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| | number = ML18037A704 | | | number = ML18037A704 |
| | issue date = 01/31/2018 | | | issue date = 01/31/2018 |
| | title = North Anna Power Station Units 1 and 2 - Response to Request for Additional Information Regarding Proposed License Amendment Request for Spent Fuel Storage and New Fuel Storage | | | title = Response to Request for Additional Information Regarding Proposed License Amendment Request for Spent Fuel Storage and New Fuel Storage |
| | author name = Bischof G T | | | author name = Bischof G |
| | author affiliation = Virginia Electric & Power Co (VEPCO) | | | author affiliation = Virginia Electric & Power Co (VEPCO) |
| | addressee name = | | | addressee name = |
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| | page count = 9 | | | page count = 9 |
| | project = CAC:MF9712, CAC:MF9713 | | | project = CAC:MF9712, CAC:MF9713 |
| | | stage = Response to RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:.. VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 January 31, 2018 Serial No.: NRA/DEA Docket Nos.: License Nos.: 10 CFR 50.90 16-383B RO 50-338/339 NPF-4/7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA) NORTH ANNA POWER STATION UNITS 1 AND 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PROPOSED LICENSE AMENDMENT REQUEST FOR SPENT FUEL STORAGE AND NEW FUEL STORAGE (CAC Nos. MF9712 AND MF9713) By letter dated May 2, 2017, Dominion submitted a license amendment request (LAR) to revise Technical Specifications {TS) 3.7.18, "Spent Fuel Pool Storage" and TS 4.3.1 "Criticality." Conforming changes were proposed to Technical Specifications Bases (TSB) 83.7.18. In an email dated December 21, 2017, the NRC transmitted a request for additional information (RAI) related to the LAR. A January 31, 2018 response date was requested. The response to the RAI is provided in Attachment 1. Attachment 2 provides a revised marked-up change to TS 4.3.1.1 and Attachment 3 provides the proposed change page forTS4.3.1.1. Should you have any questions in regard to this submittal, please contact Diane E. Aitken at (804) 273-2694. Sincerely, Vice President -Nuclear Operations and Fleet Performance COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald T. Bischof, who is Vice President -Nuclear Operations and Fleet Performance of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behaW of that Company, and that the statements in the dM true to the best of his knowledge and belief Acknowledged before me this 3...1!£.. day of , 2018. ftp O I My Commission Expires: S -3 J -/8 . . z /J / | | {{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 |
| * p._ i, . <..AldL_,, r. If,. Notary Public f V Commitments made in this letter: None Attachments: 1. Response to Request for Additional Information 2. Marked-up Technical Specification page 3. Proposed Technical Specification change page Serial No. 16-3838 Docket Nos.: 50-338/339 Page 2 of 3
| | . January 31, 2018 10 CFR 50.90 U.S. Nuclear Regulatory Commission Serial No.: 16-383B Attention: Document Control Desk NRA/DEA RO Washington, DC 20555 Docket Nos.: 50-338/339 License Nos.: NPF-4/7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA) |
| ., cc: U.S. Nuclear Regulatory Commission -Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 State Health Commissioner Virginia Department of Health James Madison Building -7th floor 109 Governor Street Suite 730 Richmond, VA 23219 Mr. James R. Hall NRC Senior Project Manager -North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Karen Cotton-Gross NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr. Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd. Suite 300 Glen Allen, VA 23060 Serial No. 16-3838 Docket Nos.: 50-338/339 Page 3 of 3 | | NORTH ANNA POWER STATION UNITS 1 AND 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PROPOSED LICENSE AMENDMENT REQUEST FOR SPENT FUEL STORAGE AND NEW FUEL STORAGE (CAC Nos. MF9712 AND MF9713) |
| | By letter dated May 2, 2017, Dominion submitted a license amendment request (LAR) to revise Technical Specifications {TS) 3.7.18, "Spent Fuel Pool Storage" and TS 4.3.1 "Criticality." Conforming changes were proposed to Technical Specifications Bases (TSB) 83.7.18. |
| | In an email dated December 21, 2017, the NRC transmitted a request for additional information (RAI) related to the LAR. A January 31, 2018 response date was requested. |
| | The response to the RAI is provided in Attachment 1. Attachment 2 provides a revised marked-up change to TS 4.3.1.1 and Attachment 3 provides the proposed change page forTS4.3.1.1. |
| | Should you have any questions in regard to this submittal, please contact Diane E. Aitken at (804) 273-2694. |
| | Sincerely, Vice President - Nuclear Operations and Fleet Performance COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today dM by Gerald T. Bischof, who is Vice President - Nuclear Operations and Fleet Performance of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behaW of that Company, and that the statements in the true to the best of his knowledge and belief Acknowledged before me this My Commission Expires: |
| | 3...1!£.. day of S -3 J- /8 . ~ |
| | , 2018. |
| | i, |
| | . z. /J / |
| | <..AldL_,, |
| | Notary Public ftp O I r. |
| | fV If,. |
| | p._ |
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| |
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| ==Attachment==
| | Serial No. 16-3838 Docket Nos.: 50-338/339 Page 2 of 3 Commitments made in this letter: None Attachments: |
| 1 RESPONSE TO Serial No. 16-3838 Docket Nos.: 50-338/339 REQUEST FOR ADDITIONAL INFORMATION VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA) NORTH ANNA POWER STATION UNITS 1 AND 2 Technical Basis for the Request Serial No. 16-3838 Docket Nos.: 50-338/339 Attachment 1 Page 1 of 1 Section 2.2 of Attachment 1 of the LAR provides a description of the changes to TS 4.3.1.1. Attachment 2 of the LAR provides marked up technical specification pages showing the proposed changes, including TS page 4.0-2, which shows the proposed deletion of the text identifying a specific document providing the methodology used to calculate uncertainties in keff, in both TS 4.3.1.1.b. and c. Section 2.2 of Attachment 1 does not describe the basis for the proposed deletions of text. NUREG-1431 contains the staff's guidance on one manner of format and content for TSs that would meet the regulatory requirements of 10 CFR 50.36. The current NAPS TS 4.3.1.1 and NUREG-1431 both cite the location of the methodologies used to calculate uncertainties in keff* It appears the LAR is proposing deletion of the location of the methodologies used to calculate uncertainties in keff in TS 4.3.1.1 without fully describing why the deletion is appropriate for NAPS. RAI Please provide a full description and justification for the proposed deletion of the location of the methodology used to calculate uncertainties in keff in TS 4.3.1.1, or, alternatively, provide a revised change to TS 4.3.1.1 that retains the citation of the location of the methodology used to calculate uncertainties in keff* RAI Response As indicated in the request for additional information (RAI), the license amendment request (LAR) submitted May 2, 2017, proposed the deletion of text identifying a specific document providing the methodology used to calculate uncertainties in keff, in both Technical Specification (TS) 4.3.1.1.b. and c without describing why the change was appropriate. The specific document cited in the current TS 4.3.1.1 as providing the methodology used to calculate uncertainties in keff is the LAR letter describing the analysis that was reviewed by the NRC prior to approval of the current TS 4.3.1.1. Deletion of this text was appropriate since the cited LAR letter was obsolete (superseded by the methodology provided in the LAR submittal dated May 2, 2017). Guidance in NUREG-1431, Standard Technical Specifications -Westinghouse Plants, Volume 1, Specifications, indicates it is appropriate to include a reference to the Final Safety Analysis Report (FSAR) as the location of the methodology used to calculate uncertainties in keff in TS 4.3.1.1. Updated Final Safety Analysis Report (UFSAR) Section 9.1 will be revised to include the methodology used to calculate uncertainties in keff during implementation of the approved LAR. Therefore, a mark-up of Technical Specification 4.3.1.1 that adds UFSAR Section 9.1 as the location of the methodology used to calculate uncertainties in keff is provided in Attachment 2. The associated proposed change to Technical Specification 4.3.1.1 is provided in Attachment 3.
| | : 1. Response to Request for Additional Information |
| | : 2. Marked-up Technical Specification page |
| | : 3. Proposed Technical Specification change page |
|
| |
|
| ==Attachment==
| | Serial No. 16-3838 Docket Nos.: 50-338/339 Page 3 of 3 |
| 2 Serial No. 16-383B Docket Nos.: 50-338/339 MARKED-UP TECHNICAL SPECIFICATION PAGE VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA) NORTH ANNA POWER STATION UNITS 1 AND 2 4.0 DESIGN FEATURES 4.3.1.1 (continued) UFSARSection 9.1 Design Features 4.0 b. keff < 1.0 if full flooded with unborated water,_............. which includes allowance for uncertainties~ calculated in ccordance with the methodology described in *
| | ., cc: U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 State Health Commissioner Virginia Department of Health James Madison Building - 7th floor 109 Governor Street Suite 730 Richmond, VA 23219 Mr. James R. Hall NRC Senior Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Karen Cotton-Gross NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr. |
| * letter dated Septe111ber 27. 2000 (Serial No. 00-491); and biases c. keff 0.95 if fu~flooded with water borated to 900 ~~)-'35fr ppm, which~cl~des an allowance for uncertainties calculated in accordance with the methodology described in w~~t.5:tr !c ctr.id flower eu111par1y 1 e L Ler* da Led 3ep L"e!mJ' , OM C3er I al No. 00 ~91); and UFSARSection9.1 d. A nominal 10 9/16 inch center to center distance between fuel assemblies placed in the fuel storage racks. 4.3.1.2 The new fuel storage racks are designed and shall be maintained with: 5.0 a. Fuel assemblies having a maximum U-235 enrichment of weight percent; 4.3.2 Drainage b. keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertain~ and biases ----'
| | Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd. |
| * c. keff 0.98 if moderated by aqueou~~m, which includes an allowance for uncertai"'nti~ and d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks. The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 285 feet, 9 inches, Mean Sea Level, USGS datum. 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1737 fuel assemblies. North Anna Units 1 and 2 4.0-2 Amendme~ts 231/212 and biases
| | Suite 300 Glen Allen, VA 23060 |
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| |
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| ==Attachment==
| | Serial No. 16-3838 Docket Nos.: 50-338/339 Attachment 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA) |
| 3 Serial No. 16-3838 Docket Nos.: 50-338/339 PROPOSED TECHNICAL SPECIFICATION CHANGE PAGE VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA) NORTH ANNA POWER STATION UNITS 1 AND 2 4.0 DESIGN FEATURES Design Features 4.0 4.3.1.1 (continued) b. keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties and biases calculated in accordance with the methodology described in UFSAR Section 9.1; c. keff 0.95 if fully flooded with water borated to 900 pp~, which includes an allowance for uncertainties and biases calculated in accordance with the methodology described in UFSAR Section 9.1; and d. A nominal 10 9/16 inch center to center distance between fuel assemblies placed in the fuel storage racks. 4.3.1.2 The new fuel storage racks are designed and shall be maintained with: 4.3.2 Drainage a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; b. keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties and biases; c. keff 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties and biases; and d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks. The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 285 feet, 9 inches, Mean Sea Level, USGS datum. 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1737 fuel assemblies. North Anna Units 1 and 2 4.0-2 Amendments | | NORTH ANNA POWER STATION UNITS 1 AND 2 |
| }} | | |
| | Serial No. 16-3838 Docket Nos.: 50-338/339 Attachment 1 Page 1 of 1 Technical Basis for the Request Section 2.2 of Attachment 1 of the LAR provides a description of the changes to TS 4.3.1.1. Attachment 2 of the LAR provides marked up technical specification pages showing the proposed changes, including TS page 4.0-2, which shows the proposed deletion of the text identifying a specific document providing the methodology used to calculate uncertainties in keff, in both TS 4.3.1.1.b. and c. Section 2.2 of Attachment 1 does not describe the basis for the proposed deletions of text. |
| | NUREG-1431 contains the staff's guidance on one manner of format and content for TSs that would meet the regulatory requirements of 10 CFR 50.36. The current NAPS TS 4.3.1.1 and NUREG-1431 both cite the location of the methodologies used to calculate uncertainties in keff* It appears the LAR is proposing deletion of the location of the methodologies used to calculate uncertainties in keff in TS 4.3.1.1 without fully describing why the deletion is appropriate for NAPS. |
| | RAI Please provide a full description and justification for the proposed deletion of the location of the methodology used to calculate uncertainties in keff in TS 4.3.1.1, or, alternatively, provide a revised change to TS 4.3.1.1 that retains the citation of the location of the methodology used to calculate uncertainties in keff* |
| | RAI Response As indicated in the request for additional information (RAI), the license amendment request (LAR) submitted May 2, 2017, proposed the deletion of text identifying a specific document providing the methodology used to calculate uncertainties in keff, in both Technical Specification (TS) 4.3.1.1.b. and c without describing why the change was appropriate. The specific document cited in the current TS 4.3.1.1 as providing the methodology used to calculate uncertainties in keff is the LAR letter describing the analysis that was reviewed by the NRC prior to approval of the current TS 4.3.1.1. |
| | Deletion of this text was appropriate since the cited LAR letter was obsolete (superseded by the methodology provided in the LAR submittal dated May 2, 2017). |
| | Guidance in NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Volume 1, Specifications, indicates it is appropriate to include a reference to the Final Safety Analysis Report (FSAR) as the location of the methodology used to calculate uncertainties in keff in TS 4.3.1.1. Updated Final Safety Analysis Report (UFSAR) |
| | Section 9.1 will be revised to include the methodology used to calculate uncertainties in keff during implementation of the approved LAR. Therefore, a mark-up of Technical Specification 4.3.1.1 that adds UFSAR Section 9.1 as the location of the methodology used to calculate uncertainties in keff is provided in Attachment 2. The associated proposed change to Technical Specification 4.3.1.1 is provided in Attachment 3. |
| | |
| | Serial No. 16-383B Docket Nos.: 50-338/339 Attachment 2 MARKED-UP TECHNICAL SPECIFICATION PAGE VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA) |
| | NORTH ANNA POWER STATION UNITS 1 AND 2 |
| | |
| | Design Features 4.0 4.0 DESIGN FEATURES 4.3.1.1 (continued) UFSARSection 9.1 and biases |
| | : b. keff < 1.0 if full flooded with unborated water,_............. |
| | which includes allowance for uncertainties~ |
| | calculated in ccordance with the methodology described in * |
| | * letter dated Septe111ber 27. 2000 (Serial No. 00-491); |
| | and biases |
| | : c. keff ~ 0.95 if fu~flooded with water borated to 900 ~~)-'35fr ppm, which~cl~des an allowance for uncertainties calculated in accordance with the methodology described in w~~t.5:tr !c ctr.id flower eu111par1y 1e LLer* da Led 3ep L"e!mJ' , OM C3er I al No. 00 ~91); and UFSARSection9.1 |
| | : d. A nominal 10 9/16 inch center to center distance between fuel assemblies placed in the fuel storage racks. |
| | 4.3.1.2 The new fuel storage racks are designed and shall be maintained with: |
| | : a. Fuel assemblies having a maximum U-235 enrichment of |
| | ~ weight percent; 5.0 |
| | : b. keff ~ 0.95 if fully flooded with unborated water, which includes an allowance for uncertain~ |
| | and biases - - - - ' * |
| | : c. keff ~ 0.98 if moderated by aqueou~~m, which includes an allowance for uncertai"'nti~ and |
| | : d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks. |
| | 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 285 feet, 9 inches, Mean Sea Level, USGS datum. |
| | 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1737 fuel assemblies. |
| | North Anna Units 1 and 2 4.0-2 Amendme~ts 231/212 |
| | |
| | Serial No. 16-3838 Docket Nos.: 50-338/339 Attachment 3 PROPOSED TECHNICAL SPECIFICATION CHANGE PAGE VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA) |
| | NORTH ANNA POWER STATION UNITS 1 AND 2 |
| | |
| | Design Features 4.0 4.0 DESIGN FEATURES 4.3.1.1 (continued) |
| | : b. keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties and biases calculated in accordance with the methodology described in UFSAR Section 9.1; |
| | : c. keff ~ 0.95 if fully flooded with water borated to 900 pp~, which includes an allowance for uncertainties and biases calculated in accordance with the methodology described in UFSAR Section 9.1; and |
| | : d. A nominal 10 9/16 inch center to center distance between fuel assemblies placed in the fuel storage racks. |
| | 4.3.1.2 The new fuel storage racks are designed and shall be maintained with: |
| | : a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; |
| | : b. keff ~ 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties and biases; |
| | : c. keff ~ 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties and biases; and |
| | : d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks. |
| | 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 285 feet, 9 inches, Mean Sea Level, USGS datum. |
| | 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1737 fuel assemblies. |
| | North Anna Units 1 and 2 4.0-2 Amendments}} |
Letter Sequence Response to RAI |
|---|
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|
MONTHYEARML17129A4512017-05-0202 May 2017
Submittal of Proposed License Amendment Request for Spent Fuel Storage and New Fuel Storage
Project stage: Request
ML17194A9742017-07-13013 July 2017
NRR E-mail Capture - North Anna Power Station Units 1and 2 - Acceptance of Amendment Request for Spent Fuel Storage and New Fuel Storage
Project stage: Acceptance Review
ML18037A7042018-01-31031 January 2018
Response to Request for Additional Information Regarding Proposed License Amendment Request for Spent Fuel Storage and New Fuel Storage
Project stage: Response to RAI
ML18180A1972018-07-27027 July 2018
Issuance of Amendments to Revise Technical Specifications Regarding New and Spent Fuel Storage (CAC Nos. MF9712 and MF9713, EPID L-2017-LLA-0240)
Project stage: Approval
2017-07-13
[Table View] |
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|---|
Category:Letter
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Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe
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Tribal Section 106 Letters-North Anna - Nansemond Indian Nation
ML24241A0692024-08-0606 August 2024
ISFSI, Submittal of Cask Registration for Spent Fuel Storage
IR 05000338/20240022024-08-0202 August 2024
Integrated Inspection Report 05000338/2024002 and 05000339/2024002
ML24206A0432024-07-26026 July 2024
Feis - Letter to the Applicant
05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-25025 July 2024
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Owners Activity Report
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
ML24177A2792024-06-20020 June 2024
Preparation and Scheduling of Operator Licensing Examinations
ML24143A1622024-06-12012 June 2024
– Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times
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DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code
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Loss of Generator Field for 2J EDG During 2-PT-82.28
05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.282024-06-0505 June 2024
Loss of Generator Field for 2J EDG During 2-PT-82.28
IR 05000338/20240012024-05-10010 May 2024
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Annual Environmental Operating Report
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ML24087A0572024-04-16016 April 2024
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2024-09-24
[Table view]
Category:Response to Request for Additional Information (RAI)
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ML23136A8832023-05-16016 May 2023
Responses to Request for Additional Information and Request for Confirmation of Information Regarding Environmental Review of Subsequent License Renewal Application
ML23103A2752023-04-13013 April 2023
Response to Request for Additional Information Regarding Proposed License Amendment Request for Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer
ML23096A2982023-04-0606 April 2023
Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion
ML23089A3542023-03-30030 March 2023
Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times
ML22312A4432022-11-0707 November 2022
NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI
ML22115A1752022-04-25025 April 2022
ASME Section XI Inservice Inspection Program - Relief Request N2-14-LMT-004 - Fourth Interval Third Period Limited Examinations - Response to Request for Additional Information
ML21350A4082021-12-16016 December 2021
Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Genera Tor Tube Inspections, Rev 1, Using the Consolidated Line-Item Improvement Process Response to RAI
ML21341B4372021-12-0606 December 2021
(Naps), Units 1 and 2 - Subsequent License Renewal Application Responses to NRC Request for Additional Information Safety Review - Set 5
ML21259A0852021-09-15015 September 2021
North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition
ML21258A3542021-09-15015 September 2021
(Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Confirmation of Information Set 2 Safety Review
ML21210A3962021-07-29029 July 2021
(Naps), Units 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 4 and Supplement 3
ML21147A2932021-05-27027 May 2021
(Naps), Units 1 and 2 Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 3 and Administrative Change to SLRA Table A4.0-1, Item 25
ML21133A2852021-05-13013 May 2021
Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code
ML21126A3152021-05-0606 May 2021
Proposed License Amendment Request to Battery Surveillance Requirements - Response to Request for Additional Information
ML21119A2872021-04-29029 April 2021
(Naps), Unit 1 and 2 - Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Safety Review - Set 2 and Flow Accelerated Corrosion Program Enhancement Completion
ML21091A1872021-04-0101 April 2021
Response to NRC Request for Additional Information Regarding Safety Review - Set 1 & Clarification to Aging Management of Fire Protection System Lined Ductile Iron Valves
ML21084A1822021-03-24024 March 2021
Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information for the Safety Review - Set 1
ML21056A5572021-02-25025 February 2021
NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Final Supplemental Response
ML21053A4332021-02-22022 February 2021
(Naps), Units 1 and 2 - Subssequent License Renewal Application (SLRA) Environmental Review - Response to NRC Request for Additional Information
ML21042B9042021-02-11011 February 2021
Subsequent License Renewal Application, Response to NRC Requests for Confirmation of Information for the Environmental Review
ML21033A3022021-01-25025 January 2021
(NAPS) Units 1 and 2 - Subsequent License Renewal Application (SLRA) - Provides Requested Documents in Response to Environmental Audit. Part 1 of 2
ML21022A1752020-12-16016 December 2020
Steam Generator Tube Inspection Report RAI Response
ML20296A7272020-10-22022 October 2020
Stations Units 1 & 2 - Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break LOCA Supplement to the Response to Request for Additional Information
ML20296A6672020-10-22022 October 2020
ASME Section XI Inservice Inspection Program Proposed Inservice Inspection Relief Request N1-I4-LMT-003 Response to Request for Additional Information
ML20268B1872020-09-24024 September 2020
ASME Section XI Inservice Inspection Program, Proposed Inservice Inspection Alternative N1-I5-NDE-002, Response to Request for Additional Information
ML20156A2872020-06-0404 June 2020
Inservice Testing Program Plan for Pumps, Valves, and Snubbers Fifth 10-Year Interval Update for Units 1 & 2 Request for Alternatives to Requirements of ASME OM Code - Response to RAI
ML20149K6942020-05-28028 May 2020
Response to Request for Additional Information, to Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident
ML20140A3362020-05-18018 May 2020
Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules - Response to Request for Additional Information
ML20021A0052020-01-17017 January 2020
Inservice Testing Program Request for Alternative to Requirements of ASME OM Code Relief Request P-9, Response to Request for Additional Information
ML19249B7672019-08-29029 August 2019
Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs
ML19248B7622019-08-22022 August 2019
Supplement to Proposed License Amendment Request - Flood Protection Dike Modification - Response to Onsite Audit Questions
ML19225D1302019-08-0808 August 2019
Response to Request for Additional Information (Follow-Up) Regarding Open Phase Protection Per NRC Bulletin 2012-01 - Proposed License Amendment Request
ML19196A1102019-07-0909 July 2019
Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages
ML19156A2072019-05-24024 May 2019
Response to Request for Additional Information on Proposed License Amendment Request Open Phase Protection Per NRC Bulletin 2012-01
ML19071A1142019-03-0707 March 2019
Response to 03/12/2012 Information Request, Seismic Probabilistic Risk Assessment Supplement for Recommendation 2.1
ML18267A0682018-09-18018 September 2018
Attachment - Response to Request for Clarification on Proposed Consolidated Emergency Operations Facility License Amendment Requests
ML18257A2272018-09-14014 September 2018
SPRA (Fukushima 50.54f) Audit (Clarification) Questions - Plant Response
ML18169A2262018-06-13013 June 2018
Attachment 1 - Response to Request for Additional Information
ML18169A2272018-06-13013 June 2018
Attachment 3 - Proposed NAPS Emergency Plan Changes
ML18093A4452018-03-28028 March 2018
Ad 2, Response to 03/12/2012 Information Request Seismic Probabilistic Risk Assessment for Recommendation 2.1
ML18092A0812018-03-26026 March 2018
Supplement to Proposed License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month
ML18037A7042018-01-31031 January 2018
Response to Request for Additional Information Regarding Proposed License Amendment Request for Spent Fuel Storage and New Fuel Storage
ML17354A1602017-12-14014 December 2017
Response to March 12, 2012 Information Request Spent Fuel Pool Seismic Evaluation for Recommendation 2.1
ML17241A0452017-08-24024 August 2017
Proposed ISI Alternatives NI-14-NDE-010 and N2-14-NDE-005 Reactor Pressure Vessel Nozzle Weld Inspections Response to Request for Additional Information
ML17171A2302017-06-14014 June 2017
Response to Request for Additional Information ASME Section XI Inservice Inspection Program Request for Proposed Alternative N1-I4-009 and N2-I4-NDE-004
ML17065A2502017-02-28028 February 2017
& Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Response to Request for Referenced Information Related to RAIs 2-2, 3-5, and 3-8
ML17025A1282017-01-20020 January 2017
Independent Spent Fuel Storage Installation - Response to Request for Additional Information for License Renewal Application (CAC L25121)
2024-03-25
[Table view] |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261
. January 31, 2018 10 CFR 50.90 U.S. Nuclear Regulatory Commission Serial No.: 16-383B Attention: Document Control Desk NRA/DEA RO Washington, DC 20555 Docket Nos.: 50-338/339 License Nos.: NPF-4/7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
NORTH ANNA POWER STATION UNITS 1 AND 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PROPOSED LICENSE AMENDMENT REQUEST FOR SPENT FUEL STORAGE AND NEW FUEL STORAGE (CAC Nos. MF9712 AND MF9713)
By letter dated May 2, 2017, Dominion submitted a license amendment request (LAR) to revise Technical Specifications {TS) 3.7.18, "Spent Fuel Pool Storage" and TS 4.3.1 "Criticality." Conforming changes were proposed to Technical Specifications Bases (TSB) 83.7.18.
In an email dated December 21, 2017, the NRC transmitted a request for additional information (RAI) related to the LAR. A January 31, 2018 response date was requested.
The response to the RAI is provided in Attachment 1. Attachment 2 provides a revised marked-up change to TS 4.3.1.1 and Attachment 3 provides the proposed change page forTS4.3.1.1.
Should you have any questions in regard to this submittal, please contact Diane E. Aitken at (804) 273-2694.
Sincerely, Vice President - Nuclear Operations and Fleet Performance COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today dM by Gerald T. Bischof, who is Vice President - Nuclear Operations and Fleet Performance of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behaW of that Company, and that the statements in the true to the best of his knowledge and belief Acknowledged before me this My Commission Expires:
3...1!£.. day of S -3 J- /8 . ~
, 2018.
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Serial No. 16-3838 Docket Nos.: 50-338/339 Page 2 of 3 Commitments made in this letter: None Attachments:
- 1. Response to Request for Additional Information
- 2. Marked-up Technical Specification page
- 3. Proposed Technical Specification change page
Serial No. 16-3838 Docket Nos.: 50-338/339 Page 3 of 3
., cc: U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 State Health Commissioner Virginia Department of Health James Madison Building - 7th floor 109 Governor Street Suite 730 Richmond, VA 23219 Mr. James R. Hall NRC Senior Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Karen Cotton-Gross NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, VA 23060
Serial No. 16-3838 Docket Nos.: 50-338/339 Attachment 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
NORTH ANNA POWER STATION UNITS 1 AND 2
Serial No. 16-3838 Docket Nos.: 50-338/339 Attachment 1 Page 1 of 1 Technical Basis for the Request Section 2.2 of Attachment 1 of the LAR provides a description of the changes to TS 4.3.1.1. Attachment 2 of the LAR provides marked up technical specification pages showing the proposed changes, including TS page 4.0-2, which shows the proposed deletion of the text identifying a specific document providing the methodology used to calculate uncertainties in keff, in both TS 4.3.1.1.b. and c. Section 2.2 of Attachment 1 does not describe the basis for the proposed deletions of text.
NUREG-1431 contains the staff's guidance on one manner of format and content for TSs that would meet the regulatory requirements of 10 CFR 50.36. The current NAPS TS 4.3.1.1 and NUREG-1431 both cite the location of the methodologies used to calculate uncertainties in keff* It appears the LAR is proposing deletion of the location of the methodologies used to calculate uncertainties in keff in TS 4.3.1.1 without fully describing why the deletion is appropriate for NAPS.
RAI Please provide a full description and justification for the proposed deletion of the location of the methodology used to calculate uncertainties in keff in TS 4.3.1.1, or, alternatively, provide a revised change to TS 4.3.1.1 that retains the citation of the location of the methodology used to calculate uncertainties in keff*
RAI Response As indicated in the request for additional information (RAI), the license amendment request (LAR) submitted May 2, 2017, proposed the deletion of text identifying a specific document providing the methodology used to calculate uncertainties in keff, in both Technical Specification (TS) 4.3.1.1.b. and c without describing why the change was appropriate. The specific document cited in the current TS 4.3.1.1 as providing the methodology used to calculate uncertainties in keff is the LAR letter describing the analysis that was reviewed by the NRC prior to approval of the current TS 4.3.1.1.
Deletion of this text was appropriate since the cited LAR letter was obsolete (superseded by the methodology provided in the LAR submittal dated May 2, 2017).
Guidance in NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Volume 1, Specifications, indicates it is appropriate to include a reference to the Final Safety Analysis Report (FSAR) as the location of the methodology used to calculate uncertainties in keff in TS 4.3.1.1. Updated Final Safety Analysis Report (UFSAR)
Section 9.1 will be revised to include the methodology used to calculate uncertainties in keff during implementation of the approved LAR. Therefore, a mark-up of Technical Specification 4.3.1.1 that adds UFSAR Section 9.1 as the location of the methodology used to calculate uncertainties in keff is provided in Attachment 2. The associated proposed change to Technical Specification 4.3.1.1 is provided in Attachment 3.
Serial No. 16-383B Docket Nos.: 50-338/339 Attachment 2 MARKED-UP TECHNICAL SPECIFICATION PAGE VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
NORTH ANNA POWER STATION UNITS 1 AND 2
Design Features 4.0 4.0 DESIGN FEATURES 4.3.1.1 (continued) UFSARSection 9.1 and biases
- b. keff < 1.0 if full flooded with unborated water,_.............
which includes allowance for uncertainties~
calculated in ccordance with the methodology described in *
- letter dated Septe111ber 27. 2000 (Serial No.00-491);
and biases
- c. keff ~ 0.95 if fu~flooded with water borated to 900 ~~)-'35fr ppm, which~cl~des an allowance for uncertainties calculated in accordance with the methodology described in w~~t.5:tr !c ctr.id flower eu111par1y 1e LLer* da Led 3ep L"e!mJ' , OM C3er I al No. 00 ~91); and UFSARSection9.1
- d. A nominal 10 9/16 inch center to center distance between fuel assemblies placed in the fuel storage racks.
4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of
~ weight percent; 5.0
- b. keff ~ 0.95 if fully flooded with unborated water, which includes an allowance for uncertain~
and biases - - - - ' *
- c. keff ~ 0.98 if moderated by aqueou~~m, which includes an allowance for uncertai"'nti~ and
- d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 285 feet, 9 inches, Mean Sea Level, USGS datum.
4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1737 fuel assemblies.
North Anna Units 1 and 2 4.0-2 Amendme~ts 231/212
Serial No. 16-3838 Docket Nos.: 50-338/339 Attachment 3 PROPOSED TECHNICAL SPECIFICATION CHANGE PAGE VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
NORTH ANNA POWER STATION UNITS 1 AND 2
Design Features 4.0 4.0 DESIGN FEATURES 4.3.1.1 (continued)
- b. keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties and biases calculated in accordance with the methodology described in UFSAR Section 9.1;
- c. keff ~ 0.95 if fully flooded with water borated to 900 pp~, which includes an allowance for uncertainties and biases calculated in accordance with the methodology described in UFSAR Section 9.1; and
- d. A nominal 10 9/16 inch center to center distance between fuel assemblies placed in the fuel storage racks.
4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;
- b. keff ~ 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties and biases;
- c. keff ~ 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties and biases; and
- d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.
4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 285 feet, 9 inches, Mean Sea Level, USGS datum.
4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1737 fuel assemblies.
North Anna Units 1 and 2 4.0-2 Amendments
