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Category:Letter type:PLA
MONTHYEARPLA-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 PLA-8131, 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 PLA-8139, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum PLA-8132, 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-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) 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) PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) 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-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-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 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) 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) 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 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) 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) 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 PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums PLA-8048, Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence2023-01-14014 January 2023 Response to Request for Additional Information Regarding License Amendment Requesting Temporary Addition of Analyzed Rod Position Sequence PLA-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence2023-01-10010 January 2023 Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence PLA-8039, Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information2022-12-22022 December 2022 Application for Order Approving Indirect Transfer of Control of License Amendments - Supplemental Information PLA-8038, Notification of Petition for Bankruptcy (PLA-8038)2022-12-14014 December 2022 Notification of Petition for Bankruptcy (PLA-8038) 2024-09-18
[Table view] Category:Licensee Event Report (LER)
MONTHYEARPLA-8131, 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 PLA-8139, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum PLA-8132, 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
[Table view] |
Text
Edward Casulli Susquehanna Nuclear, LLC Site Vi ce Pr esid ent 769 Sa l em Bou levard Berwick, PA I 8603 TALEN~
Te l. 570.542.3795 Fax 570.542. 1504 Edward.Casul l i@T alenEnergy.co m ENERGY
May 23, 2024
Attn: Document Control Desk 10 CFR 50.73 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387/2024-001-00 UNIT 1 LICENSE NO. NPF-14 PLA-8123 Docket No. 50-387
Attached is Licensee Event Report (LER) 50-387/2024-001-00. The LER reports an event involving inoperability of a Main Steam Line Isolation Valve that was determined to be reportable in accordance with 10 CFR 50.7 3(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
There were no actual consequences to the health and safety of the public as a result of this event.
This letter contains no new or revised regulatory commitments.
E. Casulli
Attachment:
L E R 50-387 / 2024-001-00
Copy: NRC Region I Ms. J. England, NRC Senior Resident Inspector Ms. A. Klett, NRC Project Manager Mr. M. Shields, PA DEP/BRP NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB : NO. 3150-0104 EXPIRES : 04/30/2027 (04 2024) Estimated burden per response to co mply 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 ticensing process and fed back to industry. Send comments regarding burden
(¥~1 LICENSEE EVENT REPORT (LER) estimate to the FOIA, Library, and Information Collections Branch.Resource @nrc.gov. and the 0MB reviewer (T-6 A \\O M), U. S. Nuc lea-Regula10f'/
.,. ___.., (See Page 2 for required number of digits/characters for each block) Comm ission, Washington, DC 20555-0001. or by email to lnfocollectsat 0MB Office of lnfonmation and Regula\\QI'/ Affairs, (3150-0104), Atln: Desk Officer for \\he Nuclear Regula10f'/
(S ee NUR EG -1022, R.3 for instruction and guida nce for comple ting this form Commission, 725 17th Street NW, Washington, DC 20503. The NRC may not conduct or sponsor, and a person is h!!Q://www.nre.gov/read ing -[!JJ/doc-col lectio ns /o u_rgg 'a/staff l sr1 022/r 3/ ). not requir ed to respond to, a collection of information unless the document requesting or requiring the collection displays a currently va lid 0MB control number.
- 1. Facility Name 00 050 2. Docket Number 3. Page Susquehanna Steam Electric Station Unit 1 052 00387 1 OF 2
- 4. Title Main Steam Isolation Valve Leakage
- 5. Event Date 6. LER Number 7. Report Date 8. Other Facilities Invol ved
Month Day Year Yea r Sequential Revision Month Day Year Facility Name Dock et Number Number No. 050
03 28 2024 2024 - 001 - 00 05 23 2024 Facility Name 052 Docket Numb e r
- 9. Operating Mode 110. Power Level 5 0
11. This Report is Submitted Pursuant to the Requirements of 10 CFR § : (Check all that apply) 10 CFR Part 20 20.2203(a)(2)(vi) 10 CFR Part 50 50. 73(a)(2)(ii)(A) 50. 73(a)(2)(viii)(A) 73.1200(a) 20.2201(b) 20.2203(a)(3)(i) 50.36(c)(1 )(i)(A) 50. 73(a)(2)(ii)(B) 50. 73(a)(2)(viii)(B) 73.1200(b) 20.2201(d) 20.2203(a)(3)(ii) 50.36(c)(1 )(ii)(A) 50.73(a)(2)(iii) 50. 73(a)(2)(ix)(A) 73.1200(c) 20.2203(a)(1) 20.2203(a)(4) 50.36(c)(2) 50. 73(a)(2)(iv)(A) 50. 73(a)(2)(x) 73.1200(d) 20.2203(a)(2)(i) 10 CFR Part 21 50.46(a)(3)(ii) 50. 73(a)(2)(v)(A) 10 CFR Part 73 73. 1200(e) 20.2203(a)(2)(ii) 21.2(c) 50.69(g) 50.73(a)(2)(v)(B) 73.77(a)(1) 73.1200(f) 20.2203(a)(2)(iii) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C) 73. 77(a)(2)(i) 73.1200(g) 20.2203(a)(2)(iv) [Z] 50. 73(a)(2)(i)(B) 50.73(a)(2)(v)(D) 73. 77(a)(2)(ii) 73.1200(h) 20.2203(a)(2)(v) 50. 73(a)(2)(i)(C) 50. 73(a)(2)(vii)
OTHER (S pecify here, in abstra ct, or NR G 366A).
- 12. Licensee Contact for this LER
Licensee Contact Phone Number (Include area code)
Brad Yarzebinski, Nuclear Regulatory Affairs Engineer 570-542-2839
- 13. Complete One Line for each Component Failure Described in this Report
Cause System Component Manufacturer Reportable to IRIS Cause System Component Manufacturer Reportable to IRIS
- 14. Supplemental Report Expected Month Day Year
- 15. Expected Submission Date No Ye s (If ye s, complete 15. Expected Submission Date) 07 26 2024 [Z]
16. Abstract (Limit to 1326 spaces, i.e., ap proximately 13 single-spaced typewritten li nes)
On March 28, 2024, during Local Leak Rate Testing (LLRT) conducted during the Unit 1 refueling outage, as-found leakage through the inboard Main Steam Isolation Valve (HV141 F0228) was 57,166 standard cubic centimeters per minute (seem) which exceeded the Technical Specification (TS) Surveillance Requirement 3.6. 1.3.12 limit of 100 standard cubic feet per hour (scfh)
(47,194 seem) for individual valve leakage. HV141 F022B was repaired resulting in a total penetration LLRT value of 1,568 seem.
There is preliminary indication that the condition ex isted longer than allowed by TS 3.6. 1.3. The condition is being reported in accordance with 10 CFR 50. 73(a)(2)(i) (B) as a condition prohibited by TS.
A cause evaluation is in progress. A supplement will be issued to provide information regarding the cause of the condition and additional corrective actions.
There were no actual consequences to the health and safety of the public as a result of this event.
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB : NO. 3150-0104 EXPIRES: 04/30/2027 (04-02 -2024) Estimated burden per re sponse to comply with this mandatory collection re quest: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorpo rated in to the lice nsing process and fed back to industry. Send comments LICENSEE EVENT REPORT (LER) regarding burden estimate to th e FOIA, Library, and Information Collections Branch (T-6 A1 OM), U. S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email to CONTINUATION SHEET ln focollects.Resource@nrc.gov, and the DMB reviewer at DMB Office of Information and Regulatory Affairs, (3150-0104), Att n: Desk Officer for the Nuclea r Regulatory Commission, 725 17th Street NW, (See NUREG - 1022, R.3 for in str uction and guidance fo r completing thi s form Washington, DC 20503. The NRG may not conduct or sponsor, and a person is not required to http ://www nrc.gov/re ading-rm /d oc-coll ecti on s/nuregs / sta ff/ sr1 02 2/r31) re spond to. a collection of information unless the documen t requesting or requiring the co llection disp lays a cu rren tly valid 0MB control number.
- ~----------~*~ 1. FACILITY NAME 050 2. DOCKET NUMBER 3. LER NUMBER SEQUENTIAL REV I,,.. NUMBER NO.
Susquehanna Steam Electric Station, Unit 1 052 I 00387 001 I 2024 I-I 1-0
NARRATIVE CONDITIONS PRIOR TO EVENT Unit 1 - Mode 5, zero (0) percent Rated Thermal Power (RTP)
Unit 2 - Mode 1, approximately 100 percent RTP
EVENT DESCRIPTION On March 28, 2024, during Local Leak Rate Testing (LLRT) conducted during the Unit 1 refueling outage,
as-found leakage through the inboard Main Steam Isolation Valve (MSIV) (HV141F022B) [EIIS System/ Component Code: SB/ISV] was 57,166 standard cubic centimeters per minute (seem) which exceeded the Technical Specification Surveillance Requirement (TS SR) 3.6.1.3.12 limit of 100 standard cubic feet per hour (scfh) (47, 194 seem) fo r individual valve leakage. HV141 F022B was repaired resulting in an acceptable as-left penetration LLRT value of 1,568 seem.
Based on preliminary information, there is evidence that the condition existed during the last operating cycle for longer than allowed by TS 3.6.1.3. The condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
CAUSE OF EVENT The cause of the event is under investigation and will be provided in a supplement to this LER.
ANALYSIS/SAFETY SIGNIFICANCE The redundant MSIV (HV141F028B) in the "B" steam line had an as-found individual leakage value of 4,029 seem, which is below the TS SR 3.6.1.3.12 limit of 100 scfh (47, 194 seem). The redundant valve, bounded by engineering evaluation,
provides assurance that the dose consequences remain within the regulatory limit of 5 rem Total Effective Dose Equivalent (TEDE) for the control room and 25 rem TEDE for the low population zone and exclusion area boundary. As such, there was no loss of safety function for the redundant valve or the main steam penetrat ion. Accordingly, this event will not be counted as a safety system functional failure in the Reactor Oversight Process Performance Indicators. There were no actual consequences to the health and safety of the public as a result of this event.
CORRECTIVE ACTIONS HV141 F022B was repaired resulting in a leak rate within the TS SR 3.6. 1.3.12 limit. Any additional corrective actions w ill be provided in a supplement to this LER.
PREVIOUS OCCURRENCES Previous occurrences, if any, will be provided in a supplement to this LER.
NRC FORM 366A (04-02-2024) Page 2 of 2