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| | author name = Nerses V | | | author name = Nerses V |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLB | | | author affiliation = NRC/NRR/ADRO/DORL/LPLB |
| | 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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| {{#Wiki_filter:August 15, 2006Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. | | {{#Wiki_filter:August 15, 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: TECHNICAL SPECIFICATION CHANGES TO THE REACTIVITYCONTROL SYSTEM ROD DROP TIME TEST (TAC NO. MC8430) | | MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATION CHANGES TO THE REACTIVITY CONTROL SYSTEM ROD DROP TIME TEST (TAC NO. MC8430) |
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| ==Dear Mr. Christian:== | | ==Dear Mr. Christian:== |
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| The Commission has issued the enclosed Amendment No. 231 to Facility Operating LicenseNo. NPF-49 for Millstone Power Station, Unit No. 3 (MPS3), in response to your applicationdated September 13, 2005.The amendment revises the MPS3 Technical Specification temperature requirement for thereactivity control system rod drop time test.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/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. 231 to Facility Operating License No. NPF-49 for Millstone Power Station, Unit No. 3 (MPS3), in response to your application dated September 13, 2005. |
| | The amendment revises the MPS3 Technical Specification temperature requirement for the reactivity control system rod drop time test. |
| | A copy of the related 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. 231 to NPF-49 | | : 1. Amendment No. 231 to NPF-49 |
| : 2. Safety Evaluationcc w/encls: See next page August 15, 2006Mr. David A. ChristianSr. 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 | | |
| | August 15, 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: TECHNICAL SPECIFICATION CHANGES TO THE REACTIVITYCONTROL SYSTEM ROD DROP TIME TEST (TAC NO. MC8430) | | MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATION CHANGES TO THE REACTIVITY CONTROL SYSTEM ROD DROP TIME TEST (TAC NO. MC8430) |
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| ==Dear Mr. Christian:== | | ==Dear Mr. Christian:== |
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| The Commission has issued the enclosed Amendment No. 231 to Facility Operating LicenseNo. NPF-49 for Millstone Power Station, Unit No. 3 (MPS3), in response to your applicationdated September 13, 2005.The amendment revises the MPS3 Technical Specification temperature requirement for thereactivity control system rod drop time test.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/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. 231 to Facility Operating License No. NPF-49 for Millstone Power Station, Unit No. 3 (MPS3), in response to your application dated September 13, 2005. |
| | The amendment revises the MPS3 Technical Specification temperature requirement for the reactivity control system rod drop time test. |
| | A copy of the related 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. 231 to NPF-49 | | : 1. Amendment No. 231 to NPF-49 |
| : 2. Safety Evaluationcc w/encls: See next page DISTRIBUTION | | : 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: |
| :PUBLICRidsNrrPMVNersesPKrohn, RGN-1 LPL1-2 R/FRidsNrrLACRaynorTBoyce RidsAcrsAcnwMailCenterRidsOgcRpGHill (2)
| | PUBLIC RidsNrrPMVNerses PKrohn, RGN-1 LPL1-2 R/F RidsNrrLACRaynor TBoyce RidsAcrsAcnwMailCenter RidsOgcRp GHill (2) |
| RidsNrrDorlLpl1-2JNakoskiFForsatyPackage Accession Number: ML062060099Amendment Accession Number: ML062060416TS(s) Accession Number: ML062270389OFFICELPLI-2/PMLPLI-2/LASPWB/CITSB/COGCLPLI-2/BC (A)NAMEVNerses:rsaCRaynorJNakoskiTKobetzSUttalBPoole DATE8/9/067/27/067/31/06no concurrence req.8/7/068/11/06OFFICIAL RECORD COPY DOMINION NUCLEAR CONNECTICUT, INC.DOCKET NO. 50-423MILLSTONE POWER STATION, UNIT NO. 3AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 231License No. NPF-491.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Dominion Nuclear Connecticut, Inc. (thelicensee) dated September 13, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the rules and regulations of the Commission;C.There is reasonable assurance: (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with 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; and E.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment, and paragraph 2.C.(2) of FacilityOperating License No. NPF-49 is hereby amended to read as follows:(2)Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 231, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. Dominion Nuclear Connecticut, Inc. shall operate the facility inaccordance with the Technical Specifications and the Environmental Protection Plan. 3.This license amendment is effective as of the date of issuance, and shall beimplemented within 60 days of issuance.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 | | RidsNrrDorlLpl1-2 JNakoski FForsaty Package Accession Number: ML062060099 Amendment Accession Number: ML062060416 TS(s) Accession Number: ML062270389 OFFICE LPLI-2/PM LPLI-2/LA SPWB/C ITSB/C OGC LPLI-2/BC (A) |
| | NAME VNerses:rsa CRaynor JNakoski TKobetz SUttal BPoole DATE 8/9/06 7/27/06 7/31/06 no concurrence req. |
| | 8/7/06 8/11/06 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. 231 License No. NPF-49 |
| | : 1. The Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Dominion Nuclear Connecticut, Inc. (the licensee) dated September 13, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied. |
| | : 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows: |
| | (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 231, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. Dominion Nuclear Connecticut, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. |
| | : 3. This license amendment is effective as of the date of issuance, and shall be implemented within 60 days of issuance. |
| | 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 Technical SpecificationsDate of Issuance: August 15, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 231FACILITY OPERATING LICENSE NO. NPF-49DOCKET NO. 50-423Replace the following page of the Appendix A, Technical Specifications, with the attachedrevised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. RemoveInsert3/4 1-253/4 1-25 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 231TO FACILITY OPERATING LICENSE NO. NPF-49DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION, UNIT NO. 3DOCKET NO. 50-42 | | Changes to the Technical Specifications Date of Issuance: August 15, 2006 |
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 231 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. |
| | Remove Insert 3/4 1-25 3/4 1-25 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 231 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 September 13, 2005, Dominion Nuclear Connecticut, Inc. (DNC or licensee) submitted to the Nuclear Regulatory Commission (NRC or the Commission) a request for a change to the Millstone Power Station, Unit No. 3 (MPS3) Technical Specifications (TSs) temperature requirement for the reactivity control system rod drop time test. |
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| | ==2.0 REGULATORY EVALUATION== |
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| ==31.0 INTRODUCTION==
| | The NRC staff reviewed the licensees September 13, 2005, application to verify that the proposed change continues to meet with the regulatory requirements as stipulated in the following General Design Criteria (GDC): |
| By letter dated September 13, 2005, Dominion Nuclear Connecticut, Inc. (DNC or licensee)submitted to the Nuclear Regulatory Commission (NRC or the Commission) a request for achange to the Millstone Power Station, Unit No. 3 (MPS3) Technical Specifications (TSs)temperature requirement for the reactivity control system rod drop time test.
| | : 1. GDC 10, Reactor design, which requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. |
| | : 2. GDC 26, Reactivity control system redundancy and capability, which requires, among other things, that two independent reactivity control systems of different design principles be provided. GDC 26 also requires that one of the systems shall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions, such as stuck rods, specified acceptable fuel design limits are not exceeded. |
| | : 3. GDC 27, Combined reactivity control systems capability, which requires that the reactivity control systems be designed to have a combined capability, in conjunction with poison addition by the emergency core cooling system, of |
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| ==2.0 REGULATORY EVALUATION==
| | reliably controlling reactivity changes to assure that under postulated accident conditions, and with appropriate margin for stuck rods, the capability to cool the core is maintained. |
| The NRC staff reviewed the licensee's September 13, 2005, application to verify that theproposed change continues to meet with the regulatory requirements as stipulated in thefollowing General Design Criteria (GDC):1.GDC 10, "Reactor design," which requires that the reactor core and associatedcoolant, control, and protection systems be designed with appropriate margin toassure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operationaloccurrences. 2.GDC 26, "Reactivity control system redundan cy and capability," which requires,among other things, that two independent reactivity control systems of differentdesign principles be provided. GDC 26 also require s that one of the systemsshall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure thatunder conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions, such as stuck rods, specified acceptable fuel design limits are not exceeded.3.GDC 27, "Combined reactivity control systems capability," which requires thatthe reactivity control systems be designed to have a combined capability, inconjunction with poison addition by the emergency core cooling system, of reliably controlling reactivity changes to assure that under postulated accidentconditions, and with appropriate margin for stuck rods, the capability to cool thecore is maintained.4.GDC 28, "Reactivity limits," which requires, among other things, that thereactivity control systems be designed with appropriate limits on the potentialamount and rate of reactivity increase to assure that the effects of postulated reactivity accidents can neither (1) result in damage to the reactor coolant pressure boundary greater than limited local yielding, nor (2) sufficiently disturb the core, its support structures or other reactor pressure vessel internals to impair significantly the capability to cool the core.Additionally, the NRC staff verified that the proposed change complies with the MPS3 licensingbasis criteria stated in the Final Safety Analysis Report. The staff used Chapter 4.6 of NUREG-0800, "Standard Review Plan (SRP) for the Review of Safety Analysis Reports forNuclear Power Plants LWR Edition," (Reference 1), and NUREG 1431, "Standard TechnicalSpecifications Westinghouse Plants," (Reference 2) as guidance during the review.
| | : 4. GDC 28, Reactivity limits, which requires, among other things, that the reactivity control systems be designed with appropriate limits on the potential amount and rate of reactivity increase to assure that the effects of postulated reactivity accidents can neither (1) result in damage to the reactor coolant pressure boundary greater than limited local yielding, nor (2) sufficiently disturb the core, its support structures or other reactor pressure vessel internals to impair significantly the capability to cool the core. |
| | Additionally, the NRC staff verified that the proposed change complies with the MPS3 licensing basis criteria stated in the Final Safety Analysis Report. The staff used Chapter 4.6 of NUREG-0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants LWR Edition, (Reference 1), and NUREG 1431, Standard Technical Specifications Westinghouse Plants, (Reference 2) as guidance during the review. |
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| ==3.0 TECHNICAL EVALUATION== | | ==3.0 TECHNICAL EVALUATION== |
| The licensee has proposed to modify Limiting Condition for Operation 3.1.3.4, which isapplicable during MODES 1 and 2, and currently reads as follows:The individual full-length (shutdown and control) rod drop time from the fully withdrawnposition shall be less than or equal to 2.7 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:a.Tavg greater than or equal to 551 F, andb.All reactor coolant pumps operating.The licensee's proposed change is to replace "551 F" with "500 F" in subpart "a."The conditions requiring control rods (or the typical terminology: rod cluster control assembly(RCCA)) drop testing are as follows:Surveillance Requirement (SR) 4.1.3.4 states that the demonstration of required RCCA droptime is required prior to reactor criticality:a.For all rods following each removal of the reactor vessel head, b.For specifically affected individual rods following any maintenance on ormodification to the Control Rod Drive System which could affect the drop time of those specific rods, andc.At least every 24 months.The RCCA drop test is intended to provide verification that RCCAs will perform as assumedduring a reactor trip from power operation. Verification of RCCA drop time allows the licensee to determine that actual drop times are consistent with the drop times assumed in the plant'ssafety analysis. The RCCA drop test ensures that the reactor internals and RCCA drivemechanisms do not interfere with RCCA motion or increase drop time, and that no degradationin the system has occurred that would adversely affect the operability of the RCCAs.The NRC staff reviewed the results from testing during the initial startup at MPS3. RCCA droptests were performed at cold (Tavg 145 F, reactor coolant system (RCS) pressure 390 psia)and hot (Tavg 557 F, RCS pressure 2250 psia ) reactor coolant temperatures with all reactorcoolant pumps operating. The tests demonstrated a slight increase in RCCA drop time asreactor coolant temperature was decreased. Specifically, a drop time increase of less than
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| | The licensee has proposed to modify Limiting Condition for Operation 3.1.3.4, which is applicable during MODES 1 and 2, and currently reads as follows: |
| was observed between the cold and hot coolant temperatures. A slight increase inRCCA drop time at lower reactor coolant temperatures is expected. At lower coolant temperatures, the coolant density increases, which increases the resistive force against a dropping RCCA, thereby increasing its drop time. Measured RCCA drop times taken duringMPS3 Cycle-10 startup were less than 1.6 seconds, and measuring the RCCA drop time at 500 F is expected to increase the RCCA drop time by less than 0.15 seconds. This wouldresult in a drop time estimate at 500 F of approximately 1.75 seconds. Based on the above,the licensee concluded that, there is sufficient margin to accommodate the slight increase indrop times as a result of performing the test at a lower temperature without changing the 2.7-seconds limit in TS 3.1.3.4. Since the decrease of the required average reactor coolanttemperature for the rod drop test would increase the rod drop time, the proposed TS change to reduce the temperature from 551 F to 500 F is still well within the existing TS value.The licensee proposes changes to the TS Bases to conform to the proposed TS change. TheNRC staff has no objection to TS Bases updates that address the proposed TS change.4 .0 | | The individual full-length (shutdown and control) rod drop time from the fully withdrawn position shall be less than or equal to 2.7 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with: |
| | : a. Tavg greater than or equal to 551 EF, and |
| | : b. All reactor coolant pumps operating. |
| | The licensees proposed change is to replace 551 EF with 500 EF in subpart a. |
| | The conditions requiring control rods (or the typical terminology: rod cluster control assembly (RCCA)) drop testing are as follows: |
| | Surveillance Requirement (SR) 4.1.3.4 states that the demonstration of required RCCA drop time is required prior to reactor criticality: |
| | : a. For all rods following each removal of the reactor vessel head, |
| | : b. For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and |
| | : c. At least every 24 months. |
| | The RCCA drop test is intended to provide verification that RCCAs will perform as assumed during a reactor trip from power operation. Verification of RCCA drop time allows the licensee |
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| | to determine that actual drop times are consistent with the drop times assumed in the plant's safety analysis. The RCCA drop test ensures that the reactor internals and RCCA drive mechanisms do not interfere with RCCA motion or increase drop time, and that no degradation in the system has occurred that would adversely affect the operability of the RCCAs. |
| | The NRC staff reviewed the results from testing during the initial startup at MPS3. RCCA drop tests were performed at cold (Tavg 145 EF, reactor coolant system (RCS) pressure 390 psia) and hot (Tavg 557 EF, RCS pressure 2250 psia ) reactor coolant temperatures with all reactor coolant pumps operating. The tests demonstrated a slight increase in RCCA drop time as reactor coolant temperature was decreased. Specifically, a drop time increase of less than 0.3 seconds was observed between the cold and hot coolant temperatures. A slight increase in RCCA drop time at lower reactor coolant temperatures is expected. At lower coolant temperatures, the coolant density increases, which increases the resistive force against a dropping RCCA, thereby increasing its drop time. Measured RCCA drop times taken during MPS3 Cycle-10 startup were less than 1.6 seconds, and measuring the RCCA drop time at 500 EF is expected to increase the RCCA drop time by less than 0.15 seconds. This would result in a drop time estimate at 500 EF of approximately 1.75 seconds. Based on the above, the licensee concluded that, there is sufficient margin to accommodate the slight increase in drop times as a result of performing the test at a lower temperature without changing the 2.7-seconds limit in TS 3.1.3.4. Since the decrease of the required average reactor coolant temperature for the rod drop test would increase the rod drop time, the proposed TS change to reduce the temperature from 551 EF to 500 EF is still well within the existing TS value. |
| | The licensee proposes changes to the TS Bases to conform to the proposed TS change. The NRC staff has no objection to TS Bases updates that address the proposed TS change. |
| | 4 .0 |
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| ==SUMMARY== | | ==SUMMARY== |
| The NRC staff has reviewed the license amendment request and concluded that the proposedTS change continues to meet the regulatory requirements as stipulated in GDC 10, 26, 27 and28. Therefore, the NRC staff finds the change is acceptable.
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| ==5.0 STATE CONSULTATION== | | The NRC staff has reviewed the license amendment request and concluded that the proposed TS change continues to meet the regulatory requirements as stipulated in GDC 10, 26, 27 and |
| In accordance with the Commission's regulations, the Connecticut State official was notified ofthe proposed issuance of the amendment. The Connecticut State official agreed with the NRC staff's conclusion as stated in Section 7.0 of this Safety Evaluation. | | : 28. Therefore, the NRC staff finds the change is acceptable. |
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| | ==5.0 STATE CONSULTATION== |
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| | In accordance with the Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The Connecticut State official agreed with the NRC staffs conclusion as stated in Section 7.0 of this Safety Evaluation. |
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| | ==6.0 ENVIRONMENTAL CONSIDERATION== |
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| | The amendment changes a requirement with respect to SRs. 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 change 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 61656). |
| | Accordingly, the amendment meets the eligibility criteria for categorical exclusion as set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or |
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| ==6.0 ENVIRONMENTAL CONSIDERATION==
| | environmental assessment need be prepared in connection with the issuance of the amendment. |
| The amendment changes a requirement with respect to SRs. The NRC staff has determinedthat the amendment involves no significant increase in the amounts, and no significant changein the types, of any effluents that may be released offsite, and that there is no significantchange 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 61656). Accordingly, the amendment meets the eligibility criteria for categorical exclusion as set forth in10 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 theamendment.
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| ==7.0 CONCLUSION== | | ==7.0 CONCLUSION== |
| The NRC staff concludes that: (1) there is reasonable assurance that the health and safety ofthe public will not be endangered by operation in the proposed manner, (2) such activity will beconducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not inimical to the common defense and security or health and safety of thepublic.
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| ==8.0 REFERENCES==
| | The NRC staff concludes 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 activity will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not inimical to the common defense and security or health and safety of the public. |
| 1.NUREG-0800, "Standard Review Plan (SRP) for the Review of Safety Analysis Reportsfor Nuclear Power Plants LWR Edition."2.NUREG 1431, "Standard Technical Specifications Westinghouse Plants."Principal Contributor: F. ForsatyDate: August 15, 2006 Millstone Power Station, Unit No. 3 cc: | |
| 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
| | ==8.0 REFERENCES== |
| | : 1. NUREG-0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants LWR Edition. |
| | : 2. NUREG 1431, Standard Technical Specifications Westinghouse Plants. |
| | Principal Contributor: F. Forsaty Date: August 15, 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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MONTHYEARML0622703892006-08-15015 August 2006
Technical Specification - Changes to the Reactivity Control System Rod Drop Time Test
Project stage: Other
ML0620601462006-08-15015 August 2006
Issuance of Amendment Technical Specification Changes to the Reactivity Control System Rod Drop Time Test
Project stage: Approval
2006-08-15
[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
August 15, 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: TECHNICAL SPECIFICATION CHANGES TO THE REACTIVITY CONTROL SYSTEM ROD DROP TIME TEST (TAC NO. MC8430)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 231 to Facility Operating License No. NPF-49 for Millstone Power Station, Unit No. 3 (MPS3), in response to your application dated September 13, 2005.
The amendment revises the MPS3 Technical Specification temperature requirement for the reactivity control system rod drop time test.
A copy of the related 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. 231 to NPF-49
- 2. Safety Evaluation cc w/encls: See next page
August 15, 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: TECHNICAL SPECIFICATION CHANGES TO THE REACTIVITY CONTROL SYSTEM ROD DROP TIME TEST (TAC NO. MC8430)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 231 to Facility Operating License No. NPF-49 for Millstone Power Station, Unit No. 3 (MPS3), in response to your application dated September 13, 2005.
The amendment revises the MPS3 Technical Specification temperature requirement for the reactivity control system rod drop time test.
A copy of the related 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. 231 to NPF-49
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrPMVNerses PKrohn, RGN-1 LPL1-2 R/F RidsNrrLACRaynor TBoyce RidsAcrsAcnwMailCenter RidsOgcRp GHill (2)
RidsNrrDorlLpl1-2 JNakoski FForsaty Package Accession Number: ML062060099 Amendment Accession Number: ML062060416 TS(s) Accession Number: ML062270389 OFFICE LPLI-2/PM LPLI-2/LA SPWB/C ITSB/C OGC LPLI-2/BC (A)
NAME VNerses:rsa CRaynor JNakoski TKobetz SUttal BPoole DATE 8/9/06 7/27/06 7/31/06 no concurrence req.
8/7/06 8/11/06 OFFICIAL RECORD COPY
DOMINION NUCLEAR CONNECTICUT, INC.
DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 231 License No. NPF-49
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Dominion Nuclear Connecticut, Inc. (the licensee) dated September 13, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 231, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. Dominion Nuclear Connecticut, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of issuance, and shall be implemented within 60 days of issuance.
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 Technical Specifications Date of Issuance: August 15, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 231 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3/4 1-25 3/4 1-25
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 231 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 September 13, 2005, Dominion Nuclear Connecticut, Inc. (DNC or licensee) submitted to the Nuclear Regulatory Commission (NRC or the Commission) a request for a change to the Millstone Power Station, Unit No. 3 (MPS3) Technical Specifications (TSs) temperature requirement for the reactivity control system rod drop time test.
2.0 REGULATORY EVALUATION
The NRC staff reviewed the licensees September 13, 2005, application to verify that the proposed change continues to meet with the regulatory requirements as stipulated in the following General Design Criteria (GDC):
- 1. GDC 10, Reactor design, which requires that the reactor core and associated coolant, control, and protection systems be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
- 2. GDC 26, Reactivity control system redundancy and capability, which requires, among other things, that two independent reactivity control systems of different design principles be provided. GDC 26 also requires that one of the systems shall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions, such as stuck rods, specified acceptable fuel design limits are not exceeded.
- 3. GDC 27, Combined reactivity control systems capability, which requires that the reactivity control systems be designed to have a combined capability, in conjunction with poison addition by the emergency core cooling system, of
reliably controlling reactivity changes to assure that under postulated accident conditions, and with appropriate margin for stuck rods, the capability to cool the core is maintained.
- 4. GDC 28, Reactivity limits, which requires, among other things, that the reactivity control systems be designed with appropriate limits on the potential amount and rate of reactivity increase to assure that the effects of postulated reactivity accidents can neither (1) result in damage to the reactor coolant pressure boundary greater than limited local yielding, nor (2) sufficiently disturb the core, its support structures or other reactor pressure vessel internals to impair significantly the capability to cool the core.
Additionally, the NRC staff verified that the proposed change complies with the MPS3 licensing basis criteria stated in the Final Safety Analysis Report. The staff used Chapter 4.6 of NUREG-0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants LWR Edition, (Reference 1), and NUREG 1431, Standard Technical Specifications Westinghouse Plants, (Reference 2) as guidance during the review.
3.0 TECHNICAL EVALUATION
The licensee has proposed to modify Limiting Condition for Operation 3.1.3.4, which is applicable during MODES 1 and 2, and currently reads as follows:
The individual full-length (shutdown and control) rod drop time from the fully withdrawn position shall be less than or equal to 2.7 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:
- a. Tavg greater than or equal to 551 EF, and
- b. All reactor coolant pumps operating.
The licensees proposed change is to replace 551 EF with 500 EF in subpart a.
The conditions requiring control rods (or the typical terminology: rod cluster control assembly (RCCA)) drop testing are as follows:
Surveillance Requirement (SR) 4.1.3.4 states that the demonstration of required RCCA drop time is required prior to reactor criticality:
- a. For all rods following each removal of the reactor vessel head,
- b. For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and
- c. At least every 24 months.
The RCCA drop test is intended to provide verification that RCCAs will perform as assumed during a reactor trip from power operation. Verification of RCCA drop time allows the licensee
to determine that actual drop times are consistent with the drop times assumed in the plant's safety analysis. The RCCA drop test ensures that the reactor internals and RCCA drive mechanisms do not interfere with RCCA motion or increase drop time, and that no degradation in the system has occurred that would adversely affect the operability of the RCCAs.
The NRC staff reviewed the results from testing during the initial startup at MPS3. RCCA drop tests were performed at cold (Tavg 145 EF, reactor coolant system (RCS) pressure 390 psia) and hot (Tavg 557 EF, RCS pressure 2250 psia ) reactor coolant temperatures with all reactor coolant pumps operating. The tests demonstrated a slight increase in RCCA drop time as reactor coolant temperature was decreased. Specifically, a drop time increase of less than 0.3 seconds was observed between the cold and hot coolant temperatures. A slight increase in RCCA drop time at lower reactor coolant temperatures is expected. At lower coolant temperatures, the coolant density increases, which increases the resistive force against a dropping RCCA, thereby increasing its drop time. Measured RCCA drop times taken during MPS3 Cycle-10 startup were less than 1.6 seconds, and measuring the RCCA drop time at 500 EF is expected to increase the RCCA drop time by less than 0.15 seconds. This would result in a drop time estimate at 500 EF of approximately 1.75 seconds. Based on the above, the licensee concluded that, there is sufficient margin to accommodate the slight increase in drop times as a result of performing the test at a lower temperature without changing the 2.7-seconds limit in TS 3.1.3.4. Since the decrease of the required average reactor coolant temperature for the rod drop test would increase the rod drop time, the proposed TS change to reduce the temperature from 551 EF to 500 EF is still well within the existing TS value.
The licensee proposes changes to the TS Bases to conform to the proposed TS change. The NRC staff has no objection to TS Bases updates that address the proposed TS change.
4 .0
SUMMARY
The NRC staff has reviewed the license amendment request and concluded that the proposed TS change continues to meet the regulatory requirements as stipulated in GDC 10, 26, 27 and
- 28. Therefore, the NRC staff finds the change is acceptable.
5.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The Connecticut State official agreed with the NRC staffs conclusion as stated in Section 7.0 of this Safety Evaluation.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to SRs. 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 change 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 61656).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion as 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.
7.0 CONCLUSION
The NRC staff concludes 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 activity will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not inimical to the common defense and security or health and safety of the public.
8.0 REFERENCES
- 1. NUREG-0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants LWR Edition.
- 2. NUREG 1431, Standard Technical Specifications Westinghouse Plants.
Principal Contributor: F. Forsaty Date: August 15, 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
