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Category:Emergency Preparedness-Emergency Plan
MONTHYEARLR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N20-0065, Emergency Plan Document Revisions Implemented September 9, 20202020-10-0505 October 2020 Emergency Plan Document Revisions Implemented September 9, 2020 LR-N19-0104, Emergency Plan Document Revision Implemented October 30, 20192019-11-15015 November 2019 Emergency Plan Document Revision Implemented October 30, 2019 LR-N19-0073, Emergency Plan Document Revision Implemented June 26, 20192019-07-23023 July 2019 Emergency Plan Document Revision Implemented June 26, 2019 LR-N19-0065, License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements2019-07-0808 July 2019 License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements LR-N18-0074, Enclosure 2 to LR-N18-0074, Emergency Plan Document Revisions Implemented June 25, 20182018-07-18018 July 2018 Enclosure 2 to LR-N18-0074, Emergency Plan Document Revisions Implemented June 25, 2018 LR-N18-0064, Emergency Plan Document Revision Implemented May 14, 20182018-06-12012 June 2018 Emergency Plan Document Revision Implemented May 14, 2018 LR-N14-0141, Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid.2014-06-16016 June 2014 Response to March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid. LR-N11-0061, Emergency Plan, Rev. 20, Section 17, Emergency Plan Administration2011-01-26026 January 2011 Emergency Plan, Rev. 20, Section 17, Emergency Plan Administration ML1105907832011-01-26026 January 2011 and Hope Creek, Emergency Plan, Rev. 16, Section 10, Accident Assessment ML1105907772011-01-26026 January 2011 and Hope Creek, Emergency Plan, Rev. 21, Section 9, Emergency Facilities and Equipment ML1105907712011-01-26026 January 2011 and Hope Creek, Emergency Plan, Rev. 15, Section 6, Notification Methods - Response Organizations ML1105907692011-01-26026 January 2011 and Hope Creek, Emergency Plan, Rev. 19, Section 2, Assignment of Responsibility ML1105907612011-01-26026 January 2011 and Hope Creek, Emergency Plan, Rev. 14, Section 1 LR-N11-0061, Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 16, Section 10, Accident Assessment2011-01-26026 January 2011 Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 16, Section 10, Accident Assessment LR-N11-0061, Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 21, Section 9, Emergency Facilities and Equipment2011-01-26026 January 2011 Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 21, Section 9, Emergency Facilities and Equipment LR-N11-0061, Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 15, Section 6, Notification Methods - Response Organizations2011-01-26026 January 2011 Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 15, Section 6, Notification Methods - Response Organizations LR-N11-0061, Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 19, Section 2, Assignment of Responsibility2011-01-26026 January 2011 Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 19, Section 2, Assignment of Responsibility LR-N11-0061, Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 14, Section 12011-01-26026 January 2011 Salem, Units 1 and 2, and Hope Creek, Emergency Plan, Rev. 14, Section 1 ML1100503752010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) ML1100504022010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) LR-N10-0355, EP Section 7, Communications.2010-10-14014 October 2010 EP Section 7, Communications. ML1100603722010-10-14014 October 2010 EP Section 7, Communications. LR-N10-0355, Hope Creek and Salem, Section 7 Emergency Communications2010-10-14014 October 2010 Hope Creek and Salem, Section 7 Emergency Communications ML1100504162010-10-14014 October 2010 Hope Creek and Salem, Section 7 Emergency Communications LR-N10-0355, Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance2010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance ML1100504152010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)2010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) LR-N10-0355, Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)2010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) ML1100503992010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix2010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix ML1100503982010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix LR-N10-0355, Salem and Hope Creek - Submittal of Emergency Action Level Changes2010-10-14014 October 2010 Salem and Hope Creek - Submittal of Emergency Action Level Changes ML1100503762010-10-14014 October 2010 Salem and Hope Creek - Submittal of Emergency Action Level Changes LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)2010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) LR-N10-0355, Hope Creek, HC.OP-AR.ZZ-0016(Q), Rev. 14, Overhead Annunciator Window Box E32010-09-17017 September 2010 Hope Creek, HC.OP-AR.ZZ-0016(Q), Rev. 14, Overhead Annunciator Window Box E3 ML1100601012010-09-17017 September 2010 Hope Creek, HC.OP-AR.ZZ-0016(Q), Rev. 14, Overhead Annunciator Window Box E3 LR-N10-0355, Hope Creek, HC.OP-AR.ZZ-0010(Q), Rev. 14, Overhead Annunciator Window Box C52010-09-12012 September 2010 Hope Creek, HC.OP-AR.ZZ-0010(Q), Rev. 14, Overhead Annunciator Window Box C5 ML1100505932010-09-12012 September 2010 Hope Creek, HC.OP-AR.ZZ-0010(Q), Rev. 14, Overhead Annunciator Window Box C5 LR-N10-0355, Hope Creek, HC.OP-AR.ZZ-0024(Q), Rev. 7, Crids Computer Points Book 5 D3624 Thru D42882010-08-24024 August 2010 Hope Creek, HC.OP-AR.ZZ-0024(Q), Rev. 7, Crids Computer Points Book 5 D3624 Thru D4288 ML1100601032010-08-24024 August 2010 Hope Creek, HC.OP-AR.ZZ-0024(Q), Rev. 7, Crids Computer Points Book 5 D3624 Thru D4288 LR-N10-0355, Hope Creek, HC.OP-AR.ZZ-0014(Q), Rev. 29, Overhead Annunciator Window Box D32010-08-24024 August 2010 Hope Creek, HC.OP-AR.ZZ-0014(Q), Rev. 29, Overhead Annunciator Window Box D3 ML1100505972010-08-24024 August 2010 Hope Creek, HC.OP-AR.ZZ-0014(Q), Rev. 29, Overhead Annunciator Window Box D3 LR-N10-0355, Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction2010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505182010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML11215A1812010-07-30030 July 2010 Attachment 5, Salem Generating Stations, EAL Technical Bases Document, EP-SC-111-201 LR-N10-0355, Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment2010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment 2023-07-10
[Table view] Category:Technical Specification
MONTHYEARLR-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-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes ML22270A3172022-09-27027 September 2022 Submittal of Technical Specification Bases Changes, Amendment No. 201 LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 2152022-09-27027 September 2022 Submittal of Technical Specification Bases Changes, Amendment No. 215 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-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0048, One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators2021-06-18018 June 2021 One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators LR-N21-0045, Submittal of Changes to Technical Specifications Bases2021-06-16016 June 2021 Submittal of Changes to Technical Specifications Bases LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N21-0006, Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions2021-02-16016 February 2021 Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report2020-12-0606 December 2020 License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report LR-N20-0060, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-29029 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements LR-N20-0003, License Amendment Request to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec2020-09-17017 September 2020 License Amendment Request to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML20142A5412020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 16, Technical Specifications LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2020-05-15015 May 2020 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N20-0015, License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling2020-05-0707 May 2020 License Amendment Request to Revise Technical Specification Actions for Suppression Pool Cooling ML19058A2212019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0127, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement.2019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0013, License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B2018-03-28028 March 2018 License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B LR-N18-0011, Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR2018-01-22022 January 2018 Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0124, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-09-21021 September 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML17157B2652017-05-0909 May 2017 Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and PSEG Nuclear LLC Quality Assurance Topical Repor LR-N17-0088, Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Re2017-05-0909 May 2017 Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Repor ML17046A2292017-01-30030 January 2017 Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85 LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 852017-01-30030 January 2017 Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85 LR-N16-0003, License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications2016-11-17017 November 2016 License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications LR-N16-0114, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using the Consolidated Line .2016-08-30030 August 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using the Consolidated Line . LR-N16-0066, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling2016-06-17017 June 2016 License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling LR-N15-0178, Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade2015-09-21021 September 2015 Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade ML15265A2242015-09-21021 September 2015 License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N15-0187, Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications2015-08-31031 August 2015 Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications LR-N15-0021, License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems2015-04-0303 April 2015 License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation2015-03-27027 March 2015 License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation ML14210A4842014-07-28028 July 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Using the Consolidated Line Item Improvement Process LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual2013-09-0505 September 2013 License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan LR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process LR-N11-0056, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2011-02-23023 February 2011 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML1100503752010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)2010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) ML1100503982010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix2010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix ML1100503992010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) LR-N10-0355, Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)2010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)2010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) ML1100504152010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance LR-N10-0355, Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance2010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance ML1100504022010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) ML1025802412010-09-0808 September 2010 License Amendment Request S10-01 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program 2023-06-23
[Table view] Category:Bases Change
MONTHYEARLR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes ML22270A3172022-09-27027 September 2022 Submittal of Technical Specification Bases Changes, Amendment No. 201 LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 2152022-09-27027 September 2022 Submittal of Technical Specification Bases Changes, Amendment No. 215 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-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0045, Submittal of Changes to Technical Specifications Bases2021-06-16016 June 2021 Submittal of Changes to Technical Specifications Bases LR-N20-0060, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-29029 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements LR-N20-0003, License Amendment Request to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec2020-09-17017 September 2020 License Amendment Request to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML20142A5412020-05-21021 May 2020 4 to Updated Final Safety Analysis Report, Section 16, Technical Specifications LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2020-05-15015 May 2020 Submittal of Hope Creek Generating Station Technical Specification Bases Changes ML19058A2212019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0127, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement.2019-02-27027 February 2019 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement. LR-N18-0013, License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B2018-03-28028 March 2018 License Amendment Request (LAR) to Amend the Hope Creek Technical Specifications (TS) to Revise Action for Inoperable Emergency Diesel Generator (EDG) a or B LR-N18-0011, Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR2018-01-22022 January 2018 Supplement to License Amendment Request- Safety Limit Minimum Critical Power Ratio Change. Includes GNF-004N5379-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary ML17157B2652017-05-0909 May 2017 Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and PSEG Nuclear LLC Quality Assurance Topical Repor LR-N17-0088, Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Re2017-05-0909 May 2017 Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Repor ML17046A2292017-01-30030 January 2017 Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85 LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 852017-01-30030 January 2017 Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85 LR-N16-0003, License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications2016-11-17017 November 2016 License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications LR-N16-0114, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using the Consolidated Line .2016-08-30030 August 2016 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing Using the Consolidated Line . LR-N16-0066, License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling2016-06-17017 June 2016 License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML15265A2242015-09-21021 September 2015 License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N15-0178, Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade2015-09-21021 September 2015 Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade LR-N15-0187, Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications2015-08-31031 August 2015 Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications LR-N15-0021, License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems2015-04-0303 April 2015 License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems ML14210A4842014-07-28028 July 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Using the Consolidated Line Item Improvement Process LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual2013-09-0505 September 2013 License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual LR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process LR-N11-0056, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2011-02-23023 February 2011 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML1100503992010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix2010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix ML1100503982010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)2010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) LR-N10-0355, Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)2010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) ML1100504022010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) ML1100503752010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)2010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) ML1100504152010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance LR-N10-0355, Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance2010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance ML1025802422010-09-0808 September 2010 License Amendment Request H10-01:, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML1025802412010-09-0808 September 2010 License Amendment Request S10-01 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program LR-N10-0355, Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction2010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505182010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction ML1100505002010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment LR-N10-0355, Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment2010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment ML1100505162010-06-24024 June 2010 Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling2010-06-24024 June 2010 Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling ML1100504772010-05-0303 May 2010 Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment LR-N10-0355, Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment2010-05-0303 May 2010 Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment 2023-03-29
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TURBINE GENERATOR TRIP EHC UNIT PANEL 10C363 TCV FAST CLOSURE MAIN STOP VALVE CLOSURE TURBINE GENERATOR VIB HI GEN STATOR CLG WATER SYS TROUBLE GEN COOLING PNL 10C120 POWER FLR GENERATOR H 2/SEAL OIL SYS TROUBLE GENERATOR TEMPERATURE HI
One or more Turbine trip signals generated. Generator output goes to zero. Rising vibration trend on any Main Turbine/Generator bearing (CRIDS). Generator Stator Water return temperature > 174.2°F (79°C) Stator Water inlet pressure 46.5 psig @ V9968 ( 64 psig at PI3607 on 10C120) Stator Water Inlet Flow 690 gpm. Decreasing hydrogen pressure/purity. Stator water (generator in let) temperature > 118 °F
Date/Time:
___ I.A Recirc. Pump speed to MINIMUM. ___ I.B the Mode Switch in SHUTDOWN.I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in
SHUTDOWN. II. Bearing 1-10 Vibration 11 mils @ 1800 RPM
- Bearing 11-12 Vibration 7 mils @ 1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator
Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.* Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
- Valves: 1-AB-HV-1026, M/S LEAD DRAIN S/U VLV. 1-AC-HV-1041/1042/1043, XAROUND STM LN DRN's. 1-AC-HV-1013A(B,C), MSV BEFORE SEAT DRN's. 1-AC-HV-1015, CV BEFORE SEAT DRAIN. 1-AC-HV-1017A(B), CV #1 & #2 STM LEAD DRN. 1-AC-HV-1018A(B), CV #3 & #4 STM LEAD DRN. 1-FW-HV-3719, RFP TURB MN STM DRN.
___ A.IF Reactor Power is 24% THEN the Mode Switch in Shutdown.
Bearing 1-10 Vibration 12 mils @ 1800 RPM Bearing 11-12 Vibration 8 mils @ 1800 RPM
Date/Time:
___ B.
the Main Turbine.
Reactor Power 24%. AND Turbine trip has occurred. Date/Time:
___ the Mode Switch in Shutdown.
Main Turbine Trip Turbine Stop, Control and Combined Intermediate Valves close. Turbine Bypass Valves Open to control pressure. Generator output and field breakers open. Generator lockout.
Turbine Trip Signal (as sensed by low air pressure
downstream of the Air Relay Dump
Valves (AC-PSL-1389)).
The following drain valves OPEN: AB-HV-1026 AC-HV-1041/1042/1043A(B, C) AC-HV-1013A (B, C, D) AC-HV-1015 AC-HV-1018A(B) AC-HV-1017A(B) FW-HV-3719 Stator Water Cooling:
Supply header Pressure
< 64 psig at PI3607 on 10C120 OR Generator Stator Water Return Temperature 174.2ºF (79ºC) Inlet Flow 690 gpm Turbine-Generator runback if initiating conditions remain for 15 seconds. Turbine Trip within: 2 minutes of loss of cooling WITH >25,000 Stator Amps (78.84% of rated) 3.5 minutes of loss of cooling WITH >7,055 Stator Amps (22.25% of rated) Recirculation Pump Runback to 30%
(12 seconds after turbine runback) 110 psig Hydrogen Seal Oil pressure Emergency Seal Oil pump auto start Stator Water Cooling Pump Trip Standby Stator Water Cooling Pump auto start
___ I.A Recirc. Pump speed to MINIMUM. ___ I.B the Mode Switch in SHUTDOWN.I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in
SHUTDOWN. II. Bearing 1-10 Vibration 11 mils @ 1800 RPM
- Bearing 11-12 Vibration 7 mils @ 1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator
Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.* Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
A. Main Turb ine Trip.......................................................................................................7 B. Main Turbine high vibration.........................................................................................11 C. Evidence of physical damage on EITHER
- Main Turbine OR Turbine Auxiliaries......................................................................................................15 D. Loss of Stat or Cooling..............................................................................................17 E. Hydrogen Seal Oil SystemMalfunction.........................................................................19 F. Generator H 2 pressure drops below 63 psig.................................................................19 G. Both the Emergency Seal Oil Pump AND The Main Seal Oil Pump CANNOT be started, OR BEFORE Generator H 2 pressure drops below 30 psig....................................................19 H. Pressure Control Valve (PCV-3096) Ma lfunction....................................................21 I. Float Trap Ma lfunction.............................................................................................21 J. High Stator Water Cooling Temperature.......................................................................23 K. Stator Cooling High Conductivity..................................................................................23
___ I.A Recirc. Pump speed to MINIMUM.
___ I.B the Mode Switch in SHUTDOWN. I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in SHUTDOWN.II. Bearing 1-10 Vibration 11 mils @
1800 RPM
- Bearing 11-12 Vibration 7 mils @
1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.
- Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence. Procedures: HC.OP-AB.BOP-0001(Q) FEEDWATER HEATING Valves: 1-EG-TIC-2423, MAIN TURB L.O. TEMP. CONTROL VLV, Panel 10C105, 137' Turb Bldg. 1-CA-HV-1991, STM SEAL EVAP MN STM.
Equipment: 0-P-108, Motor Suction Pump. Main Turbine Lift pumps A(B,C,D,E,F,G,H,J)P110 OP111 Turning Gear Oil Pump Unit Protection Lockout Relay 86UR is located in the Upper Relay Room. Unit Protection Lockout Relay 86UB (Back up) is located in the Upper Relay Room. SWC Pump Control Switches (10C120 Generator H2 & Stator Cooling Water Panel,
TB El. 102')
Main Turbine Trips: 108% Primary Overspeed 110% Emergency Overspeed Condenser low vacuum (7.5" Hg A)
Axial Position +/- 35 mils Low bearing oil pressure Exhaust Hood high temperature (225°F)
Loss of Stator Coolant without a successful runback Loss of Emergency Trip System Low Shaft Driven Oil Pump discharge pressure Loss of both speed signals Moisture Separator high level Reactor water high level Generator protective devices actuation Load Reject, 40% mismatch Manual trip Loss of EHC oil pressure
A.1 the following CLOSED:
___ Turbine Control Valves
___ Turbine Stop Valves
___ Combined Intermediate Valves ___ A.2 IF the Reactor is NOT Scrammed THEN Feedwater Heating Abnormal BOP-0001 concurrently.
A.3 the following are running:
___ Motor Suction Pump
___ Turning Gear Oil Pump
___ A.4 1-CA-HV-1991 is OPEN to provide Main steam to the Steam Seal Evaporator. ___ A.5 WHEN Main Turbine Speed <900 rpm, all Main Turbine Lift Pumps running. A.6 If necessary:
WHEN the cause of the Trip is KNOWN AND CORRECTED, the following:
___ a. both Stator Coolant Pump Control Switches to PULL-TO-LOCK.
___ b.
the Unit Protection Lockout 86 Relays. ___ c. Stator Cooling Water Pump A(B)
Control Switch to CLOSE.
___ A.7 Main Turbine Lube Oil Coolers Temperature Controller 1EG-TIC-2423 for 85°F.
A. Main Turbine Trip Date/Time:
___ I.A Recirc. Pump speed to MINIMUM.
___ I.B the Mode Switch in SHUTDOWN. I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in SHUTDOWN.II. Bearing 1-10 Vibration 11 mils @
1800 RPM
- Bearing 11-12 Vibration 7 mils @
1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.
- Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
Equipment: 0-P-108, Motor Suction Pump. Main Turbine Lift pumps A(B,C,D,E,F,G,H,J)P110 OP111 Turning Gear Oil Pump Unit Protection Lockout Relay 86UR is located in the Upper Relay Room. Unit Protection Lockout Relay 86UB (Back up) is located in the Upper Relay Room. SWC Pump Control Switches (10C120 Generator H2 & Stator Cooling Water Panel,
TB El. 102')
Main Turbine Trips: 108% Primary Overspeed 110% Emergency Overspeed Condenser low vacuum (7.5" Hg A)
Axial Position +/- 35 mils Low bearing oil pressure Exhaust Hood high temperature (225°F)
Loss of Stator Coolant without a successful runback Loss of Emergency Trip System Low Shaft Driven Oil Pump discharge pressure Loss of both speed signals Moisture Separator high level Reactor water high level Generator protective devices actuation Load Reject, 40% mismatch Manual trip Loss of EHC oil pressure
A. Main Turbine Trip ___ A.8 IF Any action taken by Hope Creek resulted in: a. Island loss of 2000 Mwe generation OR
- b. Sustained 500 kV voltage excursions
<450 kV or >550 kV, OR
- c. Major damage to 500 kV breakers or transmission network, OR
- d. Unplanned loss of any offsite transmission line, OR e. Damage to Main Generator, OR
- f. Damage to Main Generator, Main Transformers or transformer protective relays (A/B/CX500)
THEN SM/CRS to refer to ECG, RAL Section 11.11.1 for NERC reporting
requirements. (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
___ I.A Recirc. Pump speed to MINIMUM. ___ I.B the Mode Switch in SHUTDOWN.I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in
SHUTDOWN. II. Bearing 1-10 Vibration 11 mils @ 1800 RPM
- Bearing 11-12 Vibration 7 mils @ 1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator
Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.* Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence. 1. Raising temperature to high in the band has been known to counteract the effects of "Oil Whip" and reduce vibrations, if this is the cause for the high vibrations. "Oil Whip" is the phenomenon of the bearing oil being drawn into a cushioning wedge with the
shaft rotation. The whip occurs when the viscosity of the oil wedge is great enough for the wedge
to be pulled out from under the turbine shaft, causing the shaft to move closer to the bearing
surface, reforming the wedge and whipping away again. This whipping action will cause a bump
or spike in the shaft's vibration at that point in the turbine and an increase in temperature in the adjacent bearings as they pick up the load. 2. The vibration levels / time limits in Steps B.2 and B.3 are assuming the Main Turbine is @1800 rpm. These limits may be exceeded / extended during testing evolutions under an approved test plan with engineering concurrence. At no time may the immediate operator action bearing
vibration threshold values be exceeded.
Valves: 1-EG-TIC-2423, MAIN TURB L.O. TEMP. CONTROL VLV, Panel 10C105, 137' Turbine Bldg.
Procedures: HC.OP-SO.MA-0001(Q), MAIN GENERATOR & EXCITOR OPERATION & SWITCHING.
HC.OP-IO.ZZ-0004(Q) SHUTDOWN FROM RATED POWER TO COLD SHUTDOWN.
B.1 the following to stabilize rising vibrations:
___ ___ Main Turbine Lube Oil Coolers Temperature Controller 1EG-TIC-2423
(110 - 120°F).
___
adequate bearing oil drain flow for bearing(s) exhibiting elevated vibration levels.___ WITH System Operator concurrence, MVAR loading. (MA)___
Engineering for additional guidance to lower turbine vibrations.
___ ___ B.2IF Turbine Bearings 1-10 Vibration
> 8 mils but < 10 mils THEN the following:
___ a. IF 24% Reactor Power THEN: WITH Operations Manager concurrence a controlled shutdown.
(IO.ZZ-0004) ___ b. IF Reactor Power <24%
THEN:
the Main Turbine (AC-0001) ___ B.3WITH Turbine Bearings 1-10 Vibration 10 mils for 15 minutes THEN the following:
- a. IF 24% Reactor Power THEN: ___ 1. Recirc. Pump speed to MINIMUM.
___ 2. the Mode Switch in SHUTDOWN.
___ 3. the Main Turbine. ___ b. IF Reactor Power <24%
THEN the Main Turbine. B. Main Turbine high vibration.
Date/Time:
___ I.A Recirc. Pump speed to MINIMUM. ___ I.B the Mode Switch in SHUTDOWN.I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in
SHUTDOWN. II. Bearing 1-10 Vibration 11 mils @ 1800 RPM
- Bearing 11-12 Vibration 7 mils @ 1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator
Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.* Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
- 3. Vibration value of 40 mils is based on the potential for bearing damage should bearing clearances be exceeded. CRIDS is limited to 15 mils. Vibration readings > 15 mils can be monitored on Main Control Room System 1 co mputer or locally at TSI cabinet 10C366. 4. Upon Main Turbine and Reactor Feed Pump Trip the applicable drain valves will reposition to OPEN. Should this occur, these valves should be returned to the CLOSED position.
Valves: AB-HV-F016, CTMT INBD STM LINE DRAIN HDR ISLN INBOARD MOV AB-HV-F019, CTMT INBD STM LINE DRAIN HDR ISLN OUTBOARD MOV 1-CG-HV-1968A1,A2,A3(B1,B2,B3), EJEC A(B) 1 ST STG. JET SUCT. 1-AB-HV-2016A(B), SJAE A(B) INL VLV. 1-CG-HV-1972 A(B,C), CNDSR SEC A(B,C) VAC BKR. 1-CA-HV-1991, STM SEAL EVAP MN STM. 1-CA-HV-1990A(B), STM PKG EXH FAN A(B).
Equipment: AK103(BK103), STEAM PACKING EXHAUSTER FAN.
___ B.4 IF Bearing Vibration is elevated (>15 mils) following a turbine trip, vibration on Main Control Room System 1 computer. IF System 1 is unavailable, THEN an Operator to the TSI cabinet 10C366 to continuously monitor turbine vibration.
___ a. IF sustained Bearing Vibration 40 mils with turbine speed above the critical speed range of 1200-1250 RPM,
AND Turbine damage is imminent THEN vacuum as follows:
___ 1. Recirc Pump Speed to MINIMUM.
___ 2. the Mode Switch in SHUTDOWN.
___ 3. the MSIVs AND Main Steam line drains F016/F019.
- 4. the following are CLOSED:
___ Main Turbine Stop Valves.
___ Control Valves.
___ Main Turbine Bypass Valves.
___ 5. CG-HV-1968 A1, A2, A3 (B1, B2, B3).
___ 6. AB-HV-2016A(B).
___ 7. CG-HV-1972A/B/C
___ 8. the following valves remain CLOSED: ___ Reactor Feed Pump Steam Line Drains.
___ Main Steam Line Drains.
- 9. WHEN Main Condenser Pressure is 29"HgA, THEN
- ___ a. CA-HV-1991.
___ b. AK103 (BK103).
B. Main Turbine high vibration.
___ c. HV-1990A(B) CLOSES.
___ I.A Recirc. Pump speed to MINIMUM.
___ I.B the Mode Switch in SHUTDOWN. I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in SHUTDOWN.II. Bearing 1-10 Vibration 11 mils @
1800 RPM
- Bearing 11-12 Vibration 7 mils @
1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.
- Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
- 5. Upon Main Turbine and Reactor Feed Pump Trip the applicable drain valves will reposition to OPEN. Should this occur, these valves should be returned to the CLOSED position. Valves: AB-HV-F016, CTMT INBD STM LINE DRAIN HDR ISLN INBOARD MOV AB-HV-F019, CTMT INBD STM LINE DRAIN HDR ISLN OUTBOARD MOV 1-CG-HV-1968A1,A2,A3(B1,B2,B3), EJEC A(B) 1 ST STG. JET SUCT. 1-AB-HV-2016A(B), SJAE A(B) INL VLV. 1-CG-HV-1972 A(B,C), CNDSR SEC A(B,C) VAC BKR. 1-CA-HV-1991, STM SEAL EVAP MN STM. 1-CA-HV-1990A(B), STM PKG EXH FAN A(B).
Equipment: AK103(BK103), STEAM PACKING EXHAUSTER FAN.
___ C.1 Recirc Pump Speed to MINIMUM.
___ C.2 the Mode Switch in SHUTDOWN.
___ C.3 the Turbine AND the Generator.
___
C.4 Main Condenser Vacuum as follows:
___ a. the MSIVs AND Main Steam line drains F016/F019.
- b. the following are CLOSED:
___ Main Turbine Stop Valves.
___ Control Valves.
___ Main Turbine Bypass Valves.
___ c. CG-HV-1968 A1, A2, A3 (B1, B2, B3).
___ d. AB-HV-2016A(B).
___ e. CG-HV-1972A/B/C
___ f. the following valves remain CLOSED:___ Reactor Feed Pump Steam Line Drains.
___ Main Steam Line Drains. g. WHEN Main Condenser Pressure is 29"HgA, THEN: ___ 1. CA-HV-1991.
___ 2. AK103 (BK103). C. Evidence of physical damage on EITHER: Main Turbine
OR Turbine Auxiliaries
Date/Time:
___ 3. HV-1990A(B) CLOSES.
___ I.A Recirc. Pump speed to MINIMUM. ___ I.B the Mode Switch in SHUTDOWN.I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in
SHUTDOWN. II. Bearing 1-10 Vibration 11 mils @ 1800 RPM
- Bearing 11-12 Vibration 7 mils @ 1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator
Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.* Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
- 6. Generator VARS reduction may be secured once Stator Water Cooling is restored and stability guidelines described in A-5-500-EEE-1686 should be reviewed. 7. To determine conductivity prior to the Lo ss of Stator Water Cooling flow use chart recorder CR-3593B on Panel 10C650. 8. Ensure that conductivity indication/alarm is valid by checking that both the inlet and outlet indicators agree within 0.1 mho and are trending similarly. If >9.9 mhos the indication is off scale. If indication is <9.9 mhos at least 10 minutes should be allowed for indication to stabilize following stator flow restoration.
Procedures: A-5-500-EEE-1686 Artificial Island Operati ng Guide and Documentation (Engineering Evaluation)
D.1 the following:
___
both Stator Water Cooling Pumps AND tank level is normal.
___ Reactor Recirculation Pump Runback. ___
Main Turbine Runback.___ ___ Generator VARS to zero.
___ D.2IF Reactor Power 24% a Stator Cooling conductivity PRIOR to Loss of Stator Water Cooling Flow AND the following:
___ IF conductivity is < 0.5 mho, THEN WITHIN 60 minutes Stator Water Cooling OR Turbine.
___ IF conductivity is > 0.5 but < 9.9 mho, THEN WITHIN 3 minutes: Stator Water Cooling OR the Main Turbine.
___ IF conductivity is 9.9 mhos THEN the Main Turbine.
___ D.3UPON restoration of Stator Cooling flow IF Conductivity is 9.9 mhos OR >.5 mho AND continues to rise THEN the following:
- a. IF 24% Reactor Power THEN
- ___ 1. Recirc. Pump speed to MINIMUM. ___ 2. the Mode Switch in SHUTDOWN.
___ 3. the Main Turbine. D. Loss of Stator Cooling Date/Time:
___ b. IF Reactor Power <24%
THEN the Main Turbine.
___ I.A Recirc. Pump speed to MINIMUM.
___ I.B the Mode Switch in SHUTDOWN. I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in SHUTDOWN.II. Bearing 1-10 Vibration 11 mils @
1800 RPM
- Bearing 11-12 Vibration 7 mils @
1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.
- Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
- 9. When the Emergency Seal Oil Pump is in operation hydrogen purity should be monitored periodically and if prolonged operation is necessary, the Seal Oil Vacuum Pump should be secured. Valves: 1-CC-SV-3523, PURITY METER VENT, 10C650, MAIN CONTROL ROOM. 1-CC-V031, GEN MAINT. ISLN VLV. (102' TURBINE BLDG.) 1-CC-V034, GEN CASING VNT TO ATM ISLN VLV. (102' TURBINE BLDG.) Procedures: HC.OP-SO.CE-0001(Q), STATOR WATER COOLING SYSTEM OPERATION.
Equipment: SWC Pump Control Switches (10C120 Generator H2 & Stator Cooling Water Panel,
TB El. 102')
___ E. Hydrogen Seal Oil SystemMalfunction.
Date/Time:
___ E.1 IF the Emergency Seal Oil Pump fails to auto start, THEN the Emergency Seal Oil Pump. F.1 IF Reactor Power 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM.
___ b. the Mode Switch in Shutdown.
___ F.2 the Turbine AND the Generator.
___
___ F.3 BOTH Stator Water Cooling Pump Control Switches to PULL TO LOCK. F. Generator H 2 pressure drops below 63 psig.
Date/Time:
___ F.4 Breaker 52-112113 Stator Coolant Water Heater 10E113 power supply.
G.1 IF Reactor Power 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM.
___ b. the Mode Switch in Shutdown.___ G.2 the Turbine AND the Generator.
G.3 the following:
___ unnecessary personnel from Turbine Generator Area
___ Turbine Building Ventilation in Purge
___
all available Turbine Building Exhaust / Supply Fans.___
the following:___ 1-CC-V031
___ 1-CC-V034.
___ SV-3523 ___
Site Protection to evaluate H 2 concerns in the Turbine Building. G. Both the Emergency Seal Oil Pump AND The Main Seal Oil Pump
CANNOT be started, OR BEFORE Generator H 2 pressure drops below 30 psig.
Date/Time:
___ I.A Recirc. Pump speed to MINIMUM.
___ I.B the Mode Switch in SHUTDOWN. I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in SHUTDOWN.II. Bearing 1-10 Vibration 11 mils @
1800 RPM
- Bearing 11-12 Vibration 7 mils @
1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.
- Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
- Valves: 1-CD-V001, FLOAT TRAP BYP VLV. 1-CD-V003, FLOAT TRAP OTL ISOL VLV. 1-CD-V009, PCV 3096 INL ISOL VLV. 1-CD-V010, PCV 3096 OTL ISOL VLV. 1-CD-V011, PCV 3096 BYP VLV 1-CD-V015, FLOAT TRAP INL ISOL VLV. P-CD-V9996, LG 3073 FLOAT TRAP UPPER BYP VLV. P-CD-V9997, LG 3073 FLOAT TRAP LOWER BYP VLV. P-CD-V9998, LG 3073 FLOAT TRAP LOWER ISOL VLV.
P-CD-V9999, LG 3073 FLOAT TRAP UPPER ISOL VLV.
Valves: 1-CC-SV-3523, PURITY METER VENT, 10C650, MAIN CONTROL ROOM. 1-CC-V031, GEN MAINT. ISLN VLV. (102' TURBINE BLDG.) 1-CC-V034, GEN CASING VNT TO ATM ISLN VLV. (102' TURBINE BLDG.)
Indications: MACHINE GAS PRESSURE (H2 pressure) PI-3579 (10C120 Generator H2 & Stator Cooling Water Panel, TB El. 102')
G.4 BEFORE H2 Pressure drops to 3 psig AND Generator H2 Pressure can be maintained <8 psig the following:
___ SV-3523 ___ 1-CC-V031 G. Both the Emergency Seal Oil Pump AND The Main Seal Oil Pump CANNOT be
- started, OR BEFORE Generator H2 pressure drops below 30 psig.
___ 1-CC-V034
___ H.1 1-CD-V011 to maintain Seal Oil Pressure 5 psig > H 2 Pressure.
H.2 the following valves:
___ 1-CD-V009 H. Pressure Control Valve (PCV-3096)
Malfunction.
Date/Time:
___ 1-CD-V010 I.1 the following valves:
___ 1-CD-V015
__ 1-CD-V003 I.2 the following valves:
___ P-CD-V9996
___ P-CD-V9997 I.3 the following valves:
___ P-CD-V9998
___ P-CD-V9999 I. Float Trap Malfunction.
Date/Time:
___ I.4 1-CD-V001 to maintain oil level in sight glass LG-3073.
___ I.A Recirc. Pump speed to MINIMUM. ___ I.B the Mode Switch in SHUTDOWN.I. Loss of Stator Cooling for > 2 min.
AND Reactor Power > 24%
Date/Time:
___ I.C the Main Turbine. II.A IF Reactor Power is 24% THEN the following:
___ a. Recirc. Pump speed to MINIMUM. ___ b. the Mode Switch in
SHUTDOWN. II. Bearing 1-10 Vibration 11 mils @ 1800 RPM
- Bearing 11-12 Vibration 7 mils @ 1800 RPM
___ II.B the Main Turbine.III. Failure of Main Turbine to runback on a Loss of Stator
Water Cooling.
Date/Time:
___ III.A
___ III.B Recirc Pump speed to MINIMUM. the Mode Switch in SHUTDOWN.* Vibration Limits may be exceeded during testing evolutions under an approved test plan with Engineering concurrence.
- 10. Ensure that conductivity indication/alarm is valid by checking that both the inlet and outlet indicators agree within 0.1 mho.
Valves: P-CE-V9981, Deionizer Outlet Isolation Valve P-CE-V9994, Deionizer Inlet Isolation Valve Indications: 1CETISH-3594, Stator Windi ng Outlet Temperature
___ J.1 IF Stator Water Cooling inlet temperature has or is expected to exceed 122 F (50 C), THEN the demineralizer as follows:
___ a. P-CE-9981
___ b. P-CE-9994
___ J.2 TACS Isolation Valves are OPEN to the Stator Cooling Heat Exchangers. J.3 IF TCV-3604 is malfunctioning: ___ a.
P-CE-V9944 to isolate air to the TC-3604 to achieve full flow through the
Stator Water Coolers.___ b.
temperature at 1CETISH-3594.J. High Stator Water Cooling Temperature.
Date/Time:
___ c.
EG-V311 and EG-V313 to achieve desired Stator Winding Outlet
Temperatures.___ ___ K.1 actual conductivity by comparing Inlet and Outlet indications.
___ K.2 IF Conductivity >.5 mhos THEN Engineering for guidance.
K.3 IF Conductivity 9.9 mhos THEN the following:
- a. IF 24% Reactor Power THEN: ___ 1. Recirc. Pump speed to MINIMUM. ___ 2. the Mode Switch in SHUTDOWN.
___ 3. the Main Turbine. K. Stator Cooling High Conductivity.
Date/Time:
___ b. IF Reactor Power <24%
THEN AND the Main Turbine.
1.1 the entry Condition into the abnormal in the Comments Section. ____
1.2 in the comments section all systems affected by the implementation of this procedure AND restoration actions (i.e. restoration line ups) completed/required. ____
1.3 photocopies of any Hard Cards utilized as part of this
procedure implementation to Attachment 1. ____
1.4 the Exit time for any applicable conditions and this abnormal are annotated in the comment section AND the Control Room Logs. ____
1.5 completed Portions of this procedure AND Sections 1 and 2 of Attachment 1 to SM/CRS for approval and Record Retention. ____
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Completion of this attachment is annotated in the Control Room Logs:
Printed Name Signature Date/Time This procedure and Attachment 1 have been reviewed for completeness and accuracy.
Entry/Exit conditions and all deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section above.
Printed Name SM/CRS Date/Time 4.1 the following in accordance wit h RM-AA-101, Records Management Program: Procedure cover page Affected Conditions and Hard Cards performed Completion and Review section Attachment 1
Biennial Review Performed: Yes No NA Packages and Affected Document Numbers incorporated into this revision:
CP No. CP Rev.
AD No.
Rev No.
None The following OTSCs were incorporated into this revision: None Adds Step A.4 to provide extraction steam from Main Steam to the Steam Seal evaporator. (70092163-0040) Adds the word 'inlet' to Step J.1 to make the step more clear. This is an editorial change.
(70091056-0020)
None