-04-18018 April 2014
Issuance of Amendment Revise Technical Specification 3/4.7.11 Ultimate Heat Sink
ML14073A0552014-04-0808 April 2014
Issuance of Amendment Calculated Containment Internal Pressure
2024-01-12
[Table view]
Category:Safety Evaluation
MONTHYEARML23341A0172024-01-12012 January 2024
Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures
ML23283A3052023-12-20020 December 2023
Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary)
ML23230A0502023-10-0202 October 2023
5 of the Quality Assurance Topical Report - Review of Program Changes
ML23226A0052023-09-26026 September 2023
Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis
ML23188A0432023-07-31031 July 2023
Authorization and Safety Evaluation for Alternative Request No. IR-04-11
ML23175A0052023-07-12012 July 2023
Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps
ML23072A0892023-05-0101 May 2023
(Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements
ML23058A4542023-03-16016 March 2023
Issuance of Amendment Nos. 345 and 285 Regarding Adoption of Technical Specification Task Force-359, Increase Flexibility in Mode Restraints
ML21320A0072022-09-0707 September 2022
Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary)
ML22201A5082022-07-28028 July 2022
Authorization and Safety Evaluation for Alternative Request No. IR-04-09
ML22095A1072022-07-11011 July 2022
Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD
ML22039A3392022-03-0303 March 2022
Request for Alternative Frequency to Supplemental Valve Position Verification Testing Requirements in the Fourth 10-year Valve Inservice Testing Program
ML22041A0102022-03-0101 March 2022
V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition
ML22007A1512022-02-16016 February 2022
Issuance of Amendment No. 282 Regarding Shutdown Bank Technical Specification Requirements and Alternate Control Rod Position Monitoring Requirements
ML21326A0992022-01-0707 January 2022
Issuance of Amendment No. 281 Regarding Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1
ML21262A0012021-11-0909 November 2021
Issuance of Amendment No. 280 Regarding Measurement Uncertainty Recapture Power Uprate
ML21284A0062021-10-29029 October 2021
Authorization and Safety Evaluation for Alternative Request No. RR-05-04 and IR-4-02
ML21227A0002021-10-0505 October 2021
Issuance of Amendment No. 279 Regarding Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss-of-Coolant Accident
ML21222A2302021-09-0909 September 2021
Issuance of Amendment No. 343 Revision to Technical Specifications for Steam Generator Inspection Frequency (L-2020-LLA-0227)
ML21174A0202021-08-0202 August 2021
Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval
ML21167A3552021-07-16016 July 2021
Authorization and Safety Evaluation for Alternative Request No. RR-05-06
ML21167A2112021-06-30030 June 2021
Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0081 Through L-2020-LLR-0088)
ML21075A0452021-03-26026 March 2021
Request to Utilize Code Case N-885
ML21043A1622021-03-25025 March 2021
Issuance of Amendment No. 278 Regarding Revision to Battery Surveillance Requirements
ML21026A1422021-02-23023 February 2021
Issuance of Amendment No. 342 Revision to Technical Specification Table 3.3-11, Accident Monitoring Instrumentation
ML20312A0022020-12-10010 December 2020
Relief Request for Limited Coverage Examinations Performed in the Third 10-Year Inservice Inspection Interval (EPID L-2020-LLR-0027 Through L-2020-LLR-0032)
ML20312A0012020-12-10010 December 2020
Relief Requests for Limited Coverage Examinations Performed in the Fourth 10-Year Inservice Inspection Interval
ML20287A4712020-10-20020 October 2020
Proposed Alternative RR-05-05 to the Requirements of the ASME Code Containment Unbonded Post-Tensioning System Inservice Inspection Requirements
ML20275A0002020-10-14014 October 2020
Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections
ML20237H9952020-09-29029 September 2020
Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program
ML20252A0072020-09-15015 September 2020
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI
ML20191A0042020-08-0707 August 2020
Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity
ML20189A2062020-07-16016 July 2020
Relief Request IR-4-03 Concerning Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping
ML20161A0002020-07-15015 July 2020
Issuance of Amendment No. 276 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals
ML20140A3692020-06-24024 June 2020
Issuance of Amendment No. 339 Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time
ML20080K5082020-03-24024 March 2020
Alternative Request RR-05-03 for the Fifth 10-Year Inservice Inspection Interval
ML19340A0252020-01-30030 January 2020
Issuance of Amendment No. 337 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components of Nuclear Power Reactors
ML19305D2482019-12-31031 December 2019
Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6
ML19338G3722019-12-18018 December 2019
Alternative Requests RR-05-01 and RR-05-02 for the Fifth 10-Year Inservice Inspection Interval
ML19340A0012019-12-18018 December 2019
Proposed Alternative Request IR-4-01 Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography
ML19340A0002019-12-13013 December 2019
Relief Request IR-3-39, Proposed Alternative to ASME Code Weld Preheat Requirements
ML19126A0002019-05-28028 May 2019
Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage
ML19098A0342019-04-30030 April 2019
Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins
ML19042A2772019-03-21021 March 2019
Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels
ML18290A6022018-11-13013 November 2018
Alternative Requests Related to the Fifth and Fourth 10-Year Interval Pump, Valve, and Snubber Inservice Testing Programs, Respectively (EPID L-2018-LLR- 0012 Through EPID L-2018-LLR-0022)
ML18275A0122018-10-0404 October 2018
Alternative Request P-06 for the 'C' Charging Pump Test Frequency
ML18246A0072018-09-25025 September 2018
Issuance of Amendment No. 335 Regarding Revision to the Integrated Leak Rate Type a and Type C Test Intervals
ML18252A0032018-09-17017 September 2018
Alternative Requests RR-04-27 and IR-3-38 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography
ML18225A0202018-08-29029 August 2018
ISFSI; North Anna 1 & 2 Isfsls, and Unit 3; Surry Power 1 & 2, and Isfsls); Dominion Energy Kewaunee, Inc. (Kewaunee Power Station and Isfsi): Request for Threshold Determination Under 10 CFR 50.80
ML18038B2002018-02-26026 February 2018
Issuance of Amendment Nos. 118, 334, and 271 to Revise Licensee'S Name (CAC Nos. MF9844, MF9845, and MF9848; EPID L-2017-LLA-0245 and EPID L-2017-LLA-0346)
2024-01-12
[Table view] |
Text
October 4, 2006 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: DELETING SECTION 2.F TO FACILITY OPERATING LICENSE NO.
NPF-49 (TAC NO. MD1056)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 234 to Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3., in response to your application dated March 28, 2006. This amendment revises Facility Operating License No. NPF-49 by deleting Section 2.F, which specifies reporting of violations of the requirements of Section 2.C of the renewed operating license.
A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosures:
- 1. Amendment No. 234 to License No. NPF-49
- 2. Safety Evaluation cc w/encls: See next page
October 4, 2006 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: DELETING SECTION 2.F TO FACILITY OPERATING LICENSE NO.
NPF-49 (TAC NO. MD1056)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 234 to Facility Operating License No. NPF-49 for the Millstone Power Station, Unit No. 3., in response to your application dated March 28, 2006. This amendment revises Facility Operating License No. NPF-49 by deleting Section 2.F, which specifies reporting of violations of the requirements of Section 2.C of the renewed operating license.
A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosures:
- 1. Amendment No. 234 to License No. NPF-49
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
RidsNrrLpl1-2 RidsOgcRp RidsRgn1MailCenter PUBLIC RidsNrrPMVNerses RidsAcrs AcnwMailCenter LPL1-2 R/F RidsNrrLACRaynor TKobetz RidsNrrDorl GHill (2)
Package Accession Number: ML061930080 Amendment Accession Number: ML061430135 Tech Specs. Accession Number: ML062790492 OFFICE LPL1-2/PM LPL1-2/LA ITSB/BC OGC/NLO LPL1-2/BC (A)
NAME VNerses:rsa CRaynor TKobetz MZobler BPoole DATE 7/26/06 7/25/06 5/18/06 8/2/06 8/3/06 OFFICIAL RECORD COPY
DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 234 License No. NPF-49
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by Dominion Nuclear Connecticut, Inc. (the licensee) dated March 28, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by deleting paragraph 2.F of Facility Operating License No. NPF-49 as indicated in the attachment to this license amendment.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Brooke D. Poole, Acting Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License Date of Issuance: October 4, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 234 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of Facility Operating License No. NPF-49 as indicated. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Page Insert Page SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.234 TO FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423
1.0 INTRODUCTION
By letter dated March 28, 2006, Dominion Nuclear Connecticut, Inc. (DNC or the licensee) requested a license amendment for Millstone Power Station, Unit No. 3 (MPS3). The licensee requested to delete Section 2.F of Facility Operating License No. NPF-49, which specifies reporting of violations of the requirements in Section 2.C. A notice announcing the availability of this proposed change using the consolidated line item improvement process (CLIIP) was published in the Federal Register on November 4, 2005 (70 FR 67202).
The Nuclear Regulatory Commission (NRC or the Commission) staffs proposed no significant hazards consideration determination of the licensees proposed amendment was published in the Federal Register on May 9, 2006 (71 FR 26997).
2.0 REGULATORY EVALUATION
A section or condition was included in the facility operating licenses issued to some nuclear power plants requiring the licensee to make reports to the NRC regarding violations of other sections of the operating license (typically Section 2.C). In the case of MPS3, Section 2.F of the Facility Operating License reads as follows:
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, [DNC] shall report any violations of the requirements contained in Section 2.C. of this renewed operating license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in [Title 10 of the Code of Federal Regulations (10 CFR)]
10 CFR Sections 50.73(b), (c) and (e).
In addition to the information provided to support licensing decisions, the NRC obtains information about plant operation, licensee programs, and other matters using a combination of inspections and reporting requirements. Routine or scheduled reports that are required to be submitted to the NRC are defined in the related regulations, specific license condition, technical specification, or an NRC-approved program document. The reporting of emergencies,
unplanned events or conditions, and other special cases may also be addressed within such documents by the inclusion of reporting thresholds and are also the focus of the reporting requirements in 10 CFR 50.72, Immediate notification requirements for operating nuclear power reactors, and 10 CFR 50.73, Licensee event report system. Changes to the reporting regulations in 10 CFR Sections 50.72 and 50.73 became effective in January 2001 (see Federal Register notice on October 25, 2000 (65 FR 63769) and included extending the allowable reporting times for licensee event reports (LERs) from 30 days to 60 days.
3.0 TECHNICAL EVALUATION
Section 2.F of the MPS3 Facility Operating License requires the licensee to report any violations of the requirements of Section 2.C of the Facility Operating License and defines the method and allowable time periods for such reports. The reporting threshold (i.e., a violation) for the conditions included in Section 2.C of the Facility Operating License duplicate those defined in 10 CFR 50.72 and 10 CFR 50.73. However, the requirements in the Facility Operating License have different deadlines than those defined in the regulations following a rule change in 2001. This difference in reporting requirements has led to variations in reporting since many facility operating licenses do not contain the subject condition. For those licensees with a 30-day reporting requirement in the Facility Operating License, the condition has decreased the benefits of the rulemaking. For those cases where the current Facility Operating License requirement to report violations is also reportable in accordance with the regulations defined in 10 CFR 50.72 and 10 CFR 50.73, the NRC staff finds that the regulations adequately address this issue and the elimination of the duplicative requirement in the Facility Operating License is acceptable.
Some of the conditions addressed in Section 2.C of the Facility Operating License may address the maintenance of particular programs, administrative requirements, or other matters where a violation of the requirement would not result in a report to the NRC in accordance with 10 CFR 50.72 or 10 CFR 50.73. In most cases, there are requirements for reports to the NRC related to these conditions in other regulations, the specific license condition or technical specification, or an NRC-approved program document. In other cases, there are reports to other agencies or news releases that would prompt a report to the NRC (in accordance with 10 CFR 50.72(b)(2)(xi)). The NRC staff also assessed violations of administrative requirements that could be reportable under the current License Condition but that may not have a duplicative requirement in a regulation or other regulatory requirement. The NRC staff finds that the requirements to report such problems within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with written reports to follow using the LER process is not needed. The NRC staff is confident that the information related to such violations that is actually important to the NRCs regulatory functions would come to light in a time frame comparable to the 60-day LER requirements. The information would become available to the appropriate NRC staff through the inspection program, updates to program documents, resultant licensing actions, public announcements, or some other reliable mechanism.
The NRC staff finds that the elimination of Section 2.F in the MPS3 Facility Operating License will not result in a loss of information to the NRC that would adversely affect either its goal to protect public health and safety or its ability to carry out its various other regulatory responsibilities. Therefore, the elimination of Section 2.F of the Facility Operating License is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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 Commissions 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: E. Thomas Date: October 4, 2006
Millstone Power Station, Unit No. 3 cc:
Lillilan M. Cuoco, Esquire Mr. Joseph Roy, Senior Counsel Director of Operations Dominion Resources Services, Inc. Massachusetts Municipal Wholesale Building 475, 5th Floor Electric Company Rope Ferry Road Moody Street Waterford, CT 06385 P.O. Box 426 Ludlow, MA 01056 Edward L. Wilds, Jr., Ph.D.
Director, Division of Radiation Mr. J. Alan Price Department of Environmental Protection Site Vice President 79 Elm Street Dominion Nuclear Connecticut, Inc.
Hartford, CT 06106-5127 Building 475, 5th Floor Rope Ferry Road Regional Administrator, Region I Waterford, CT 06385 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Chris Funderburk King of Prussia, PA 19406 Director, Nuclear Licensing and Operations Support First Selectmen Dominion Resources Services, Inc.
Town of Waterford 5000 Dominion Boulevard 15 Rope Ferry Road Glen Allen, VA 23060-6711 Waterford, CT 06385 Mr. David W. Dodson Mr. J. W. "Bill" Sheehan Licensing Supervisor Co-Chair NEAC Dominion Nuclear Connecticut, Inc.
19 Laurel Crest Drive Building 475, 5th Floor Waterford, CT 06385 Rope Ferry Road Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870
