|
|
| (3 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML072960179 | | | number = ML072960179 |
| | issue date = 10/29/2007 | | | issue date = 10/29/2007 |
| | title = Millstone Power Station, Unit 3 - Request for Additional Information, Stretch Power Uprate Amendment Request (TAC MD6070) | | | title = Request for Additional Information, Stretch Power Uprate Amendment Request |
| | author name = Lamb J G | | | author name = Lamb J |
| | 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, Virginia Electric & Power Co (VEPCO) | | | addressee affiliation = Dominion Nuclear Connecticut, Inc, Virginia Electric & Power Co (VEPCO) |
| | docket = 05000423 | | | docket = 05000423 |
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:October 29, 2007 | | {{#Wiki_filter:October 29, 2007 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 |
| | |
| Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| MILLSTONE POWER STATION, UNIT NO. 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING STRETCH POWER UPRATE AMENDMENT REQUEST (TAC NO. MD6070) | | MILLSTONE POWER STATION, UNIT NO. 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING STRETCH POWER UPRATE AMENDMENT REQUEST (TAC NO. MD6070) |
|
| |
|
| ==Dear Mr. Christian:== | | ==Dear Mr. Christian:== |
|
| |
|
| By letter dated July 13, 2007, as supplemented on September 12, 2007, Dominion Nuclear | | By letter dated July 13, 2007, as supplemented on September 12, 2007, Dominion Nuclear Connecticut, Inc. submitted a stretch power uprate license amendment request for Millstone Power Station, Unit No. 3. The proposed license amendment would allow an increase in the maximum authorized core power level from 3411 megawatts thermal (MWt) to 3650 MWt, and would make changes to the Technical Specifications, as necessary, to support operation at the stretch power level. |
| | | In order to complete its review of the reports, the U.S. Nuclear Regulatory Commission staff requires responses to the enclosed questions. The questions were sent by e-mail on October 15 and 19, 2007, and were discussed via teleconference on October 23, 2007, with your staff to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. Mr. Mohamed Elmaghrabi of your staff agreed to respond within 21 days of the date of this letter. |
| Connecticut, Inc. submitted a stretch power uprate license amendment request for Millstone Power Station, Unit No. 3. The proposed license amendment would allow an increase in the maximum authorized core power level from 3411 megawatts thermal (MWt) to 3650 MWt, and would make changes to the Technical Specifications, as necessary, to support operation at the stretch power level. | | Please note that if you do not respond to this letter within the prescribed response times or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-3100. |
| | | Sincerely, |
| In order to complete its review of the reports, the U.S. Nuclear Regulatory Commission staff requires responses to the enclosed questions. The questions were sent by e-mail on October 15 and 19, 2007, and were discussed via teleconference on October 23, 2007, with your staff to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. Mr. Mohamed Elmaghrabi of your staff agreed to respond within 21 days of the date of this letter. | | /RA/ |
| | | John G. Lamb, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423 |
| Please note that if you do not respond to this letter within the prescribed response times or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-3100. | |
| | |
| Sincerely, | |
| /RA/
| |
| John G. Lamb, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
| | |
| Docket No. 50-423 | |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| As stated | | As stated cc w/encl: See next page |
| | |
| cc w/encl: See next page | |
|
| |
|
| ML072960179 | | ML072960179 |
| * Concurrence provided by memo OFFICE LPL1-2/PM LPL1-2/LA DCI/CVIB/BC LPL1-2BC NAME JLamb ABaxter MMitchell HChernoff DATE 10 / 25 /07 10 / 25 /07 08/27/07 | | * Concurrence provided by memo OFFICE LPL1-2/PM LPL1-2/LA DCI/CVIB/BC LPL1-2BC NAME JLamb ABaxter MMitchell HChernoff DATE 10 / 25 /07 10 / 25 /07 08/27/07 |
| * 10 / 25 /07 Enclosure REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT No. 3 STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST TAC NO. MD6070 DOCKET NO. 50-423 By letter dated July 13, 2007, as supplemented on September 12, 2007, Dominion Nuclear Connecticut, Inc. (DNC or licensee) submitted a stretch power uprate (SPU) license amendment request for Millstone Power Station, Unit No. 3 (MPS3). The proposed license amendment would allow an increase in the maximum authorized core power level from 3411 megawatts thermal (MWt) to 3650 MWt, and would make changes to the Technical Specifications, as necessary, to support operation at the stretch power level. | | * 10 / 25 /07 REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT No. 3 STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST TAC NO. MD6070 DOCKET NO. 50-423 By letter dated July 13, 2007, as supplemented on September 12, 2007, Dominion Nuclear Connecticut, Inc. (DNC or licensee) submitted a stretch power uprate (SPU) license amendment request for Millstone Power Station, Unit No. 3 (MPS3). The proposed license amendment would allow an increase in the maximum authorized core power level from 3411 megawatts thermal (MWt) to 3650 MWt, and would make changes to the Technical Specifications, as necessary, to support operation at the stretch power level. |
| | | The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. |
| The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. | | Vessels & Internals Integrity Branch CVIB-07-001 Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, provides fracture toughness requirements for ferritic materials (low alloy steel or carbon steel) materials in the reactor coolant pressure boundary (RCPB) components. 10 CFR Part 50, Appendix G also identifies that RCPB materials must satisfy the criteria in Appendix G of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) to ensure the structural integrity of the ferritic components of the RCPB during any condition of normal operation, including anticipated operational occurrences and hydrostatic tests. |
| | | Consistent with the requirements specified in 10 CFR Part 50, Appendix G, the licensee performed fracture toughness analyses of the ferritic reactor vessel (RV) materials. |
| Vessels & Internals Integrity Branch | | The staff requests that the licensee confirm that these analyses bound the fracture toughness requirements of the ferritic RCPB components other than the RV components at MPS3. |
| | | CVIB-07-002 Section 2.1.2.2-1 delineates the difference between 1/4T neutron fluence (E > 1 MeV) estimated in the license extension application and the value proposed in the current application for SPU, i.e., 1.97x1019 n/cm2 and 1.63x1019 n/cm2, respectively. Similarly, Section 2.1.3.2.3 indicates a similar difference between the peak inside surface vessel fluence to 54 effective full power years (EFPYs) of operation. Apparently, both calculations were carried out using methodologies adhering to the guidance in Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence. |
| CVIB-07-001 | |
| | |
| Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, provides fracture toughness requirements for ferritic materials (low alloy steel or carbon steel) materials in the reactor coolant pressure boundary (RCPB) components. 10 CFR Part 50, Appendix G also identifies that RCPB materials must satisfy the criteria in Appendix G of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) to ensure the structural integrity of the ferritic components of the RCPB during any condition of normal operation, including anticipated operational occurrences and hydrostatic tests. | |
| | |
| Consistent with the requirements specified in 10 CFR Part 50, Appendix G, the licensee performed fracture toughness analyses of the ferritic reactor vessel (RV) materials. | |
| | |
| The staff requests that the licensee confirm that these analyses bound the fracture toughness requirements of the ferritic RCPB components other than the RV components at MPS3. | |
| | |
| CVIB-07-002 Section 2.1.2.2-1 delineates the difference between 1/4T neutron fluence (E > 1 MeV) estimated in the license extension application and the value proposed in the current application for SPU, i.e., 1.97x10 19 n/cm 2 and 1.63x10 19 n/cm 2, respectively. Similarly, Section 2.1.3.2.3 indicates a similar difference between the peak inside surface vessel fluence to 54 effective full power years (EFPYs) of operation. Apparently, both calculations were carried out using methodologies adhering to the guidance in Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence." | |
| | |
| Please describe the physical reasons that justify the lower fluence value for the 54 EFPYs under SPU conditions. | | Please describe the physical reasons that justify the lower fluence value for the 54 EFPYs under SPU conditions. |
| CVIB-07-003
| | Enclosure |
| | |
| In 2001, one Babcock and Wilcox licensee experienced failures of two control rod drive mechanism 17-4 precipitation hardened (PH) lead screw male couplings. The failures were attributed to thermal embrittlement of the 17-4 PH martensitic stainless steel materials.
| |
| | |
| The staff issued NRC Information Notice (IN) 2007-02, AFailure of Control Rod Drive Mechanism Lead Screw Male Coupling at a Babcock and Wilcox Designed Facility.
| |
| @ In IN 2007-02, the staff reiterated the importance of implementing frequent visual and surface examinations for identifying thermal embrittlement in 17-4 PH martensitic stainless steel reactor vessel internals (RVI) components.
| |
|
| |
|
| The staff requests that the licensee provide the following information with respect to monitoring the aging degradation of the 17-4 PH martensitic stainless steel materials used in RVI components at MPS3: 1. Identify 17-4 PH martensitic stainless steel RVI components at MPS3, if any. | | CVIB-07-003 In 2001, one Babcock and Wilcox licensee experienced failures of two control rod drive mechanism 17-4 precipitation hardened (PH) lead screw male couplings. The failures were attributed to thermal embrittlement of the 17-4 PH martensitic stainless steel materials. |
| | The staff issued NRC Information Notice (IN) 2007-02, AFailure of Control Rod Drive Mechanism Lead Screw Male Coupling at a Babcock and Wilcox Designed Facility.@ In IN 2007-02, the staff reiterated the importance of implementing frequent visual and surface examinations for identifying thermal embrittlement in 17-4 PH martensitic stainless steel reactor vessel internals (RVI) components. |
| | The staff requests that the licensee provide the following information with respect to monitoring the aging degradation of the 17-4 PH martensitic stainless steel materials used in RVI components at MPS3: |
| | : 1. Identify 17-4 PH martensitic stainless steel RVI components at MPS3, if any. |
| : 2. Identify the method of inspection that was performed thus far on these components and provide information regarding any aging degradation that was identified thus far in these components. | | : 2. Identify the method of inspection that was performed thus far on these components and provide information regarding any aging degradation that was identified thus far in these components. |
| Balance of Plant Branch | | Balance of Plant Branch SBPB-07-004 In Attachment 5, on page 2.5-114, under the section ATurbine Driven Feedwater Pump Turbine Control Valves,@ the licensee stated in the application that A[the] engineering evaluation to confirm whether or not more steam flow is required for turbine driven feedwater pump turbines for SPU conditions is in progress.@ |
| | | The NRC staff cannot initiate a review of this section until the results of the evaluation and a description of any impacts or modifications are submitted. |
| SBPB-07-004 | | Please provide the results of the evaluation and a description of any impacts or modifications. |
| | | SBPB-07-005 In Attachment 5, on page 2.5-22, under the section, ATurbine Results,@ DNC performed high-pressure turbine rotor phased array testing of the tangential-entry dovetail regions of the wheel rim, which revealed indications on the turbine first stage wheel. DNC is currently evaluating either installing a new high-pressure rotor, or disassembling first stage buckets, conducting inspections, removing indications and possible repairs. DNC needs to identify their proposed resolution and affects on the proposed SPU before the NRC staff can complete its review. |
| In Attachment 5, on page 2.5-114, under the section ATurbine Driven Feedwater Pump Turbine Control Valves,@ the licensee stated in the application that A[the] engineering evaluation to confirm whether or not more steam flow is required for turbine driven feedwater pump turbines for SPU conditions is in progress. | |
| @ The NRC staff cannot initiate a review of this section until the results of the evaluation and a description of any impacts or modifications are submitted.
| |
| | |
| Please provide the results of the evaluation and a description of any impacts or modifications. | |
| | |
| SBPB-07-005 | |
| | |
| In Attachment 5, on page 2.5-22, under the section, ATurbine Results,@ DNC performed high-pressure turbine rotor phased array testing of the tangential-entry dovetail regions of the wheel rim, which revealed indications on the turbine first stage wheel. DNC is currently evaluating either installing a new high-pressure rotor, or disassembling first stage buckets, conducting inspections, removing indications and possible repairs. DNC needs to identify their proposed resolution and affects on the proposed SPU before the NRC staff can complete its review. | |
| | |
| Millstone Power Stat ion, Unit No. 3
| |
| | |
| cc:
| |
| | |
| Lillilan M. Cuoco, Esquire Senior Counsel Dominion Resources Services, Inc.
| |
| Building 475, 5 th Floor Rope Ferry Road Waterford, CT 06385
| |
| | |
| Edward L. Wilds, Jr., Ph.D.
| |
| Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
| |
| | |
| Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
| |
| | |
| First Selectmen Town of Waterford 15 Rope Ferry Road Waterford, CT 06385
| |
| | |
| Mr. J. W. "Bill" Sheehan Co-Chair NEAC 19 Laurel Crest Drive 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
| |
| | |
| Mr. Joseph Roy, Director of Operations Massachusetts Municipal Wholesale Electric Company Moody Street P.O. Box 426 Ludlow, MA 01056
| |
| | |
| Mr. J. Alan Price Site Vice President Dominion Nuclear Connecticut, Inc.
| |
| Building 475, 5 th Floor Rope Ferry Road Waterford, CT 06385
| |
| | |
| Mr. Chris Funderburk Director, Nuclear Licensing and Operations Support Dominion Resources Services, Inc.
| |
| 5000 Dominion Boulevard Glen Allen, VA 23060-6711
| |
|
| |
|
| Mr. David W. Dodson Licensing Supervisor Dominion Nuclear Connecticut, Inc. | | Millstone Power Station, Unit No. 3 cc: |
| Building 475, 5 th Floor Rope Ferry Road Waterford, CT 06385}} | | 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}} |
Letter Sequence RAI |
|---|
|
Initiation
- Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
|
MONTHYEARML0720002812007-07-13013 July 2007
License Amendment Request - Stretch Power Uprate - Supplemental Information
Project stage: Supplement
ML0720003862007-07-13013 July 2007
License Amendment Request, Stretch Power Uprate
Project stage: Request
ML0726702162007-10-15015 October 2007
Stretch Power Uprate Acceptance Review
Project stage: Acceptance Review
ML0727005452007-10-18018 October 2007
Westinghouse Electric Company LLC Request for Withholding Information from Public Disclosure Regarding Letter (CAW-07-2296), Subject: NEU-07-128 P-Attachment, Millstone Nuclear Power Station Unit 2 Stretch Power Uprate Program Supplemental
Project stage: Withholding Request Acceptance
ML0729601792007-10-29029 October 2007
Request for Additional Information, Stretch Power Uprate Amendment Request
Project stage: RAI
ML0732309762007-11-19019 November 2007
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request
Project stage: Response to RAI
ML0731706652007-11-26026 November 2007
Request for Additional Information on Instrumentation and Controls and Fire Protection Regarding Stretch Power Uprate Amendment Request
Project stage: RAI
ML0734802402007-12-13013 December 2007
Supplemental Information for License Amendment Request Stretch Power Uprate
Project stage: Supplement
ML0733703842007-12-14014 December 2007
Request for Additional Information on the Stretch Power Uprate Amendment Request
Project stage: RAI
ML0732500812007-12-14014 December 2007
Westinghouse Electric Company LLC Request for Withholding Information from Public Disclosure Regarding Letter (CAW-07-2252), Subject: WCAP-16271-P, Millstone Unit 3 Spent Fuel Pool Criticality Safety Analysis, March 2007 (Proprietary), Date
Project stage: Withholding Request Acceptance
ML0735200512007-12-17017 December 2007
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request
Project stage: Response to RAI
ML0801006002008-01-10010 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions EEEB-07-0049 Through EEEB-07-0057
Project stage: Response to RAI
ML0801006112008-01-10010 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question CPNB-07-0048
Project stage: Response to RAI
ML0801006042008-01-10010 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question AADB-07-0012
Project stage: Response to RAI
ML0801006062008-01-10010 January 2008
Response to Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions SCVB-07-0058 and SCVB-07-0059
Project stage: Response to RAI
ML0805804762008-01-11011 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions SRXB-07-0013 Through SRXB-07-0047
Project stage: Response to RAI
ML0801704952008-01-11011 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question EMCB-07-0070
Project stage: Response to RAI
ML0801400772008-01-11011 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Response to Questions SBPB-07-0082 Through SBPB-07-0087
Project stage: Response to RAI
ML0801106952008-01-11011 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Response to Questions CSGB-07-0010 and CSGB-07-0011
Project stage: Response to RAI
ML0801405702008-01-14014 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions EMCB-07-0060 Through EMCB-07-0069 and EMCB-07-0071 Through EMCB-07-0081
Project stage: Response to RAI
ML0802205062008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question EICB-07-0106
Project stage: Response to RAI
ML0802205272008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question SBPB-07-0105
Project stage: Response to RAI
ML0802205302008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions SCVB-07-0091 Through SCVB-07-0104
Project stage: Response to RAI
ML0802205412008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Questions SRXB-07-0088 Through SRXB-07-0090
Project stage: Response to RAI
ML0802803752008-01-18018 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Response to Question AADB-07-0107
Project stage: Response to RAI
ML0803203082008-01-31031 January 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question EMCB-07-0070
Project stage: Response to RAI
ML0805603922008-02-25025 February 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Supplemental Response to Question EMCB-07-0072
Project stage: Supplement
ML0805606152008-02-25025 February 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Revised and Supplemental Responses to Questions AFPB-07-0007 & AFPB-07-0008
Project stage: Supplement
ML0807103912008-03-10010 March 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question SCVB-07-0091
Project stage: Response to RAI
ML0807103772008-03-10010 March 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Response to Question AADB-07-0107
Project stage: Response to RAI
ML0803501322008-03-13013 March 2008
Request for Withholding Information from Public Disclosure Regarding Millstone Power Station, Unit 3
Project stage: Withholding Request Acceptance
ML0808405272008-03-17017 March 2008
Nancy Burton Petition to Intervene and Request for Hearing
Project stage: Request
ML0808508942008-03-25025 March 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Supplemental Response to Question EEEB-07-0052
Project stage: Supplement
ML0808802682008-03-27027 March 2008
Supplemental Information Regarding Stretch Power Uprate License Amendment Request
Project stage: Supplement
ML0804606202008-03-28028 March 2008
Potential Schedule Change for Proposed Stretch Power Uprate License Amendment Request
Project stage: Other
ML0814300142008-04-0404 April 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Supplemental Response to Question EMCB-07-0072
Project stage: Supplement
ML0810800242008-04-23023 April 2008
Request for Additional Information, Stretch Power Uprate Amendment Request
Project stage: RAI
ML0811506792008-04-24024 April 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Supplemental Information, Rod Withdrawal at Power Event
Project stage: Supplement
ML0812006432008-04-29029 April 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Revised Response to Questions EEEB-07-0052, EEEB-07-0054 and EEEB-07-0055
Project stage: Response to RAI
ML0813606252008-05-15015 May 2008
Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request Revised Response to Follow-ups EEEB-08-0108 Through EEEB08-0113 to Question EEEB-07-0052
Project stage: Response to RAI
ML0814204432008-05-20020 May 2008
Supplemental Information Regarding Stretch Power Uprate License Amendment Request Miscellaneous Updates to the License Amendment Request
Project stage: Supplement
ML0814208242008-05-21021 May 2008
Stretch Power Uprate License Amendment Request Additional Information in Connection with the NRC Audit Held on May 13, 2008 in Rockville, Maryland
Project stage: Request
ML0808704572008-05-29029 May 2008
Draft Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate
Project stage: Draft Other
ML0817502222008-06-16016 June 2008
Notice of Appeal
Project stage: Request
ML0819302742008-07-10010 July 2008
Stretch Power Uprate License Amendment Request DNC Comments on Draft Safety Evaluation - Stretch Power Uprate
Project stage: Draft Request
ML0819307572008-07-11011 July 2008
Follow-up to Dominion Nuclear Connecticut, Inc. Letter, Dated July 10, 2008, Regarding the Draft Safety Evaluation - Stretch Power Uprate
Project stage: Draft Approval
ML0819901122008-07-16016 July 2008
Stretch Power Uprate License Amendment Request - Supplement to DNC Comments on Draft Safety Evaluation - Stretch Power Uprate
ML0819300702008-07-30030 July 2008
Final Environmental Assessment and Finding of No Significant Impact for Proposed Stretch Power Uprate
Project stage: Other
ML0816105852008-08-12012 August 2008
License Amendment, Stretch Power Uprate
Project stage: Other
ML0822504182008-08-12012 August 2008
Stretch Power Uprate, Tec Specs to Amd 242
Project stage: Acceptance Review
2008-03-17
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24317A2562024-11-12012 November 2024
Core Operating Limits Report, Gycle 30
IR 05000245/20240012024-11-12012 November 2024
Safstor Inspection Report 05000245/2024001
IR 05000336/20240032024-11-0707 November 2024
Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001
ML24289A0152024-10-21021 October 2024
Review of the Fall 2023 Steam Generator Tube Inspection Report
05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024
Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary
IR 05000336/20244022024-10-0808 October 2024
Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only)
ML24281A1102024-10-0707 October 2024
Requalification Program Inspection
05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024
Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
ML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
ML24260A2192024-09-16016 September 2024
Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification
ML24260A1952024-09-16016 September 2024
Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel
ML24248A2272024-09-0404 September 2024
Operator Licensing Examination Approval
ML24240A1532024-09-0303 September 2024
Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel
IR 05000336/20240052024-08-29029 August 2024
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005
IR 05000336/20240022024-08-13013 August 2024
Integrated Inspection Report 05000336/2024002 and 05000423/2024002
ML24221A2872024-08-0808 August 2024
Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage
IR 05000336/20244412024-08-0606 August 2024
Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only)
ML24212A0742024-08-0505 August 2024
Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification
ML24211A1712024-07-25025 July 2024
Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change
IR 05000336/20244032024-07-22022 July 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403
IR 05000336/20245012024-07-0101 July 2024
Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501
ML24180A0932024-06-28028 June 2024
Readiness for Additional Inspection: EA-23-144
IR 05000336/20240102024-06-26026 June 2024
Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010
ML24178A2422024-06-25025 June 2024
2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46
IR 05000336/20244402024-06-24024 June 2024
Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only)
ML24176A2622024-06-20020 June 2024
Update to the Final Safety Analysis Report, Revision 37
ML24176A1782024-06-20020 June 2024
Update to the Final Safety Analysis Report
ML24281A2072024-06-20020 June 2024
Update to the Final Safety Analysis Report, Revision 37 (Redacted Version)
ML24177A2792024-06-20020 June 2024
Preparation and Scheduling of Operator Licensing Examinations
ML24280A0012024-06-20020 June 2024
Update to the Final Safety Analysis Report (Redacted Version)
05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024
Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications
ML24170B0532024-06-10010 June 2024
DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code
ML24165A1292024-06-0505 June 2024
ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023
ML24128A2772024-06-0404 June 2024
Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary)
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
ML24110A0562024-05-21021 May 2024
Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter)
ML24109A0032024-05-21021 May 2024
Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary)
05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024
Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
ML24142A0952024-05-20020 May 2024
End of Cycle 22 Steam Generator Tube Inspection Report
ML24141A2432024-05-20020 May 2024
Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15
IR 05000336/20240012024-05-14014 May 2024
Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation
05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024
Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
ML24123A2042024-05-0202 May 2024
Pre-Decisional Replay to EA-23-144
IR 05000336/20244012024-04-30030 April 2024
Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only)
ML24123A1222024-04-30030 April 2024
Inservice Inspection Program - Owners Activity Report, Refueling Outage 22
ML24116A0452024-04-25025 April 2024
Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only)
ML24114A2662024-04-24024 April 2024
Submittal of 2023 Annual Radioactive Effluent Release Report
ML24116A1742024-04-24024 April 2024
Annual Radiological Environmental Operating Report
ML24103A0202024-04-22022 April 2024
Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits
ML24106A2032024-04-15015 April 2024
2023 Annual Environmental Operating Report
2024-09-04
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24213A2602024-07-31031 July 2024
Request for Additional Information LAR to Support Implementation of Framatome Gaia Fuel
IR 05000336/20244032024-07-22022 July 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403
ML24113A2502024-04-22022 April 2024
Request for Additional Information (e-mail 4/22/2024) License Renewal Commitment for Aging Management Program of Alloy 600 Components
ML24065A3112024-03-0505 March 2024
Request for Additional Information (Redacted) (03/05/2025 E-mail from R. Guzman to S. Sinha) Framatome Gaia Fuel LOCA LAR
ML23318A0952023-11-14014 November 2023
Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel
ML23199A2832023-07-18018 July 2023
Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits
ML23171B0522023-06-20020 June 2023
NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted)
ML23089A1882023-03-29029 March 2023
Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report
ML23073A1802023-03-14014 March 2023
Notification of Commercial Grade Dedication Inspection (05000336/2023010 and 05000423/2023010) and Request for Information
ML22251A1292022-09-0909 September 2022
Request for Additional Information Related to Response to Generic Letter 2004-04
ML22242A0452022-08-23023 August 2022
NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000)
ML21225A5022021-08-13013 August 2021
Request for Additional Information for North Anna Power Station, Units 1 and 2, Surry Power Station, Units 1 and 2, and Millstone Power Station, Units 2 and 3, Appendix E of Fleet Report Com-Naf-2 (EPID:L02021-LLT-0000) Public Version
ML21195A2442021-07-13013 July 2021
NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code
ML21182A2902021-07-0101 July 2021
7/1/2021 E-mail - Request for Additional Information Alternative Frequency to Supplemental Valve Position Verification Testing Requirements
ML21112A3082021-04-22022 April 2021
Request for Additional Information (E-mail Dated 4/22/2021) License Amendment Request for Measurement Uncertainty Recapture Power Uprate
ML21105A1152021-04-15015 April 2021
Request for Additional Information (e-mail Dated 4/15/2021) Proposed LAR for Addition of Analytical Methodology to the Core Operating Limits Report for a LBLOCA
ML21078A0332021-03-18018 March 2021
NRR E-mail Capture - Millstone Power Station, Unit 2 - Request for Additional Information - Proposed LAR to Revise TSs for Steam Generator Inspection Frequency
ML21076A4622021-03-17017 March 2021
NRR E-mail Capture - Draft RAI for Versatile Internals and Component Program for Reactors Vipre Code Review (L-2021-LLT-0000)
ML21077A1652021-02-26026 February 2021
(02/26/2021 E-mail) Draft Request for Additional Information LAR to Revise Technical Specifications for Steam Generator Inspection Frequency
ML21034A5762021-02-0303 February 2021
Request for Additional Information (e-mail Dated 1/3/2021) Alternative Request RR-05-06 Inservice Inspection Interval Extension for Steam Generator Weld Inspections
ML20246G5612020-09-0202 September 2020
Request for Additional Information (E-mail Dated 9/2/2020) License Amendment Request for a One-Time Deferral of the Steam Generator Inspections
ML20244A2902020-08-31031 August 2020
Request for Additional Information (E-mail Dated 8/31/2020) License Amendment Request to Revise Battery Surveillance Requirements
ML20231A7172020-08-18018 August 2020
Request for Additional Information (e-mail Dated 8/18/2020) License Amendment Request to Revise TS Table 3.3-11 Accident Monitoring Instrumentation
ML20184A0052020-07-0202 July 2020
Request for Additional Information (E-mail Dated 7/2/2020) Relief Request IR-3-33 for Limited Coverage Examiniations
ML20075A0322020-03-15015 March 2020
Request for Additional Information (E-mail Dated 3/15/2020) Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity
ML20050F9212020-02-19019 February 2020
Request for Additional Information (E-mail Dated 2/19/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating
ML20023D0372020-01-23023 January 2020
Request for Additional Information (E-mail Dated 1/23/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating
ML19361A0382019-12-23023 December 2019
12/23/19 E-mail from R.Guzman to S. Sinha - Draft Request for Additional Information Planned Audit of LAR to Revise TS 3.8.1.1
ML19277B9082019-10-0707 October 2019
Supplemental Information Needed for Acceptance of Requested Licensing Action Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time
ML19248D7552019-09-0505 September 2019
Request for Additional Information Via E-mail from R.Guzman to S. Sinha Proposed License Amendment Request to Adopt 10 CFR 50.69
ML19169A0962019-06-17017 June 2019
NRR E-mail Capture - Request for Additional Information Emergency Action Level Scheme Change for Millstone Power Station - Units 1, 2, and 3, North Anna Power Station - Units 1 and 2, and Surry Power Station - Units 1 and 2
ML19162A0052019-06-10010 June 2019
NRR E-mail Capture - Draft RAIs for Dominion EAL Scheme Change
ML19042A1822019-02-11011 February 2019
Request for Additional Information LAR for TS Changes to Spent Fuel Storage and New Fuel Storage, 02/11/2019 E-mail from R. Guzman to S. Sinha
ML18291B3262018-10-18018 October 2018
Request for Additional Information LAR Regarding Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage, E-mail from R.Guzman to S.Sinha
ML18277A1762018-10-0404 October 2018
Request for Additional Information LAR to Revise TS Action Statement for Loss of Control Building Inlet Ventilation Rad Monitor Instrumentation Channels (e-mail from R.Guzman to M.Whitlock, EPID: L-2018-LLA-0099)
ML18213A1152018-08-0101 August 2018
Request for Additional Information Alternative Request P-06 'C' Charging Pump (08/01/2018 E-mail from R. Guzman to M. Whitlock)
ML18171A1532018-06-20020 June 2018
Request for Additional Information Via E-mail from R.Guzman to W.Craft Alternative Requests for Inservice Testing Program (E-mail from R.Guzman to W.Craft) (EPID: L-2018-LLR-0012-LLR-0022)
ML18137A3132018-05-17017 May 2018
Request for Additional Information Via E-mail from R.Guzman to W.Craft Proposed License Amendment Request to Revise ILRT Type a and Type C Test Intervals
ML17297A8472017-10-27027 October 2017
Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools (CAC No. MF9430; EPID L-2016-LRC-0001)
ML17033B6142017-02-0202 February 2017
Request for Additional Information, 2017/02/02 E-mail from R.Guzman to W.Craft Proposed Alternative RR-04-24 and IR-3-30 for the Elimination of Reactor Pressure Vessel Threads in Flange Examination (CAC Nos. MF8468/MF8469)
ML17005A3282017-01-0505 January 2017
MPS2 EOC-23 and MPS3 EOC-17 Steam Generator Tube Inspection Reports - Requests for Additional Information
ML16260A0062016-09-16016 September 2016
2016/09/16 E-mail from R. Guzman to W. Craft Request for Additional Information - License Amendment Request Realistic Large Break Loss of Coolant Accident Analysis (MF7761)
ML16267A0022016-09-12012 September 2016
2016/09/12 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Revise ECCS TS and FSAR Ch. 14 to Remove Charging (MF7297)
ML16133A3562016-05-12012 May 2016
E-mail from R. Guzman to C. Sly Request for Additional Information Supporting License Amendment Request to Remove Charging Credit
ML16068A4142016-03-0808 March 2016
Request for Additional Information - Relief Request RR-04-19 Examination Cat R-A, Risk-Informed Piping Examinations (MF6569)
ML16055A5302016-02-24024 February 2016
2016/02/24 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Adopt Dominion Core Design and Safety Analysis Methods (MF6251)
ML16047A1712016-02-16016 February 2016
2016/02/16 E-mail from R.Guzman to M. Whitlock Request for Additional Information - Small Break Loss of Coolant Accident Re-Analysis (MF6700)
ML16043A5232016-02-12012 February 2016
Request for Additional Information 2016/02/12 E-mail from R. Guzman to M.Whitlock Relief Requests IR-3-22 and IR-3-23 (CAC Nos. MF6573 and MF6574)
ML16013A4772016-01-13013 January 2016
NRR E-mail Capture - Millstone Power Station, Units 2 and 3 - Request for Additional Information License Amendment Request for Removal of Severe Line Outage Detection (Slod) from the Offsite Power System - (MF6430, MF6431)
ML16011A5172016-01-11011 January 2016
NRR E-mail Capture - Millstone Power Station, Unit 3, Reactor Vessel Surveillance Capsule Withdrawal Schedule - Request for Additional Information
2024-07-31
[Table view] |
Text
October 29, 2007 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING STRETCH POWER UPRATE AMENDMENT REQUEST (TAC NO. MD6070)
Dear Mr. Christian:
By letter dated July 13, 2007, as supplemented on September 12, 2007, Dominion Nuclear Connecticut, Inc. submitted a stretch power uprate license amendment request for Millstone Power Station, Unit No. 3. The proposed license amendment would allow an increase in the maximum authorized core power level from 3411 megawatts thermal (MWt) to 3650 MWt, and would make changes to the Technical Specifications, as necessary, to support operation at the stretch power level.
In order to complete its review of the reports, the U.S. Nuclear Regulatory Commission staff requires responses to the enclosed questions. The questions were sent by e-mail on October 15 and 19, 2007, and were discussed via teleconference on October 23, 2007, with your staff to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. Mr. Mohamed Elmaghrabi of your staff agreed to respond within 21 days of the date of this letter.
Please note that if you do not respond to this letter within the prescribed response times or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If you have any questions, I can be reached at (301) 415-3100.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
As stated cc w/encl: See next page
ML072960179
- Concurrence provided by memo OFFICE LPL1-2/PM LPL1-2/LA DCI/CVIB/BC LPL1-2BC NAME JLamb ABaxter MMitchell HChernoff DATE 10 / 25 /07 10 / 25 /07 08/27/07
- 10 / 25 /07 REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT No. 3 STRETCH POWER UPRATE LICENSE AMENDMENT REQUEST TAC NO. MD6070 DOCKET NO. 50-423 By letter dated July 13, 2007, as supplemented on September 12, 2007, Dominion Nuclear Connecticut, Inc. (DNC or licensee) submitted a stretch power uprate (SPU) license amendment request for Millstone Power Station, Unit No. 3 (MPS3). The proposed license amendment would allow an increase in the maximum authorized core power level from 3411 megawatts thermal (MWt) to 3650 MWt, and would make changes to the Technical Specifications, as necessary, to support operation at the stretch power level.
The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
Vessels & Internals Integrity Branch CVIB-07-001 Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, provides fracture toughness requirements for ferritic materials (low alloy steel or carbon steel) materials in the reactor coolant pressure boundary (RCPB) components. 10 CFR Part 50, Appendix G also identifies that RCPB materials must satisfy the criteria in Appendix G of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) to ensure the structural integrity of the ferritic components of the RCPB during any condition of normal operation, including anticipated operational occurrences and hydrostatic tests.
Consistent with the requirements specified in 10 CFR Part 50, Appendix G, the licensee performed fracture toughness analyses of the ferritic reactor vessel (RV) materials.
The staff requests that the licensee confirm that these analyses bound the fracture toughness requirements of the ferritic RCPB components other than the RV components at MPS3.
CVIB-07-002 Section 2.1.2.2-1 delineates the difference between 1/4T neutron fluence (E > 1 MeV) estimated in the license extension application and the value proposed in the current application for SPU, i.e., 1.97x1019 n/cm2 and 1.63x1019 n/cm2, respectively. Similarly, Section 2.1.3.2.3 indicates a similar difference between the peak inside surface vessel fluence to 54 effective full power years (EFPYs) of operation. Apparently, both calculations were carried out using methodologies adhering to the guidance in Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence.
Please describe the physical reasons that justify the lower fluence value for the 54 EFPYs under SPU conditions.
Enclosure
CVIB-07-003 In 2001, one Babcock and Wilcox licensee experienced failures of two control rod drive mechanism 17-4 precipitation hardened (PH) lead screw male couplings. The failures were attributed to thermal embrittlement of the 17-4 PH martensitic stainless steel materials.
The staff issued NRC Information Notice (IN) 2007-02, AFailure of Control Rod Drive Mechanism Lead Screw Male Coupling at a Babcock and Wilcox Designed Facility.@ In IN 2007-02, the staff reiterated the importance of implementing frequent visual and surface examinations for identifying thermal embrittlement in 17-4 PH martensitic stainless steel reactor vessel internals (RVI) components.
The staff requests that the licensee provide the following information with respect to monitoring the aging degradation of the 17-4 PH martensitic stainless steel materials used in RVI components at MPS3:
- 1. Identify 17-4 PH martensitic stainless steel RVI components at MPS3, if any.
- 2. Identify the method of inspection that was performed thus far on these components and provide information regarding any aging degradation that was identified thus far in these components.
Balance of Plant Branch SBPB-07-004 In Attachment 5, on page 2.5-114, under the section ATurbine Driven Feedwater Pump Turbine Control Valves,@ the licensee stated in the application that A[the] engineering evaluation to confirm whether or not more steam flow is required for turbine driven feedwater pump turbines for SPU conditions is in progress.@
The NRC staff cannot initiate a review of this section until the results of the evaluation and a description of any impacts or modifications are submitted.
Please provide the results of the evaluation and a description of any impacts or modifications.
SBPB-07-005 In Attachment 5, on page 2.5-22, under the section, ATurbine Results,@ DNC performed high-pressure turbine rotor phased array testing of the tangential-entry dovetail regions of the wheel rim, which revealed indications on the turbine first stage wheel. DNC is currently evaluating either installing a new high-pressure rotor, or disassembling first stage buckets, conducting inspections, removing indications and possible repairs. DNC needs to identify their proposed resolution and affects on the proposed SPU before the NRC staff can complete its review.
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
