ML14108A376: Difference between revisions
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| number = ML14108A376 | | number = ML14108A376 | ||
| issue date = 05/08/2014 | | issue date = 05/08/2014 | ||
| title = | | title = Summary of Meeting with Southern Nuclear Operating Company to Discuss Deletion of the Residual Heat Removal Autoclosure Interlock | ||
| author name = Williams S | | author name = Williams S | ||
| author affiliation = NRC/NRR/DORL/LPLII-1 | | author affiliation = NRC/NRR/DORL/LPLII-1 | ||
| addressee name = | | addressee name = | ||
| Line 13: | Line 13: | ||
| document type = Meeting Summary | | document type = Meeting Summary | ||
| page count = 4 | | page count = 4 | ||
| project = TAC:MF3716 | |||
| stage = Meeting | |||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:LICENSEE: Southern Nuclear Operating Company FACILITY: Joseph M. Farley, Units 1 and 2 | |||
==SUBJECT:== | |||
==SUMMARY== | |||
OF APRIL 23,2014, MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY TO DISCUSS DELETION OF THE RESIDUAL HEAT REMOVAL AUTOCLOSURE INTERLOCK (TAC NO. MF3716) | |||
On April 23, 2014, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Southern Nuclear Operating Company (SNC) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the technical justification for a future amendment to eliminate the Residual Heat Removal System (RHR) Autoclosure Interlock (ACI). The RHR ACI provides protection against over pressurization of the low pressure RHR system by the high pressure reactor coolant system. | |||
The meeting notice and agenda, dated April 9, 2014, is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML14099A215. A list of attendees is provided in Enclosure 1. The licensee's presentation can be found at ADAMS Accession No. ML14120A225. | |||
The licensee described the proposed approach that will be utilized for the technical justification for the future amendment request to remove the RHR ACI feature from the plant and to delete the associated technical specifications. The licensee's planned approach includes a probabilistic analysis that is described in WCAP-11736-A, Revision 0.0, "Residual Heat Removal System Autoclosure Interlock Removal Report," dated August 8, 1989. SNC stated that a plant-specific probabilistic analysis was completed in 1996 for Farley Units 1 and 2; however the probabilistic analysis did not consider Regulatory Guide (RG) 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-informed Activities" at that time. Therefore, SNC stated that they will assess the technical adequacy of the probabilistic risk assessment models/analyses that were completed in 1996 against the guidance endorsed in RG 1.200. SNC stated that the metrics for assessing the risk associated with the probabilistic risk assessment models/analyses will be the initiating event frequency change of interfacing system LOCAs, the RHR unavailability change, and the consequence category (non-success end states) for the low temperature over-pressurization analysis. | |||
The NRC staff clarified that any future amendment to eliminate the RHR ACI would be based on a deterministic review and that any "risk" information is only useful supplementary information that cannot be used as the basis for a staff decision. For any risk information to form such a basis, the amendment would have to be submitted under RG 1.174, meeting the requirements of RG 1.200. | |||
Other comments include suggestions to provide information on the 2010 event that caused SNC to purse this amendment; to include detailed drawings and logic drawings, and to consider human factors. | |||
Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 | |||
==Enclosure:== | |||
List of Attendees cc w/encl: Distribution via Listserv | |||
LIST OF ATTENDEES APRIL 23,2014, MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY RESIDUAL HEAT REMOVAL AUTOCLOSURE INTERLOCK Nuclear Regulatory Commission Staff Robert Martin, NRRIDORL Jennifer Gall, NRRIDSS, Reactor Systems Branch David Rahn, NRRIDE, Instrumentation & Controls Branch Kristy Bucholtz, NRRJDSS, Technical Specifications Branch Samina Shaikh, NRRJ DSS, Containment and Ventilation Branch Robert Dennig, NRR/DSS, Containment and Ventilation Branch Hossein Hamzehee, NRRIDSS, PRA Licensing Branch Ray Gallucci, NRRIDRA, PRA Licensing Branch Licensee Participants Ken McElroy, SNC Licensing Manager Jamie Coleman, SNC Licensing Engineer Jim Andrachek, Westinghouse Jerry Andre, Westinghouse Enclosure | |||
ML14108A376 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 5/7/14 5/7/14 5/8/14 5/8/14}} | |||
Latest revision as of 07:49, 5 December 2019
| ML14108A376 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/08/2014 |
| From: | Shawn Williams Plant Licensing Branch II |
| To: | Southern Nuclear Company |
| Williams S | |
| References | |
| TAC MF3716 | |
| Download: ML14108A376 (4) | |
Text
LICENSEE: Southern Nuclear Operating Company FACILITY: Joseph M. Farley, Units 1 and 2
SUBJECT:
SUMMARY
OF APRIL 23,2014, MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY TO DISCUSS DELETION OF THE RESIDUAL HEAT REMOVAL AUTOCLOSURE INTERLOCK (TAC NO. MF3716)
On April 23, 2014, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Southern Nuclear Operating Company (SNC) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the technical justification for a future amendment to eliminate the Residual Heat Removal System (RHR) Autoclosure Interlock (ACI). The RHR ACI provides protection against over pressurization of the low pressure RHR system by the high pressure reactor coolant system.
The meeting notice and agenda, dated April 9, 2014, is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML14099A215. A list of attendees is provided in Enclosure 1. The licensee's presentation can be found at ADAMS Accession No. ML14120A225.
The licensee described the proposed approach that will be utilized for the technical justification for the future amendment request to remove the RHR ACI feature from the plant and to delete the associated technical specifications. The licensee's planned approach includes a probabilistic analysis that is described in WCAP-11736-A, Revision 0.0, "Residual Heat Removal System Autoclosure Interlock Removal Report," dated August 8, 1989. SNC stated that a plant-specific probabilistic analysis was completed in 1996 for Farley Units 1 and 2; however the probabilistic analysis did not consider Regulatory Guide (RG) 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-informed Activities" at that time. Therefore, SNC stated that they will assess the technical adequacy of the probabilistic risk assessment models/analyses that were completed in 1996 against the guidance endorsed in RG 1.200. SNC stated that the metrics for assessing the risk associated with the probabilistic risk assessment models/analyses will be the initiating event frequency change of interfacing system LOCAs, the RHR unavailability change, and the consequence category (non-success end states) for the low temperature over-pressurization analysis.
The NRC staff clarified that any future amendment to eliminate the RHR ACI would be based on a deterministic review and that any "risk" information is only useful supplementary information that cannot be used as the basis for a staff decision. For any risk information to form such a basis, the amendment would have to be submitted under RG 1.174, meeting the requirements of RG 1.200.
Other comments include suggestions to provide information on the 2010 event that caused SNC to purse this amendment; to include detailed drawings and logic drawings, and to consider human factors.
Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
LIST OF ATTENDEES APRIL 23,2014, MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY RESIDUAL HEAT REMOVAL AUTOCLOSURE INTERLOCK Nuclear Regulatory Commission Staff Robert Martin, NRRIDORL Jennifer Gall, NRRIDSS, Reactor Systems Branch David Rahn, NRRIDE, Instrumentation & Controls Branch Kristy Bucholtz, NRRJDSS, Technical Specifications Branch Samina Shaikh, NRRJ DSS, Containment and Ventilation Branch Robert Dennig, NRR/DSS, Containment and Ventilation Branch Hossein Hamzehee, NRRIDSS, PRA Licensing Branch Ray Gallucci, NRRIDRA, PRA Licensing Branch Licensee Participants Ken McElroy, SNC Licensing Manager Jamie Coleman, SNC Licensing Engineer Jim Andrachek, Westinghouse Jerry Andre, Westinghouse Enclosure
ML14108A376 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 5/7/14 5/7/14 5/8/14 5/8/14