Similar Documents at Surry |
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Category:Letter
MONTHYEARML24302A1762024-10-22022 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 IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 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 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) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection 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 IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24115A1952024-04-24024 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 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 2024-09-03
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000280/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 05000280/LER-2022-003, Loss of Emergency Switchgear Room Cooling Due to Use of Incorrect Air Handler Fan V-Belts2022-11-11011 November 2022 Loss of Emergency Switchgear Room Cooling Due to Use of Incorrect Air Handler Fan V-Belts 05000280/LER-2022-002, Failure of Unit 1 Emergency Diesel Generator Results in an Operation or Condition Prohibited by Technical Specifications2022-09-19019 September 2022 Failure of Unit 1 Emergency Diesel Generator Results in an Operation or Condition Prohibited by Technical Specifications 05000280/LER-2022-001, Unit 2, Failure of Two Intake Canal Level Probes Due to Biofouling2022-05-18018 May 2022 Unit 2, Failure of Two Intake Canal Level Probes Due to Biofouling 05000280/LER-2021-001, Unanalyzed Condition Due to Appendix R Concern Identified with Cable Separation2021-11-11011 November 2021 Unanalyzed Condition Due to Appendix R Concern Identified with Cable Separation 05000281/LER-2020-001, Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication2020-11-0606 November 2020 Cancellation of LER 2020-001-00 for Surry Power Station Unit 2 Re Loss of Containment Cooling Affecting Containment Partial Pressure Indication 05000280/LER-2019-0022020-02-0404 February 2020 LER 2019-002-00 for Surry Power Station Unit 1, Items Non-Conforming to Design for Tornado Missile Protection 05000280/LER-2017-0012017-10-0606 October 2017 1 OF 3, LER 17-001-00 for Surry, Unit 1, Regarding Shutdown due to an Unisolable Leak in Reactor Coolant Pressure Boundary 05000281/LER-2016-0012016-12-0202 December 2016 Unit 2 Reactor Trip due to Generator Differential Lockout, LER 16-001-00 for Surry Power Station, Unit 2, Regarding Reactor Trip Due to Generator Differential Lockout 05000280/LER-2016-0012016-07-11011 July 2016 1 OF 4, LER 16-001-00 for Surry Power Station, Unit 1 and 2, Regarding Emergency Service Water Pump Inoperable Due to Corrosion of Valve Support ML1015505662009-03-0404 March 2009 Event Notification for Surry on Relief Valve Failure Results in Tritium and Cesium Spill ML0702501902007-01-17017 January 2007 Special Report on Qpt Not Less than Two Percent for Twenty Four Hours ML19105B1281979-08-21021 August 1979 LER 1979-011-03X for Surry Units 1 & 2 Loss of Power with Both Units at Cold Shutdown, Observed Radiation Monitors Without Power ML19093B4141978-09-26026 September 1978 Reporting Condenser Cooling Water Outlet Temperature to James River Decreased by 3.5oF as Measured at Station Discharge Structure ML19105A3001978-09-0808 September 1978 LER 78-013-03X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank ML19105A3011978-09-0101 September 1978 LER 1978-028-03L-0 for Surry 2 Re Containment Pressure Exceeded Allowable Limit ML19095A4971978-08-25025 August 1978 Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste ML19095A4981978-08-22022 August 1978 Submit Licensee Event Report Nos. LER 1978-019/03L-0, LER 1978-021/03L-0, LER 1978-022/03L-0, LER 1978-023/03L-0, LER 1978-025/03L-0, LER 1978-026/03L-0 for Surry Unit No. 1 ML19105A0781978-08-16016 August 1978 Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria ML19105A0771978-08-16016 August 1978 Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria ML19105A0791978-08-11011 August 1978 LER 78-026/03L-0. Follow-up Inspection for Valve Cleanliness, Discovered That Containment Spray Isolation Valves (MOV-CS-201C and D) Contained No More That Five Milliliters. Technical Specification TS 6.6.2.b.(3) ML19095A4991978-08-0404 August 1978 Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required ML19105A0801978-07-28028 July 1978 LER 1978-022-03L-0 Re Axial Power Distribution Monitoring Was Exceeded,& Three LERs 1978-021-03L-0, LER 1978-023-03L-0, & LER 1978-024-03L-0 Re Inlet Circulating Water Temperature Exceeded ML19095A5001978-07-28028 July 1978 Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid ML19095A2281978-07-27027 July 1978 Reporting & Providing Additional Information on Incidence of Missing Two Steam Generator Tube Plugs Found During Inspection ML19095A2291978-07-26026 July 1978 Reporting of Cooling Water Discharge Temperature Change Rate on 7/9/1978 & Found No Evidence of Any Detrimental Effects in River or Its Inhabitants ML19095A5011978-07-21021 July 1978 Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening ML19105A0811978-07-17017 July 1978 LER 1978-025-03L for Surry Unit 2 Excessive Gap Around Battery Room Ventilation Duct ML19105A0821978-07-17017 July 1978 LER 1978-025-03L for Surry Unit 2 Excessive Gap Around Battery Room Ventilation Duct ML19095A5021978-07-0707 July 1978 Submit Licensee Event Report Nos. LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded ML19095A5041978-06-27027 June 1978 Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces ML19095A5031978-06-27027 June 1978 Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces ML19105A0831978-06-23023 June 1978 LER 1978-017-03L, LER 1978-018-03L, LER 1978-019-03L, & LER 1978-020-03L for Surry Unit 2 Related to Snubbers ML19095A2481978-06-19019 June 1978 06/19/1978 Letter Reporting Increase of Condenser Cooling Water Discharge ML19095A5051978-06-0707 June 1978 Submit Licensee Event Report No. LER-78-012/03L-0 Re Inside Recirculation Spray Pump 1-RS-P-1A, Failure to Rotate by Hand ML19095A5061978-05-23023 May 1978 Submit Licensee Event Report Nos. LER-78-008/03L-0, LER-78-009/03L-0, LER-78-010/03L-0, LER-78-011/03L-0 for Surry Unit No. 1 ML19105A0851978-05-23023 May 1978 LER 1978-015-03L for Surry Unit 2 Finding of Air Leak on Header of Control Room Emergency Air Supply Bank ML19105A0861978-05-12012 May 1978 LER 1978-013-03L for Surry Unit 2 Reactor Brought Critical Below Minimum Insertion Limit on D Control Bank ML19095A5071978-05-0505 May 1978 Submit Licensee Event Report No. LER-78-007/03L-0 Re Leak on Body to Bonnet Joint Diaphragm Valve 1-CH-98 ML19105A0871978-05-0505 May 1978 LER 1978-014-03L for Surry Unit 2 Charging Pump Service Water Pump a Tripped on High Current ML19095A5081978-04-19019 April 1978 Submit Licensee Event Report No. LER-78-006/01T-0 Re Seismically Disqualified Two Pipe Extensions on Fire Protection Yard Piping ML19105A0881978-04-19019 April 1978 LER 1978-006-01T for Surry Unit 2 Review of Fire Protection Yard Piping Revealed That Two Pipe Extensions May Not Have Been Seismically Qualified ML19095A5091978-04-0707 April 1978 Forwarding Licensee Event Report No. LER-78-005/01T-0 Re Westinghouse'S Error in LOCA-ECCS Evaluation Model, Which Will Result in Higher Calculated Peak Clad Temperature ML19105A0901978-04-0606 April 1978 LER 1978-012-01T for Surry Unit 2 Failure to Meet Containment Integrity ML19095A5101978-04-0404 April 1978 Submit Licensee Event Report No. LER-78-004/03L-0 Re Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler ML19105A0921978-04-0404 April 1978 LER 1978-011-03L for Surry Unit 1 Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler ML19105A0931978-03-30030 March 1978 LER 1978-008-03L Re Snubber Body in Contact with Structure; LER 1978-009-03L Re Trip of Boric Acid Transfer Pump; & LER 1978-010-03L Re Failure of Pressurizer Channel ML19095A5111978-03-28028 March 1978 Submit Licensee Event Report No. LER-78-003/03L-0 Re Failed Heat Tracing, Panel 8 Circuit 24 ML19095A5121978-03-21021 March 1978 Submit Licensee Event Report No. LER-78-002/01T-0 Re Additional Radial Peaking Factor Surveillance ML19105A0941978-02-27027 February 1978 LER 1978-006-03L Re Failure of Sola Transformer, & LER 1978-007-03L Re Trip of Boric Acid Transfer Pump on Thermal Overload 2024-07-30
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LER-2019-002, |
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10CFR50.73 Virginia Electric and Power Company Surry Power Station 5570 Hog Island Road Surry, Virginia 23883 February 4, 2020 U. S. Nuclear Regulatory Commission Serial No.: 20-041 Attention: Document Control Desk SPS: SCN Washington, D. C. 20555-0001 Docket No.: 50-280 50-281 License No.: DPR-32 DPR~37
Dear Sir ot Madam:
Pursuant to 10CFR50.7'3, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Units 1 and 2.
Report No. 50-280, 50-281 / 2019-002-00 This report has been reviewed by the Station Facility Safety Review Committee and will be forwarded to the Management Safety Review Committee.
Very truly yours, F. Mladen Site Vice President Surry Power Station Enclosure Commitment contained in this letter: None cc: U.S. Nuclear Regulatory Commission, Region II Marquis One Tower, Suite 1200 2~5 Peachtree Center Ave., NE Atlanta, GA 30303-1257 TEZZ
-~'
NRG Senior Resident Inspector Surry Power Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018) Estimated burden per response to comply with this mandatory collection request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons !earned are incorporated into the licensing process and fed back to
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tt,.fl REG(I(
.,.,, LICENSEE EVENT REPORT (LER) indusby. Send comments regarding burden estimate to U,e Information Services Branch (T-2 F43). U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail
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(See Page 2 for required number of digits/characters for each block) to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and
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.* f~ (See NUREG-1022, R.3 for instruction and guidance for completing this form Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budge~
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..... ~o~ httg://www.nrc.gov/reading-rm/doc-collectjonsJnuregs/staff/sr1022/r3/)
Washington, DC 20503. If a means used to impose an information collection does not display a currently valid 0MB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. Facility Name 2. Docket Number 3. Page Surry Power Station Unit 1 05000 280 1 OF 3
- 4. Title Items Non-Conforming to Design for Tornado Missile Protection
- 5. Event Date 6. LER Number 7. Report Date 8. Other Facilities Involved Facility Name Docket Number Month Day Year Year I Sequential Number I Rev No.
Month Day Year Surry Power Station Unit 2 05000 Docket Number 281 12 11 2019 2019 - 002 ~
00 02 04 2020 Facility Name 05000
- 9. Operating Mode 11. This Report is Submitted Pursuant to the Requirements of 1 O CFR §: (Check all that apply)
D 20.2201(b) D 20.2203(a)(3)(i) D 50.73(a)(2)(ii)(A) D 50. 73(a)(2)(viii)(A)
D 20.2201(d) D 20.2203(a)(3)(ii) [2] 50. 73(a)(2)(ii)(B) D 50. 73(a)(2)(viii)(B)
N D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii) D 50. 73(a)(2)(ix)(A)
D 20.2203(a)(2)(i) D 50.36(c)(1 )(i)(A) D 50.73(a)(2)(iv)(A) D 50.73(a)(2)(x)
~-.*~
- 10. Power Level D 20.2203(a)(2)(ii) D 50.36(c)(1 )(ii)(A) D 50.73(a)(2)(v)(A) D 73.71(a)(4)
D 20.2203(a)(2)(iii) D 50.36(c)(2) D 50.73(a)(2)(v)(B) *o 73. 71 (a)(5)
D 20.2203(a)(2)(iv) D 50.46(a)(3)(ii) D 50.73(a)(2)(v)(C) D 73. 77(a)(1) 100 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D) D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi) [2] 50.73(a)(2)(i)(B) D 50.73(a)(2)(vii) D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
D Other (Specify in Abstract below or in NRC Form 366A)
- 12. Licensee Contact for this LER Licensee Contact Telephone Number (Include Area Code)
Stephen C. Newman, Nuclear Engineer Ill 757-365-3397
- 13. Complete One Line for each Component Failure Described in this Report Cause System Component Manufacturer Reportable to ICES Cause System Component Manufacturer IReportable to ICES I I I I I Month Day Year
- 14. Supplemental Report Expected
- 15. Expected Submission Date D Yes (If yes, complete 15. Expected Submission Date) [2] No Abstract (Limit to 1400 spaces. i.e., approximately 14 single-spaced typewritten lines)
On December 11, 2019, Surry Nuclear Power Plant determined that the certain Unit 1 and 2 Class 1 Structures, Systems, and Components (SSCs) did not conform with the licensing basis for protection against a design basis tornado generated missile.
The affected equipment was declared inoperable and enforcement discretion invoked in accordance with NRG Enforcement Guidance Memorandum (EGM) 15-002, Rev. 1, "Enforcement Discretion for Tornado Missile Protection Noncompliance." Initial compensatory measures were implemented pursuant to the guidance of NRG Interim Staff Guidance DSS-ISG-2016-01, Appendix A, within the time allowed by the applicable Limiting Conditions for Operation and the associated systems were then declared operable, but nonconforming.
Since the condition was part of the original plant design and licensing of the station, there was no specific cause identified.
There were no safety consequences as a result of this event. Actions are underway to address the condition.
NRC FORM 366 (04-2018)
l I
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments LICENSEE EVENT REPORT (LER) regarding burden estimate to the Information Services Branch (T-2 F43), U. S. Nuclear Regulatory CONTINUATION SHEET Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of lnfonmation and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an infonmation (See NUREG-1022, R.3 for instruction and guidance for completing this form collection does not display a currently valid 0MB control number, the NRG may not conduct or http://www.nrc.gov/reading-rm/doc-collections/nuregs/staffisr1022/r3/) sponsor, and a person is not required to respond to, the infonmation collection.
- 2. DOCKET NUMBER 3. LER NUMBER
- 1. FACILITY NAME SEQUENTIAL REV I c:lYEAR NUMBER NO.
Surry Power Station Unit 1 05000- 280 I ~-I 002 1-0 NARRATIVE
Background:
Surry Nuclear Power Station, Units 1 and 2, are Westinghouse 3-Loop Pressurized Water Reactors [EIIS: AC] with a licensed maximum power level of 2546 megawatts thermal. Surry Unit 1 received its initial operating license on May 25, 1972, and Surry Unit 2 received its initial operating license on January 29, 1973, based in part on the design as described in Surry Power Station's Updated Final Safety Analysis Report (UFSAR).
As described in Chapter 2.0 of the UFSAR, Class 1 structures and systems, or parts thereof, whose failure might prevent the simultaneous cold shutdown of both reactor units during a loss-of-power incident will withstand by design a tornado missile with the following characteristics and associated effects:
- Missile equivalent to a wooden utility pole 40-foot long, with 12-inch diameter, weighing 50 lbs/ft3, and traveling in a vertical or horizontal direction at 150 mph.
- Missile equivalent to a 1-ton automobile traveling at 150 mph.
A: Plant Operating Conditions Prior to Event:
Units 1/2 Date: December 11, 2019 Power level: 100 percent/100 percent Mode: N/f\J There were no SSCs out-of-service that contributed to this event.
B: Description of Event:
On December 11, 2019, at 1356 [EST], it was concluded that certain Class 1 SSCs are vulnerable to design basis tornado missiles which could render the equipment inoperable and unable to perform its design function. Specifically, this condition affected the following equipment:
- 1. Component Cooling Water [cl IS: CC] piping for the 'A' Spent Fuel Cooling Water system heat exchanger [El IS: DA-HX]. This heat exchanger is vulnerable to a horizontal missile traveling through the fuel building roll-up door.
- 2. All three (3) Emergency Service Water (ESW) pumps [EIIS: BI-P] and their diesel fuel oil supply tank [EIIS: DC-TK].
The ESW pumps and diesel fuel oil tank are vulnerable to a horizontal missile penetrating the tornado missile screens
[EIIS: SCN].
- 3. Certain Component Cooling Water system pump discharge piping is vulnerable from a vertical missile penetrating the auxiliary building [EIIS: NF] roof.
- 4. The Unit 1 Auxiliary Feedwater (AFW) system pumps [EIIS: BA-P] and the pump suction and discharge piping are vulnerable to a missile traveling through the tornado missile screens on the sides and roof of the main steam valve [EIIS:
SB-VJ house. This vulnerability also exists for the Unit 2 AFW system.
- 5. The Unit 2 Service Water (SW) supply valves [EIIS: KE-V] to the river water make-up pump are vulnerable to a vertical missile traveling through the turbine building roof.
NRC FORM 366A (04-2018) Page 2 of 3
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments LICENSEE EVENT REPORT (LER) regarding burden estimate to the Information Services Branch (T-2 F43), U. S. Nuclear Regulatory CONTINUATION SHEET Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of lnfonmation and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an infonmation (See NUREG-1022, R.3 for instruction and guidance for completing this form collection does not display a currently valid 0MB control number, the NRG may not conduct or http://www.nrc.gov/reading-rrn/doc-collections/nuregs/staff/sr1022/r3/l sponsor, and a person is not required to respond to, the infonmation collection.
- 2. DOCKET NUMBER 3. LER NUMBER
- 1. FACILITY NAME YEAR SEQUENTIAL REV
~ NUMBER NO.
Surry Power Station Unit 1 05000-1 280 I ~-I 002 1-~
NARRATIVE The affected equipment was declared inoperable and enforcement discretion invoked in accordance with NRC Enforcement Guidance Memorandum (EGM) 15-002, Rev. 1, "Enforcement Discretion for Tornado Missile Protection Noncompliance." Initial compensatory measures were implemented pursuant to tlie guidance of NRC Interim Staff Guidance DSS-ISG-2016-01, Appendix A, within the time allowed by the applicable Limiting Conditions for Operation (LCOs) and the associated systems were then declared operable, but nonconforming. An 8-hour ENS notification was submitted [Event Notification 54437].
This event is reportable in accordance with 10 CFR 50. 73(a)(2)(i)(B) as a condition prohibited by Technical Specification and 10 CFR 50.73(a)(2)(ii)(B) as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degraded plant safety. These reporting criteria were selected based on the historical nature of the issue.
C: Cause of Event:
This condition was part of the original plant design and licensing of the station. There was no specific cause identified.
D: Safety Consequences:
As documented EGM 15-002 (Rev. 1), tornado missile scenarios that may lead to core damage are very low probability events because safety-related SSCs are typically designed to withstand the effects of tornados. In addition, because plants are designed with redundancy and diversity, the tornado missiles would have to affect multiple trains of safety systems and/or means of achieving safe shutdown. -*
E: Corrective Action:
For the Surry Power Station, enforcement discretion provided by EGM 15-002 remains in effect until June 10, 2020, at which time modifications, analysis, license amendments, or other actions must be implemented to resolve the missile vulnerabilities.
F: Previous Occurrences:
There have been no previous Licensee Event Reports at Surry Power Station on this issue.
G: Component Failures:
None.
NRC FORM 366A (04-2018) Page 3 of 3