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| {{#Wiki_filter:March 4, 2013 | | {{#Wiki_filter:March 4, 2013 |
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| Technical Specifications Task Force (TSTF) 11921 Rockville Pike, Suite 100 Rockville, MD 20852 | | Technical Specifications Task Force (TSTF) 11921 Rockville Pike, Suite 100 |
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| | Rockville, MD 20852 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION RE: TRAVELER TSTF-537, REVISION 0, "INCREASE CIV [CONTAINMENT ISOLATION VALVE] | | REQUEST FOR ADDITIONAL INFORMATION RE: TRAVELER TSTF-537, REVISION 0, "INCREASE CIV [CONTAINMENT ISOLATION VALVE] |
| COMPLETION TIME; UPDATE OF TSTF-373" (TAC NO. ME8311) | | COMPLETION TIME; UPDATE OF TSTF-373" (TAC NO. ME8311) |
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| ==Dear Members of the TSTF:== | | ==Dear Members of the TSTF:== |
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| By letter dated March 27, 2012 (Agencywide Documents Access and Management System Accession No. ML12087A274), the TSTF submitted for U.S. Nuclear Regulatory Commission (NRC) staff review Traveler TSTF-537, Revision 0, "Increase CIV Completion Time; Update of TSTF-373." Upon review of the information provided, the NRC staff has determined that additional information is needed to complete the review. On February 14, 2013, Brian Mann, Vice President of Industry Programs, EXCEL Services Corporation, and I agreed that the NRC staff will receive your response to the enclosed request for additional information (RAI) questions within 90 days of the date of this letter. If you have any questions regarding the enclosed RAI questions, please contact me at 301-415-1774 or via e-mail at Michelle.Honcharik@nrc.gov. | | By letter dated March 27, 2012 (Agencywide Documents Access and Management System Accession No. ML12087A274), the TSTF submitted for U.S. Nuclear Regulatory Commission (NRC) staff review Traveler TSTF-537, Revision 0, "Increase CIV Completion Time; Update of TSTF-373." Upon review of the information provided, the NRC staff has determined that additional information is needed to complete the review. On February 14, 2013, Brian Mann, Vice President of Industry Programs, EXCEL Services Corporation, and I agreed that the NRC staff will receive your response to the enclosed request for additional information (RAI) questions within 90 days of the date of this letter. If you have any questions regarding the enclosed RAI questions, please contact me at 301-415-1774 or via e-mail at Michelle.Honcharik@nrc.gov. |
| Sincerely, /RA/ Michelle C. Honcharik, Sr. Project Manager Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation | | Sincerely, /RA/ Michelle C. Honcharik, Sr. Project Manager Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encl: See next page | | As stated |
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| | cc w/encl: See next page |
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| ML13045A860; *concurred via memo (ML122280730); *concurred via e-mail NRR-106 OFFICE PLPB/PM PLPB/LA APLA/BC PLPB/BC STSB/BC PLPB/PM NAME MHoncharik DBaxley DHarrison* AMendiola RElliott MHoncharik* DATE 02/14/2013 02/21/2013 02/05/2013 02/25/2013 02/28/2013 03/04/2013 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION TRAVELER TSTF-537, REVISION 0, "INCREASE CIV [CONTAINMENT ISOLATION VALVE] COMPLETION TIME; UPDATE OF TSTF-373" TECHNICAL SPECTIFICATIONS TASK FORCE (TSTF) PROJECT NO. 753 1. The U.S. Nuclear Regulatory Commission's (NRC's) safety evaluation (SE) of the Combustion Engineering Owners' Group (CEOG) Joint Application Report (JAR) | | ML13045A860; *concurred via memo (ML122280730); *concurred via e-mail NRR-106 OFFICE PLPB/PM PLPB/LA APLA/BC PLPB/BC STSB/BC PLPB/PM NAME MHoncharik DBaxley DHarrison* AMendiola RElliott MHoncharik* DATE 02/14/2013 02/21/2013 02/05/2013 02/25/2013 02/28/2013 03/04/2013 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION TRAVELER TSTF-537, REVISION 0, "INCREASE CIV [CONTAINMENT ISOLATION VALVE] |
| Combustion Engineering (CE) NPSD-1168-1, "Joint Applications Report for Containment Isolation Valve AOT [Allowed Outage Time] Extension," January 2001, available in the Agencywide Documents Access and Management System (ADAMS) as Accession No. ML003721663 states: We agree with the CEOG findings that, based on the use of bounding risk parameters for CE designed plants, the proposed increase in containment isolation valve (CIV) AOT from 4 hours to 7 days does not result in an unacceptable incremental conditional core damage probability (ICCDP) or incremental conditional large early release probability (ICLERP) according to the criteria of Regulatory Guide 1.177 when the items identified below are acceptably addressed by individual licensees referencing this report in plant-specific submittals. Given that the topical report was completed a while ago, assess whether the bounding risk parameters may still be considered bounding or not, and provide the basis for your conclusion. In addition, since generic unreliability and unavailability data can change over a long period of time, discuss whether CIV performance based on data since the completion of the JAR is consistent with assumptions made in the supporting JAR analyses, and provide the basis for the conclusions. 2. TSTF-537 notes that the JAR identified three sets of valves to which the revised completion time (CT) will not apply. This includes containment sump supply valves to the emergency core cooling systems and containment spray system pumps, valves associated with the main feedwater system, and main steam isolation valves. Please clarify how the proposed Standard Technical Specification (STS) 3.6.3 precludes the application of the extended CT to the main feedwater valves and main steam isolation valves. 3. TSTF-537 proposes to address common cause failures with Required Action B.1. Required Action B.1 should require verification that the redundant CIVs in a penetration flow path are not rendered inoperable due to reasons besides common cause failure prior to exceeding the existing 4-hour CT. Since redundant CIVs may fail due to common cause or other reasons, how does TSTF-537 ensure operability of the redundant CIVs for reasons other than common cause failure prior to entering the extended CT? 4. Condition E of TSTF-537 includes a change in the CT from 72 hours to 7 days. This had been proposed in TSTF-373, Revision 2, previously under Condition D. The bases for "Required Actions" E.1 and E.2 provide criteria for penetrations: Penetration flow paths eligible for application of the 7 day Completion Time meet the following criteria: | | COMPLETION TIME; UPDATE OF TSTF-373" TECHNICAL SPECTIFICATIONS TASK FORCE (TSTF) |
| | PROJECT NO. 753 |
| | : 1. The U.S. Nuclear Regulatory Commission |
| | 's (NRC's) safety evaluation (SE) of the Combustion Engineering Owners' Group (CEOG) Joint Application Report (JAR) |
| | Combustion Engineering (CE) |
| | NPSD-1168-1, "Joint Applications Report for Containment Isolation Valve AOT [Allowed Outage Time] Extension," January 2001, available in the Agencywide Documents Access and Management System (ADAMS) as Accession No. ML003721663 states: |
| | We agree with the CEOG findings that, based on the use of bounding risk parameters for CE designed plants, the proposed increase in containment isolation v alve (CIV) AOT from 4 hours to 7 days does not result in an unacceptable incremental conditional core damage probability (ICCDP) or incremental conditional large early release probability (ICLERP) according to the criteria of Regulatory Guide 1.177 when the items identified below are acceptably addressed by individual licensees referencing this report in plant-specific submittals. |
| | Given that the topical report was completed a while ago, assess whether the bounding risk parameters may still be considered bounding or not, and provide the basis for your conclusion. In addition, since generic unreliability and unavailability data can change over a long period of time, discuss whether CIV performance based on data since the completion of the JAR is consistent with assumptions made in the supporting JAR analyses, and provide the basis for the conclusions. |
| | : 2. TSTF-537 notes that the JAR identified three sets of valves to which the revised completion time (CT) will not apply. This includes containment sump supply valves to the emergency core cooling systems and containment spray system pumps, valves associated with the main feedwater system, and main steam isolation valves. Please clarify how the proposed Standard Technical Specification (STS) 3.6.3 precludes the application of the extended CT to the main feedwater valves and main steam isolation valves. |
| | : 3. TSTF-537 proposes to address common cause failures with Required Action B.1. Required Action B.1 should require verification that the redundant CIVs in a penetration flow path are not rendered inoperable due to reasons besides common cause failure prior to exceeding the existing 4-hour CT. Since redundant CIVs may fail due to common cause or other reasons, how does TSTF-537 ensure operability of the redundant CIVs for reasons other than common cause failure prior to entering the extended CT? |
| | : 4. Condition E of TSTF-537 includes a change in the CT from 72 hours to 7 days. This had been proposed in TSTF-373, Revision 2, previously under Condition D. |
| | The bases for "Required Actions" E.1 and E.2 provide criteria for penetrations: |
| | Penetration flow paths eligible for application of the 7 day Completion Time meet the following criteria: |
| * Containment isolation valves in penetrations connected to nonessential containment cooling systems; | | * Containment isolation valves in penetrations connected to nonessential containment cooling systems; |
| * The closed system piping inside containment is seismically qualified; and, | | * The closed system piping inside containment is seismically qualified; and, |
| * Containment isolation valves in the penetration flow paths are air operated valves designed to fail in the closed position and are designed to close automatically by an engineered safety feature actuation system (ESFAS) signal. a. Please indicate in which supporting documentation these criteria are discussed. b. What is meant by a nonessential containment cooling system? 5. Section 2.3, "Verification and Commitments," of the model application does not mention the following important considerations in the licensee's submittal for this Traveler: a. Regulatory Guide (RG) 1.174 for probabilistic risk assessment quality considerations, and other information for risk-informed considerations. b. Licensees adopting this Traveler must confirm plant-specific implementation and monitoring in accordance with the guidance in RG 1.174 and RG 1.177; c. Plant-specific Tier 3 information must be provided in submittals; d. The Tier 3 Configuration Risk Management Program (CRMP) enhancement to include large early release frequency (LERF) and ICLERP is not mentioned; rather, line item Number 4 requests licensees to commit to "implementing methodologies." A licensee's CRMP, including those implemented under the maintenance rule 10 CFR 50.65(a)(4), must be enhanced to include a LERF/ICLERP assessment. This assessment must be documented in a regulatory commitment in the plant-specific application. e. Plant-specific applicability of Tier 2 analysis; f. The licensee considers specific penetrations consistent with those analyzed, and provides a plant-specific analysis for configurations not addressed by the groups described in CE NPSD-1168-A; g. Licensees provide supporting information that verifies that a penetration remains intact during maintenance activities, including corrective maintenance; h. Licensees must confirm that the action of locking open a subject CIV will not result in the design basis technical specification leakage being exceeded; i. For external events, in performing the plant-specific analyses, credit for physical barrier integrity outside containment can only be given for seismically qualified piping; and, j. Evaluation of cumulative risk on a plant-specific basis consistent with RG 1.174. | | * Containment isolation valves in the penetration flow paths are air operated valves designed to fail in the closed position and are designed to close automatically by an engineered safety feature actuation system (ESFAS) signal. a. Please indicate in which supporting documentation these criteria are discussed. |
| | : b. What is meant by a nonessential containment cooling system? |
| | : 5. Section 2.3, "Verification and Commitments," of the model application does not mention the following important considerations in the licensee's submittal for this Traveler: |
| | : a. Regulatory Guide (RG) 1.174 for probabilistic risk assessment quality considerations, and other information for risk-informed considerations. |
| | : b. Licensees adopting this Traveler must confirm plant-specific implementation and monitoring in accordance with the guidance in RG 1.174 and RG 1.177; |
| | : c. Plant-specific Tier 3 information must be provided in submittals; |
| | : d. The Tier 3 Configuration Risk Management Program (CRMP) enhancement to include large early release frequency (LERF) and ICLERP is not mentioned; rather, line item Number 4 requests licensees to commit to "implementing methodologies." A licensee's CRMP, including those implemented under the maintenance rule 10 CFR 50.65(a)(4), must be enhanced to include a LERF/ICLERP assessment. This assessment must be documented in a regulatory commitment in the plant-specific application. e. Plant-specific applicability of Tier 2 analysis; |
| | : f. The licensee considers specific penetrations consistent with those analyzed, and provides a plant-specific analysis for configurations not addressed by the groups described in CE NPSD-1168-A; |
| | : g. Licensees provide supporting information that verifies that a penetration remains intact during maintenance activities, including corrective maintenance; |
| | : h. Licensees must confirm that the action of locking open a subject CIV will not result in the design basis technical specification leakage being exceeded; |
| | : i. For external events, in performing the plant-specific analyses, credit for physical barrier integrity outside containment can only be given for seismically qualified piping; and, j. Evaluation of cumulative risk on a plant-specific basis consistent with RG 1.174. |
| Technical Specifications Task Force Project No. 753 cc: | | Technical Specifications Task Force Project No. 753 cc: |
| Technical Specifications Task Force 11921 Rockville Pike Suite 100 Rockville, MD 20852 Attention: Donald R. Hoffman E-mail: donaldh@excelservices.com Robert A. Slough Comanche Peak Nuclear Power Plant P. O. Box 1002, Mail Code A08 Glen Rose, Texas 76043 E-mail: robert.slough@luminant.com Roy A. (Tony) Browning Duane Arnold Energy Center 3277 DAEC Rd. PSC/Licensing Palo, IA 52324-9785 E-mail: Tony.Browning@nexteraenergy.com | | Technical Specifications Task Force 11921 Rockville Pike |
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| | Suite 100 |
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| | Rockville, MD 20852 Attention: Donald R. Hoffman E-mail: donaldh@excelservices.com Robert A. Slough Comanche Peak Nuclear Power Plant P. O. Box 1002, Mail Code A08 |
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| | Glen Rose, Texas 76043 E-mail: robert.slough@luminant.com |
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| | Roy A. (Tony) Browning Duane Arnold Energy Center 3277 DAEC Rd. |
| | PSC/Licensing Palo, IA 52324-9785 E-mail: Tony.Browning@nexteraenergy.com |
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| | Wendy E. Croft |
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| | Exelon Nuclear 200 Exelon Way, Suite 340 Kennett Square, PA 19348 E-mail: Wendi.Croft@exeloncorp.com |
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| | Otto W. Gustafson Entergy Nuclear Operations, Inc. Palisades Nuclear Power Plant 27780 Blue Star Memorial Highway Covert, MI 49043 |
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| | E-mail: ogustaf@entergy.com |
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| | Brian D. Mann EXCEL Services Corporation 11921 Rockville Pike, Suite 100 |
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| Wendy E. Croft Exelon Nuclear 200 Exelon Way, Suite 340 Kennett Square, PA 19348 E-mail: Wendi.Croft@exeloncorp.com
| | Rockville, MD 20852 |
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| Otto W. Gustafson Entergy Nuclear Operations, Inc. Palisades Nuclear Power Plant 27780 Blue Star Memorial Highway Covert, MI 49043 E-mail: ogustaf@entergy.com Brian D. Mann EXCEL Services Corporation 11921 Rockville Pike, Suite 100 Rockville, MD 20852 E-mail: brianm@excelservices.com}}
| | E-mail: brianm@excelservices.com}} |
Letter Sequence RAI |
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TAC:ME8311, Increase CIV Completion Time from 72 Hours to 7 Days (NPSD-1168), Increase CIV Completion Time - Update of TSTF-373 (Open) |
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Category:Letter
MONTHYEARML24106A2762024-08-0101 August 2024 Draft Safety Evaluation of Technical Specifications Task Force Traveler TSTF-576, Revision 3, “Revise Safety/Relief Valve Requirements” (EPID L -2019-PMP-0207) ML24207A1822024-07-25025 July 2024 TSTF-601, Extend Shield Building Completion Time After Refueling, Acceptance Review Letter ML24114A2572024-04-24024 April 2024 TSTF-599 Acceptance Review Letter ML24114A2652024-04-24024 April 2024 TSTF-597 Acceptance Review Letter ML23325A2132023-12-18018 December 2023 Cover Letter for Final Model SE of TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML23262B2292023-09-21021 September 2023 Cover Letter Transmitting Final SE of TSTF-591, Revision 0, Revise Risk-Informed Completion Time (RICT) Program ML23124A2212023-09-11011 September 2023 Cover Letter for Final SEs of TSTF-589, Eliminate Automatic Diesel Generator (DG) Start During Shutdown ML23206A1242023-07-31031 July 2023 TSTF-584 Cover Letter for Final SE ML23205A2342023-07-0606 July 2023 Draft TSTF-601, 'Extend Shield Building Completion Time After Refueling' ML23012A2812023-03-13013 March 2023 Draft SEs of TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation ML23059A3342023-02-28028 February 2023 TSTF-576 Open Issues Letter ML23010A2592023-01-11011 January 2023 Request for Additional Information Traveler TSTF-592, Revision 0, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML22272A5542022-10-0707 October 2022 Request for Additional Information Traveler TSTF-591, Revise Risk Informed Completion Time (RICT) Program TSTF-22-07, Transmittal of TSTF-592, Revision 0, Revise Automatic Depressurization System (ADS) Instrumentation Requirements2022-07-19019 July 2022 Transmittal of TSTF-592, Revision 0, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML22193A2372022-07-12012 July 2022 Request for Additional Information TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown TSTF-22-06, Technical Specifications Task Force - Request for a Workshop to Discuss the Interaction of Natural Phenomena Protection Design Features and Operability2022-07-0808 July 2022 Technical Specifications Task Force - Request for a Workshop to Discuss the Interaction of Natural Phenomena Protection Design Features and Operability ML22110A1712022-04-26026 April 2022 Acceptance for Review Regarding Traveler Tstf-584, Rev 0, Eliminate Automatic RWCU System Isolation on SLC Initiation TSTF-22-04, Technical Specifications Task Force - Transmittal of TSTF-591, Revision 0, Revise Risk Informed Completion Time (RICT) Program2022-03-22022 March 2022 Technical Specifications Task Force - Transmittal of TSTF-591, Revision 0, Revise Risk Informed Completion Time (RICT) Program ML21188A2782021-07-11011 July 2021 Cover Letter Transmitting Final SEs of CLIIP TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR (Residual Heat Removal) Shutdown Cooling TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 12021-06-23023 June 2021 TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1 ML21054A2512021-05-26026 May 2021 Cover Letter Transmitting Draft SEs of CLIIP TSTF-580, RHR Shutdown Cooling System - Hot Shutdown ML21106A2452021-04-20020 April 2021 Cover Letter Transmitting Final Model SE of TSTF 554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21098A2422021-04-14014 April 2021 Cover Letter for Final SEs of TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML21068A4012021-03-24024 March 2021 Cover Letter for Draft SEs TSTF 577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections TSTF-21-01, Transmittal of TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2021-01-26026 January 2021 Transmittal of TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML20322A3612020-12-18018 December 2020 TSTF-554 Cover Letter for Final SE ML20308A6562020-11-0606 November 2020 Request for Additional Information Traveler TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections ML20168A3962020-10-30030 October 2020 Cover Letter Transmitting Draft SE of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML20265A1152020-10-0909 October 2020 Cover Letter Transmitting Model SE of TSTF-582 and TSTF-583-T ML20133J8832020-07-29029 July 2020 Letter Transmitting Draft SE of Traveler TSTF-582, Revision 0, RPV WIC Enhancements TSTF-20-04, Technical Specifications Task Force - Transmittal of TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections2020-06-0808 June 2020 Technical Specifications Task Force - Transmittal of TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections ML20133J8152020-05-13013 May 2020 Letter Transmitting Revised Final SE of Traveler TSTF-564, Revision 2, Safety Limit MCPR, Using the Consolidated Line Item Improvement Process ML20132A1832020-05-11011 May 2020 Request for Additional Information TSTF-576, Revision 0, Revised Safety/Relief Valve Requirement TSTF-20-01, Transmittal of TSTF-IG-20-02, Guidance on Evaluating One-Time Surveillance Frequency Changes Under the Surveillance Frequency Control Program (TSTF-425M SFCP)2020-04-0909 April 2020 Transmittal of TSTF-IG-20-02, Guidance on Evaluating One-Time Surveillance Frequency Changes Under the Surveillance Frequency Control Program (TSTF-425M SFCP) TSTF-19-14, Technical Specifications Task Force - TSTF Response to NRC Questions on TSTF-582, RPV WIC Enhancements2020-02-12012 February 2020 Technical Specifications Task Force - TSTF Response to NRC Questions on TSTF-582, RPV WIC Enhancements TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements2020-01-16016 January 2020 TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements ML19325C4362019-12-17017 December 2019 Cover Letter Transmitting Final SEs of Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements2019-12-13013 December 2019 Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements ML19323E9282019-12-10010 December 2019 Cover Letter Transmitting Final SEs of Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position TSTF-19-13, Technical Specifications Task Force - Updated TSTF Membership and Distribution2019-12-0303 December 2019 Technical Specifications Task Force - Updated TSTF Membership and Distribution TSTF-19-12, TSTF Comments on Draft Safety Evaluations for Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position.2019-11-0505 November 2019 TSTF Comments on Draft Safety Evaluations for Traveler TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position. TSTF-19-10, Transmittal of Errata Changes to TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2019-08-28028 August 2019 Transmittal of Errata Changes to TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML19176A1892019-08-14014 August 2019 Cover Letter Transmitting Final Safety Evaluations of Traveler TSTF-569, Revision 2, Revise Response Time Testing Definition TSTF-19-03, Request for Fee Exemption for TSTF-554, Revision 0, Revise Reactor Coolant Leakage Requirements - Letter2019-07-0808 July 2019 Request for Fee Exemption for TSTF-554, Revision 0, Revise Reactor Coolant Leakage Requirements - Letter TSTF-19-08, Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements.2019-07-0303 July 2019 Draft of Traveler TSTF-582, Revision 0, RPV WIC Enhancements. TSTF-19-06, TSTF Comments on Draft Safety Evaluations for Traveler TSTF-569, Revision 1, Revise Response Time Testing Definition2019-06-25025 June 2019 TSTF Comments on Draft Safety Evaluations for Traveler TSTF-569, Revision 1, Revise Response Time Testing Definition TSTF-19-05, Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2019-06-18018 June 2019 Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position TSTF-19-07, TSTF Handout for October 16, 2019, Meeting: Elimination of Commitment to Adopt TSTF-4932019-06-18018 June 2019 TSTF Handout for October 16, 2019, Meeting: Elimination of Commitment to Adopt TSTF-493 ML19017A2222019-05-29029 May 2019 Letter Transmitting Draft Safety Evaluations of Technical Specifications Task Force Traveler TSTF-569, Revision 1, Revise Response Time Testing Definition ML19028A2852019-02-21021 February 2019 Final SEs of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems (Transmittal Letter) 2024-08-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23222A2272023-08-10010 August 2023 Request for Additional Information Traveler TSTF-592, Revision 1, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML23010A2592023-01-11011 January 2023 Request for Additional Information Traveler TSTF-592, Revision 0, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML22272A5542022-10-0707 October 2022 Request for Additional Information Traveler TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML22235A7382022-08-19019 August 2022 NRR E-mail Capture - Draft RAIs for TSTF-591 (L-2022-PMP-0003) ML22193A2372022-07-12012 July 2022 Request for Additional Information TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML21109A1352021-04-12012 April 2021 TSTF-576 NRC Comments on Draft Rev 1 and Draft RAI Response ML20308A6562020-11-0606 November 2020 Request for Additional Information Traveler TSTF-577, Revision 0, Revised Frequencies for Steam Generator Tube Inspections ML20132A1832020-05-11011 May 2020 Request for Additional Information TSTF-576, Revision 0, Revised Safety/Relief Valve Requirement ML20065J9902020-03-0505 March 2020 March 5 2020 TSTF Quarterly Meeting Handout, Agenda Item Iiib - Generic RAIs for LARs to Adopt TSTF-505 Rict ML19323D5342019-11-19019 November 2019 Draft RAIs TSTF-554, Revise Reactor Coolant Leakage ML18134A0752018-05-21021 May 2018 Request for Additional Information (RAI) Technical Specifications Task Force (TSTF) Traveler TSTF-569, Revise Response Time Testing Definition ML18127A4052018-05-0707 May 2018 Draft RAI TSTF-569, Revise Response Time Testing Definition. ML18122A1662018-04-27027 April 2018 Draft RAIs TSTF-568, Clarify Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3. ML18095A2292018-04-12012 April 2018 Request for Additional Information Traveler TSTF-564, Safety Limit MCPR ML18085A0252018-03-20020 March 2018 Traveler TSTF-564, Safety Limit MCPR, Draft RAIs ML18100A0942018-01-29029 January 2018 Draft RAIs from Apla TSTF-563, Revise Instrument Testing Definitions to Incorporate SFCP ML16215A1252016-08-0202 August 2016 Request for Additional Information for Technical Specifications Task Force TSTF-553, Revision 0, Add Action for Two Inoperable Control Room Emergency Air Temperature Control System Trains, CAC No. MF7061 ML16028A4532016-02-23023 February 2016 Request for Additional Information TSTF-553, Add Action for Two Inoperable Creatcs (Control Room Emergency Air Temperature Control System) Trains. ML15322A2842016-02-0404 February 2016 Request for Additional Information TSTF-537, Revision 0, Increase CIV Completion Time; Update of TSTF-373. ML15322A2702016-01-12012 January 2016 Request for Additional Information Regarding Traveler TSTF-454, Revision 3, Extend PCIV Completion Times (NEDC-33046). ML15293A1612015-12-0808 December 2015 Request for Additional Information (RAI) TSTF 542, Rev. 1, Reactor Pressure Vessel Water Inventory Control, ML15281A2912015-11-18018 November 2015 Request for Additional Information Regarding TSTF-551, Revision 1, Revise Secondary Containment Surveillance Requirements. ML15208A2872015-08-13013 August 2015 Request for Additional Information Traveler TSTF-541, Rev 0, Add Exceptions to Surveillance Requirements When the Safety Function Is Being Performed ML15033A1082015-06-0202 June 2015 Draft Request for Additional Information Traveler TSTF-529, Revision 2, Clarify Use and Application Rules TSTF-14-17, Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 32015-03-31031 March 2015 Technical Specification Task Force - Response to NRC Request for Additional Information Regarding TSTF-454, Revision, Extend PCIV Completion Times (NEDC-33046) and Submittal of TSTF-454, Revision 3 ML15057A2482015-02-26026 February 2015 Notice of Forthcoming Public Meeting Between the U.S. Nuclear Regulatory Commission and the Technical Specifications Task Force TSTF-551 ML14310A3442014-11-0606 November 2014 Draft RAI from Srxb TSTF-547, Clarification of Rod Position Requirements. ML14196A4142014-07-0707 July 2014 TSTF Handout from 7/10/14 Meeting TSTF Concerns with TSTF-505 RAIs ML13045A8602013-03-0404 March 2013 Request for Additional Information Traveler TSTF-537, Revision 0, Increase CIV (Containment Isolation Valve) Completion Time; Update of TSTF-373 ML12279A2082012-10-19019 October 2012 TSTF-531 RAIs ML12279A1342012-10-19019 October 2012 TSTF-454, Rev 2, RAIs ML12158A5472012-06-13013 June 2012 TSTF-523 Acceptance Letter and RAIs ML1108908172011-04-12012 April 2011 Request for Additional Information Regarding TSTF-508, Revision 1, Revise Control Room Habitability Actions to Address Lessons Learned from TSTF-448 Implementation ML1020402322010-07-27027 July 2010 Request for Additional Information Regarding TSTF-505, Revision 0, on Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML1015304012010-07-0707 July 2010 Acceptance for Review and Request for Additional Information for TSTF-432, Revision 0, Change in Technical Specifications End States (WCAP-16294). ML0914704322009-06-11011 June 2009 Request for Additional Information Regarding TSTF-514 on Reactor Coolant System Leakage Detection ML0906808132009-04-17017 April 2009 Request for Additional Information Regarding TSTF-508, Revision 0, Revise Control Room Habitability Actions to Address Lessons Learned from TSTF-448 Implementation ML0828004842008-11-0404 November 2008 Evaluation of TSTF Responses to NRC Staff Request for Additional Information (RAI) Regarding Traveler TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions. ML0820406052008-08-13013 August 2008 RAI for Review of TSTF-506, Rev 0 ML0812101752008-06-0404 June 2008 Request for Additional Information Regarding TSTF-500, Rev. 0, DC Electrical Rewrite - Update to TSTF-360. ML0810400032008-05-0505 May 2008 Request for Additional Information Regarding TSTF-501, Revision 0, Relocate Stored Fuel Oil and Lube Oil Values to Licensee Control ML0721206302007-10-0202 October 2007 Request for Additional Information (RAI) Regarding TSTF Traveler 425, Revision 1, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5. ML0627700892006-11-0909 November 2006 Request for Additional Information Regarding TSTF-478, Revision 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control 2023-08-10
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Text
March 4, 2013
Technical Specifications Task Force (TSTF) 11921 Rockville Pike, Suite 100
Rockville, MD 20852
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: TRAVELER TSTF-537, REVISION 0, "INCREASE CIV [CONTAINMENT ISOLATION VALVE]
COMPLETION TIME; UPDATE OF TSTF-373" (TAC NO. ME8311)
Dear Members of the TSTF:
By letter dated March 27, 2012 (Agencywide Documents Access and Management System Accession No. ML12087A274), the TSTF submitted for U.S. Nuclear Regulatory Commission (NRC) staff review Traveler TSTF-537, Revision 0, "Increase CIV Completion Time; Update of TSTF-373." Upon review of the information provided, the NRC staff has determined that additional information is needed to complete the review. On February 14, 2013, Brian Mann, Vice President of Industry Programs, EXCEL Services Corporation, and I agreed that the NRC staff will receive your response to the enclosed request for additional information (RAI) questions within 90 days of the date of this letter. If you have any questions regarding the enclosed RAI questions, please contact me at 301-415-1774 or via e-mail at Michelle.Honcharik@nrc.gov.
Sincerely, /RA/ Michelle C. Honcharik, Sr. Project Manager Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
Project No. 753
Enclosure:
As stated
cc w/encl: See next page
ML13045A860; *concurred via memo (ML122280730); *concurred via e-mail NRR-106 OFFICE PLPB/PM PLPB/LA APLA/BC PLPB/BC STSB/BC PLPB/PM NAME MHoncharik DBaxley DHarrison* AMendiola RElliott MHoncharik* DATE 02/14/2013 02/21/2013 02/05/2013 02/25/2013 02/28/2013 03/04/2013 ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION TRAVELER TSTF-537, REVISION 0, "INCREASE CIV [CONTAINMENT ISOLATION VALVE]
COMPLETION TIME; UPDATE OF TSTF-373" TECHNICAL SPECTIFICATIONS TASK FORCE (TSTF)
PROJECT NO. 753
- 1. The U.S. Nuclear Regulatory Commission
's (NRC's) safety evaluation (SE) of the Combustion Engineering Owners' Group (CEOG) Joint Application Report (JAR)
Combustion Engineering (CE)
NPSD-1168-1, "Joint Applications Report for Containment Isolation Valve AOT [Allowed Outage Time] Extension," January 2001, available in the Agencywide Documents Access and Management System (ADAMS) as Accession No. ML003721663 states:
We agree with the CEOG findings that, based on the use of bounding risk parameters for CE designed plants, the proposed increase in containment isolation v alve (CIV) AOT from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 7 days does not result in an unacceptable incremental conditional core damage probability (ICCDP) or incremental conditional large early release probability (ICLERP) according to the criteria of Regulatory Guide 1.177 when the items identified below are acceptably addressed by individual licensees referencing this report in plant-specific submittals.
Given that the topical report was completed a while ago, assess whether the bounding risk parameters may still be considered bounding or not, and provide the basis for your conclusion. In addition, since generic unreliability and unavailability data can change over a long period of time, discuss whether CIV performance based on data since the completion of the JAR is consistent with assumptions made in the supporting JAR analyses, and provide the basis for the conclusions.
- 2. TSTF-537 notes that the JAR identified three sets of valves to which the revised completion time (CT) will not apply. This includes containment sump supply valves to the emergency core cooling systems and containment spray system pumps, valves associated with the main feedwater system, and main steam isolation valves. Please clarify how the proposed Standard Technical Specification (STS) 3.6.3 precludes the application of the extended CT to the main feedwater valves and main steam isolation valves.
- 3. TSTF-537 proposes to address common cause failures with Required Action B.1. Required Action B.1 should require verification that the redundant CIVs in a penetration flow path are not rendered inoperable due to reasons besides common cause failure prior to exceeding the existing 4-hour CT. Since redundant CIVs may fail due to common cause or other reasons, how does TSTF-537 ensure operability of the redundant CIVs for reasons other than common cause failure prior to entering the extended CT?
- 4. Condition E of TSTF-537 includes a change in the CT from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days. This had been proposed in TSTF-373, Revision 2, previously under Condition D.
The bases for "Required Actions" E.1 and E.2 provide criteria for penetrations:
Penetration flow paths eligible for application of the 7 day Completion Time meet the following criteria:
- Containment isolation valves in penetrations connected to nonessential containment cooling systems;
- The closed system piping inside containment is seismically qualified; and,
- Containment isolation valves in the penetration flow paths are air operated valves designed to fail in the closed position and are designed to close automatically by an engineered safety feature actuation system (ESFAS) signal. a. Please indicate in which supporting documentation these criteria are discussed.
- b. What is meant by a nonessential containment cooling system?
- 5. Section 2.3, "Verification and Commitments," of the model application does not mention the following important considerations in the licensee's submittal for this Traveler:
- a. Regulatory Guide (RG) 1.174 for probabilistic risk assessment quality considerations, and other information for risk-informed considerations.
- b. Licensees adopting this Traveler must confirm plant-specific implementation and monitoring in accordance with the guidance in RG 1.174 and RG 1.177;
- c. Plant-specific Tier 3 information must be provided in submittals;
- d. The Tier 3 Configuration Risk Management Program (CRMP) enhancement to include large early release frequency (LERF) and ICLERP is not mentioned; rather, line item Number 4 requests licensees to commit to "implementing methodologies." A licensee's CRMP, including those implemented under the maintenance rule 10 CFR 50.65(a)(4), must be enhanced to include a LERF/ICLERP assessment. This assessment must be documented in a regulatory commitment in the plant-specific application. e. Plant-specific applicability of Tier 2 analysis;
- f. The licensee considers specific penetrations consistent with those analyzed, and provides a plant-specific analysis for configurations not addressed by the groups described in CE NPSD-1168-A;
- g. Licensees provide supporting information that verifies that a penetration remains intact during maintenance activities, including corrective maintenance;
- h. Licensees must confirm that the action of locking open a subject CIV will not result in the design basis technical specification leakage being exceeded;
- i. For external events, in performing the plant-specific analyses, credit for physical barrier integrity outside containment can only be given for seismically qualified piping; and, j. Evaluation of cumulative risk on a plant-specific basis consistent with RG 1.174.
Technical Specifications Task Force Project No. 753 cc:
Technical Specifications Task Force 11921 Rockville Pike
Suite 100
Rockville, MD 20852 Attention: Donald R. Hoffman E-mail: donaldh@excelservices.com Robert A. Slough Comanche Peak Nuclear Power Plant P. O. Box 1002, Mail Code A08
Glen Rose, Texas 76043 E-mail: robert.slough@luminant.com
Roy A. (Tony) Browning Duane Arnold Energy Center 3277 DAEC Rd.
PSC/Licensing Palo, IA 52324-9785 E-mail: Tony.Browning@nexteraenergy.com
Wendy E. Croft
Exelon Nuclear 200 Exelon Way, Suite 340 Kennett Square, PA 19348 E-mail: Wendi.Croft@exeloncorp.com
Otto W. Gustafson Entergy Nuclear Operations, Inc. Palisades Nuclear Power Plant 27780 Blue Star Memorial Highway Covert, MI 49043
E-mail: ogustaf@entergy.com
Brian D. Mann EXCEL Services Corporation 11921 Rockville Pike, Suite 100
Rockville, MD 20852
E-mail: brianm@excelservices.com