Similar Documents at Surry |
---|
Category:Letter
MONTHYEARML24318C4622024-11-13013 November 2024 Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - License Amendment Nos. 315 and 315 Updated Information Regarding TSC Ventilation Design IR 05000280/20240032024-11-12012 November 2024 Integrated Inspection Report 05000280-2024003 and 05000281-2024003 ML24302A1762024-10-22022 October 2024 Core Operating Limits Report Surry 2 Cycle 33 Pattern Hot Revision 0 ML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 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 ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 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 IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2862024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign 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 ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20240112024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 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 ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - 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 2024-09-03
[Table view] |
Text
VIRGINIA ELECTRIC A N D POWER COMPANY RICHMOND, VIRGINIA 23261 September 7, 2004 U.S. Nuclear Regulatory Commission Serial No.04-506 Attention: Document Control Desk NL&OS/GDM R3 Washington, D.C. 20555 Docket Nos. 50-280/281 License Nos. DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY CDOMINION)
SURRY POWER STATION UNITS 1 AND 2 INSERVICE TESTING CIST) PROGRAM FOR PUMPS AND VALVES CHECK VALVE CONDITION MONITORING PROGRAM EXTENSION OF SURRY UNIT 2 IST PROGRAM THIRD TESTING INTERVAL The purpose of this letter is to inform the NRC that Surry Power Station will implement a check valve condition monitoring program in accordance with the ASME OM Code ISTC, Appendix II, for the fourth interval of the lnservice Testing (IST) programs for Units 1 and 2. Also, Surry Power Station has extended the third interval for the Unit 2 IST program from May 10, 2004 to May 10, 2005. The fourth interval for Unit 2 will start on May 10, 2005. Surry Power Station started the fourth interval for the Unit 1 IST program on May 10, 2004. The ASME OM Code edition and addenda effective for the fourth interval for both Surry Units 1 and 2 is the 1998 Edition, the 1999 Addenda and the 2000 Addenda.
The Surry Units 1 and 2 fourth interval IST programs will comply with Appendix II, "Check Valve Condition Monitoring Program," of the ASME OM Code, Subsection ISTC, as an alternative to the requirements of ISTC-3510, ISTC-3520, ISTC-3540 and ISTC-5221, and subject to the following provisions and limitations. According to the Code of Federal Regulations, 10CFR50.55a(b)(3)(iv),
"Appendix I/. Licensees applying Appendix II, "Check Valve Condition Monitoring Program," of the OM Code, 1995 Edition with the 1996 and 1997 Addenda, shall satisfy the requirements of paragraphs (b)(3)(iv)(A),
(b)(3)(iv)(B), and (b)(3)(iv)(C) of this section. Licensees applying Appendix II, 1998 Edition through the latest edition and addenda incorporated by reference in paragraph (b)(3) of this section, shall satisfy the requirements of paragraphs (b)(3)(iv)(A),(b)(3)(iv)(B),and (b)(3)(iv)(D)of this section.
(A) Valve opening and closing functions must be demonstrated when flow testing or examination methods (nonintrusive, or disassembly and inspection) are used.
Serial No.04-506 Docket Nos. 50-280,281 Page 2 of 3 (B) The initial interval for tests and associated examinations may not exceed two fuel cycles or 3 years, whichever is longer; any extension of this interval may not exceed one fuel cycle per extension with the maximum interval not to exceed 10 years; trending and evaluation of existing data must be used to reduce or extend the time interval between tests.
(C) If the Appendix II condition monitoring program is discontinued, then the requirements of ISTC 4.5.1 through 4.5.4 must be implemented.
(D)The provisions of ISTC-3510, ISTC-3520, and ISTC-3540 in addition to ISTC-5221 must be implemented if the Appendix II condition monitoring program is discontinued.
The Surry Unit 2 third interval IST program complies with the ASME Code Section XI, 1989 Edition, which invokes OMa-1988 Addenda, Part 6, for pump testing and Part 10 for valve testing. The third interval for Unit 2 was extended by one year (from May 10, 2004 to May 10, 2005) as allowed by Section XI 1989 Edition, Subsection IWA, paragraph IWA-2430(d). IWA-2430(d) states:
For components inspected under Program B, each of the inspection intervals may be extended or decreased by as much as 1 year. Adjustments shall not cause successive intervals to be altered by more than 1 year from the original pattern of intervals.
Surry Power Station uses Inspection Program B which divides the original 40-year life of the plant into four 10-year intervals as defined in IWA-2432. The third interval was extended to provide sufficient time for the determination of appropriate test measures to meet new ASME OM Code requirements imposed on the fourth interval IST program.
If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.
Very truly yours, L. N. Hartz Vice President - Nuclear Engineering
Serial No.04-506 Docket Nos. 50-280, 281 Page 3 of 3 Commitment made in this letter:
- 1. Surry Power Station will implement a check valve condition monitoring program in accordance with the ASME OM Code ISTC, Appendix II, for the fourth interval of the Inservice Testing (IST) Programs for Surry Units 1 and 2.
cc: US. Nuclear Regulatory Commission Region II Sam Nunn Federal Atlanta Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. S. R. Monarque U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8H12 Rockville, Maryland 20852 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station Mr. R. Smith Authorized Nuclear Insurance Inspector Surry Power Station