On December 5, 2016 Three Mile Island Unit 1 was in a cold shutdown condition for a planned maintenance outage to replace the Reactor Coolant Pump 1A seal package. The reactor coolant system ( RCS) was being filled and vented prior to pressurizing the RCS. Plant limits and precautions were not adhered to with respect to protecting the RCS from Low Temperature Overpressurization ( LTOP) conditions by having RCS inventory too high with the Make-up system pump (MUP) breakers racked-in. This plant condition violated TMI-1 Technical Specification 3.1.12.1 and existed for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> until recognized. Once recognized, RCS inventory (Pressurizer level) was reduced within an hour per the TS action statement. The cause was attributed to operators not reviewing, understanding and complying with procedure limits and precautions-for the plant condition. Corrective actions include coaching involved individuals on procedure use and adherence, and, procedure revisions to include actionable steps to improve LTOP Technical Specification compliance. This event is reported as a condition prohibited by Technical Specifications pursuant to 10 CFR 50.73(a)(2)(i)(B). This event had no effect on public health and safety. |
|
---|
Category:Letter
MONTHYEARML24038A0222024-02-0505 February 2024 Achp Letter on Section 106 Programmatic Agreement Participation IR 05000289/20230062024-01-29029 January 2024 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report No. 05000289/2023006 ML23342A1242024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23325A1092024-01-0505 January 2024 Review of the Management Plan for Three Mile Island Station, Unit No. 2, Debris Material ML23354A2062023-12-20020 December 2023 (TMI-2), Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 IR 05000320/20230032023-11-28028 November 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2, NRC Inspection Report No. 05000320/2023003 ML23243A9082023-08-29029 August 2023 Shpo Letter to TMI-2 Regarding Section 106 Activities IR 05000320/20230022023-08-17017 August 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report 05000320/2023002 IR 05000289/20230052023-08-14014 August 2023 Constellation Energy Generation, LLC, Three Mile Island Nuclear Station, Unit 1 - NRC Inspection Report 05000289/2023005 ML23216A1732023-08-14014 August 2023 Consultation Letter to Christine Turner for TMI-2 ML23216A1742023-08-14014 August 2023 Consultation Letter to David Morrison for TMI-2 ML23216A1752023-08-14014 August 2023 Consultation Letter to Joanna Cain for TMI-2 ML23216A1772023-08-14014 August 2023 Consultation Letter to Rebecca Countess for TMI-2 ML23216A1782023-08-14014 August 2023 Consultation Letter to Steve Letavic for TMI-2 ML23221A1402023-08-0808 August 2023 (TMI-2), Response to Requests for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 ML23200A1882023-07-31031 July 2023 TMI-2 Correction Letter Amendment 67 ML23209A7632023-07-28028 July 2023 Letter from PA Shpo to TMI-2 Solutions on Cultural and Historic Impacts of Decommissioning ML23192A8272023-07-10010 July 2023 TMI-2 Solutions, LLC - Response to Shpo Request for Additional Information for Er Project 2021PR03278.006, TMI-2 Decommissioning Project ML23167A4642023-07-0505 July 2023 Letter - TMI-2- Exemption 10 CFR Part 20 Append G Issuance ML23167A0312023-06-28028 June 2023 Acceptance Review and Schedule for the Request for Exemption from a Requirement from 10 CFR 20, Appendix G, Section Iii.E, EPID L-2023-LLE-0016 ML23171B0222023-06-19019 June 2023 (TMI-2) - Notification Pursuant to 10 CFR 72.140(d) Regarding Application of Previously Approved TMI-2 Quality Assurance Program to Independent Spent Fuel Storage Installation Activities ML23138A0662023-05-17017 May 2023 TMI-2 NHPA Section 106 Shpo Letter to NRC 5-17-23 ML23137A2822023-05-17017 May 2023 (TMI-2), Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23026A3132023-05-0202 May 2023 Issuance of Exemption from 10 CFR 70.24 (EPID-L-2023-LLE-0003) ML23121A2492023-05-0101 May 2023 License Amendment Request, Historic and Cultural Resources Review, Response to Request for Additional Information ML23122A1842023-05-0101 May 2023 Shpo_Er_Summary_Letter ML23117A0012023-04-26026 April 2023 Commitment Revision Summary Report ML23027A0832023-04-24024 April 2023 Environmental Assessment/Finding of No Significant Impact - Request for Exemption from 10 CFR 70.24 ML23108A0822023-04-18018 April 2023 Annual Radiological Environmental Operating Report ML23108A0802023-04-18018 April 2023 Annual Radiological Effluent Release Report IR 05000320/20230012023-04-12012 April 2023 TMI-2 Solutions, LLC, Three Mile Island Nuclear Station, Unit 2 - NRC Inspection Report No. 05000320/2023001 ML23108A2002023-04-10010 April 2023 CFR 20.2206(b) Personnel Radiation Exposure Report for 2022 ML23102A0382023-04-10010 April 2023 Occupational Radiation Exposure Annual Report ML23093A0602023-04-0606 April 2023 Letter to Steve Letavic, Manager, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2402023-04-0606 April 2023 Letter to Darren Bonaparte, Thpo, St. Regis Mohawk Tribe, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23086C0522023-04-0606 April 2023 Letter to David Morrison, Exec Dir, Historic Harrisburg Assoc Re, Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23086C0652023-04-0606 April 2023 Ltr Larry Heady, Thpo, De. Tribe of Indian; Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI Nuclear Station, Unit 2 ML23094A2352023-04-0606 April 2023 Letter to Bryan Printup, Thpo, Tuscarora Nation, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23086A0132023-04-0606 April 2023 Letter to Emma Dehi, PA Shpo; Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI-2 ML23094A2562023-04-0606 April 2023 Letter to Tonya Tipton, Thpo, Shawnee Tribe, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 ML23093A0582023-04-0606 April 2023 Letter to Christine Turner, Executive Director, Re., Ongoing Activities Related to the Proposed License Amendment Request for Three Mile Island Nuclear Station, Unit 2 ML23094A2392023-04-0606 April 2023 Letter to Courtney Gerzetich, Thpo, Onedia Nation of Wisconsin, Re., Initiation of Consultation Under Section 106 of the NHPA for the Proposed License Amendment Request for TMI 2 2024-02-05
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000289/LER-2017-0042018-02-0505 February 2018 Items Nonconforming to Design for Tornado Missile Protection, LER 17-004-00 for Three Mile Island, Unit 1, Regarding Items Nonconforming to Design for Tornado Missile Protection 05000289/LER-2017-0032017-11-0606 November 2017 Primary Containment Declared Inoperable Due to Both Airlock Doors Open Simultaneously, LER 17-003-00 for Three Mile Island, Unit 1 Regarding Primary Containment Declared Inoperable Due to Both Airlock Doors Open Simultaneously 05000289/LER-2017-0022017-02-0606 February 2017 1 OF 5, LER 17-002-00 for Three Mile Island, Unit 1 Regarding Leak at High Pressure Connection on Reactor Coolant Pump "A" Thermal Barrier 05000289/LER-2017-0012017-02-0303 February 2017 Low Temperature Over-Pressurization (LTOP) Technical Specification Requirements Were Not Met, LER 17-001-00 for Three Mile Island Unit 1 Regarding Low Temperature Over-Pressurization (LTOP) Technical Specification Requirements Were Not Met TMI-15-062, Special Report - Radioactive Gaseous Process and Effluent Monitoring Instrumentation2015-05-0808 May 2015 Special Report - Radioactive Gaseous Process and Effluent Monitoring Instrumentation ML1012303422009-11-24024 November 2009 Decision Documentation for Reactive Inspection (Deterministic & Risk Criteria Analyzed) (Mc 0309 Enclosure 1) ML1007805012009-11-23023 November 2009 E-mail from Eric Thomas, NRR to Richard Conatser, NRR on 11/23/09 NRC Operations Center Event Report Page ML1007802702009-11-22022 November 2009 Draft Event Notice on Offsite Notification TMI 2018-02-05
[Table view] |
comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
05000-289
3. LER NUMBER
2017 001 - 00
A. EVENT DESCRIPTION
Plant Conditions before the event:
Babcock & Wilcox - Pressurized Water Reactor - 2568 MWth Core Power Date/Time: December 5, 2016 / 16:00 hours Power Level: 0% Mode: Cold Shutdown Three Mile Island Unit 1 (TMI-1) was in a cold shutdown condition with the Reactor Coolant System (RCS) depressurized and drained in support of a Reactor Coolant Pump seal package replacement in December 2016. On 12/05/2016 at 04:36, maintenance activities completed and Operations personnel began to fill the RCS to allow the plant to be re-pressurized.
The final fill of the RCS was performed using the RCS Water Level Control procedure (1103-11), that filled the pressurizer to a maximum level of 390 inches. With the pressurizer at 390 inches, the Control Room Supervisor directed the continuation of another operating procedure to shift the Makeup & Purification (MU) system from Shutdown Mode to Low Temperature Overpressure (LTOP) Mode (procedure OP-TM- 211-101). Procedure OP-TM-211-101 provides the guidance and steps to rack-in the breakers for the makeup pumps.
TMI-1 Technical Specification 3.1.12.1 LTOP Protection requires:
3.1.12.1 LTOP Protection If the reactor vessel head is installed and indicated RCS temperature is 5 313°F, High Pressure Injection Pump breakers shall not be racked in unless:
a. MU-V16A/B/C/D are closed with their breakers open, and MU-V217 is closed, and b. Pressurizer level is maintained 5 100 inches. If pressurizer level is > 100 inches, restore level to 5 100 inches within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
[For purposes of clarity in this report: MU-V-16A/B/C/D are throttle valves for high pressure injection to RCS; MU-V-217 is the high capacity makeup valve to RCS] The plant condition with the makeup pump breakers racked in and pressurizer level greater than 100 inches went unrecognized as a Technical Specification (TS) violation for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> from -16:00 to approximately 19:00. Over this 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period, an operations crew turnover occurred. An oncoming crew member questioned the appropriateness of the makeup pump breakers being racked in with pressurizer level greater than 100 inches. The crew rationalized that a pressurizer level of 390 inches with the RCS depressurized and vented would be equivalent to a pressurizer level of 100 inches once the RCS was pressurized. The pressurization of the RCS commenced per procedure 1103-11.
When the RCS was pressurized to -.35-45psig, pressurizer level stabilized at a level greater than 100 inches. The crew recognized this condition was not allowed by Technical Specification 3.1.12.1 and a one comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
05000-289
3. LER NUMBER
2017 - 001 - REV - 00
- c . , hour clock to exit the condition was entered at 20:27 and immediate action to lower pressurizer level was initiated. At 21:25, pressurizer level was stabilized at less than 100 inches and the Technical Specification action statement was exited.
B. CAUSE OF EVENT
The apparent cause was determined to be inadequate procedure use and adherence fundamentals associated with reviewing, understanding and complying with procedure limitations and precautions. The procedures in use during the violated condition contained guidance to avoid exceeding the LTOP TS requirements.
C. ANALYSIS / SAFETY SIGNIFICANCE
This event had no effect on the health and safety of the public. There were no actual safety consequences for the condition because the Pilot Operated Relief Valve (PORV) was available during the entire time at which the violated TS condition existed. The PORV low pressure set-point for LTOP protection was enabled, operable and available and would have mitigated a potential RCS overpressurization event.
D. CORRECTIVE ACTIONS
Immediate actions were taken to address gaps in understanding.
- The involved individuals were coached for gaps in accountability with procedure use and adherence fundamentals associated with reviewing, understanding and complying with procedure limitations and precautions. -
- The applicable procedures will be revised with actionable steps to improve LTOP TS compliance.
- Complete a performance analysis to determine training needs to improve understanding of the LTOP Technical Specification for various plant conditions.
E. PREVIOUS OCCURENCES
Previous Events Previous Event Review None * Energy Industry Identification System (EllS), System Identification (SI) and Component Function Identification (CFI) Codes are included in brackets, [SI/CFI] where applicable, as required by 10 CFR 50.73 (b)(2)(ii)(-F).