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| | number = ML16070A360 | | | number = ML16070A360 |
| | issue date = 03/09/2016 | | | issue date = 03/09/2016 |
| | title = Millstone Unit 3 - E-mail from R.Guzman to W. Craft Errors in Safety Evaluation - Review of Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3(CAC No. MF5868) | | | title = E-mail from R.Guzman to W. Craft Errors in Safety Evaluation - Review of Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3 |
| | author name = Guzman R V | | | author name = Guzman R |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Craft W D | | | addressee name = Craft W |
| | addressee affiliation = Dominion Nuclear Connecticut, Inc | | | addressee affiliation = Dominion Nuclear Connecticut, Inc |
| | docket = 05000423 | | | docket = 05000423 |
| | license number = NPF-049 | | | license number = NPF-049 |
| | contact person = Guzman R V | | | contact person = Guzman R |
| | case reference number = CAC MF5868 | | | case reference number = CAC MF5868 |
| | document type = E-Mail | | | document type = E-Mail |
| | page count = 1 | | | page count = 1 |
| | project = CAC:MF5868 | | | project = CAC:MF5868 |
| | stage = Other | | | stage = Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: Guzman, Richard Sent: Wednesday, March 09, 2016 2:47 PM To: 'Wanda D Craft (Generation - 6)' | | {{#Wiki_filter:From: Guzman, Richard Sent: Wednesday, March 09, 2016 2:47 PM To: 'Wanda D Craft (Generation - 6)' |
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| ==Subject:== | | ==Subject:== |
| RE: Review of Alternative Request IR 27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3(CAC No. MF5868) Wanda, I agree that the two items you identify below are minor editorial errors. Please consider this email as an official record of the staff's acknowledgement of the identified errors in the subject NRC safety evaluation dated February 16, 2016 (ADAMS Accession No. ML16038A001). From: Wanda D Craft (Generation - 6) [mailto:wanda.d.craft@dom.com] Sent: Tuesday, March 08, 2016 3:25 PM To: Guzman, Richard <Richard.Guzman@nrc.gov> | | RE: Review of Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3(CAC No. MF5868) |
| | : Wanda, I agree that the two items you identify below are minor editorial errors. Please consider this email as an official record of the staffs acknowledgement of the identified errors in the subject NRC safety evaluation dated February 16, 2016 (ADAMS Accession No. ML16038A001). |
| | From: Wanda D Craft (Generation - 6) [mailto:wanda.d.craft@dom.com] |
| | Sent: Tuesday, March 08, 2016 3:25 PM To: Guzman, Richard <Richard.Guzman@nrc.gov> |
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| ==Subject:== | | ==Subject:== |
| [External_Sender] Review of Alternative Request IR 27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3(CAC No. MF5868)
| | [External_Sender] Review of Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3(CAC No. MF5868) |
| | | : Rich, As we discussed, during review of the NRC Safety Evaluation for the MPS3 Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel Third Inservice Inspection Interval dated Feb. 16, 2016, two minor editorial items were noted. On the top of page 4, item 1, 4th sentence, the acronym RTmaxx is defined as Radiographic Testing - maximum. It should be Reference Temperature - maximum. |
| Rich, As we discussed, during review of the NRC Safety Evaluation for the MPS3 Alternative Request IR 27 for Implementation of Extended Reactor Vessel Third Inservice Inspection Interval dated Feb. 16, 2016, two minor editorial items were noted. On the top of page 4, item 1, 4th sentence, the acronym RTmaxx is defined as "Radiographic Testing - maximum." It should be "Reference Temperature - maximum." | | On page 6, second paragraph, the 3rd sentence states .TWCF95-TOTAL for MPS3 was 1.44 x 10-3,. but the correct value for TWCF95-TOTAL is 1.44 x 10-13. |
| On page 6, second paragraph, the 3rd sentence states "-.TWCF95-TOTAL for MPS3 was 1.44 x 10-3,-." but the correct value for TWCF95-TOTAL is 1.44 x 10-13. If you have any questions, please let me know. Thanks. Wanda D. Craft Nuclear Licensing and Operations Support Dominion Resources Services, Inc (804) 273-4687 tie-line 730-4687 CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you. | | If you have any questions, please let me know. Thanks. |
| }} | | Wanda D. Craft Nuclear Licensing and Operations Support Dominion Resources Services, Inc (804) 273-4687 tie-line 730-4687 CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.}} |
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MONTHYEARML16038A0012016-02-16016 February 2016
Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel Inservice Inspection Interval
Project stage: Other
ML16070A3602016-03-0909 March 2016
E-mail from R.Guzman to W. Craft Errors in Safety Evaluation - Review of Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3
Project stage: Approval
2016-02-16
[Table View] |
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Category:E-Mail
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Change in Estimated Review Schedule Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC
ML24024A0202024-01-24024 January 2024
Correction to Safety Evaluation Associated Wit Amendment No. 288 - Revision to Applicability Term for RCS Heat-Up and Cooldown Pressure-Temperature Limitations Figures
ML24024A2452024-01-24024 January 2024
1/24/2024 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in SE for Amendment No. 288 - Revision to Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures
ML23326A0132023-11-22022 November 2023
Acceptance Review Determination LAR to Support Implementation of Framatome Gaia Fuel
ML23318A0952023-11-14014 November 2023
Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel
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Acceptance Review Determination - License Amendment Request Modification of TS SR 4.3.6.a
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E-mail to File - Summary of September 13, 2023, Meeting with Dominion to Discuss Proposed LAR to Support Cycle Reloads Using Framatome Gaia Fuel
ML23265A2302023-09-22022 September 2023
Acceptance Review Determination - License Amendment Request Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC
ML23258A0552023-08-31031 August 2023
Setup of Online Reference Portal and Audit Plan for the NRC Staff'S Review of LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies (08/31/2023 e-mail)
ML23199A2832023-07-18018 July 2023
Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits
ML23172A0752023-06-21021 June 2023
Acceptance Review Determination LAR to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel
ML23171B0522023-06-20020 June 2023
NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted)
ML23145A0052023-05-25025 May 2023
Acceptance Review Determination Exemption to Use Framatome Gaia Fuel Assemblies Containing Fuel Rods Fabricated with M5 Fuel Rod Cladding
ML23145A0042023-05-25025 May 2023
Acceptance Review Determination LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies
ML23115A3022023-04-24024 April 2023
4/24/2023 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Issuance of Amendments Adoption of TSTF-359, Increase Flexibility in Mode Restraints
ML23089A1882023-03-29029 March 2023
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NRR E-mail Capture - RAI for North Anna, 1 & 2, Surry 1 & 2, Millstone, 2 & 3, Request for Approval of App. F Fleet Report DOM-NAF-2-P, Qual of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion VIPRE-D Computer Code
ML23038A0152023-02-0707 February 2023
Acceptance Review Determination LAR to Revise the Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures
ML23024A1522023-01-24024 January 2023
Acceptance Review Determination LAR to Supplement Burnup Credit of Criticality Safety Analysis
ML23018A0352023-01-17017 January 2023
NRR E-mail Capture - Acceptance Review for Fleet Report Re Appendix F of DOM-NAF-2-P (L-2022-LLT-0003)
ML22320A5752022-11-16016 November 2022
E-mail to File - Summary of October 18, 2022, Meeting with Dominion to Discuss Requested Actions for Implementing Framatome Gaia Fuel
ML22298A2052022-10-25025 October 2022
Acceptance Review Determination for Alternative Request for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles
ML22292A3212022-10-19019 October 2022
Acceptance Review Determination for Alternative Request for Containment RSS Pump Periodic Verification Testing Program
ML22297A1802022-10-0707 October 2022
Email Acknowledgement to Dominion Energy Nuclear Decommissioning Trust Fund Disbursement 30 Day Notification for Millstone Power Station Unit 1: Docket No 50-245
ML22278A0932022-10-0505 October 2022
E-mail to File - Summary of September 7, 2022, Meeting with Dominion to Discuss Proposed Supplement to the Spent Fuel Pool Criticality Safety Analysis (EPID L-2022-LRM-0059
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Memo E-mail to File - Summary of August 29, 2022, Meeting with Dominion to Discuss Proposed Alternative Request Post-peening follow-up Volumetric Exam of RPV Head Penetration Nozzle
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Memo E-mail to File - Summary of August 9, 2022, Meeting with Dominion to Discuss Proposed Alternative Reqeust Recirculation Spray Pump Flow Testing (EPID L:2022-LRM-0057)
ML22242A0452022-08-23023 August 2022
NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000)
ML22174A3552022-06-23023 June 2022
NRR E-mail Capture - Acceptance Review for Dominion Fleet LAR to Implement TSTF-554 (L-2022-LLA-0078)
ML22123A0812022-05-0303 May 2022
Acceptance Review Determination for Proposed LAR for TS Change Applicable to TSTF-359, Increase Flexibility in Mode Restraints
ML22069A7192022-03-10010 March 2022
E-mail from R. Guzman to S. Sinha - Millstone Unit 3 Steam Generator Outage Conference Call
ML22020A4122022-01-11011 January 2022
1/11/2022 State Consultation E-mail, R. Guzman to J. Semancik Millstone Power Station, Unit 3 Planned Issuance of Amendment to Clarify Shutdown Bank TS and Add Alternate Control Rod Position Monitoring Requirements
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ML21286A7372021-10-13013 October 2021
Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR
ML21223A3042021-08-11011 August 2021
Request for Withholding Information from Public Disclosure Proposed LAR to Add an Analytical Methodology to the COLR for a Large Break LOCA
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7/19/2021 E-mail Pressurizer Steam Space Line Classification
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
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7/1/2021 E-mail - Request for Additional Information Alternative Frequency to Supplemental Valve Position Verification Testing Requirements
ML21147A2982021-05-27027 May 2021
Correction to Projected Review Completion Date, ASME Section XI Inservice Inspection Program Relief Requests, Limited Coverage Examinations, Third Period, 3rd 10-year Inservice Inspection Interval (EPID L-2020-LLR-0081 to LLR-0088)
ML21141A0482021-05-18018 May 2021
5/18/2021 E-mail Proposed License Amendment Request Measurement Uncertainty Recapture Power Uprate
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
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NRR E-mail Capture - Millstone Unit No. 3 - Acceptance Review Determination: Request for Alternative Frequency to Supplemental Valve Position Indication Verification Testing Requirement
ML21084A0042021-03-25025 March 2021
3/25/2021 E-mail, Acceptance Review Determination, Proposed License Amendment Request to Revise Shutdown Bank TS Requirements and Add Alternate Control Rod Position Monitoring Requirements
2024-02-01
[Table view] |
Text
From: Guzman, Richard Sent: Wednesday, March 09, 2016 2:47 PM To: 'Wanda D Craft (Generation - 6)'
Subject:
RE: Review of Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3(CAC No. MF5868)
- Wanda, I agree that the two items you identify below are minor editorial errors. Please consider this email as an official record of the staffs acknowledgement of the identified errors in the subject NRC safety evaluation dated February 16, 2016 (ADAMS Accession No. ML16038A001).
From: Wanda D Craft (Generation - 6) [1]
Sent: Tuesday, March 08, 2016 3:25 PM To: Guzman, Richard <Richard.Guzman@nrc.gov>
Subject:
[External_Sender] Review of Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel ISI Interval - MPS3(CAC No. MF5868)
- Rich, As we discussed, during review of the NRC Safety Evaluation for the MPS3 Alternative Request IR-3-27 for Implementation of Extended Reactor Vessel Third Inservice Inspection Interval dated Feb. 16, 2016, two minor editorial items were noted. On the top of page 4, item 1, 4th sentence, the acronym RTmaxx is defined as Radiographic Testing - maximum. It should be Reference Temperature - maximum.
On page 6, second paragraph, the 3rd sentence states .TWCF95-TOTAL for MPS3 was 1.44 x 10-3,. but the correct value for TWCF95-TOTAL is 1.44 x 10-13.
If you have any questions, please let me know. Thanks.
Wanda D. Craft Nuclear Licensing and Operations Support Dominion Resources Services, Inc (804) 273-4687 tie-line 730-4687 CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.
