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Category:Response to Request for Additional Information (RAI)
MONTHYEARULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) ML23156A6372023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23129A7972023-05-0909 May 2023 Response to Audit Questions ML23088A1322023-03-29029 March 2023 Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ML23052A0442023-02-21021 February 2023 Enclosure 2 - Supplement to License Amendment Request ML23052A0422023-02-21021 February 2023 Response to Request for Additional Information and Supplement to License Amendment Request Regarding Spent Fuel Storage (LDCN 22-0015) ML23052A0432023-02-21021 February 2023 Enclosure 1 - Response to Request for Additional Information ML22342B2662022-12-0808 December 2022 Enclosure - Ameren Missouri Response to NRC RAIs ML22335A4992022-11-16016 November 2022 Enclosure 1: Responses to Requested Information ML22244A1692022-09-0101 September 2022 Updated Response to RAT HFE-l ML22194A8032022-07-13013 July 2022 Enclosure 2: Ameren Missouri Verification Ofagreement Letters with State and EPZ Counties for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ML22194A8022022-07-13013 July 2022 Enclosure 1: Ameren Missouri Response to NRC Requests for Additional Information ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ML22186A1052022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ML22146A3392022-05-26026 May 2022 Enclosure 1: Ameren Missouri Response to NRC RAIs ML22068A0292022-03-0808 March 2022 Response to Audit Question/Item 23 in NRC Letter Dated September 14, 2021 ML21286A6822021-10-13013 October 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ULNRC-06629, Response to Request for Additional Information Pertaining to Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2021-01-0707 January 2021 Response to Request for Additional Information Pertaining to Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs ULNRC-06602, Response to Request for Addition Information Pertaining to Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and TS 5.3.1.2 -2020-09-0202 September 2020 Response to Request for Addition Information Pertaining to Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and TS 5.3.1.2 - ML20238C1072020-08-25025 August 2020 Response to Request for Additional Information (Redacted) ULNRC-06591, Supplemental Information for Response to March, 2012 Information Request, Seismic Probabilistic Risk Assessment for Recommendation 2.12020-07-10010 July 2020 Supplemental Information for Response to March, 2012 Information Request, Seismic Probabilistic Risk Assessment for Recommendation 2.1 ML19325D6732019-11-21021 November 2019 Attachment 2 - Callaway Energy Center Seismic Probabilistic Risk Assessment in Response to 50.54(F) Letter with Regard to NTTF 2.1 Seismic - Supplemental Information ML19051A1372019-02-20020 February 2019 Attachment 1: Response to Request for Additional Information ULNRC-06482, Response to Request for Additional Information Pertaining to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2019-02-0808 February 2019 Response to Request for Additional Information Pertaining to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ML19039A3542019-02-0808 February 2019 RAI Questions and Responses ML19025A0712019-01-25025 January 2019 Response to Request for Additional Information Pertaining to Relief Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds ULNRC-06479, Attachment a - Mitsubishi Responses to NRC Wjp RAIs2019-01-25025 January 2019 Attachment a - Mitsubishi Responses to NRC Wjp RAIs ULNRC-06440, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools - Request for Supplemental Information2018-05-31031 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools - Request for Supplemental Information ULNRC-06410, Callaway Plant, Unit 1 - Response to Request for Additional Information Concerning Proposed Revision of FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (Ldcn 16-0001)2018-02-0505 February 2018 Callaway Plant, Unit 1 - Response to Request for Additional Information Concerning Proposed Revision of FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (Ldcn 16-0001) ML18036A6762018-02-0505 February 2018 Enclosure 6: Response to Request for Additional Information (RAI) 1.d (MOV Performance Indicator Report for Cycle 21) ML18036A6742018-02-0505 February 2018 Enclosure 5: Response to Request for Additional Information (RAI) 1.d (MOV Performance Indicator Report for Cycle 20) ML18036A6732018-02-0505 February 2018 Enclosure 4: Response to Request for Additional Information (RAI) 1.d (MOV Performance Indicator Report for Cycle 19) ML18036A6722018-02-0505 February 2018 Enclosure 3: Response to Request for Additional Information (RAI) 1.c ULNRC-06410, Response to Request for Additional Information Concerning Proposed Revision of FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001)2018-02-0505 February 2018 Response to Request for Additional Information Concerning Proposed Revision of FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001) ML18036A6692018-02-0505 February 2018 Enclosure 1: Responses to Requests for Additional Information ML18036A6712018-02-0505 February 2018 Enclosure 2: Response to Request for Additional Information (RAI) Item 1.a ULNRC-06381, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-10-0303 October 2017 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML17138A2132017-05-18018 May 2017 Response to Request for Additional Information Concerning Revision of TS 5.6.5, Core Operating Limits Report (Colr), to Allow the Use of the Paragon and Nexus Core Design Methods (LDCN 16-0011) ULNRC-06357, Response to Request for Additional Information, 2016 Steam Generator Tube Inspections2017-03-23023 March 2017 Response to Request for Additional Information, 2016 Steam Generator Tube Inspections ULNRC-06321, Response to Request for Additional Information, Third 10-Year Interval Inservice Inspection Request for Relief No. I3R-082016-07-0707 July 2016 Response to Request for Additional Information, Third 10-Year Interval Inservice Inspection Request for Relief No. I3R-08 ULNRC-06275, Response to Request for Additional Information (RA) Related to Operating Quality Assurance Manual (Oqam), Revision 31, Oqam Change Notice 15-0022016-01-12012 January 2016 Response to Request for Additional Information (RA) Related to Operating Quality Assurance Manual (Oqam), Revision 31, Oqam Change Notice 15-002 ULNRC-06266, Response to Request for Additional Information, Third 10-Year Interval Inservice Inspection, Request for Relief No. 13R-112015-11-24024 November 2015 Response to Request for Additional Information, Third 10-Year Interval Inservice Inspection, Request for Relief No. 13R-11 ULNRC-06238, Response to Supplemental Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 62015-08-31031 August 2015 Response to Supplemental Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6 ULNRC-06230, Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 62015-07-16016 July 2015 Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6 ULNRC-06233, Submittal of Requested Information on FSAR Section 3.1.2., Per July 9, 2015 Telephone Call2015-07-13013 July 2015 Submittal of Requested Information on FSAR Section 3.1.2., Per July 9, 2015 Telephone Call ULNRC-06227, Response to Request for Additional Information Related to License Amendment Request for Emergency Action Level Upgrade Adopting NRC-Endorsed NEI 99-01, Rev 62015-07-0606 July 2015 Response to Request for Additional Information Related to License Amendment Request for Emergency Action Level Upgrade Adopting NRC-Endorsed NEI 99-01, Rev 6 2023-08-17
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Enclosure to ULNRC-06803 Page 1 of 7 Response to Request for Additional Information Callaway Plant, Unit 1 -
SG Inspection Report Review EPID: L-2022-LRO-0143 on November 1, 2022 (ULNRC-06773, Results ofSteam Generatorlube In-Service Inspection ML22305A680) Union Electric Company, dba Ameren Missouri, submitted information summarizing the spring 2022 steam generator (SG) tube inspections performed at Callaway Plant, Unit 1, during refueling outage 25. Callaway Plant, Unit 1 Technical Specification (TS) Section 5.6.10, Steam Generator Tube Inspection Report, requires that a report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with TS Section 5.5.9, Steam Generator (SG) Program Subpart c.2 of 5.6.10 states that the report shall include the location, orientation (if linear), measured size (if available), and voltage response for each indication. For tube wear at support structures less than 20 percent through-wall, only the total number of indications needs to be reported.
Req uest:
To complete its review of the inspection report, the NRC staff requests the following additional information:
In the SG Tube Inspection Report submitted on November 1, 2022, Table 5 indicates the presence of tube support plate wear indications in SGs B and C that were greater than or equal to 20 percent through-wall in depth. Please provide the location, orientation (if linear), measured size (if available),
and voltage response for these indications.
Response
SG B and SG C each contain one indication of tube support plate wear of greater than or equal to 20 percent through-wall in depth. The following two attachments provide additional details pertaining to these indications, including the requested information.
to Enclosure of ULNRC-06803 Page 1 of 3 Callaway Plant Unit 1 Steam Generator B TSP Wear Indications 20% 39% -
Refuel Outage 25, April 2022 2 pages follow this cover sheet
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Framatome Inc 05/04/22 09:41:34 Customer: Ameren Plant: Callaway Unit: 1 Component: S/G B Page 2 of 2 TSP Wear 20% 39%
QUERY: QueryMl{1] .qry ROW COL VOLTS 0EG CHAN 1N0 %TW LOCATION EXT EXT UTIL 1 UTIL 2 UTIL 3 CAL LEG PROBE lOX 89 59 0.28 136 94 TWO 20 05H +0.35 TEC TEE 6 HOT 610H5 1141 Total Tubes : 1 Total Records: 1 to Enclosure of ULNRC-06803 Page 1 of 3 Callaway Pla nt U nit 1 Stea m Generator C Tsp Wear Indications 20% 39% -
Refuel Outage 25, April 2022 2 pages follow this cover sheet
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Frainatcme Inc 05/04/22 09:46:02 Customer: Aznenn Plant: Callavay Unit: 1 Cerponent: S/G C Page 2 of 2 TSP Wear 20% 39%
QUERY: Querylil[1] .qry ROW COL VOLTS DEC CRAW IND %TW LOCATION ECT CT UTIL 1 UTIL 2 UTIL 3 CAL LEG PROBE lOX 112 60 0.33 124 P4 P1W 23 04C +0.46 TEC TEE 2 HOT 61055 1566 Total Tithes : 1 Total Records : 1