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Category:Letter
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NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 – Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure 2024-09-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23096A1972023-04-0606 April 2023 License Amendment Request - Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure - Response to Request for Additional Information 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 ML23044A0392023-02-11011 February 2023 Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request for Additional Information ML23025A1252023-01-25025 January 2023 Response to Request for Additional Information License Amendment Request, NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure ML22343A0002022-12-0909 December 2022 Response to Request for RAI on ASME Operation & Maintenance Code Inservice Testing Program - Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML22342A4242022-12-0707 December 2022 Response to 3/12/2012 Request for Information Enclosure 2, Recommendation 2.0, Flooding Focused Evaluation Integrated Assessment Submittal Revised Commitment Completion Date 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 ML22300A1882022-10-27027 October 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information ML22220A2162022-08-0808 August 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability Supplemental Information ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit 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 ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis 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 ML21098A2612021-04-0808 April 2021 Subsequent License Renewal Application, Response to Request for Additional Information Re Environmental Review ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification ML21056A5412021-02-25025 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 ML21042B9262021-02-11011 February 2021 ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative Requests S1-I5-ISl-05 and S2-I5-ISl-06 - Response to Request for Additional Information ML22040A1012021-02-0909 February 2021 Response to Request for Additional Information 2021 Steam Generator Inservice Report 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 ML20247J6352020-09-0303 September 2020 Virginia Electric & Power Co - Subsequent License Renewal Application (SLRA) Environmental Review, Response to Request for Additional Information Concerning Aquatic Resources ML20181A4222020-06-29029 June 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Response to Request for Additional Information ML20181A3082020-06-23023 June 2020 Response to Request for Additional Information on 2019 Steam Generator Inservice Inspection Report ML20269A4072020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 2 of 3 ML20269A4062020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 3 of 3 ML20269A4082020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 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Text
e e VIRGINIA ELECTRIC A.ND POWER COMPANY RICHMOND, VIRGINIA 23261 January 11, 1977 Mr. Norman C. Moseley, Director
()dl~
Serial No. 345/112476 Office of Inspection and Enforcement PO&M/GRMjr:clw U.S. Nuclear Regulatory Conunission Region II - Suite 818 Docket 230 Peachtree Street, Northwest Atlanta, Georgia 30303 License
Dear Mr. Moseley:
In your letter of November 24, 1976 you forwarded IE Circular 76-06, "Stress Corrosion Cracking in Stagnant, Low Pressure Stainless Piping Containing Boric Acid Solution at PWR's, 11 for our review. This circular defines five (5) actions required to be taken by the licensee. The purpose of this letter is to address those action items identified in your letter.
The aforementioned circular cites a recent occurrence at Unit Nos. 1 and 2 of Surry Power Station associated with the piping of the recirculation spray sys-tems. The cracking of the Surry piping has been determined to be intergranular stress corrosion cracking which initiated on the inside of the piping. However, the three (3) conunon factors associated with the corrosion mechanism identified in the circular may not be completely applicable for the Surry event. In our letter of November 22, 1976, Serial No. 308A, we forwarded Licensee Event Report No. USRE-S2-76-15 which provides a complete description of the Surry event, there-fore, it will not be described herein. Each of the action items identified in your letter are listed below.
NRC ACTION ITEM
- 1. "Description of your program for assuring continued integrity of those safety-related piping systems which are not frequent-ly flushed, or which contain nonflowing liquids. This pro-gram should include consideration of hydrostatic testings in accordance with ASME Code Section XI rules (1974 Edition) for all active systems required for safety injection and contain-ment spray, including their recirculation modes, from source of water supply up to the second isolation valve of the pri-mary system. Similar test should be considered for other safety related systems."
. . ~
VIRGINIA ELECTRIC AND POWEil COMPANY TO Mr. Norman C. Moseley Page 2
RESPONSE
Portions of the safety related system, i.e. the high head safety injection system, the low head safety injection system, and the containment spray systems are presently flushed on a monthly basis to avoid stagnation resulting in a con-centration of p'otential contaminants. The flushing and sampling is defined in Technical Specification 4.1.E. The recirculation spray and containment spray piping are normally dry, except for testing of the pumps of the outside recircu-lation spray system. As mentioned in the aforementioned circular, portions of the recirculation spray piping installed at the Surry Power Station, Unit Nos. 1 and 2, recently experienced stress corrosion cracking as a result of the intrusion of contaminants from foreign sources. In addition, the inside containment sump was identified to contain contaminants. A program is being initiated to assure th~
sump is dry prior to testing of the inside recirculation spray pumps. In our letter of November 22, 1976, Serial No. 308A, we forwarded Licensee Event Report USRE-S2-76-15 update, which describes the event and our corrective action. We believe that the current flushing program in conjunction with the nondestructive examination programs proposed below will provide assurance that degradation of pip-ing will be detected.
NRG ACTION ITEM
- 2. "Your program should also consider volumetric examination of a representative number of circumferential pipe welds by nondestructive examination techniques. Such examination should be performed generally in accordance with Appendix I of Section XI of the ASME Code, except that the examined area should cover a distance of approximately six (6) times the pipe wall thickness (but not less than 2 inches and need not exceed 8 inches) on each .side of the weld. Supplementary examination techniques such as radiography, should be used where necessary for evaluation or confirmation of ultrasonic indications resulting from such examinations."
RESPONSE
A volumetric examination will be performed on the recirculation and contain-ment spray system. Twenty (20) selected circumferential pipe welds with pre-ference given to welds located in low areas will undergo nondestructive examination.
The nondestructive examination will be performed at each scheduled refueling outage. The examination will be performed generally in accordance with Appendix I of Section XI of the ASME Code, except that the examined area will cover a distance of approximately six (6) times the pipe wall thickness (but not less than two (2) inches and need not exceed eight (8) inches) on each ~ide of the weld.
Supplementary examination techniques such as radiography, will be used where necessary for evaluation or confirmation of ultrasonic indications resulting from such examinations.
,_ VIR~INIA E~CTRIC AND POWER Co~'NY TO Mr. Norman c.
Moseley Page 3 NRC ACTION ITEM
- 3. "A report describing your program and schedule for those inspections should be submitted within 30 days after receipt of this Circular."
RESPONSE
This letter is intended to satisfy the requirements of Item No. 3.
NRC ACTION ITEM
- 4. "The NRC Regional Office should be informed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of any adverse findings during nondestructive evaluation of the accessible piping welds identified above."
RESPONSE
The NRC Regional Office will be informed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of any confirmed adverse findings resulting during nondestructive evaluation of the accessible piping welds identified in the test program.
NRC ACTION ITEM
- 5. "A summary report of the examination and evaluation of results should be submitted within 60 days from the date of completion of proposed testing and examinations.
This summary report should also include a brief description of plant conditions, operating procedures or other activities which provide assurance that the effluent chemistry will maintain low levels of potential corrodants in such stagnant regions within the piping."
RESPONSE
A summary of the examination and evaluation of the results will be submitted within 90 days of completion of the proposed testing and examination. This report will also include a brief description of activities which will provide assurance that the piping will be dry or flushed to maintain the low levels of corrodants.
Very truly yours,
.1-;*, ) /;. ,_;;(<( / ;,)_;
C. M. Stallings Vice President-Power Supply and Production Operations