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{{#Wiki_filter:}} | {{#Wiki_filter:LICENSEE: STP Nuclear Operating Company FACILITY: South Texas Project, Units 1 and 2 | ||
SUBJECT: SUMMARY OF JULY 7, 2014, PRE-LICENSING PUBLIC MEETING WITH STP NUCLEAR OPERATING COMPANY TO DISCUSS THE PROPOSED LICENSE AMENDMENT REQUEST FOR REPLACING CROSSFLOW ULTRASONIC FLOW MEASUREMENT WITH LEADING EDGE FLOW METER TECHNOLOGY (TAC NOS. MF4291 AND MF4292) On July 7, 2014, a public meeting was held between the U.S. Nuclear Regulatory Commission (NRC), and representatives of STP Nuclear Operating Company (STPNOC, the licensee), at NRC Headquarters, Rockville, Maryland. The meeting notice and agenda, dated June 23, 2014, is located in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML 14174B375. The purpose of the meeting was to discuss the license amendment request (LAR) for replacing Crossflow Ultrasonic Flow Measurement (UFM) technology with Leading Edge Flow Meter (LEFM) technology. This change affects Technical Specification (TS) 6.9.1.6, "Core Operating Limits Report (COLR)." A list of meeting attendees is provided in Enclosure 1 to this meeting summary. Meeting Summary The discussion was based on the following meeting materials/handouts, which is provided in Enclosure 2 of this meeting summary: | |||
* Slides provided by STPNOC, "AMAG [Advanced Measurements & Analysis Group] Crossflow UFM Change to Cameron I Caldon LEFM, July 7, 2014" (Enclosure 2) Discussion: | |||
* The licensee stated that its objective was to change the administrative section of TS 6.9.1.6. The proposed LARwill replace the Crossflow UFM with LEFM technology, which is an NRC-approved technology. The licensee stated that it intends to follow the guidance in Regulatory Issue Summary (RIS) 2002-03, "Guidance on the Content of Measurement Uncertainty Recapture Power Uprate Applications," dated January 31, 2002 (ADAMS Accession No. ML013530183). The licensee clarified that the proposed LAR is not associated with a licensed thermal power uprate and the plant will continue to operate at the current power level. | |||
* The NRC staff recommended that the licensee include plans in the proposed LAR to implement long-term trending and data collection of other plant | |||
-2 -parameters to substantiate the accuracy of the Caldon Ultrasonic Technology Center (Caldon) equipment. The staff proposed that Caldon could help the licensee determine what parameters to trend. | |||
* The NRC staff stated that uncertainties for the LEFM technology are significantly less than UFM technology and requested that the licensee include a discussion on how the uncertainties will be treated in the proposed LAR. | |||
* In response to the licensee's request for an expedited review, the NRC staff stated that it may not be able to support the review schedule requested by the licensee. Based on the available resources, the NRC staff will make every effort to support the proposed schedule. After the conclusion of the meeting, the NRC staff noted page 3 of the STP presentation incorrectly stated the TS number. The correct TS number is 6.9.1.6, as stated in page 8 (summary slide) of the STP presentation. No Public Meeting Feedback Forms were received for this meeting. Please direct any inquiries to me at (301) 415-3016, or balwant.singal@nrc.gov. Docket Nos. 50-445 and 50-446 | |||
===Enclosures:=== | |||
1. List of Attendees 2. Licensee Presentation Slides cc w/encl: Distribution via Listserv | |||
Sincerely,Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LIST OF ATTENDEES JULY 7, 2014. MEETING WITH STP NUCLEAR OPERATING COMPANY LLC REGARDING REPLACING CROSSFLOW UFM WITH LEFM TECHNOLOGY Name Sujata Goetz Balwant Singal Peter Snyder Matthew Hamm Warren Lyon Samir Darbali Joanna Phillips Ernie Hauser Jacob Park Lance Sterling Mike Murray Jonathan Pierce Gary Jones Francis Comeaux Charles Albury Rafael Gonzales SOUTH TEXAS PROJECT. UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 Title Organization Project Manager NRR/DORLILPL4-1 Senior Project Manager NRR/ DORLILPL4-1 Reactor Systems Engineer NRR/DSS/STSB Reactor Systems Engineer NRR/DSS/STSB Senior Reactor Engineer NRR/DSS/SRXB Electronics Engineer NRR/DE/EICB Cameron** Cameron** STPNOC STPNOC STPNOC STPNOC STPNOC STPNOC STPNOC STPNOC ** STPNOC Contractor Enclosure 1 ENCLOSURE 2 LICENSEE SLIDE PRESENTATION JULY 7, 2014, MEETING South Texas Project AMAG Crossflow UFM change to Cameron/Caldon LEFM License Amendment Request (LAR) July 7, 2014 Desired Outcomes Provide LAR scope Discuss schedule for LAR and implementation Capture NRC Insights 2 LAR Scope Change to the administrative section of the Technical Specifications (TS 6.1.9.6) o Section states Crossflow UFM technology is input to COLR o LARwill replace Crossflow UFM technology with LEFM technology 3 LAR Details Change is not a power uprate Change uses NRC-approved technology o (Cal don Ultrasonics Engineering Report ER-1 5 7(P-A) Rev. 8 and Rev. 8 Errata, "Supplement to Caldon Topical Report ER-80P: Basis for Power Uprates with an LEFM Check or an LEFM CheckPius System,") Replacement is considered equivalent or better than current AMAG UFM system 4 Strategy Based on equipment change and Admin TS change only, does the NRC have any questions regarding this strategy 5 Schedule Submit july 31, 2014 Request expedited NRC review (Feb 201 5) Install in Unit 2 (Spring 201 5 refueling outage) Install in Unit 1 (Fall 201 5 refueling outage) 6 u 0::: z -c c:: rd u 0 c z 0 *-Q. V') V') I-::::s u Vl V') *--c c Q) c. 0 ..... | |||
Summary Not a power uprate Change to the administrative Technical Specification Section (TS 6.9.1 .6) Cameron/Caldon LEFM is NRC-approved Expedited review requested 8 | |||
-2-* parameters to substantiate the accuracy of the Caldon Ultrasonic Technology Center (Caldon) equipment. The staff proposed that Caldon could help the licensee determine what parameters to trend. | |||
* The NRC staff stated that uncertainties for the LEFM technology are significantly less than UFM technology and requested that the licensee include a discussion on how the uncertainties will be treated in the proposed LAR. | |||
* In response to the licensee's request for an expedited review, the NRC staff stated that it may not be able to support the review schedule requested by the licensee. Based on the available resources, the NRC staff will make every effort to support the proposed schedule. After the conclusion of the meeting, the NRC staff noted page 3 of the STP presentation incorrectly stated the TS number. The correct TS number is 6.9.1.6, as stated in page 8 (summary slide) of the STP presentation. No Public Meeting Feedback Forms were received for this meeting. Please direct any inquiries to me at (301) 415-3016, or balwant.singal@nrc.gov. | |||
Sincerely,IRA/ Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446 | |||
===Enclosures:=== | |||
1 . List of Attendees 2. Licensee Presentation Slides cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 r/f RidsAcrsAcnw_MaiiCTR Resource RidsNrrDe/EICB Resource RidsNrrDorllpl4-1 Resource RidsNrrDssSrxb Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMSouth Texas Resource RidsRgn4MaiiCenter Resource SGoetz, NRR/DORL/LP4-1 REIIiott, NRR!DSS/STSB PSnyder, NRR/DSS/STSB MHamm, NRR/DSS/STSB SDarbali, NRR/DE/EICB Wlyon, NRR/DSS/SRXB ADAMS Accession No.: ML 14192A984 *Via e-mail OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/PM NRRIDORL/LPL4-1 /LA NRR/DSS/STSB/BC NAME SGoetz BSingal JBurkhardt REIIiott DATE 7/22/14 7/22/14 7/22/14 7/23/14 OFFICE NRR/DSS/SRXB/BC NRR/DE/EICB/BC NRR/DORL/LPL4-1 /BC NRR/DORL!LPL4-1 /PM NAME CJackson (UShoop for) JThorp MMarkley (EOesterle for) BSingal DATE 7/29/14 7/29/14 8/1/14 8/4/14 OFFICIAL RECORD COPY}} |
Revision as of 04:53, 16 March 2018
ML14192A984 | |
Person / Time | |
---|---|
Site: | South Texas ![]() |
Issue date: | 08/04/2014 |
From: | Singal B K Plant Licensing Branch IV |
To: | |
Singal B K | |
References | |
TAC MF4291, TAC MF4292 | |
Download: ML14192A984 (13) | |
Text
LICENSEE: STP Nuclear Operating Company FACILITY: South Texas Project, Units 1 and 2
SUBJECT: SUMMARY OF JULY 7, 2014, PRE-LICENSING PUBLIC MEETING WITH STP NUCLEAR OPERATING COMPANY TO DISCUSS THE PROPOSED LICENSE AMENDMENT REQUEST FOR REPLACING CROSSFLOW ULTRASONIC FLOW MEASUREMENT WITH LEADING EDGE FLOW METER TECHNOLOGY (TAC NOS. MF4291 AND MF4292) On July 7, 2014, a public meeting was held between the U.S. Nuclear Regulatory Commission (NRC), and representatives of STP Nuclear Operating Company (STPNOC, the licensee), at NRC Headquarters, Rockville, Maryland. The meeting notice and agenda, dated June 23, 2014, is located in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML 14174B375. The purpose of the meeting was to discuss the license amendment request (LAR) for replacing Crossflow Ultrasonic Flow Measurement (UFM) technology with Leading Edge Flow Meter (LEFM) technology. This change affects Technical Specification (TS) 6.9.1.6, "Core Operating Limits Report (COLR)." A list of meeting attendees is provided in Enclosure 1 to this meeting summary. Meeting Summary The discussion was based on the following meeting materials/handouts, which is provided in Enclosure 2 of this meeting summary:
- Slides provided by STPNOC, "AMAG [Advanced Measurements & Analysis Group] Crossflow UFM Change to Cameron I Caldon LEFM, July 7, 2014" (Enclosure 2) Discussion:
- The licensee stated that its objective was to change the administrative section of TS 6.9.1.6. The proposed LARwill replace the Crossflow UFM with LEFM technology, which is an NRC-approved technology. The licensee stated that it intends to follow the guidance in Regulatory Issue Summary (RIS) 2002-03, "Guidance on the Content of Measurement Uncertainty Recapture Power Uprate Applications," dated January 31, 2002 (ADAMS Accession No. ML013530183). The licensee clarified that the proposed LAR is not associated with a licensed thermal power uprate and the plant will continue to operate at the current power level.
- The NRC staff recommended that the licensee include plans in the proposed LAR to implement long-term trending and data collection of other plant
-2 -parameters to substantiate the accuracy of the Caldon Ultrasonic Technology Center (Caldon) equipment. The staff proposed that Caldon could help the licensee determine what parameters to trend.
- The NRC staff stated that uncertainties for the LEFM technology are significantly less than UFM technology and requested that the licensee include a discussion on how the uncertainties will be treated in the proposed LAR.
- In response to the licensee's request for an expedited review, the NRC staff stated that it may not be able to support the review schedule requested by the licensee. Based on the available resources, the NRC staff will make every effort to support the proposed schedule. After the conclusion of the meeting, the NRC staff noted page 3 of the STP presentation incorrectly stated the TS number. The correct TS number is 6.9.1.6, as stated in page 8 (summary slide) of the STP presentation. No Public Meeting Feedback Forms were received for this meeting. Please direct any inquiries to me at (301) 415-3016, or balwant.singal@nrc.gov. Docket Nos. 50-445 and 50-446
Enclosures:
1. List of Attendees 2. Licensee Presentation Slides cc w/encl: Distribution via Listserv
Sincerely,Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LIST OF ATTENDEES JULY 7, 2014. MEETING WITH STP NUCLEAR OPERATING COMPANY LLC REGARDING REPLACING CROSSFLOW UFM WITH LEFM TECHNOLOGY Name Sujata Goetz Balwant Singal Peter Snyder Matthew Hamm Warren Lyon Samir Darbali Joanna Phillips Ernie Hauser Jacob Park Lance Sterling Mike Murray Jonathan Pierce Gary Jones Francis Comeaux Charles Albury Rafael Gonzales SOUTH TEXAS PROJECT. UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499 Title Organization Project Manager NRR/DORLILPL4-1 Senior Project Manager NRR/ DORLILPL4-1 Reactor Systems Engineer NRR/DSS/STSB Reactor Systems Engineer NRR/DSS/STSB Senior Reactor Engineer NRR/DSS/SRXB Electronics Engineer NRR/DE/EICB Cameron** Cameron** STPNOC STPNOC STPNOC STPNOC STPNOC STPNOC STPNOC STPNOC ** STPNOC Contractor Enclosure 1 ENCLOSURE 2 LICENSEE SLIDE PRESENTATION JULY 7, 2014, MEETING South Texas Project AMAG Crossflow UFM change to Cameron/Caldon LEFM License Amendment Request (LAR) July 7, 2014 Desired Outcomes Provide LAR scope Discuss schedule for LAR and implementation Capture NRC Insights 2 LAR Scope Change to the administrative section of the Technical Specifications (TS 6.1.9.6) o Section states Crossflow UFM technology is input to COLR o LARwill replace Crossflow UFM technology with LEFM technology 3 LAR Details Change is not a power uprate Change uses NRC-approved technology o (Cal don Ultrasonics Engineering Report ER-1 5 7(P-A) Rev. 8 and Rev. 8 Errata, "Supplement to Caldon Topical Report ER-80P: Basis for Power Uprates with an LEFM Check or an LEFM CheckPius System,") Replacement is considered equivalent or better than current AMAG UFM system 4 Strategy Based on equipment change and Admin TS change only, does the NRC have any questions regarding this strategy 5 Schedule Submit july 31, 2014 Request expedited NRC review (Feb 201 5) Install in Unit 2 (Spring 201 5 refueling outage) Install in Unit 1 (Fall 201 5 refueling outage) 6 u 0::: z -c c:: rd u 0 c z 0 *-Q. V') V') I-::::s u Vl V') *--c c Q) c. 0 .....
Summary Not a power uprate Change to the administrative Technical Specification Section (TS 6.9.1 .6) Cameron/Caldon LEFM is NRC-approved Expedited review requested 8
-2-* parameters to substantiate the accuracy of the Caldon Ultrasonic Technology Center (Caldon) equipment. The staff proposed that Caldon could help the licensee determine what parameters to trend.
- The NRC staff stated that uncertainties for the LEFM technology are significantly less than UFM technology and requested that the licensee include a discussion on how the uncertainties will be treated in the proposed LAR.
- In response to the licensee's request for an expedited review, the NRC staff stated that it may not be able to support the review schedule requested by the licensee. Based on the available resources, the NRC staff will make every effort to support the proposed schedule. After the conclusion of the meeting, the NRC staff noted page 3 of the STP presentation incorrectly stated the TS number. The correct TS number is 6.9.1.6, as stated in page 8 (summary slide) of the STP presentation. No Public Meeting Feedback Forms were received for this meeting. Please direct any inquiries to me at (301) 415-3016, or balwant.singal@nrc.gov.
Sincerely,IRA/ Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
1 . List of Attendees 2. Licensee Presentation Slides cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 r/f RidsAcrsAcnw_MaiiCTR Resource RidsNrrDe/EICB Resource RidsNrrDorllpl4-1 Resource RidsNrrDssSrxb Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMSouth Texas Resource RidsRgn4MaiiCenter Resource SGoetz, NRR/DORL/LP4-1 REIIiott, NRR!DSS/STSB PSnyder, NRR/DSS/STSB MHamm, NRR/DSS/STSB SDarbali, NRR/DE/EICB Wlyon, NRR/DSS/SRXB ADAMS Accession No.: ML 14192A984 *Via e-mail OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/PM NRRIDORL/LPL4-1 /LA NRR/DSS/STSB/BC NAME SGoetz BSingal JBurkhardt REIIiott DATE 7/22/14 7/22/14 7/22/14 7/23/14 OFFICE NRR/DSS/SRXB/BC NRR/DE/EICB/BC NRR/DORL/LPL4-1 /BC NRR/DORL!LPL4-1 /PM NAME CJackson (UShoop for) JThorp MMarkley (EOesterle for) BSingal DATE 7/29/14 7/29/14 8/1/14 8/4/14 OFFICIAL RECORD COPY