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| | issue date = 04/26/2011 | | | issue date = 04/26/2011 |
| | title = Draft Request for Additional Information EAL Upgrade | | | title = Draft Request for Additional Information EAL Upgrade |
| | author name = Johnson D A | | | author name = Johnson D |
| | author affiliation = NRC/NSIR | | | author affiliation = NRC/NSIR |
| | addressee name = Williams L L | | | addressee name = Williams L |
| | addressee affiliation = Energy Northwest | | | addressee affiliation = Energy Northwest |
| | docket = 05000397 | | | docket = 05000397 |
| | license number = NPF-021 | | | license number = NPF-021 |
| | contact person = Thadani M C, NRR/DLPM, 415-1476 | | | contact person = Thadani M, NRR/DLPM, 415-1476 |
| | case reference number = TAC ME4589 | | | case reference number = TAC ME4589 |
| | package number = ML112070405 | | | package number = ML112070405 |
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| {{#Wiki_filter:Columbia Generating Station U.S. Nuclear Regulatory Commission Request for Additional Information (RAI) Emergency Action Level Scheme Change to NEI 99-01, Revision 5 Format DRAFT RAI # EAL Question 1 General Due to recurring issues within the industry, please confirm that all stated values, set points, and indications provided are within the calibrated range of the applicable instrumentation and that the instrumentation is appropriate for the specific EAL. | | {{#Wiki_filter:Columbia Generating Station U.S. Nuclear Regulatory Commission Request for Additional Information (RAI) |
| | Emergency Action Level Scheme Change to NEI 99-01, Revision 5 Format DRAFT RAI # EAL Question Due to recurring issues within the industry, please confirm that all stated values, set points, and indications provided are within the 1 General calibrated range of the applicable instrumentation and that the instrumentation is appropriate for the specific EAL. |
| | Please provide documentation on the two new 618-11 site-specific Emergency Action Levels that were approved for addition to the 2 General site emergency plan as outlined in License Amendment No.218 in response to the licensees application dated April 28, 2010. |
| | This section does not contain information on the treatment of Section 2.0 multiple events and classification upgrading as outlined in the 3 |
| | Discussion endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance. |
| | Initiating Condition lists Unexpected rise in plant radiation which is inconsistent with the endorsed guidance that lists this Initiating 4 RU2.1 Condition as Unplanned rise in plant radiation. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance. |
| | Initiating Condition in Technical Bases document lists Unexpected rise in plant radiation which is inconsistent with the endorsed 5 RU2.2 guidance that lists this Initiating Condition as Unplanned rise in plant radiation. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance. |
| | Emergency Action Level lists Any unexplained RPV leakage indication, Table C-1 which is inconsistent with the endorsed 6 CG3.2 guidance that lists this EAL as Unplanned level rise in (site specific sump or tank). Please provide justification for this inconsistency, or revise accordingly per endorsed guidance. |
| | The Emergency Action Level states, Multi Purpose Container (MPC) CONFINEMENT BOUNDRY breach. As worded this EAL would require an actual breach of the boundary versus damage to 7 EU1.1 the confinement boundary for EAL declaration. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance. |
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| 2 General Please provide documentation on the two new 618-11 site-specific Emergency Action Levels that were approved for addition to the site emergency plan as outlined in License Amendment No.218 in response to the licensee's application dated April 28, 2010.
| | Columbia Generating Station U.S. Nuclear Regulatory Commission Request for Additional Information (RAI) |
| 3 Section 2.0 Discussion This section does not contain information on the treatment of multiple events and classification upgrading as outlined in the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
| | Emergency Action Level Scheme Change to NEI 99-01, Revision 5 Format DRAFT Clarify if Table C-4/S-2, Communications Systems, includes the CU5.1 8 Health Physics Network, communication systems as required by SU6.1 the endorsed guidance. |
| 4 RU2.1 Initiating Condition lists "Unexpected rise in plant radiation" which is inconsistent with the endorsed guidance that lists this Initiating Condition as "Unplanned rise in plant radiation". Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
| | HU1.4 HU2.1 HA1.2 Table H-1 uses the term in vicinity of associated with the 9 HA1.4 referenced structures which is inconsistent with endorsed HA1.3 guidance. Please provide justification for this inconsistency, or HA1.5 revise accordingly per endorsed guidance. |
| 5 RU2.2 Initiating Condition in Technical Bases document lists "Unexpected rise in plant radiation" which is inconsistent with the endorsed guidance that lists this Initiating Condition as "Unplanned rise in plant radiation". Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
| | HA2.1 HA3.1 Clarify the process / instrumentation used to perform the calculation to subtract reactor building closed cooling water from 10 SU8.1 the unidentified leakage total and the timeliness of this process. |
| 6 CG3.2 Emergency Action Level lists "Any unexplained RPV leakage indication, Table C-1 which is inconsistent with the endorsed guidance that lists this EAL as "Unplanned level rise in" (site specific sump or tank). Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
| | The Initiating Condition uses the term Security Defined Owner IC HA4 Controlled Area which is inconsistent with the endorsed guidance. |
| 7 EU1.1 The Emergency Action Level states, "Multi Purpose Container (MPC) CONFINEMENT BOUNDRY breach". As worded this EAL would require an actual breach of the boundary versus damage to the confinement boundary for EAL declaration. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
| | 11 Please provide justification for this inconsistency, or revise EAL HA4.1 accordingly per endorsed guidance. |
| | | : 1. Fuel Clad Barrier L.1 lists PC flooding required (SAG entry) due to either: which is inconsistent with the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance |
| Columbia Generating Station U.S. Nuclear Regulatory Commission Request for Additional Information (RAI) Emergency Action Level Scheme Change to NEI 99-01, Revision 5 Format DRAFT 8 CU5.1 SU6.1 Clarify if Table C-4/S-2, Communications Systems, includes the Health Physics Network, communication systems as required by the endorsed guidance. | | : 2. Containment Barrier PL.1 lists PC flooding required (SAG Fission entry) due to either: and lists two entry requirements which 12 Product is inconsistent with the endorsed guidance. Please provide Barrier justification for this inconsistency, or revise accordingly per Matrix endorsed guidance. |
| | | : 3. Containment Barrier L.3 removed the endorsed guidance wording after primary containment isolation signal which is inconsistent with the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.}} |
| 9 HU1.4 HU2.1 HA1.2 HA1.4 HA1.3 HA1.5 HA2.1 HA3.1 Table H-1 uses the term "in vicinity of" associated with the referenced structures which is inconsistent with endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
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| 10 SU8.1 Clarify the process / instrumentation used to perform the calculation to subtract reactor building closed cooling water from the unidentified leakage total and the timeliness of this process.
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| 11 IC HA4 EAL HA4.1 The Initiating Condition uses the term "Security Defined Owner Controlled Area" which is inconsistent with the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
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| 12 Fission Product Barrier Matrix 1. Fuel Clad Barrier L.1 lists "PC flooding required (SAG entry) due to either:" which is inconsistent with the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance
| |
| : 2. Containment Barrier PL.1 lists "PC flooding required (SAG entry) due to either:" and lists two entry requirements which is inconsistent with the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance. | |
| : 3. Containment Barrier L.3 removed the endorsed guidance wording "after primary containment isolation signal" which is inconsistent with the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.}} | |
Letter Sequence Draft RAI |
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Category:Request for Additional Information (RAI)
MONTHYEARML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection ML22343A1802022-12-0808 December 2022 February 2023 Emergency Preparedness Program Inspection - Request for Information ML22301A1432022-10-28028 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Adopt TSTF-505 - EPID L-2022-LLA-0023 ML22242A1082022-08-30030 August 2022 Information Request, Information Request, Security IR 2022404 ML22235A1052022-08-22022 August 2022 August 2022 Emergency Preparedness Exercise Inspection Request for Information ML22145A4462022-06-0606 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000397/2022401 ML22144A0342022-05-18018 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22041A4572022-02-10010 February 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000397/2022010) and Request for Information ML21277A3572021-10-12012 October 2021 CGS Brq RFI Letter, Columbia Generating Station - Notification of Inspection (NRC Inspection Report 05000397/2021004) and Request for Information ML21216A0502021-08-0303 August 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia - License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO EPID L-2021-LLA-0259 ML21209A9792021-07-28028 July 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35) - EPID L-2021-LLA-0074 ML21120A1182021-04-30030 April 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - On-Site Cooling System Sediment Disposal Approval Request - EPID L-2020-LLL-0031 ML21068A2842021-03-0404 March 2021 2021002 Inservice Inspection (ISI) Request for Information (RFI) ML20336A1852020-11-30030 November 2020 NRR E-mail Capture - Final - RAI - Columbia - One -Time Exemption from 10 CFR 73, App B, Sect VI, Subsection C.3.(l)(1) Regarding Annual Force-On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172 ML20325A0402020-11-19019 November 2020 NRR E-mail Capture - Draft - RAI - Columbia - One -Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force -On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172 ML20267A5162020-09-23023 September 2020 NRR E-mail Capture - Columbia Generating Station - Final - Request for Additional Information - Fourth Ten-Year Interval Inservice Inspection (ISI) Program Relief Request 4ISI-09 - EPID L-2020-LLR-0068 ML20245E2822020-08-31031 August 2020 NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time ML20239A9702020-08-26026 August 2020 NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time ML20149K4362020-05-26026 May 2020 NRR E-mail Capture - Formal RAIs for Columbia (COVID-19) QA Plan Change Surveillance, Request Response by Tuesday June 2, 2020 ML20112F4572020-04-21021 April 2020 NRR E-mail Capture - Official Release of NRC RAIs for Columbia Covid Exigent Due Friday April 24, 2020 ML20034E6082020-02-0303 February 2020 NRR E-mail Capture - RAI Formal Release Columbia TSTF 563 LAR, 30 Day Response Period Due March 3, 2020 ML20028E1512020-01-27027 January 2020 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000397/2020002) and Request for Information ML19267A1842019-09-24024 September 2019 Request for Information for Upcoming Open Phase Condition Inspection at Columbia Generating Station ML19232A2282019-08-20020 August 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Columbia Exigent Amendment - One Electrical RAI, ML19183A4752019-07-0202 July 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Columbia HVAC LAR L-2019-LLA-0034 ML18088A0152018-03-29029 March 2018 Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment Plans (05000397/2018010) and Request for ML17341B0272017-12-0707 December 2017 NRR E-mail Capture - RAI Associated with Columbia Amendment Request Revise Tech Spec 5.5.12 for Permanent Extension of Type a and Type C Containment Testing Frequencies for MF9469, EPID: L-2017-LLA-0197, ILRT, LLRT LAR - New RAI Response Da ML17292A0572017-10-18018 October 2017 NRR E-mail Capture - New RWCU RAI Due Date Now November 24, 2017 ML17249A6882017-09-0606 September 2017 NRR E-mail Capture - RAIs for Columbia Relief Request RAI (MF8925), 3ISI-19 ML17205A3152017-07-20020 July 2017 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000397/2017004) and Request for Information ML17193A2192017-07-12012 July 2017 NRR E-mail Capture - Columbia RWCU LAR MF8318, Formal Release of RAIs ML17144A1702017-05-24024 May 2017 NRR E-mail Capture - NRC RAIs for Columbia Relief Request MF8922, 3ISI-16 ML17047A7492017-02-16016 February 2017 Response to Request for Additional Information, Columbia Mur LAR Evib Rais ML17006A0922017-01-0404 January 2017 NRR E-mail Capture - Eicb RAIs for Columbia Mur ML17006A0902017-01-0404 January 2017 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate ML16356A1382016-12-21021 December 2016 NRR E-mail Capture - Columbia Mur LAR Evib RAIs Non - Proprietary Version - Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate ML16342C4322016-12-0707 December 2016 NRR E-mail Capture - Columbia Measurement Uncertainty Recapture Power Uprate LAR Rais: Human Performance: MF8060, Formal Release for Response on Monday January 9, 2017 ML16327A1842016-11-22022 November 2016 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate ML16323A1192016-11-16016 November 2016 NRR E-mail Capture - Eicb RAIs for Columbia Mur ML16218A3902016-08-0808 August 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Request for Measurement Uncertainty Recapture (Mur) Power Uprate (from 3486 Mwt to 3544 Mwt) ML16194A3702016-07-11011 July 2016 Notification of NRC Triennial Heat Sink Performance Inspection 05000397/2016003 and Request for Information ML16069A3592016-03-0909 March 2016 NRR E-mail Capture - Second Round Rais: Columbia MF6042 LAR TSTF-425 ML16061A5542016-03-0101 March 2016 Notification of NRC Design Bases Inspection (05000397/2016007) and Initial Request for Information ML16061A5662016-03-0101 March 2016 Notification of Design Bases Inspection (Programs)(Inspection Report 05000397/2016008) and Initial Request for Information ML15254A2572015-09-16016 September 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1 Seismic Reevaluations ML15215A0432015-08-18018 August 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations ML14262A3412014-09-24024 September 2014 Request for Additional Information, Round 2, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High ML14192B0312014-08-13013 August 2014 Redacted, Request for Additional Information, Nrr/Dss/Scvb, Request to Modify Emergency Core Cooling Systems Surveillance Requirements for Low Pressure Core Spray and Low Pressure Coolant Injection Pump Flows ML14206A0112014-07-31031 July 2014 Request for Additional Information, License Amendment Request to Revise TS Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High 2024-01-10
[Table view] |
Text
Columbia Generating Station U.S. Nuclear Regulatory Commission Request for Additional Information (RAI)
Emergency Action Level Scheme Change to NEI 99-01, Revision 5 Format DRAFT RAI # EAL Question Due to recurring issues within the industry, please confirm that all stated values, set points, and indications provided are within the 1 General calibrated range of the applicable instrumentation and that the instrumentation is appropriate for the specific EAL.
Please provide documentation on the two new 618-11 site-specific Emergency Action Levels that were approved for addition to the 2 General site emergency plan as outlined in License Amendment No.218 in response to the licensees application dated April 28, 2010.
This section does not contain information on the treatment of Section 2.0 multiple events and classification upgrading as outlined in the 3
Discussion endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
Initiating Condition lists Unexpected rise in plant radiation which is inconsistent with the endorsed guidance that lists this Initiating 4 RU2.1 Condition as Unplanned rise in plant radiation. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
Initiating Condition in Technical Bases document lists Unexpected rise in plant radiation which is inconsistent with the endorsed 5 RU2.2 guidance that lists this Initiating Condition as Unplanned rise in plant radiation. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
Emergency Action Level lists Any unexplained RPV leakage indication, Table C-1 which is inconsistent with the endorsed 6 CG3.2 guidance that lists this EAL as Unplanned level rise in (site specific sump or tank). Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
The Emergency Action Level states, Multi Purpose Container (MPC) CONFINEMENT BOUNDRY breach. As worded this EAL would require an actual breach of the boundary versus damage to 7 EU1.1 the confinement boundary for EAL declaration. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.
Columbia Generating Station U.S. Nuclear Regulatory Commission Request for Additional Information (RAI)
Emergency Action Level Scheme Change to NEI 99-01, Revision 5 Format DRAFT Clarify if Table C-4/S-2, Communications Systems, includes the CU5.1 8 Health Physics Network, communication systems as required by SU6.1 the endorsed guidance.
HU1.4 HU2.1 HA1.2 Table H-1 uses the term in vicinity of associated with the 9 HA1.4 referenced structures which is inconsistent with endorsed HA1.3 guidance. Please provide justification for this inconsistency, or HA1.5 revise accordingly per endorsed guidance.
HA2.1 HA3.1 Clarify the process / instrumentation used to perform the calculation to subtract reactor building closed cooling water from 10 SU8.1 the unidentified leakage total and the timeliness of this process.
The Initiating Condition uses the term Security Defined Owner IC HA4 Controlled Area which is inconsistent with the endorsed guidance.
11 Please provide justification for this inconsistency, or revise EAL HA4.1 accordingly per endorsed guidance.
- 1. Fuel Clad Barrier L.1 lists PC flooding required (SAG entry) due to either: which is inconsistent with the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance
- 2. Containment Barrier PL.1 lists PC flooding required (SAG Fission entry) due to either: and lists two entry requirements which 12 Product is inconsistent with the endorsed guidance. Please provide Barrier justification for this inconsistency, or revise accordingly per Matrix endorsed guidance.
- 3. Containment Barrier L.3 removed the endorsed guidance wording after primary containment isolation signal which is inconsistent with the endorsed guidance. Please provide justification for this inconsistency, or revise accordingly per endorsed guidance.