|
|
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear L.L. C.DEC 1 42009 TS 3.3.3.7 TS 6.9.4 LR-N09-0267 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Salem Generating Station Unit No. 2 Facility Operating License DPR-75 NRC Docket No. 50-311 | | {{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear L.L. C. |
| | TS 3.3.3.7 DEC 1 42009 TS 6.9.4 LR-N09-0267 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Salem Generating Station Unit No. 2 Facility Operating License DPR-75 NRC Docket No. 50-311 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Special Report 311/2009-001, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater Than 30 Days The attached Special Report is being submitted pursuant to the requirements of Salem Unit 2 Technical Specification (TS) 3.3.3.7, which requires that both channels of Reactor Vessel Level Instrumentation System (RVLIS) be operable in Modes 1, 2 and 3. With one channel inoperable, the action statement requires that channel be restored to operable status within 30 days or submit a Special Report in accordance with administrative TS 6.9.4. There are no commitments contained in this letter.Should there be any questions regarding this matter please contact Brian Thomas at 856-339-2022.Robert Braun Site Vice President | | Special Report 311/2009-001, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater Than 30 Days The attached Special Report is being submitted pursuant to the requirements of Salem Unit 2 Technical Specification (TS) 3.3.3.7, which requires that both channels of Reactor Vessel Level Instrumentation System (RVLIS) be operable in Modes 1, 2 and 3. With one channel inoperable, the action statement requires that channel be restored to operable status within 30 days or submit a Special Report in accordance with administrative TS 6.9.4. There are no commitments contained in this letter. |
| -Salem Attachment Piiz-Document Control Desk Page 2 LR-N09-0267 DEC 1 42009 C Mr. S. Collins, Administrator, Region I, NRC Mr. D. Schroeder, USNRC Senior Resident Inspector, Salem (x24)Mr. P. Mulligan, Manager IV, NJBNE L. Marabella, Corporate Commitment Tracking Coordinator H. Berrick, Salem Commitment Tracking Coordinator Attachment DEC 1 4 2009 LR-N09-0267 Special Report 311/09-001-00 Description Of Occurrence The Salem Unit 2 Technical Specification (TS) 3.3.3.7 requires both channels of Reactor Vessel Level Instrumentation System (RVLIS) to be operable in Modes 1, 2 and 3. With one channel inoperable, TS 3.3.3.7 Action 8 requires the inoperable channel to be returned to operable status within 30 days or submit a Special Report in accordance with administrative TS 6.9.4.On November 5, 2009, while in Mode 4 and performing plant heat up and pressurization during the seventeenth refueling outage (2R17) control room operators noted that the 'B' train RVLIS remote display showed an error status. At that time the dynamic head reading for the 'B' train did not align with the 'A' train. Troubleshooting was conducted in an effort to restore the 'B'RVLIS train to operable status prior to entry into Mode 3. As a result of troubleshooting efforts and consultation with the vendor, the error is attributed to either loss of water from the sealed capillary line causing the bellows internal valve to go closed or the bellows internal plunger may not be allowing free vertical motion as a result of the capillary line being found bent. The capillary lines coming out of the bottom of the bellows were found bent and were straightened; however, this did not fix the indication error. Based on the nature of the repairs, the unit would need to be placed in mode 5 to make the repairs followed by a fill and vent of the RVLIS system which would take approximately 5 days and will require vendor support. Since the 'A' RVLIS channel was responding properly and vendor support to perform the repairs was not available, a management decision was made to proceed with Unit 2 mode ascension and operations with the 'B' RVLIS train inoperable. | | Should there be any questions regarding this matter please contact Brian Thomas at 856-339-2022. |
| On November 9, 2009, Salem Unit 2 entered Mode 3.Preplanned Alternate Monitoring Method Procedure S2.OP-SO.RVL-0001 (Q), "Reactor Vessel Level Instrumentation System," in Step 3.9, states that when one or both RVLIS channels are inoperable, the preplanned alternate method of monitoring for inadequate core cooling is that the required channels in TS Table 3.3-11 for both the Reactor Coolant System (RCS) Sub-cooling Margin Monitor and the Core Exit Thermocouples (CET) are operable. | | Robert Braun Site Vice President - Salem Attachment Piiz- |
| These channels are operable.Cause of the Inoperability The cause of the inoperability appears to be a result of the bent capillary tube coming out of the bottom of the RVLIS Train 'B' bellows.Plans to Return to Operable Status The 'B' RVLIS train will be returned to operable status in the next refueling outage (2R1 8)scheduled for the Spring of 2011.}} | | |
| | Document Control Desk DEC 1 42009 Page 2 LR-N09-0267 C Mr. S. Collins, Administrator, Region I, NRC Mr. D. Schroeder, USNRC Senior Resident Inspector, Salem (x24) |
| | Mr. P. Mulligan, Manager IV, NJBNE L. Marabella, Corporate Commitment Tracking Coordinator H. Berrick, Salem Commitment Tracking Coordinator |
| | |
| | Attachment DEC 1 4 2009 LR-N09-0267 Special Report 311/09-001-00 Description Of Occurrence The Salem Unit 2 Technical Specification (TS) 3.3.3.7 requires both channels of Reactor Vessel Level Instrumentation System (RVLIS) to be operable in Modes 1, 2 and 3. With one channel inoperable, TS 3.3.3.7 Action 8 requires the inoperable channel to be returned to operable status within 30 days or submit a Special Report in accordance with administrative TS 6.9.4. |
| | On November 5, 2009, while in Mode 4 and performing plant heat up and pressurization during the seventeenth refueling outage (2R17) control room operators noted that the 'B' train RVLIS remote display showed an error status. At that time the dynamic head reading for the 'B' train did not align with the 'A' train. Troubleshooting was conducted in an effort to restore the 'B' RVLIS train to operable status prior to entry into Mode 3. As a result of troubleshooting efforts and consultation with the vendor, the error is attributed to either loss of water from the sealed capillary line causing the bellows internal valve to go closed or the bellows internal plunger may not be allowing free vertical motion as a result of the capillary line being found bent. The capillary lines coming out of the bottom of the bellows were found bent and were straightened; however, this did not fix the indication error. Based on the nature of the repairs, the unit would need to be placed in mode 5 to make the repairs followed by a fill and vent of the RVLIS system which would take approximately 5 days and will require vendor support. Since the 'A' RVLIS channel was responding properly and vendor support to perform the repairs was not available, a management decision was made to proceed with Unit 2 mode ascension and operations with the 'B' RVLIS train inoperable. On November 9, 2009, Salem Unit 2 entered Mode 3. |
| | Preplanned Alternate Monitoring Method Procedure S2.OP-SO.RVL-0001 (Q), "Reactor Vessel Level Instrumentation System," in Step 3.9, states that when one or both RVLIS channels are inoperable, the preplanned alternate method of monitoring for inadequate core cooling is that the required channels in TS Table 3.3-11 for both the Reactor Coolant System (RCS) Sub-cooling Margin Monitor and the Core Exit Thermocouples (CET) are operable. These channels are operable. |
| | Cause of the Inoperability The cause of the inoperability appears to be a result of the bent capillary tube coming out of the bottom of the RVLIS Train 'B' bellows. |
| | Plans to Return to Operable Status The 'B' RVLIS train will be returned to operable status in the next refueling outage (2R1 8) scheduled for the Spring of 2011.}} |
Similar Documents at Salem |
---|
Category:Letter type:LR
MONTHYEARLR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20222022-12-20020 December 2022 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022 LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG2022-12-0909 December 2022 Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)2022-11-17017 November 2022 Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095) LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2022-11-10010 November 2022 Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2022-09-27027 September 2022 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022 License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM) LR-N22-0063, Spent Fuel Cask Registration2022-08-10010 August 2022 Spent Fuel Cask Registration LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature LR-N22-0062, Spent Fuel Cask Registration2022-07-21021 July 2022 Spent Fuel Cask Registration LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022 Core Operating Limits Report - Cycle 29 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022 Request for Relief from ASME Code Defect Removal for Service Water Buried Piping LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0022, Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds2022-03-21021 March 2022 Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0013, In-Service Inspection Activities - 90-Day Report2022-02-10010 February 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0061, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2021-12-0909 December 2021 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2021-11-10010 November 2021 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations 2023-09-08
[Table view] Category:Licensee 30-Day Written Event Report
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear L.L. C.
TS 3.3.3.7 DEC 1 42009 TS 6.9.4 LR-N09-0267 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Salem Generating Station Unit No. 2 Facility Operating License DPR-75 NRC Docket No. 50-311
Subject:
Special Report 311/2009-001, One Channel of Reactor Vessel Level Instrumentation System (RVLIS) Inoperable Greater Than 30 Days The attached Special Report is being submitted pursuant to the requirements of Salem Unit 2 Technical Specification (TS) 3.3.3.7, which requires that both channels of Reactor Vessel Level Instrumentation System (RVLIS) be operable in Modes 1, 2 and 3. With one channel inoperable, the action statement requires that channel be restored to operable status within 30 days or submit a Special Report in accordance with administrative TS 6.9.4. There are no commitments contained in this letter.
Should there be any questions regarding this matter please contact Brian Thomas at 856-339-2022.
Robert Braun Site Vice President - Salem Attachment Piiz-
Document Control Desk DEC 1 42009 Page 2 LR-N09-0267 C Mr. S. Collins, Administrator, Region I, NRC Mr. D. Schroeder, USNRC Senior Resident Inspector, Salem (x24)
Mr. P. Mulligan, Manager IV, NJBNE L. Marabella, Corporate Commitment Tracking Coordinator H. Berrick, Salem Commitment Tracking Coordinator
Attachment DEC 1 4 2009 LR-N09-0267 Special Report 311/09-001-00 Description Of Occurrence The Salem Unit 2 Technical Specification (TS) 3.3.3.7 requires both channels of Reactor Vessel Level Instrumentation System (RVLIS) to be operable in Modes 1, 2 and 3. With one channel inoperable, TS 3.3.3.7 Action 8 requires the inoperable channel to be returned to operable status within 30 days or submit a Special Report in accordance with administrative TS 6.9.4.
On November 5, 2009, while in Mode 4 and performing plant heat up and pressurization during the seventeenth refueling outage (2R17) control room operators noted that the 'B' train RVLIS remote display showed an error status. At that time the dynamic head reading for the 'B' train did not align with the 'A' train. Troubleshooting was conducted in an effort to restore the 'B' RVLIS train to operable status prior to entry into Mode 3. As a result of troubleshooting efforts and consultation with the vendor, the error is attributed to either loss of water from the sealed capillary line causing the bellows internal valve to go closed or the bellows internal plunger may not be allowing free vertical motion as a result of the capillary line being found bent. The capillary lines coming out of the bottom of the bellows were found bent and were straightened; however, this did not fix the indication error. Based on the nature of the repairs, the unit would need to be placed in mode 5 to make the repairs followed by a fill and vent of the RVLIS system which would take approximately 5 days and will require vendor support. Since the 'A' RVLIS channel was responding properly and vendor support to perform the repairs was not available, a management decision was made to proceed with Unit 2 mode ascension and operations with the 'B' RVLIS train inoperable. On November 9, 2009, Salem Unit 2 entered Mode 3.
Preplanned Alternate Monitoring Method Procedure S2.OP-SO.RVL-0001 (Q), "Reactor Vessel Level Instrumentation System," in Step 3.9, states that when one or both RVLIS channels are inoperable, the preplanned alternate method of monitoring for inadequate core cooling is that the required channels in TS Table 3.3-11 for both the Reactor Coolant System (RCS) Sub-cooling Margin Monitor and the Core Exit Thermocouples (CET) are operable. These channels are operable.
Cause of the Inoperability The cause of the inoperability appears to be a result of the bent capillary tube coming out of the bottom of the RVLIS Train 'B' bellows.
Plans to Return to Operable Status The 'B' RVLIS train will be returned to operable status in the next refueling outage (2R1 8) scheduled for the Spring of 2011.