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Category:Safety Evaluation
MONTHYEARML24029A1472024-01-31031 January 2024
TSTF-592 Cover Letter for Final SE of TSTF-592
ML24029A1482024-01-31031 January 2024
Final Traveler SE of TSTF-592
ML23325A2142023-12-18018 December 2023
Final Model SE of TSTF-591, Revise Risk Informed Completion Time (RICT) Program
ML23262B2302023-09-21021 September 2023
Final SE of TSTF-591, Revision 0, Revise Risk-Informed Completion Time (RICT) Program
ML23241B0402023-09-11011 September 2023
Final Traveler SE of TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown
ML23153A1442023-09-11011 September 2023
Draft SE of Traveler TSTF-591, Revise Risk-Informed Completion Time (RICT) Program
ML23206A0762023-07-31031 July 2023
Final Traveler SE of TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
ML23206A0752023-07-31031 July 2023
Final Model SE of TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
ML21188A2252021-07-11011 July 2021
Final Model SE of CLIIP TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR (Residual Heat Removal) Shutdown Cooling
ML21188A2272021-07-11011 July 2021
Final Traveler SE of CLIIP TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR (Residual Heat Removal) Shutdown Cooling
ML21053A3962021-05-26026 May 2021
Draft Model SE of CLIIP TSTF-580, RHR Shutdown Cooling System - Hot Shutdown
ML21053A3882021-05-26026 May 2021
Draft Traveler SE of CLIIP TSTF-580, RHR Shutdown Cooling System - Hot Shutdown
ML21106A2392021-04-20020 April 2021
Final Model SE of TSTF 554, Revision 1, Revise Reactor Coolant Leakage Requirements
ML21096A2742021-04-14014 April 2021
Final Model SE of TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
ML21098A1882021-04-14014 April 2021
Final SE of Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
ML20311A6642020-12-21021 December 2020
Draft Model Safety Evaluation of TSTF-554 Revise Reactor Coolant Leakage Requirements
ML20353A2092020-12-21021 December 2020
Cover Letter Transmitting Draft Model TSTF-554, Revise Reactor Coolant Leakage Requirements
ML20322A0242020-12-18018 December 2020
Final SE of Traveler TSTF-554, Revise Reactor Coolant Leakage Requirements
ML20154K6062020-10-30030 October 2020
Draft Safety Evaluation of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
ML20248H5372020-10-0909 October 2020
Model Safety Evaluation of TSTF-582, RPV WIC Enhancements with Optional TSTF-583-T Variation
ML20132A2602020-05-13013 May 2020
Revised Final SE of Traveler TSTF-564, Revision 2, Safety Limit MCPR, Using the Consolidated Line Item Improvement Process
ML19248C8232020-02-25025 February 2020
Revised Final Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR, Using the Consolidated Line Item Improvement Process
ML19325C4342019-12-17017 December 2019
Final Safety Evaluation of Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2
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.
ML19176A1902019-08-14014 August 2019
Final Model Safety Evaluation of Traveler TSTF-569, Revision 2, Revise Response Time Testing Definition (EPID L-2018-PMP-0002) (Enclosure 2)
ML19176A1912019-08-14014 August 2019
Final Safety Evaluation of Traveler TSTF-569, Revision 2, Revise Response Time Testing Definition (EPID L-2018-PMP-0002) (Enclosure 1)
ML19017A2172019-05-29029 May 2019
Draft Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-569, Revision 1, Revise Response Time Testing Definition (Enclosure 2)
ML19028A2862019-02-21021 February 2019
Final Model SE of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems (Enclosure 2)
ML19028A2872019-02-21021 February 2019
Final SE of Traveler TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems (Enclosure 1)
ML19007A2272019-01-15015 January 2019
Final Model SE of Traveler TSTF-557, Revision 1, Spent Fuel Storage Rack Neutron Absorber Monitoring Program.
ML19007A2262019-01-15015 January 2019
Final SE of Traveler TSTF-557, Revision 1, Spent Fuel Storage Rack Neutron Absorber Monitoring Program.
ML18333A1472018-12-0404 December 2018
Final Model SE of Traveler TSTF 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (Enclosure 2)
ML18333A1442018-12-0404 December 2018
Final SE of Traveler TSTF 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program.
ML18267A2592018-11-21021 November 2018
Final Revised Model Safety Evaluation of Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
ML18299A0692018-11-16016 November 2018
Final Traveler SE of TSTF-564, Revision 2, Safety Limit MCPR
ML18299A0762018-11-16016 November 2018
Final Model SE of TSTF-564, Revision 2, Safety Limit MCPR
ML18299A0832018-11-16016 November 2018
NRC Disposition of TSTF Comments on the Draft Safety Evaluation of TSTF-564, Safety Limit MCPR
ML18226A3182018-09-20020 September 2018
Draft Model SE of Traveler TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (SFCP) - Enclosure 2
ML18226A2562018-09-20020 September 2018
Draft SE of Traveler TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (SFCP) - Enclosure 1
TSTF-18-07, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-505, Provide Risk-Informed Extended Completion Times and Submittal of TSTF-505, Revision 22018-07-0202 July 2018
TSTF Comments on Draft Safety Evaluation for Traveler TSTF-505, Provide Risk-Informed Extended Completion Times and Submittal of TSTF-505, Revision 2
ML17341A3262018-03-26026 March 2018
Draft Model Safety Evaluation of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues.
ML17080A4142017-07-0303 July 2017
Draft Safety Evaluation of Technical Specifications Task Force Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements
ML16343B0082016-12-20020 December 2016
Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (Tac No. MF3487)
ML16343B0652016-12-20020 December 2016
Final Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control
ML15328A3502016-03-0404 March 2016
Final Safety Evaluation (SE) of TSTF-547, Rev. 1, Clarification of Rod Position Requirements
ML15314A3052015-12-11011 December 2015
TSTF-545 Final Model SE
ML15181A0372015-09-0909 September 2015
Proposed Model Se for Plant-Specific Adoption of Traveler TSTF-545, Revision 2, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the CLIIP
ML13113A1812013-07-0909 July 2013
Proposed Model Safety Evaluation for PLANT-SPECIFIC Adoption of Technical Specifications Task Force Traveler TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
ML12355A7722013-02-19019 February 2013
Model Safety Evaluation for Plant-Specific Adoption of Tech Spec Task Force Traveler TSTF-535, Rev. 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs, Using the Consolidated Line Item Improvement Process
ML12097A5962013-01-0707 January 2013
TSTF-426 Nfc Model Safey Evaluation
2024-01-31
[Table view] |
Text
U.S. Nuclear Regulatory Commission Staff Disposition of Comments to June 20, 2011 (76 FR 35923), Federal Register Notice, Notice of Opportunity to Provide Written Comments on Proposed Model Safety Evaluation for Plant-Specific Adoption of TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection The U.S. Nuclear Regulatory Commission (NRC) staff evaluated the public comments received on the model safety evaluation (SE) published in the Federal Register on June 20, 2011 (76 FR 35923). Comments were received from Mr. Clayton Webber of Tennessee Valley Authority (TVA) on June 30, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11238A001) and the Technical Specifications Task Force (TSTF) on July 17, 2011 (ADAMS Accession No. ML11201A231). The TSTF and TVA comments along with the NRC staff disposition of each comment are as follows.
TVA Comment:
Revision 2 of the TSTF-510 provides description of intervals and periods. In ASME [American Society of Mechanical Engineers] codes, Periods combined make up an Interval. The Intervals are 10 years. The NRC has suggested that Intervals combined make up a Period. Is there a basis for not using similar terminology as the ASME code, since it is familiar to inspection personnel?
NRC disposition:
No changes were made to the SE; the terminology contained in TSTF-510 and the Technical Specifications (TS) remains unchanged. The current TS and TSTF-510 wording maintains consistency with current Industry Guidance. Changing the definition of Period and Interval to match the ASME Code use would create conflicts and inconsistencies with Industry Guidance and cause differences between plants that implement TSTF-510 and those that do not; adding to more confusion. Therefore, TSTF-510 use of Period and Interval remains unchanged.
TSTF Comment 1:
The model Safety Evaluation, Section 3.9, Page 11, the section titled, "Proposed Change," contains an inconsistency with TSTF-510, Revision 2. The first sentence in the model Safety Evaluation states: "After the first refueling outage following SG installation, inspect each SG at least every 72 effective full power months or at least every other refueling outage (whichever results in more frequent inspections)." (Emphasis added.)
TSTF-510, Revision 2, states:
"After the first refueling outage following SG installation, inspect each SG at least every 72 effective full power months or at least every third refueling outage (whichever results in more frequent inspections)." (Emphasis added.)
The model Safety Evaluation should be revised to be consistent with TSTF-510, Revision 2.
Note that the model Safety Evaluation correctly reflects the TSTF-510, Revision 2, requirements in the "Assessment" section (Page 12, second paragraph): "Under the proposed changes to paragraph 5.5.9.d.2, the required minimum inspection frequency for alloy 690 TT (every 72 EFPM or every third refueling outage (whichever is less)) would remain materially unchanged."
NRC Disposition:
The NRC staff agrees that the SE should state every third instead of every other. The model SE has been revised to be consistent with TSTF-510, Revision 2.
TSTF Comment 2:
The model Safety Evaluation, Section 3.9, Page 11, the section titled, "Proposed Change," contains an inconsistency with TSTF-5 10, Revision 2. The second sentence in the model Safety Evaluation states: "In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a b and c below." (Emphasis added.)
TSTF-5 10, Revision 2, states: "In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection period as defined in a, b c and d below." (Emphasis added.)
The quoted paragraph in the proposed Technical Specifications is followed by Items a through d. The model Safety Evaluation should be revised to be consistent with TSTF 510, Revision 2.
NRC disposition:
The NRC staff agrees that the SE should include item d. The model SE has been revised to be consistent with TSTF-510, Revision 2.
TSTF Comment 3:
The model Safety Evaluation, Section 3.11, "Specification 5.6.7, 'Steam Generator Inspection Report'," Page 14, discusses the elimination of the word "Active" from Item b but does not discuss the elimination of the word "active" in Item e, as shown in TSTF-510, Revision 2. The justification for the elimination of the word "active" is the same for both Item b and Item e. The model Safety Evaluation should be revised to discuss the elimination of the word "active" from Specification 5.6.7, Item e.
NRC disposition:
The NRC staff agrees that the SE should discuss the elimination of the word "active" in Item e.
The model SE has been revised to be consistent with TSTF-510, Revision 2.