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Category:Technical Specification
MONTHYEARML24158A5232024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition ML24158A5252024-06-0606 June 2024 Revised Technical Specification Pages (Clean Pages) ML24158A5242024-06-0606 June 2024 Proposed Technical Specification Changes (Mark-up) ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ML23310A0512023-11-0606 November 2023 EIP-ZZ.OO1O1, Addendum 2, Revision 22, Emergency Action Level Technical Bases Document ML23227A1272023-08-15015 August 2023 Corrected Proposed Technical Specification 55.16 Changes (Markup) ML23206A2242023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Markup) ML23206A2252023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ML23088A1232023-03-29029 March 2023 Attachment 3: Marked-Up Technical Specification, Bases Pages ML23088A1212023-03-29029 March 2023 Attachment 1: Marked-Up Technical Specification Pages ML23088A1222023-03-29029 March 2023 Attachment 2: Revised (Clean) Technical Specification Pages ML23088A2542023-03-23023 March 2023 EIP-ZZ-00101, Addendum 2, Revision 020, Emergency Action Level Technical Bases Document ML23052A0472023-02-21021 February 2023 Enclosure 5 - Revised Technical Specification Bases (for Information Only) ML23067A1812022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B2, Safety Limits (Sls) ML23067A1822022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.8, Electrical Power Systems ML23067A1742022-12-29029 December 2022 Rev. 18 to Technical Specifications, Bases Change, Chapter 3.7, Plant Systems ML23067A1802022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.1, Reactivity Control Systems ML23067A1752022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.3, Instrumentation ML23067A1762022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.5, Emergency Core Cooling System S(Eccs) ML23067A1832022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Table of Contents ULNRC-06782, Rev. 18 to Technical Specification Bases, List of Effective Sections2022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, List of Effective Sections ML23067A1772022-12-29029 December 2022 Rev. 18 to Technical Specification Bases Change, Chapter B3, Safety Limits (Sls) ML23067A1862022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.2, Power Distribution Limits ML23067A1852022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B 3.9, Refueling Operations ML23067A1782022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.6, Containment Systems ML23067A1792022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Implemented Change Notice Log ML23067A1842022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.4, Reactor Coolant System ULNRC-06781, Attachment 2 - Proposed TS Bases Changes (Markups)2022-12-0101 December 2022 Attachment 2 - Proposed TS Bases Changes (Markups) ML22335A5092022-12-0101 December 2022 Description and Assessment of the Proposed Change ML22307A3142022-11-0303 November 2022 Attachment 2: Proposed Technical Specification 5.5.16 Changes (Markup) ML22307A3152022-11-0303 November 2022 Attachment 3: Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML22285A1202022-10-12012 October 2022 Attachment 3 to Enclosure 1: Marked-Up Technical Specifications Bases (for Information Only) ML22242A1262022-08-29029 August 2022 Attachment 2 to Enclosure 1 - Revised Clean Technical Specifications ML22242A1272022-08-29029 August 2022 Attachment 3 to Enclosure 1 - Marked-Up Technical Specification Bases ML22242A1252022-08-29029 August 2022 Attachment 1 to Enclosure 1 - Marked-Up Existing Technical Specifications ML22216A2422022-08-0404 August 2022 Proposed Technical Specification Changes (Mark-Up) ML22181B1342022-06-30030 June 2022 Attachment 4 - Replacement for Attachment 4, Proposed Changes to Technical Specification Bases Changes (Mark-Up) Pages (for Information), of ULNRC-06688 ML22153A1792022-06-0202 June 2022 Attachment 3 - Marked-Up Technical Specifications Bases ULNRC-06686, Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up)2021-12-0909 December 2021 Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up) ML21335A4572021-12-0101 December 2021 Enclosure 5: Proposed Technical Specification Bases Changes (Mark-up - for Info Only) ML21294A4102021-10-21021 October 2021 Enclosure 10 - Program Implementation ML21294A4112021-10-21021 October 2021 Enclosure 11 - Monitoring Program ML21294A4092021-10-21021 October 2021 Enclosure 9 - Key Assumptions and Sources of Uncertainty ULNRC-06688, Enclosure 12 - Risk Management Action Examples2021-10-21021 October 2021 Enclosure 12 - Risk Management Action Examples ML21294A4072021-10-21021 October 2021 Enclosure 7 - PRA Model Update Process ML21294A4062021-10-21021 October 2021 Enclosure 6 - Justification of Application of At-Power PRA Models to Shutdown Modes ML21294A4052021-10-21021 October 2021 Enclosure 5 - Baseline Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) ML21294A4042021-10-21021 October 2021 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models ML21294A4032021-10-21021 October 2021 Enclosure 3 - Information Supporting Technical Adequacy of PRA Models Without PRA Standards Endorsed by Regulatory Guide 1.200, Revision 2 2024-06-06
[Table view] Category:Amendment
MONTHYEARML23206A2252023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23206A2242023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Markup) ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ML23088A1222023-03-29029 March 2023 Attachment 2: Revised (Clean) Technical Specification Pages ML23088A1212023-03-29029 March 2023 Attachment 1: Marked-Up Technical Specification Pages ML22242A1252022-08-29029 August 2022 Attachment 1 to Enclosure 1 - Marked-Up Existing Technical Specifications ML22242A1262022-08-29029 August 2022 Attachment 2 to Enclosure 1 - Revised Clean Technical Specifications ML21294A4022021-10-21021 October 2021 Enclosure 2 - Information Supporting Consistency with Regulatory Guide 1.200, Revision 2 ULNRC-06688, Enclosure 12 - Risk Management Action Examples2021-10-21021 October 2021 Enclosure 12 - Risk Management Action Examples ML21294A4102021-10-21021 October 2021 Enclosure 10 - Program Implementation ML21294A4112021-10-21021 October 2021 Enclosure 11 - Monitoring Program ML21294A4092021-10-21021 October 2021 Enclosure 9 - Key Assumptions and Sources of Uncertainty ML21294A4082021-10-21021 October 2021 Enclosure 8 - Attributes of the Real Time Risk Model ML21294A4072021-10-21021 October 2021 Enclosure 7 - PRA Model Update Process ML21294A4062021-10-21021 October 2021 Enclosure 6 - Justification of Application of At-Power PRA Models to Shutdown Modes ML21294A4052021-10-21021 October 2021 Enclosure 5 - Baseline Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) ML21294A4042021-10-21021 October 2021 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models ML21294A4032021-10-21021 October 2021 Enclosure 3 - Information Supporting Technical Adequacy of PRA Models Without PRA Standards Endorsed by Regulatory Guide 1.200, Revision 2 ML21294A4012021-10-21021 October 2021 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions ML21294A3992021-10-21021 October 2021 Attachment 5 - Cross-Reference of TSTF-505 and Callaway Technical Specifications ML21294A4002021-10-21021 October 2021 Attachment 6 - Description and Assessment Specific to TSTF-439 ML21294A3972021-10-21021 October 2021 Attachment 3 - Revised Technical Specification Pages ML21294A3962021-10-21021 October 2021 Attachment 2 - Proposed Technical Specification Changes (Mark-Up) ML21294A3952021-10-21021 October 2021 Attachment 1 - Description and Assessment ML20070R1142020-03-10010 March 2020 Description and Assessment of the Proposed Change ML20070R1212020-03-10010 March 2020 Technical Specification Page Markup ULNRC-06433, License Amendment Request for Emergency Action Level (EAL) Changes2018-09-0404 September 2018 License Amendment Request for Emergency Action Level (EAL) Changes ULNRC-06264, Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology2015-11-0909 November 2015 Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology ML15062A0522015-03-0606 March 2015 NRC-Callaway-TS-renewed License ULNRC-05832, Revision of Technical Specification 3.3.8, TAC No. ME51732011-12-13013 December 2011 Revision of Technical Specification 3.3.8, TAC No. ME5173 ML1130706942011-11-0303 November 2011 Attachment 5 - Control Building Room Locations and P&ID Excerpts ML1130706832011-11-0303 November 2011 Attachment 1 - Technical Specification Page Mark Up ML1130706812011-11-0303 November 2011 Enclosure Page 1 of 22, Evaluation of the Proposed Change ULNRC-05804, Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025)2011-06-30030 June 2011 Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025) ULNRC-05793, Application for Amendment to Facility Operating License NPF-30 (LDCN 10-0036) Revision of Technical Specification 3.3.8,2011-06-16016 June 2011 Application for Amendment to Facility Operating License NPF-30 (LDCN 10-0036) Revision of Technical Specification 3.3.8, ULNRC-05682, Application for Amendment, Revision of Technical Specification 3.3.92010-03-0404 March 2010 Application for Amendment, Revision of Technical Specification 3.3.9 ULNRC-05560, Revision of Technical Specifications 3.8.4 and 3.8.5, Application for Amendment to Facility Operating License NPF-30 (LDCN 08-002)2008-12-29029 December 2008 Revision of Technical Specifications 3.8.4 and 3.8.5, Application for Amendment to Facility Operating License NPF-30 (LDCN 08-002) ML0824602412008-11-24024 November 2008 Issuance of Amendment No. 187, Revise Technical Specification 5.5.8, Inservice Testing Program, Testing Frequencies ULNRC-05494, Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.82008-06-0303 June 2008 Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.8 ML0706803502007-03-21021 March 2007 License and Technical Specification Pages - Amendment No. 182 Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System ML0632801852006-11-17017 November 2006 Callaway - Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238) ULNRC-05345, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms).2006-11-17017 November 2006 Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms). ULNRC-05314, Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.2006-07-19019 July 2006 Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation. ULNRC-05301, Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.132006-06-0707 June 2006 Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.13 ULNRC-05297, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System2006-05-25025 May 2006 Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)2006-03-28028 March 2006 Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238) ULNRC-05206, License Amendment Request OL 1258 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfiv'S)2005-09-0909 September 2005 License Amendment Request OL 1258 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfiv'S) ML0506903182005-03-0808 March 2005 Technical Specification Pages Re Elimination of Requirements to Provide Monthly Operating Reports & Annual Occupational Radiation Exposure Reports ULNRC-05117, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-02-11011 February 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project ML0503301832005-01-31031 January 2005 Issuance of License Amendment 165 Re Plant Protection Test Times, Completion Times and Surveillance Test Intervals 2023-07-25
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ML23215A1972023-08-0303 August 2023 Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002) ML23088A1202023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Evaluation of the Proposed Change ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ML22335A5082022-12-0101 December 2022 License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ML22307A3142022-11-0303 November 2022 Attachment 2: Proposed Technical Specification 5.5.16 Changes (Markup) ULNRC-06765, Evaluation of the Proposed Change2022-11-0303 November 2022 Evaluation of the Proposed Change ML22307A3132022-11-0303 November 2022 Attacchment 1: 54032-CALC-01, Revision 1,Callaway Plant: Evaluation of Risk Significance of Permanent ILRT Extension ML22307A3152022-11-0303 November 2022 Attachment 3: Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML22285A1172022-10-12012 October 2022 Enclosure 1: Description and Assessment of the Proposed Change ML22285A1182022-10-12012 October 2022 Attachment 1 to Enclosure 1: Marked-Up Existing Technical Specifications ML22285A1192022-10-12012 October 2022 Attachment 2 to Enclosure 1: Revised Clean Technical Specifications ML22285A1202022-10-12012 October 2022 Attachment 3 to Enclosure 1: Marked-Up Technical Specifications Bases (for Information Only) ML22285A1222022-10-12012 October 2022 Attachment 5 to Enclosure 1: ANP-3947NP, Callaway Unit 1 License Amendment Request Inputs for Use of Framatome Fuel, Revision 3, Dated October 2022 ML22285A1232022-10-12012 October 2022 Attachment 6 to Enclosure 1: ANP-3944NP, Callaway Realistic Large Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1242022-10-12012 October 2022 Attachment 7 to Enclosure 1: ANP-3943NP, Callaway Small Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ULNRC-06768, Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 20222022-10-12012 October 2022 Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 2022 ML22285A1212022-10-0707 October 2022 Attachment 4 to Enclosure 1: Framatome Affidavits for Withholding from Public Disclosure ML22242A1242022-08-29029 August 2022 Enclosure 1: Description and Assessment of the Proposed Change ML22242A1252022-08-29029 August 2022 Attachment 1 to Enclosure 1 - Marked-Up Existing Technical Specifications ML22242A1262022-08-29029 August 2022 Attachment 2 to Enclosure 1 - Revised Clean Technical Specifications ML22242A1272022-08-29029 August 2022 Attachment 3 to Enclosure 1 - Marked-Up Technical Specification Bases ULNRC-06723, Attachment 5 to Enclosure 1 - Criticality Safety Evaluation Report2022-08-29029 August 2022 Attachment 5 to Enclosure 1 - Criticality Safety Evaluation Report ML22216A2412022-08-0404 August 2022 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) - Description and Assessment ML22242A1282022-06-30030 June 2022 Attachment 4 to Enclosure 1 - Holtec Affidavit for Withholding ML22181B1312022-06-30030 June 2022 Attachment 1 - Replacement for Attachment 1, Description and Assessment, of ULNRC-06688 ML22181B1352022-06-30030 June 2022 Attachment 5 - Replacement for Attachment 5, Cross-Reference of TSTF-505 and Callaway Technical Specifications, of ULNRC-06688 ML22181B1372022-06-30030 June 2022 Attachment 7 - Proposed Operating License Changes (Mark-up) ML22181B1382022-06-30030 June 2022 Attachment 8 - Revised Operating License Changes ML22181B1392022-06-30030 June 2022 Attachment 9 - Responses to NRC Audit Questions ML22153A1752022-06-0202 June 2022 ULNRC-06729: Application for Technical Specification Change and Exemption Request Regarding Transition to Framatome Fuel, LDCN 22-0002 ML22153A1762022-06-0202 June 2022 Enclosure 1 - Description and Assessment of the Proposed Change ML22153A1812022-06-0202 June 2022 Attachment 5 - Non-Proprietary Version of Licensing Summary Report ML22039A3192022-02-0808 February 2022 Enclosure 1: Callaway Plant - Description of the Proposed Changes ML22027A8072022-01-27027 January 2022 Enclosure 2: Callaway, Unit 1, License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02 ULNRC-06690, Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138)2022-01-27027 January 2022 Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138) ML21335A4532021-12-0101 December 2021 Enclosure 1: Full Scope Implementation of Alternative Source Term - Evaluation of Proposed Changes ML21335A4522021-12-0101 December 2021 Supplement to License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications ML21328A1842021-11-24024 November 2021 Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0007 ML21294A4032021-10-21021 October 2021 Enclosure 3 - Information Supporting Technical Adequacy of PRA Models Without PRA Standards Endorsed by Regulatory Guide 1.200, Revision 2 ML21294A4022021-10-21021 October 2021 Enclosure 2 - Information Supporting Consistency with Regulatory Guide 1.200, Revision 2 ML21294A4012021-10-21021 October 2021 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions ML21294A3992021-10-21021 October 2021 Attachment 5 - Cross-Reference of TSTF-505 and Callaway Technical Specifications ML21294A4002021-10-21021 October 2021 Attachment 6 - Description and Assessment Specific to TSTF-439 ML21294A3982021-10-21021 October 2021 Attachment 4 - Proposed Changes to Technical Specification Bases Changes (Mark-Up) Pages (for Information) ML21294A4042021-10-21021 October 2021 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models ML21294A4052021-10-21021 October 2021 Enclosure 5 - Baseline Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) ML21294A4062021-10-21021 October 2021 Enclosure 6 - Justification of Application of At-Power PRA Models to Shutdown Modes ML21294A3972021-10-21021 October 2021 Attachment 3 - Revised Technical Specification Pages 2023-08-03
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E12-1 ENCLOSURE 12 License Amendment Request Callaway Unit No. 1 Renewed Facility Operating License NPF-30 NRC Docket No. 50-483 Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b" Risk Management Action Examples 2
Risk Management Action Examples E12-2
1.0 INTRODUCTION
This enclosure describes the process for identification and implementation of Risk Management Actions (RMA) applicable during extended Completion Times (CT) and provides examples of RMAs. RMAs will be governed by plant procedures for planning and scheduling maintenance activities. These procedures will provide guidance for the determination and implementation of RMAs when entering the RICT Program and is consistent with the guidance set forth in NEI 06-09-A (Reference 2).
2.0 RESPONSIBILITIES For planned entries into the RICT Program, the Operations Department is responsible for developing the RMAs with assistance from the Work Management Department and Probabilistic Risk Assessment (PRA) group. Operations is responsible for approval and implementation of RMAs. For emergent entry into extended CTs, Operations is also responsible for developing the RMAs.
3.0 PROCEDURAL GUIDANCE For planned maintenance activities, implementation of RMAs will be required if it is anticipated that the risk management action time (RMAT) will be exceeded. For emergent activities, RMAs must be implemented if the RMAT is reached. Also, if an emergent event occurs requiring recalculation of an RMAT already in place, the procedure will require a reevaluation of the existing RMAs for the new plant configuration to determine if new RMAs are appropriate. These requirements of the RICT Program are consistent with the guidance of NEI 06-09-A. (Reference 2).
For emergent entry into a RICT, if the extent of condition is not known, RMAs related to the success of redundant and diverse structures, systems, or components (SSC) and reducing the likelihood of initiating events relying on the affected function will be developed to address the increased likelihood of a common cause event.
RMAs will be implemented in accordance with current procedures (e.g. References 7, 8, and 9) no later than the time at which an incremental core damage probability (ICDP) of 1E-6 is reached, or no later than the time when an incremental large early release probability (ILERP) of 1E-7 is reached. If, as the result of an emergent condition, the instantaneous core damage frequency (ICDF) or the instantaneous large early release frequency (ILERF) exceeds 1E-3 per year or 1E-4 per year, respectively, RMAs are also required to be implemented. These requirements are consistent with the guidelines of NEI 06-09-A. (Reference 2).
By determining which SSCs are most important from a CDF or LERF perspective for a specific plant configuration, RMAs may be created to protect these SSCs. Similarly, knowledge of the hazard, initiating event, and/or sequence contribution to the configuration-specific CDF or LERF allows development of RMAs that enhance the capability to mitigate such events. The guidance in NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making (Reference 3) and EPRI TR-1026511, Practical Guidance on the Use of PRA in Risk-Informed Applications with a Focus on the Treatment of Uncertainty (Reference 4) will be used in examining PRA results for significant contributors for the configuration, to aid in identifying appropriate compensatory measures; e.g., related to risk-significant systems that may provide diverse protection, or important support systems, or human 2
Risk Management Action Examples E12-3 actions. Enclosure 9 identifies several areas of uncertainty in the internal events, internal flooding, seismic, high winds and fire PRAs that will be considered in defining configuration-specific RMAs when entering a RICT.
It is possible to credit RMAs in RICT calculations, to the extent the associated plant equipment and operator actions are modeled in the PRA; however, such quantification of RMAs is neither required nor expected by NEI 06-09-A. Nonetheless, if RMAs will be credited to determine RICTs, the procedure instructions will be consistent with the guidance in NEI 06-09-A. (Reference 2).
4.0 TYPES OF RISK MANAGEMENT ACTIONS NEI 06-09-A (Reference 2) classifies RMAs into three categories, as discussed below.
- 1. Actions to increase risk awareness and control.
Shift brief.
Pre-job brief.
Training (formal or informal).
Presence of system engineer or other subject matter expert related to the activity.
Special purpose procedure to identify risk sources and contingency plans.
- 2. Actions to reduce the duration of maintenance activities.
Pre-staging materials.
Conducting training on mock-ups.
Performing the activity around the clock.
Performing walkdowns on the actual system(s) to be worked on prior to beginning work.
- 3. Actions to minimize the magnitude of the risk increase.
Suspending or minimizing activities on redundant systems.
Suspending or minimizing activities on other systems that adversely affect the CDF or LERF.
Suspending or minimizing activities on systems that may cause a trip or transient to minimize the likelihood of an initiating event that the out-of-service component is meant to mitigate.
Using temporary equipment to provide backup power, ventilation, etc.
Rescheduling other maintenance activities.
5.0 GENERIC RAI INFO The below criteria and insights (e.g., important fire areas, important operator actions) can be used to determine the compensatory measures and RMAs to apply in specific instances.
- a. Phoenix Risk Monitor (PRM) will calculate the most important equipment, and/or hazard areas, to protect based on the Risk Achievement Worth (RAW) 2 Risk Management Action Examples E12-4 importance measure. This list of equipment, and/or hazard areas, can be referenced to choose suitable RMAs from the appropriate procedure(s).
- b. Similarly, PRM estimates important operator actions based on an approximate Fussel-Vesely (FV) value. Approximate values are utilized to speed the quantification time. These important operator actions can be used to brief operations crews on these proceduralized actions, throughout the maintenance window, thus decreasing the likelihood of cognition or execution failures of those operator actions.
- c. Common cause RMAs are additional RMAs focused on ensuring availability of redundant components, ensuring availability of diverse or alternate systems, reducing the likelihood of initiating events that require operation of the out-of-service components, and readiness of plant personnel to respond to additional failures.
6.0 EXAMPLE RMAs Multiple example RMAs that may be considered during a RICT Program entry to reduce the risk impact and ensure adequate defense-in-depth are provided below. Specific examples are given for unavailability of one Diesel Generator (DG), one train of Component Cooling Water (CCW), or the Turbine Driven Aux Feed Pump (PAL02).
A. Diesel Generator (Using NE01 as an example):
- 1. Actions to increase risk awareness and control.
- i. For Risk Management Actions established during the current shift:
MAKE a plant announcement of the Risk Management Actions established.
In the Control Room narrative log, RECORD the time Risk Management Actions are established and EITHER of the following:
- a. A list of all Risk Management Actions implemented.
- b. A reference to the applicable section of the procedure including any exceptions or additions.
ii. Risk Management Actions established for the scheduled work that will extend into the next shift will be listed on the Shift Manager Operational Focus Items.
iii. ENSURE shift and plant briefs address any risk assessment resulting in a yellow, orange or red status.
iv. ENSURE shift and plant briefs address any Risk Management Actions which are to be performed during the shift.
- v. ENSURE door postings per Checklist 1, Placing Postings for A Train ESW or EDG Out of Service.
2 Risk Management Action Examples E12-5 vi. Perform a walkdown of and confirm availability of applicable suppression, detection and fire barriers for the following Fire Walk down areas:
TB-1 (4301, 4302, 4303, 4316, 4318, 4319, 4321, 4322, 4351, 4401, 4501): TB 2000', 2015', 2033' and 2065' Elevation.
C-22 (3801): Upper Cable Spreading Room.
vii. For the above Fire Walk down areas, minimize the accumulation of transient combustibles in accordance with the station Fire Protection Program.
- 2. Actions to reduce the duration of maintenance activities.
- i. For preplanned RICT entry, create a sub schedule (fragnet) related to the specific evolution which is reviewed for personnel resource availability.
ii. Confirm parts availability prior to entry into a preplanned RICT.
- 3. Actions to minimize the magnitude of the risk increase.
- i. NO unscheduled safety work without performing a risk assessment per EDP-ZZ-01129, Callaway Energy Center Risk Assessment.
ii. FOLLOW established fragnets.
iii. MAINTAIN opposite train systems as the Protected OPERABLE Train.
iv. MAINTAIN TDAFP (PAL02) OPERABLE.
- v. Only allow necessary switchyard work that has been evaluated for risk with necessary controls and mitigating actions established.
vi. MINIMIZE loose items in switchyard that could become airborne/missile hazards in high winds. ENSURE such items are properly secured or stored when NOT being used.
[Ref: OTO-ZZ-00012, Severe Weather.]
vii. DO NOT allow work on AEPS system.
viii. LIMIT access to the AEPS Diesel Generators to just Operations and Security Personnel.
ix. DO NOT allow work on Security Diesel.
- x. Implement 10 CFR 50.65(a)(4) fire-specific RMA's as required.
B. Train of CCW OOS (Using 'A' train as an example)
- 1. Actions to increase risk awareness and control.
- i. For Risk Management Actions established during the current shift:
MAKE a plant announcement of the Risk Management Actions established.
In the Control Room narrative log, RECORD the time Risk Management Actions are established and EITHER of the following:
- a. A list of all Risk Management Actions implemented.
- b. A reference to the applicable section of the procedure including any exceptions or additions.
2 Risk Management Action Examples E12-6 ii. Risk Management Actions established for the scheduled work that will extend into the next shift will be listed on the Shift Manager Operational Focus Items.
iii. ENSURE shift and plant briefs address any risk assessment resulting in a yellow, orange or red status.
iv. ENSURE shift and plant briefs address any Risk Management Actions which are to be performed during the shift.
- v. Perform a walkdown of and confirm availability of applicable suppression, detection and fire barriers for the following Fire Walk down areas:
A-21 (1501): CTRL RM A/C UNIT 'B' Room, C-10 (3302): NB02 SWGR Room, TB-1 (4316): Condensate Polisher Area, YD-1: Prohibit work on and within approximately 50 feet in the yard area around the Startup Transformer.
vi. For the above Fire Walk down areas, minimize the accumulation of transient combustibles in accordance with the station Fire Protection Program.
- 2. Actions to reduce the duration of maintenance activities.
- i. For preplanned RICT entry, creation of a sub schedule (fragnet) related to the specific evolution which is reviewed for personnel resource availability.
ii. Confirmation of parts availability prior to entry into a preplanned RICT.
- 3. Actions to minimize the magnitude of the risk increase
- i. NO unscheduled safety work without performing a risk assessment per EDP-ZZ-01129, Callaway Energy Center Risk Assessment.
ii. FOLLOW established fragnets.
iii. MAINTAIN opposite train systems as the Protected OPERABLE train.
iv. Only allow necessary switchyard work that has been evaluated for risk with necessary controls and mitigating actions established.
- v. MINIMIZE loose items in switchyard that could become airborne/missile hazards in high winds. ENSURE such items are properly secured or stored WHEN NOT being used. (Reference OTO-ZZ-00012, Severe Weather.)
vi. DO NOT allow work on Alternate Emergency Power System (AEPS) system.
vii. LIMIT access to the AEPS Diesel Generators to just Operations and Security Personnel.
viii. DO NOT allow work on Security Diesel.
ix. MAINTAIN TDAFP (PAL02) OPERABLE.
- x. Implement 10 CFR 50.65(a)(4) fire-specific RMA's as required.
2 Risk Management Action Examples E12-7 C. Turbine Driven Aux Feed Pump (PAL02) OOS:
- 1. Actions to increase risk awareness and control.
- i. For Risk Management Actions established during the current shift:
MAKE a plant announcement of the Risk Management Actions established.
In the Control Room narrative log, RECORD the time Risk Management Actions are established and EITHER of the following:
- a. A list of all Risk Management Actions implemented.
- b. A reference to the applicable section of the procedure including any exceptions or additions.
ii. Risk Management Actions established for the scheduled work that will extend into the next shift will be listed on the Shift Manager Operational Focus Items.
iii. ENSURE shift and plant briefs address any risk assessment resulting in a yellow, orange or red status.
iv. ENSURE shift and plant briefs address any Risk Management Actions which are to be performed during the shift.
- v. ENSURE door postings per Checklist 9, Placing Postings for TDAFP (PAL02) being Out of Service.
vi. Perform a walkdown of and confirm availability of applicable suppression, detection and fire barriers for the following Fire Walk down areas:
YD-1 (C&S): Circ and Service Building.
C-27 (3601): Not required, The Control Room is continuously occupied and adjacent areas share HVAC, thus prompt manual detection is assumed.
vii. For the above Fire Walk down areas, minimize the accumulation of transient combustibles in accordance with the station Fire Protection Program.
- 2. Actions to reduce the duration of maintenance activities.
- i. For preplanned RICT entry, creation of a sub schedule (fragnet) related to the specific evolution which is reviewed for personnel resource availability.
ii. Confirmation of parts availability prior to entry into a preplanned RICT.
- 3. Actions to minimize the magnitude of the risk increase
- i. NO unscheduled safety work without performing a risk assessment per EDP-ZZ-01129, Callaway Energy Center Risk Assessment.
ii. FOLLOW established fragnets.
iii. Only allow necessary switchyard work that has been evaluated for risk with necessary controls and mitigating actions established.
iv. MINIMIZE loose items in switchyard that could become airborne/missile hazards in high winds. ENSURE such items are properly secured or stored WHEN NOT being used. (Reference OTO-ZZ-00012, Severe Weather.)
2 Risk Management Action Examples E12-8
- v. IF TDAFP (PAL02) is NONFUNCTIONAL, MAINTAIN NSAFP (PAP01) as protected and posted in accordance with ODP-ZZ-00002 Appendix 1, Protected Equipment Program.
vi. DO NOT allow work on Alternate Emergency Power System (AEPS) system.
vii. LIMIT access to the AEPS Diesel Generators to just Operations and Security Personnel.
viii. DO NOT allow work on Security Diesel.
ix. MAINTAIN three of four AEPS Diesel Generators FUNCTIONAL.
- x. Implement 10 CFR 50.65(a)(4) fire-specific RMA's as required.
7.0 REFERENCES
- 1. U.S. Nuclear Regulatory Commission (NRC) Letter from Jennifer M. Golder to Biff Bradley (Nuclear Energy Institute [NEI]), Final Safety Evaluation for Nuclear Energy Institute (NEI) Topical Report (TR) NEI 06-09, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS)
Guidelines, May 17, 2007 (ADAMS Accession No. ML071200238).
- 2. Nuclear Energy Institute (NEI) Topical Report NEI 06-09-A, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines, Revision 0, October 12, 2012 (ADAMS Accession No. ML12286A322).
- 3. NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making, Revision 1, U.S. Nuclear Regulatory Commission, March 2017 (ADAMS Accession No. ML17062A466).
- 4. EPRI TR-1026511, Practical Guidance on the Use of Probabilistic Risk Assessment in Risk-Informed Applications with a Focus on the Treatment of Uncertainty, Technical Update, Electric Power Research Institute (EPRI),
December 2012.
- 5. TSTF-505-A, Revision 2, Technical Specifications Task Force Improved Standard Technical Specifications Change Traveler, November 2018.
- 6. Southern Nuclear letter to NRC, Vogtle Electric Generating Plant, Units 1 and 2 Response to Request for Additional Information on Technical Specifications Change to Adopt Risk Informed Completion Times, April 14, 2017 (ADAMS Accession No. ML17108A253).
- 7. CEC Procedure, ODP-ZZ-00002, APP 2, "Risk Management Actions for Planned Risk Significant Activities", Revision 019.
- 8. CEC Procedure, ODP-ZZ-00002, APP 3, "Risk Management Actions for Fire Risk Systems and Components", Revision 003.
- 9. CEC Procedure, APA-ZZ-00315, "Configuration Risk Management Program",
Revision 015.