ML13101A354: Difference between revisions
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| issue date = 04/18/2013 | | issue date = 04/18/2013 | ||
| title = Request for Additional Information Concerning Revising the Condensate Storage Tank Level (TAC ME9293 and ME9294) | | title = Request for Additional Information Concerning Revising the Condensate Storage Tank Level (TAC ME9293 and ME9294) | ||
| author name = Brown E | | author name = Brown E | ||
| author affiliation = NRC/NRR/DORL/LPLII-1 | | author affiliation = NRC/NRR/DORL/LPLII-1 | ||
| addressee name = Pierce C | | addressee name = Pierce C | ||
| addressee affiliation = Southern Nuclear Operating Co, Inc | | addressee affiliation = Southern Nuclear Operating Co, Inc | ||
| docket = 05000348, 05000364 | | docket = 05000348, 05000364 | ||
| license number = NPF-002, NPF-008 | | license number = NPF-002, NPF-008 | ||
| contact person = Brown E | | contact person = Brown E NRR/DORL/LPL2-1 | ||
| case reference number = TAC ME9293, TAC ME9294 | | case reference number = TAC ME9293, TAC ME9294 | ||
| document type = Letter, Request for Additional Information (RAI) | | document type = Letter, Request for Additional Information (RAI) | ||
Line 30: | Line 30: | ||
==Dear Mr. Pierce:== | ==Dear Mr. Pierce:== | ||
By letter dated August 20,2012, Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The LAR would revise the condensate storage tank (CST) level requirement specified in Technical Specification Surveillance Requirement 3.7.6.1. The change is related to the calculational basis for the level with respect to potential vortexing and assumptions regarding heat loads on CST volume. The U.S. Nuclear Regulatory Commission (NRC) staff finds that additional information is needed as set forth in the Enclosure. | By letter dated August 20,2012, Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The LAR would revise the condensate storage tank (CST) level requirement specified in Technical Specification Surveillance Requirement 3.7.6.1. The change is related to the calculational basis for the level with respect to potential vortexing and assumptions regarding heat loads on CST volume. The U.S. Nuclear Regulatory Commission (NRC) staff finds that additional information is needed as set forth in the Enclosure. | ||
A response to the enclosed Request for Additional Information (RAI) is needed before the NRC staff can complete the review. This request was discussed with Mr. Ken McElroy of your staff on March 30, 2013, and as no response date was suggested to this request and another issued by the NRC staff on November 26,2012, SNC is requested to reply within 60 days of the issuance of this letter. Please note that if SNC does not respond to this letter by the date provided, the NRC staff may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information." Sincerely, IRA! Eva A Brown, 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 Request for Additional cc w/encl: Distribution via DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsNrrDssStsb Resource SSun, NRR RidsNrrPMFarley Resource WLyon, NRR GArmstrong, NRR MHamm, NRR RisNrrDssSbpb ADAMS Accession No" | A response to the enclosed Request for Additional Information (RAI) is needed before the NRC staff can complete the review. This request was discussed with Mr. Ken McElroy of your staff on March 30, 2013, and as no response date was suggested to this request and another issued by the NRC staff on November 26,2012, SNC is requested to reply within 60 days of the issuance of this letter. Please note that if SNC does not respond to this letter by the date provided, the NRC staff may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information." Sincerely, IRA! Eva A Brown, 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 Request for Additional cc w/encl: Distribution via DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsNrrDssStsb Resource SSun, NRR RidsNrrPMFarley Resource WLyon, NRR GArmstrong, NRR MHamm, NRR RisNrrDssSbpb ADAMS Accession No" ML13101A354 | ||
"" OFFICE DORLlLPL2-1/PM DORLlLPL2-1/LA DSS/SRXBI BC DORLlLPL2-1/BC NAME EBrown SFigueroa CJackson (SSun for) RPascarelli DATE 04/11/13 04/16/13 04/17/13 04/18/13 OFFICIAL RECORD COPY}} | "" OFFICE DORLlLPL2-1/PM DORLlLPL2-1/LA DSS/SRXBI BC DORLlLPL2-1/BC NAME EBrown SFigueroa CJackson (SSun for) RPascarelli DATE 04/11/13 04/16/13 04/17/13 04/18/13 OFFICIAL RECORD COPY}} |
Revision as of 05:09, 22 June 2019
ML13101A354 | |
Person / Time | |
---|---|
Site: | Farley |
Issue date: | 04/18/2013 |
From: | Ellen Brown Plant Licensing Branch II |
To: | Pierce C Southern Nuclear Operating Co |
Brown E NRR/DORL/LPL2-1 | |
References | |
TAC ME9293, TAC ME9294 | |
Download: ML13101A354 (3) | |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 18, 2013 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. Post Office Box 1295 -BIN 038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2-REQUEST ADDITIONAL INFORMATION CONCERNING REVISING THE STORAGE TANK LEVEL (TAC NOS. ME9293 AND
Dear Mr. Pierce:
By letter dated August 20,2012, Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The LAR would revise the condensate storage tank (CST) level requirement specified in Technical Specification Surveillance Requirement 3.7.6.1. The change is related to the calculational basis for the level with respect to potential vortexing and assumptions regarding heat loads on CST volume. The U.S. Nuclear Regulatory Commission (NRC) staff finds that additional information is needed as set forth in the Enclosure.
A response to the enclosed Request for Additional Information (RAI) is needed before the NRC staff can complete the review. This request was discussed with Mr. Ken McElroy of your staff on March 30, 2013, and as no response date was suggested to this request and another issued by the NRC staff on November 26, 2012, SNC is requested to reply within 60 days of the issuance of this letter. Please note that if SNC does not respond to this letter by the date provided, the NRC staff may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information. " Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 SOUTHERN NUCLEAR OPERATING COMPANY DOCKET NOS. 50-348 AND 50-364 Farley uses a vortex correlation developed by Harleman (1959) for a vertically downward configuration that differs from the 45 degree upward flow pipe used at Farley. This correlation is shown to over-predict the submergence by a factor of three when compared to Catawba and McGuire test data at the Froude number that corresponds to the maximum flow rate from the CST. This would be a sufficient margin to justify using the Harleman correlation to support the LAR if the test data were established to be applicable.
Achieving this requires an acceptable description of the plant configurations, the test configurations, and the test data. Provide a complete description of the tests and test results for each test used to substantiate determination of critical submergence that includes the following: Drawing of the plant tank and the plant suction pipe within the tank that provides all relevant dimensions, Drawing of the corresponding test configuration that provides all relevant dimensions, Description of how quantitative air entrainment is determined during testing, Description of conduct of the test that includes any observations, and Summary of the test data such as a plot of critical submergence as a function of Froude number.
References:
Harleman, D. R. (1959). "Selective Withdrawal from a Vertically Stratified Fluid". Proceedings, Eighth Congress of the International Association for Hydraulics Research, Paper 10-C. Enclosure April 18, 2013 Mr. C. R Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. Post Office Box 1295 -BIN 038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2-REQUEST FOR ADDITIONAL INFORMATION CONCERNING REVISING THE CONDENSATE STORAGE TANK LEVEL (TAC NOS. ME9293 AND ME9294)
Dear Mr. Pierce:
By letter dated August 20,2012, Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The LAR would revise the condensate storage tank (CST) level requirement specified in Technical Specification Surveillance Requirement 3.7.6.1. The change is related to the calculational basis for the level with respect to potential vortexing and assumptions regarding heat loads on CST volume. The U.S. Nuclear Regulatory Commission (NRC) staff finds that additional information is needed as set forth in the Enclosure.
A response to the enclosed Request for Additional Information (RAI) is needed before the NRC staff can complete the review. This request was discussed with Mr. Ken McElroy of your staff on March 30, 2013, and as no response date was suggested to this request and another issued by the NRC staff on November 26,2012, SNC is requested to reply within 60 days of the issuance of this letter. Please note that if SNC does not respond to this letter by the date provided, the NRC staff may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information." Sincerely, IRA! Eva A Brown, 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 Request for Additional cc w/encl: Distribution via DISTRIBUTION PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsNrrDssStsb Resource SSun, NRR RidsNrrPMFarley Resource WLyon, NRR GArmstrong, NRR MHamm, NRR RisNrrDssSbpb ADAMS Accession No" ML13101A354
"" OFFICE DORLlLPL2-1/PM DORLlLPL2-1/LA DSS/SRXBI BC DORLlLPL2-1/BC NAME EBrown SFigueroa CJackson (SSun for) RPascarelli DATE 04/11/13 04/16/13 04/17/13 04/18/13 OFFICIAL RECORD COPY