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MONTHYEARML13365A0602013-12-18018 December 2013 Request for Alternative to Requirements of ASME Boiler and Pressure Vessel Code Request for Alternative - IWE1 Project stage: Request ML14014A2642014-01-14014 January 2014 NRR E-mail Capture - Acceptance Review - North Anna 1 & 2 - RR- Alternative to ASME Boiler and Pressure Vessel Code-IWE-5240 (TACs MF3292 and MF3293) Project stage: Acceptance Review ML14051A1062014-02-17017 February 2014 Response to Request for Additional Information (RAI) Alternative to Requirements of ASME Boiler and Pressure Vessel Code Request for Alternative - IWE1 Project stage: Response to RAI ML14064A1332014-03-0505 March 2014 NRR E-mail Capture - Request for Additional Information (RAI) for North Anna Power Stations, Units 1 and 2 Alternative Request to Use Code Case N-649 Project stage: Request ML14199A4562014-08-0505 August 2014 Relief Request (RR) IWE-5240, Visual Examinations of Various Components Project stage: Other 2014-02-17
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Category:Letter
MONTHYEARIR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1892024-08-0808 August 2024 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 Automatic Reactor Trip Due to Prni High Negative Rate ML24206A0902024-07-24024 July 2024 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 ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24082A2742024-03-22022 March 2024 Request for Approval of Alternative Request N1-I5-NDE-007 to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24086A4682024-03-21021 March 2024 Summary of Facility Changes, Tests and Experiments ML24005A0042024-03-18018 March 2024 Issuance of Amendment Nos. 296 and 279, Regarding Revised Emergency Plan for Relocation of the Technical Support Center ML24074A3012024-03-14014 March 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000338-2024403 and 05000339-2024403) IR 05000338/20244012024-03-0808 March 2024 Security Baseline Inspection Report 05000338/2024401, 05000339/2024401 and 07200016/2024401 IR 05000338/20230062024-02-28028 February 2024 Annual Assessment Letter for North Anna Power Station, Units 1 and 2 - NRC Inspection Reports 05000338/2023006 and 05000339/2023006 2024-09-23
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10 CFR 50.55a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 17, 2014 U. S. Nuclear Regulatory Commission Serial No. 13-648A Attention: Document Control Desk NAPS/JHL RO Washington, D.C. 20555 Docket Nos. 50-338, 339 License Nos. NPF-4, 7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS I AND 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI)
ALTERNATIVE TO REQUIREMENTS OF ASME BOILER AND PRESSURE VESSEL CODE REQUEST FOR ALTERNATIVE - IWEI In a letter dated December 18, 2013, Dominion requested NRC approval of an alternative associated with the Second 10-Year Containment Inservice Inspection (ISI)
Program Interval for North Anna Power Station Units 1 and 2. The second interval of the North Anna 1 and 2 Containment ISI Program complies with the ASME Boiler and Pressure Vessel (B&PV) Code, Section Xl Rules for Inservice Inspection of Nuclear Power Plant Components, 2001 Edition with 2003 Addenda.
The request for alternative would permit extending ASME Code Case N-649 applicability to the 2001 Edition / 2003 Addenda for use in the North Anna Units 1 and 2 second 10-year Containment Inservice Inspection Interval. In a January 24, 2014 e-mail from Dr. V. Sreenivas, the NRC requested additional information to complete the technical review of the proposed alternative. The attachment to this letter provides the requested information.
Dominion continues to request approval of this request for alternative by September 1, 2014 to support the upcoming North Anna Unit 2 refueling outage.
If you have any questions or require additional information, please contact Mr. Thomas Shaub at (804) 273-2763.
Respectfully, M. D. Sartain Vice President - Nuclear Engineering Commitments made in this letter: None Attachment - Response to Request for Additional Information - Alternative to Requirements of ASME Boiler and Pressure Vessel Code Request for Alternative - IWE1
Serial No. 13-648A Docket Nos. 50-338, 339 Request for Alternative IWE1 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060 NRC Senior Resident Inspector North Anna Power Station Ms. M. C. Barillas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 G9A 11555 Rockville Pike Rockville, Maryland 20852 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738
Serial No. 13-648A Docket No. 50-338/339 ATTACHMENT CONTAINMENT INSERVICE INSPECTION PROGRAM SECOND 10-YEAR INTERVAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI)
ALTERNATIVE TO REQUIREMENTS OF ASME BOILER AND PRESSURE VESSEL CODE REQUEST FOR ALTERNATIVE - IWE1 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2
Serial No. 13-648A Docket No. 50-338/339 Attachment Page 1 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI)
FOR ALTERNATIVE TO REQUIREMENTS OF ASME BOILER AND PRESSURE VESSEL CODE REQUEST FOR ALTERNATIVE - IWE1
Background
By letter dated December 18, 2013 (ML13365A060), Virginia Electric and Power Company (Dominion), requested a relief request to the Renewed Facility Operating License (FOL) Numbers NPF-4 and NPF-7 for North Anna Power Station (NAPS) Units 1 and 2. The proposed request would permit use of Alternative to Requirements of ASME Boiler and Pressure Vessel Code," Cases of ASME Boiler and Pressure Vessel Code, Case N-649, "Alternative Requirements for IWE-5240 Visual Examination, Section Xl, Division 1," March 28, 2001.
In a January 24, 2014 e-mail from Dr. V. Sreenivas, the NRC Staff requested additional information to complete its detailed technical review. The additional information was requested by February 24, 2014.
NRC Question American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section Xl, Paragraph IWE-5220, "System Pressure Tests: Tests Following Repair/Replacement Activities," requires, in part, that, "repair / replacement activities performed on the pressure retaining boundary of Class MC or Class CC components shall be subjected to a pneumatic leakage test..."
Section 5.0 of the proposed alternative states that, "a detailed visual examination in accordance with IWE-2310 prior to the Appendix J pressure test is adequate to assess the condition of the surfaces affected by repair/replacement activities and to determine the magnitude and extent of any deterioration and distress of these surfaces." No discussion is provided in Reference 1 of visual examinations conducted on areas affected by repair/replacement activities after the pressure test.
Paragraph (b) of Code Case N-649 states in part, "when the pressure test is performed, the requirements of the above paragraph shall be met." The "above paragraph" refers to Paragraph (a) which states in part "... [visual examination] shall be performed during or after the pressure test on the areas affected by the repair/replacement activity."
Explain how the requirements of ASME Code Case N-649, for a visual examination of areas affected by repair/replacement activities during or after the required pressure test, will be met.
Serial No. 13-648A Docket No. 50-338/339 Attachment Page 2 of 2 Dominion Response The pressure test (Type A) has not been performed. Satisfactory detailed visual examinations (VT-1), and dye-penetrant (PT) tests were completed on the areas affected by the repair/replacement activities prior to returning them to service, which satisfies the Code Case N-649 alternative of paragraph (b). The use of the alternative is requested to permit the use of Code Case N-649 which allows the pressure test (Type A) to be performed without the concurrent visual examination required under Section Xl, Paragraph IWE-5240.
Following the pressure test (Type A) for each unit, additional VT-3 visual examinations will be performed on the areas affected by the repair/replacement activities to meet the requirements of Code Case N-649 paragraph (a). In accordance with Code Case N-649 paragraph (a), a post pressure test visual examination (VT-3) will be performed to provide verification that surface conditions have not changed following pressure testing and that no conditions adverse to safety or quality exist. Completion of the VT-1 and VT-3 examinations exceed the requirements of Code Case N-649 to provide alternative requirements for IWE-5240 Visual Examinations.