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Category:Letter
MONTHYEARPLA-8145, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-81452024-10-21021 October 2024 Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-8145 ML24291A1562024-10-16016 October 2024 Missed Annual Inventory Required by 40 CFR 266, Subpart in PLE 0026645 PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024 Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310 PLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) PLA-8123, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) ML24092A4022024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance ML24044A2532024-03-14014 March 2024 Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting)) IR 05000387/20240112024-02-29029 February 2024 Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods ML24037A3072024-02-22022 February 2024 Summary of Regulatory Audit in Support of Relief Request 5RR-02 PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024 Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099) IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8088, Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088)2023-12-0505 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088) PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear PLA-8123, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage 05000388/LER-2017-0102018-02-0202 February 2018 Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches, LER 17-010-00 for Susquehanna, Unit 2 Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches 05000387/LER-2017-0072017-10-0909 October 2017 Secondary Containment Declared Inoperable Due to the opening of a plenum., LER 17-007-00 for Susquehanna Steam Electric Station Regarding Secondary Containment Declared Inoperable Due to Supply Air Flow 05000387/LER-2017-0052017-10-0404 October 2017 Automatic Reactor Protection System Trip on High Neutron Flux, LER 17-005-01 for Susquehanna, Unit 1 Regarding Automatic Reactor Protection System Trip on High Neutron Flux 05000388/LER-2017-0082017-09-18018 September 2017 1 OF 3, LER 17-008-00 for Susquehanna, Unit 2, Regarding Condition Prohibited by Technical Specifications Due to a Loose Terminal Block Associated with a Primary Containment Isolation Valve 05000387/LER-2017-0062017-09-0606 September 2017 Control Room Envelope In-leakage Exceeded the Technical Specification Limit, LER 17-006-00 for Susquehanna, Unit 2, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Exhaust Fan 05000387/LER-2017-0042017-08-0404 August 2017 Secondary Containment Declared Inoperable Due to Failure of an Exhaust Fan Breaker., LER 17-004-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Failure of an Exhaust Fan Breaker 05000388/LER-2017-0022017-05-0505 May 2017 Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 during Unit 2 Refueling, LER 17-002-00 for Susquehanna, Unit 2, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 During Unit 2 Refueling 05000387/LER-2017-0032017-05-0505 May 2017 Susquehanna Steam Electric Station Unit 1 05000387, LER 17-003-00 for Susquehanna, Units 1 and 2, Regarding Loss of Secondary Containment Zone 3 Due to Fan Trip 05000387/LER-2017-0012017-05-0505 May 2017 Secondary Containment Breach Due to Simultaneous Opening of Airlock Doors, LER 17-001-00 for Susquehanna, Unit 2, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Sticking Door Latch 05000387/LER-2017-0022017-04-12012 April 2017 Secondary Containment Breach due to Simultaneous Opening of Airlock Doors, LER 17-002-00 for Susquehanna, Unit 1, Regarding Secondary Containment Breach due to Simultaneous Opening of Airlock Doors 05000388/LER-2016-0052016-07-12012 July 2016 Unit 2 HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient, LER 16-005-00 for Susquehanna, Unit 2, Regarding HPCI Manually Overridden Prior to a Manual Scram During a Plant Transient 05000387/LER-2016-0152016-06-15015 June 2016 Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error, LER 16-015-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error 05000387/LER-2016-0132016-06-0909 June 2016 Secondary Containment Declared Inoperable Due to Simultaneous Opening of Double Airlock Doors, LER 16-013-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Simultaneous Opening of Double Airlock Doors 05000387/LER-2016-0142016-06-0909 June 2016 Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error, LER 16-014-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to a Human Performance Error 05000387/LER-2016-0102016-05-31031 May 2016 Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Medical Emergency, LER 16-010-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Medical Emergency 05000387/LER-2016-0092016-05-26026 May 2016 Valid Primary Containment Isolation Actuation during Local Leak Rate Testing due to Human Performance Error, LER 16-009-00 for Susquehanna, Unit 1, Regarding Valid Primary Containment Isolation Actuation During Local Leak Rate Testing Due to Human Performance Error 05000387/LER-2016-0082016-05-19019 May 2016 Inoperability of Diesel Generator Due to Misalignment of MOC Switch Contacts Due to Inadequate Post Maintenance Testing, LER 16-008-00 for Susquehanna, Unit 1, Regarding Inoperability of Diesel Generator Due to Misalignment of MOC Switch Contacts Due to Inadequate Post Maintenance Testing 05000387/LER-2016-0052016-05-16016 May 2016 Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Human Performance Error, LER 16-005-00 for Susquehanna, Units 1 and 2, Regarding Secondary Containment Declared Inoperable Due to Airlock Doors Open Due to Human Performance Error 05000387/LER-2016-0112016-05-16016 May 2016 Valve inoperability for a period longer than allowed by Technical Specifications, LER 16-011-00 for Susquehanna, Unit 1, Regarding Valve Inoperability for a Period Longer Than Allowed by Technical Specifications 05000387/LER-2016-0042016-05-10010 May 2016 Momentary Loss of Secondary Containment due to Both Airlock Doors on Elevation 779 of the Unit 2 Reactor Building being Opened at the Same Time, LER 16-004-00 for Susquehanna, Unit 1, Regarding Momentary Loss of Secondary Containment Due to Both Airlock Doors on Elevation 779 of the Unit 2 Reactor Building Being Opened at the Same Time 05000387/LER-2016-0062016-05-10010 May 2016 Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3, LER 16-006-00 for Susquehanna, Unit 1, Regarding Implementation of Enforcement Guidance Memorandum (EGM) 11-003, Revision 3 05000387/LER-2016-0032016-05-0606 May 2016 Unit 2 Zone 3 HVAC unable to maintain Zone 3 differential pressure greater than 0.25 in wg, LER 16-003-00 for Susquehanna, Unit 1, Regarding Unit 2 Zone 3 HVAC Unable to Maintain Zone 3 Differential Pressure Greater Than 0.25 in wg 05000387/LER-2016-0072016-05-0303 May 2016 Inoperability of Swing Bus Transfer Switch Due to Deformed Bolt on Linkage, LER 16-007-00 for Susquehanna, Unit 1, Regarding Inoperability of Swing Bus Transfer Switch Due to Deformed Bolt on Linkage 05000387/LER-2016-0012016-04-18018 April 2016 Secondary Containment Declared Inoperable Due to an Airlock Doors Open Due to Random Occurrence, LER 16-001-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to an Airlock Doors Open Due to Random Occurrence 05000387/LER-2016-0022016-04-18018 April 2016 Secondary Containment Declared Inoperable Due to an Airlock Doors Open Due to Random Occurrence, LER 16-002-00 for Susquehanna, Unit 1, Regarding Secondary Containment Declared Inoperable Due to an Airlock Doors Open Due to Random Occurrence 05000387/LER-2015-0062016-03-30030 March 2016 Loss of Safety Function due to Inoperability of Both Trains of the Standby Gas Treatment System and a Loss of Safety Function of the Control Room Emergency Outside Air Supply System due to Air Flow Controller found in Manual, LER 15-006-01 for Susquehanna, Unit 1, Regarding Loss of Safety Function due to Inoperability of Both Trains of the Standby Gas Treatment System and a Loss of Safety Function of the Control Room Emergency Outside Air Supply System due to Air Flow... 05000387/LER-2015-0012016-02-10010 February 2016 Inoperability of the 'B' Emergency Diesel Generator due to Fuel Oil Leakage, LER 15-001-01 for Susquehanna, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Steam Dome - Low Switches 05000387/LER-2015-0032016-01-26026 January 2016 Secondary Containment Inoperability Due to Failure to Meet Technical Specification Surveillance Requirement 3.6.4.1.1, LER 15-003-01 for Susquehanna, Unit 1, Regarding Secondary Containment Inoperability Due to Failure to Meet Technical Specification Surveillance Requirement 3.6.4.1.1 05000387/LER-2015-0092016-01-11011 January 2016 Pressure Boundary Leakage From an Inadequate Weld Repair in Small Bore Pump Seal Vent Piping, LER 15-009-00 for Susquehanna, Unit 1, Regarding Pressure Boundary Leakage From an Inadequate Weld Repair in Small Bore Pump Seal Vent Piping 05000387/LER-2015-0072016-01-0808 January 2016 Unit 1 'B' Inboard Main Steam Isolation Valve, HV141F022B closed during surveillance test which caused a SCRAM on Unit 1, LER 15-007-00 for Susquehanna, Unit 1, Regarding 'B' Inboard Main Steam Isolation Valve, HV141 F022B Closed During Surveillance Test Which Caused a SCRAM PLA-7323, LER 015-001-00 for Susquehanna Regarding Inoperability of the B Emergency Diesel Generator Due to Fuel Oil Leakage2015-04-28028 April 2015 LER 015-001-00 for Susquehanna Regarding Inoperability of the B Emergency Diesel Generator Due to Fuel Oil Leakage 2024-09-16
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JAN 2 5 2018 Brad Berryman Site Vice President U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Brad.Berryman@TalenEnergy.com SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387(388)/2017-007-00 UNIT !LICENSE NO. NPF-14 UNIT 2 LICENSE NO. NPF -22 PLA-7674 TALEN-4 ENERGY 10 CFR 50.73 Docket No. 50-387 50-388 Attached is Licensee Event Repmt (LER) 50-387(388)/2017-007-00.
The LER repmts an event which caused a loss of Secondary Containment differential pressure.
This event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v)(C) as a condition that could have prevented fulfilment of a safety function.
There were no actual consequences to the health and safety of the public as a result of this event. This letter contains no new regulatory commitments.
B. BenY"man
Attachment:
LER 50-387(388)/2017-007-00 Copy: NRC Region I Ms. T. E. Hood, NRC Project Manager Ms. L. H. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017)
Estimated burden per response to comply with this mandatory collection r equest: 80 hou r s. LICENSEE EVENT REPORT (LER) Reported l essons l ea rn ed are i n corporated into the licensing process and fed back to industry. Send comments regarding burden es tim ate to the Information Services Branch (T-2 F43), U.S. (See P age 2 for required number of digits/characters for each block) Nuclear Regulatory Commiss i on, Washington, D C 20555-000 1, or by e-ma il t o lnf oco ll ec t s. ...... t-"' Resource@nrc
.gov, and t o the Desk Officer, Office of Information and Regulatory Affairs, (See NUREG-1 0 22, R.3 for instruction and guidance for completing this form N E OB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose a n information co ll ection does n ot display a cur r en tly va lid OMB co nt ro l num ber, httQ://www. nrc.gov/readi ng-rm/doc-colle cti ons/nur§9s/staff/
sr 1 022/r3D the NRC may n ot conduct or sponso r, and a person is n ot required to r espond t o, the information collection.
- 1. FACILITY NAME DOCKET NUMBER .PAGE Susquehanna Steam Electric Station Unit 1 05000387 1 OF2 4. TITLE Secondary Containment Declared Inoperable Due to the opening of a plenum. 5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED SEQUENTIAL FACILITY NAME DOCKET NUMBER MONTH DA Y YEAR Y EAR REV MONTH DA Y YEAR Susqueahanna Steam Electric Station Unit 2 NUMBER NO. 05000388 11 30 2017 2017 -007 -00 01 ..25 2018 FACILITY NAME DOCKET NUMBER 05000 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: Check all that apply) 1 D 20.2201(b)
D 20.2203(a)(3)(i) 0 50.73(a)(2)(i i)(A) D 50.73(a)(2)(viii)(A)
D 2o.2201{d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
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) 0 50.36{c)(1)(i)(A) 0 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x) 10. POWER LEVEL D 20.2203(a)(2)(ii) 0 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 50.3 6(c)(2) D 50.73{a)(2)(v)(B)
D 73.71(a)(5) 100 D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii) 1:81 50.73(a)(2)(v)(C) D 73.77(a)(1) 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)
D 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) 0 OTHER Specify in Abstract below o r in NRC F orm 366A 12. LICENSEE CONTACT FOR THIS LER LI CENSEE CON TA CT NUMBER (Include Area Code) /Nicole PaQiiaro-LicensinQ Specialist-Nuclear Regulatory Affairs k 570) 542-6578 13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CA U S E SYSTEM COMPONENT MANU-REPORTABLE CAUSE SYSTEM COMPONENT MANU-REPORTABLE FACTURER T O EPI X FACTURER T O EPI X 14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DA Y YEAR YES (If yes, complete 15. EXPECTED SUBMISSION DATE) D NO SUBMISSION 02 23 20 18 DATE ft\BSTRA CT (Umit t o 1400 spaces, i.e., ap pro ximately 15 s in gle-spaced typewritten lin es) On November 30, 2017 at 1026, the Susquehanna Control Room received indication that a loss of Secondary Containment Zone 2 differential pressure had occurred.
Control Room operators noted a differential pressure of 0" Water Column (WC) for several seconds, followed by a high differential pressure of 0.5" WC. System differential pressure was restored to normal in 3 minutes. The cause of the pressure swings is under investigation.
Zone 2 differential pressures being less than 0.25" WC constitutes a loss of Secondary Containment based on not meeting requirements of Technical Specification (T.S.) 3.6.4.1 Surveillance Requirement 3.6.4.1.1 This condition is being reported in accordance with 10 CFR 50. 73(a)(2)(v)(C) as a condition that could have prevented fulfillment of safety function.
This event was reported in ENS 53098 under 10 CFR 50.72(b){3)(v)(c)
There is no redundant Susquehanna Secondary Containment system. There were no actual consequences to the health and safety of the public as a result of this event. NRC F O RM 366 (04-2017)
NRC FORM 366A (04-2017)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020 LICENSEE EVENT REPORT (LER) CONTINUATION SHEET (See NUREG-1 022, R.3 for instruction and guidance for completing this form http://WoNV-J.nr c.gov/readinq-rm/doc-colle c tions/nureas/s ta ff/sr1 0 22/r 3 D 1. FACILITY NAME Susquehanna Steam Electric Station Unit 1 NARRATIVE CONDITIONS PRIOR TO EVENT Estimated burden per r esponse to comply with this mandatory co ll ection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons l earned are incorporated into the licensing process and fed back to industry.
Send comments r egarding burden estimate to the Inf ormatio n SeiVices Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555*000 1 , or by e-m ail to lnf oco lle cts.Resource@nrc.gov, and to the Desk Officer, Office of Inf ormation and Regulatory Aff airs, NEOB-10 202, (3150-0104).
Office of Manag e ment and Budget , Washington, DC 20503. If a means u se d t o im pose a n in f ormatio n co ll ectio n do es n ot display a currently valid OMB control num ber, the NRC may not cond u ct or sponsor, and a person is not req uired to respond to, the information co ll ec ti on. 2. DOCKET NUMBER YEAR 05000387 2017 3. LER NUMBER SEQ UENTIA L NUMB ER -007 REV NO. -00 Unit 1 -Mode 1 , approximately 1 00 percent Rated Thermal Power Unit 2 -Mode 1, approximately 100 percent Rated Thermal Power There were no structures, systems, or components that were inoperable at the start of the event that contributed to the event. EVENT DESCRIPTION On November 30, 2017 at 1026, the Susquehanna Control Room received indication that a loss of Secondary Containment Zone 2 differential pressure had occurred.
Control Room operators noted a differential pressure of 0" Water Column (WC) for several seconds, followed by a high differential pressure of 0.5" WC. System differential pressure was restored to normal in 3 minutes. The cause of the pressure swings is under investigation.
Zone 2 differential pressures being less than 0.25" WC constitutes a loss of Secondary Containment based on not meeting requirements of Technical Specification (T.S.) 3.6.4.1 Surveillance Requirement 3.6.4.1. There were no actual consequences to the health and safety of the public as a result of this event. The condition is being reported in accorance with 10 CFR 50.73(a)(2)(v)(C) as a condition that could have prevented fulfillment of a safety function.
This event was reported in ENS 53098 under 10 CFR 50.72(b)(3)(v)(c).
There is no redundant Susquehanna Secondary Containment system. CAUSE OF EVENT This event is still under investigation. The cause will be provided in the supplement.
ANALYSIS/SAFETY SIGNIFICANCE This event is still under investigation. The safety significance will be provided in the supplement CORRECTIVE ACTIONS This event is still under investigation.
The corrective action will be provided in the supplement.
PREVIOUS SIMILAR EVENTS This event is still under investigation.
Previous similar events will be identified under the supplement NRC F ORM 3668 (04-2017)
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