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Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0658, Southern Nuclear Operating Company - 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Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. 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Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 2024-01-29
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Text
Mark J. Ajluni, P.E. Southern Nuclear Nuclea r Licens ing Director Operating Company, Inc.
40 Invernes s Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992 .7673 Fax 205.992.7885 October 29, 2012 SOUTHERN'\
COMPANY Docket No.: 50-424 NL-12-2224 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington , D. C. 20555-0001 Vogtle Electric Generating Plant - Unit 1 Proposed Alternative VEGP-ISI-ALT-08 in Accordance with 10 CFR 50.55a(a)(3)(ii)
Response to Request for Additional Information Ladies and Gentlemen :
By letter NL-12-2110, dated October 25,2012, Southern Nuclear Operating Company (SNC) requested NRC approval of a proposed alternative to the specified ASME Boiler and Pressure Vessel Code Section XI requirements in order to stop a pinhole leak in a seal weld on a valve in the Unit 1 Chemical and Volume Control System (CVCS) .
Subsequent discussion with the Nuclear Regulatory Commission (NRC) resulted in NRC requests for additional information on October 29, 2012. The enclosure to this letter provides responses to the requests for additional information .
This letter contains no NRC commitments. If you have any questions, please contact Doug McKinney at (205) 992-5982.
Respectfully submitted, M. J. Ajluni Nuclear Licensing Director MJAlDWD
Enclosure:
Response to Request for Additional Information
U. S. Nuclear Commission NL-12-2224 Page 2 cc:
Kuczynski, Chairman, Vice President & Nuclear Officer Mr. T. E. President-Mr. L Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Operations RType: CVC7000 U. S. Nuclear Regulatorv Commission Mr. V. M. Regional Administrator Mr. R. Martin, NRR Senior Project Manager - Fleet Mr. L M. Resident Inspector Vogtle
Vogtle Electric Generating Plant - Unit 1 Proposed Alternative VEGP-ISI-ALT-08 in Accordance with 10 CFR SO.SSa(a)(3)(ii)
Enclosure Response to Request for Additional Information
Enclosure Response to Request for Additional Information Request for Additional Information (RAil - 1 The alternative is proposed in accordance with 10 CFR 50.55a(a){3)(ii) i.e. compliance with specified requirements would in hardship or unusual difficulty without a compensating increase in the level of quality and safety. On page of your October 2012 submittal In the second paragraph you state that, "It was determined that the cycling of plant equipment and personnel to to Mode 5 presented a hardship without a compensating increase in the level of quality or safety." Could you elaborate on the hardship involved? Typically difficulty or hardship described in of plant or personnel safety, AlARA concerns, increased numbers of cycles on plant equipment, equipment availability, etc.
In addition to inherent risk associated with a shutdown transient (e.g., maneuvering the plant to Mode going to Mode 5 for repair of non-pressure boundary leak would subject plant equipment to an extra cycle of thermal and pressure stresses and cause an extra 400 - 500 mR to personnel through such shutdown and startup activities as depressurizing Reactor Coolant System (RCS). crud burst and cleanup, venting the Emergency Core Cooling System (ECCS), placing the Residual Heat Removal (RHR) system into service and performing visual inspections of the RCS reactor head. These work activities also present otherwise unnecessary challenges to personnel safety.
In the October 2012 submittal you indicate the steam was stopped by installation of a mechanical clamp and leak sealant injection on October 13, 201 However, after additional system heatup reoccurred on October 1 2012 and October 22, 201 (1) Is there industry Operating Experience (OE) that indicates this method can effectively contain the steam leak? If provide some examples. (2) Discuss why the leakage reoccurred after the mechanical clamp was installed. (3) Discuss your corrective actions should the leakage reoccur in the near future.
SNC Response to RAI 2 (1) Per vendor, this type of clamp with injection has used in the industry for similar leakage situations. Although a response was received from only one user in the short time frame available, and in that case was not stopped completely, use of the clamp and sealant was reported to resulted in a reduction of leakage.
(2) As briefly discussed in October 25, 2012 submittal on page E3, leakage reoccurred from mechanical clamp due to the initial injection temperature of the sealant. The sealant "2x," was designed to work at temperatures of 350"F and above. With the injections occurring at a skin temperature of 140°F, the sealant was not able to properly cure. This sealant uses a liquid to help transport the resin throughout clamp with the intention that the liquid portion of sealant be evaporated quickly, allowing resin fill a portion of the area between the clamp and the valve. With injection of the occurring at a lower temperature, the liquid portion of the did not E1
Enclosure Response to Request for Additional Information fully evaporate before the resin hardened. When the plant systems heated up and the liquid evaporated off, voids, also referred to as honeycombs, were left in the hardened sealant in place of the liquid, thereby resulting in steam leakage.
The second injection failed to fully stop the leak since the re-application of sealant was not able to fill all the voids in the hardened sealant that were incurred due to the original injection at a lower temperature. Despite the fact that leakage was not stopped completely, the original clamp application clearly improved the situation.
(3) Leakage would continue to be monitored if (1) leakage was to reoccur and the new leakage does not result in a boric acid corrosion concern to adjacent or surrounding components and (2) if the new leakage does not hinder the identification of or mask new leaks inside containment.
If leakage occurs, it will be measured and categorized as unidentified leakage, with a Technical Specifications limit of 1 gpm. Currently, leakage is not detectable by performance of the RCS leak rate calculations, the method used for Technical Specification compliance. The current total unidentified leakage for Unit 1 is 0.02 gpm.
Should the leakage interfere with the required RCS leakage detection systems, these systems will be declared inoperable as appropriate, and the required Technical Specification actions will be performed, including unit shutdown, if necessary.
Is the mechanical clamp sealing method proposed in the alternative different from the current configuration in any way other than the sealant injection temperature and the injection port location?
SNC Response to RAI 3 The mechanical clamp sealing method that is proposed in the Alternative to be installed in place of the current configuration does not differ from the first mechanical clamp installed except as noted in the question (Le. sealant injection temperature and injection port location). The sealant will be initially injected at Normal Operating Temperature, i.e., 40QoF, rather than at 140°F, and one of the injection ports will be moved to a location on the outer periphery of the clamp that is closer to the actual defect, i.e., pinhole, in the seal weld.
In the October 25, 2012 submittal on page E6 you indicate monitoring of the mechanical clamp for leakage will include weekly monitoring by installing a camera and VT-2 examination every 30 days via containment entry. If the leak reoccurs after installation of the clamp proposed in the alternative the staff believes the monitoring plan should E2
Enclosure Response to Request for Additional Information include provisions for increased monitoring. Discuss your monitoring plan if the leakage reoccurs after clamp installation.
SNC Response to RAI 4 Daily inspections are to be performed after installation to verify adequacy of the proposed alternative. Seven days after alternative installation, if no leakage is observed, the proposed long-term monitoring frequency (7 day visual and 30 day VT-2 inspection) will be implemented.
If leakage reoccurs after installation, daily monitoring via remote camera will be performed in addition to the 30 day VT-2 inspection.
Discuss the sensitivity and capability of the reactor coolant system leakage detection system if the leakage reoccurs. Include in the discussion, clarification of how many hours after a leak occurs and at what leak rate would the operator be notified.
SNC Response to RAI 5 The leak detection systems are designed in accordance with the requirements of 10 CFR 50 and the general design criterion 30 to provide a means of detecting and, to the extent practical, identifying the source of the reactor coolant leakage. The systems conform with Regulatory Guide 1.45. Main systems that monitor the environmental condition of the containment include the sump level monitoring system, the airborne particulate radioactivity monitoring systems, and the containment fan cooler condensate measuring system. In addition to the above systems, the humidity, temperature, pressure, and radiogas monitors provide indirect indication of leakage to the containment.
The RCS leakage detection system is designed to detect a 1 gpm increase in unidentified leakage within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. In addition, control room annunciation is available for Containment activity radiation monitors, normal sump levels and containment cooler leakage detection.
Operating history has demonstrated that the operator would be able to detect leak rates as low as 0.1 gpm by performance of an RCS inventory balance. Technical Specifications require the ReS inventory balance to be performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (SR 3.4.13.1); however, the Operations daily surveillance procedure requires an RCS inventory balance to be performed once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Therefore, if leakage were to reoccur after installation, an increase in leakage as low as 0.1 gpm would be detected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and if the leakage is of significant magnitude (i.e. 1 gpm or more), it is expected that RCS leakage detection instrumentation would identify the increase in leakage within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
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