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| If the current P-T limit curves do not consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period, provide appropriately revised P-T limit curves to the NRC for review. | | If the current P-T limit curves do not consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period, provide appropriately revised P-T limit curves to the NRC for review. |
| Please submit the response to these RAIs by February 15, 2015. If you have any questions please contact me at your earliest. | | Please submit the response to these RAIs by February 15, 2015. If you have any questions please contact me at your earliest. |
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MONTHYEARML14246A1902014-08-27027 August 2014 Proposed License Amendment Request, Clarification of Reactor Coolant System Heatup and Cooldown Technical Specification Figures Project stage: Request ML14265A0022014-09-18018 September 2014 NRR E-mail Capture - Acceptance Review: North Anna Power Station Units 1 and 2, Revise Technical Specifications (TS)-Clarification of RCS Heatup and Cooldown TS Figures (TACs MF4707 and MF4708) Project stage: Acceptance Review ML15015A6662015-01-14014 January 2015 NRR E-mail Capture - NAPS 1&2: RAI-CLARIFICATION of Reactor Coolant System Heatup and Cooldown Technical Specification Figures (Tac. Nos. MF4707 and MF4708) Project stage: Other ML15051A3682015-02-16016 February 2015 Response to Request for Additional Information Proposed License Amendment Request Clarification of Reactor Coolant System Heatup and Cooldown Technical Specifications Figures Project stage: Response to RAI ML15187A4242015-07-27027 July 2015 Issuance of Amendments to Change the Reactor Coolant System Pressure and Temperature Limits Regarding Vacuum Fill Operations Project stage: Approval 2015-01-14
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Category:E-Mail
MONTHYEARML24107A9112024-04-15015 April 2024 NRC to Fws, Follow-up on Request for Concurrence for North Anna SLR ML24107A9122024-04-11011 April 2024 Fws to NRC, Follow-up on Request for Concurrence for North Anna SLR ML24087A0102024-03-26026 March 2024 NRR E-mail Capture - Verbal Relief for North Anna Unit 1 - (ASME Code), Section XI, Subsection IWB-2430 ML24087A0112024-03-23023 March 2024 NRR E-mail Capture - Draft RAIs for Reactor Coolant Pump (RCP) Relief Request (L-2024-LLR-0022) ML24107B1562024-02-20020 February 2024 Cherokee Nation E.Toombs Na Removal Request ML24044A2462024-02-0606 February 2024 001 Radiation Safety Baseline Inspection Information Request ML23320A1122024-01-18018 January 2024 NRC to Fws, Concurrence with Endangered Species Act Determinations for North Anna Power Station, Units 1 and 2, Subsequent License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment ML23355A2722023-12-21021 December 2023 NRR E-mail Capture - Schedule Revision for Emergency Preparedness Staff Augmentation Times License Amendment Request ML23318A1172023-11-13013 November 2023 NRR E-mail Capture - Formal Issuance of RAIs for North Anna Technical Support Center (TSC) License Amendment Request (LAR) (L-2023-LLA-0006) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23219A1602023-08-0707 August 2023 003 Radiation Safety Baseline Inspection Information Request ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23075A0232023-03-15015 March 2023 NRR E-mail Capture - RAI - License Amend Req (LAR) to Revise Tech Spec (Ts) 3.6.8 Limiting Condition for Operation to Remove Refueling Water Chemical Addition Tank and Replace the Containment Sump Buffer North Anna, 1 and 2 (L-2022-LLA-0162 ML23067A2162023-03-0707 March 2023 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 ML23060A0932023-03-0101 March 2023 NRR E-mail Capture - Formal Issuance of RAIs for Surry/North Anna Emergency Plans LAR ML23059A2282023-02-28028 February 2023 NRR E-mail Capture - Draft RAIs for Containment Buffer Change to Natb (L-2022-LLA-0162) ML23039A1712023-02-0808 February 2023 NRR E-mail Capture - Acceptance Review for Technical Support Center (TSC) Relocation (L-2023-LLA-0006) 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) ML22342B1472022-12-0808 December 2022 NRR E-mail Capture - Acceptance Review for LAR Re NAPS Post LOCA Buffer Change (L-2022-LLA-0162) ML22335A4842022-12-0101 December 2022 NRR E-mail Capture - Acceptance Review for LAR North Anna Power Station - Units 1 and 2 and Surry Power Station - Units 1 and 2 Emergency Plan Staff Augmentation Times (L-2022-LLA-0166) 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) ML22104A0252022-04-14014 April 2022 NRR E-mail Capture - Dominion Presentation Slides for April 21, 2022 Public Meeting on Emergency Preparedness Submittal for the North Anna Power Station and the Surry Power Station ML22083A2102022-03-24024 March 2022 NRR E-mail Capture - Draft RAI - Relief Request N2-14-LMT-003 Fourth Ten Year Inservice Inspection Interval ML22032A0962022-02-0101 February 2022 002 Radiation Safety Baseline Inspection Information Request ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22007A2672022-01-0707 January 2022 NRR E-mail Capture - North Anna, Unit 2, ASME Section XI Inservice Inspection Program Relief Request N2-14-LMT-003 Fourth Interval Third Period Limited Examinations (L-2021-LLR-0088) ML21335A0812021-12-0101 December 2021 NRR E-mail Capture - Acceptance Review for OMN-28 Request Alternative to ISTC-3700, Position Verification Testing (L-2021-LLR-0086) ML21334A1922021-11-30030 November 2021 NRR E-mail Capture - Audit Plan for Reactor Core Thermal-Hydraulics Using the VIPRE-D Appendix E Review ML21327A3652021-11-23023 November 2021 NRR E-mail Capture - Draft RAI for TSTF-577 LAR ML21326A1502021-11-22022 November 2021 NRR E-mail Capture - Acceptance Review for Relocation of Unit Staff Requirements to the QAPD LAR (L-2021-LLA-0195) ML21322A0962021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21312A0082021-11-0404 November 2021 Enclosure 2 - NAPS Draft SER Table A.1-1 Markup ML21312A0012021-11-0404 November 2021 Comments on North Anna Draft SER ML21312A0112021-11-0404 November 2021 Enclosure 3 - NAPS Draft SER Section 3 Comments ML21306A3302021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review for TSTF-569 LAR ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR ML21274A0022021-09-30030 September 2021 NRR E-mail Capture - Acceptance Review for TSTF-577 LAR (L-2021-LLA-0158) ML21312A0072021-09-21021 September 2021 Enclosure 1 - E-mail - Enclosure B - NAPS SER App a - Dominion Comments 9-21-2021 ML21312A0032021-09-21021 September 2021 Enclosure 1 - E-mail - Enclosure a - Dominion Table A4.4-1 Clean Version ML21312A0022021-09-21021 September 2021 Enclosure 1 - E-mail - NAPS SLR SER Appendix a for Dominion Review ML21256A0672021-09-13013 September 2021 Final Request for Confirmation of Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21152A1722021-09-0707 September 2021 NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for North Anna Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations ML21238A0942021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21225A5512021-08-13013 August 2021 Discussion Point for Public Meeting Regarding Fire Protection Piping Cyclic Loading - Transmittal E-mail 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 ML21188A1632021-07-0707 July 2021 Final Request for Additional Information Set 4 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21154A0152021-06-0101 June 2021 NRR E-mail Capture - Acceptance Review for Primary Grade Water LAR (L-2021-LLA-0082) ML21140A3682021-05-20020 May 2021 Response to North Anna Hardship (Temporary Staff Guidance Additional Guidance for FOF Inspections During the PHE) 2024-04-15
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NRR-PMDAPEm Resource From: Sreenivas, V Sent: Wednesday, January 14, 2015 2:04 PM To: 'david.heacock@dom.com' Cc: 'david.sommers@dom.com'; Pascarelli, Robert; Tom Shaub; Jay Leberstien (jay.leberstien@dom.com); 'Gary D Miller'; Vicki Hull (vicki.hull@dom.com)
Subject:
NAPS 1&2: RAI-CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES ( TAC. NOS. MF4707 AND MF4708)
REQUEST FOR ADDITIONAL INFORMATION PROPOSED CHANGES TO NORTH ANNA POWER STATION UNITS 1 AND 2 REGARDING CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES NORTH ANNA POWER STATION, UNITS 1 AND 2 By letter dated August 27, 2014, Virginia Electric Power Company (Dominion, the licensee) provided a proposed license amendment request, Clarification of Reactor Coolant System Heatup and Cooldown Technical Specification Figures (Agencywide Documents Access and Management System (ADAMS)
Accession Number ML14246A190). The licensee submitted a request for changes to the North Anna Power Station (North Anna) Units 1 and 2 Technical Specifications pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90. The proposed amendment would revise Figures 3.4.3-1, Reactor Coolant System Heatup Limitations and 3.4.3-2, Reactor Coolant System Cooldown Limitations, to address vacuum fill operations.
RAI 1
BACKGROUND 10 CFR Part 50, Appendix G requires that pressure-temperature (P-T) limits be developed to bound all ferritic materials in the reactor vessel (RV). Further, Sections I and IV.A of 10 CFR, Part 50, Appendix G specify that all ferritic reactor coolant pressure boundary (RCPB) components outside of the RV must meet the applicable requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section III, Rules for Construction of Nuclear Facility Components.
ISSUE As clarified in Regulatory Information Summary (RIS) 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components (ADAMS Accession No. ML14149A165), P-T limit calculations for ferritic RV components other than those materials with the highest reference temperature, may define curves that are more limiting than those calculated for the RV beltline shell materials because the consideration of stress levels from structural discontinuities (such as nozzles) may produce a lower allowable pressure.
REQUEST Describe how the P-T limit curves for North Anna Units 1 and 2 consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period.
If the current P-T limit curves do not consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period, provide appropriately revised P-T limit curves to the NRC for review.
Please submit the response to these RAIs by February 15, 2015. If you have any questions please contact me at your earliest.
1
V. Sreenivas, PH.D., C.P.M.,
Project Manager, Rm.#O8F6, LPL2-1 North Anna Power Stations, Units 1 and 2 Division of Operating Reactor Licensing-NRR (301) 415-2597, v.sreenivas@nrc.gov
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2
Hearing Identifier: NRR_PMDA Email Number: 1812 Mail Envelope Properties (V.Sreenivas@nrc.gov20150114140400)
Subject:
NAPS 1&2: RAI-CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES ( TAC. NOS. MF4707 AND MF4708)
Sent Date: 1/14/2015 2:04:19 PM Received Date: 1/14/2015 2:04:00 PM From: Sreenivas, V Created By: V.Sreenivas@nrc.gov Recipients:
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Tracking Status: None "Vicki Hull (vicki.hull@dom.com)" <vicki.hull@dom.com>
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"'david.heacock@dom.com'" <david.heacock@dom.com>
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