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| number = ML14339A030
| number = ML14339A030
| issue date = 01/09/2015
| issue date = 01/09/2015
| title = Virgil C. Summer Nuclear Station, Unit No. 1 - Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis (TAC No. MF4699)
| title = Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis
| author name = Williams S A
| author name = Williams S
| author affiliation = NRC/NRR/DORL/LPLII-1
| author affiliation = NRC/NRR/DORL/LPLII-1
| addressee name = Gatlin T D
| addressee name = Gatlin T
| addressee affiliation = South Carolina Electric & Gas Co
| addressee affiliation = South Carolina Electric & Gas Co
| docket = 05000395
| docket = 05000395
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 9, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 9, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065


==SUBJECT:==
==SUBJECT:==
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS (TAG NO. MF4699)  
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS (TAG NO. MF4699)


==Dear Mr. Gatlin:==
==Dear Mr. Gatlin:==
By letter dated August 27, 2014, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a license amendment request to revise Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requests approval to revise the licensing basis to incorporate a supplemental analysis to the steam generator tube rupture accident.
By letter dated August 27, 2014, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a license amendment request to revise Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requests approval to revise the licensing basis to incorporate a supplemental analysis to the steam generator tube rupture accident.
The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure.
The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAis within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.
We request that SCE&G respond to these RAis within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.
Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 .
Docket No. 50-395  
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395


==Enclosure:==
==Enclosure:==


Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 . Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Virgil C. Summer Nuclear Station License Amendment Request (LAR), LAR-12-04269, dated August 27, 2014, concerning the license basis changes required due to an update to the Steam Generator Tube Rupture (SGTR) analysis.
Request for Additional Information cc w/encl: Distribution via Listserv
The NRC staff has determined that the following request for additional information (RAJ) is required to complete its review.
 
RAI No.1 I In application dated August 27, 2014, it stated: New SGTR dose analyses are also performed by Westinghouse using, consistent with the Virgil C. Summer Licensing Basis, the RADTRAD computer program following the guidance of Regulatory Guide 1.183. Dose consequences are provided for the mass transfer input from the current licensing basis and new transient analyses.  
REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Virgil C. Summer Nuclear Station License Amendment Request (LAR), LAR-12-04269, dated August 27, 2014, concerning the license basis changes required due to an update to the Steam Generator Tube Rupture (SGTR) analysis. The NRC staff has determined that the following request for additional information (RAJ) is required to complete its review.
-During the review process the NRC staff noticed what appear to be some differences between the current license basis SGTR analysis parameters and the proposed SGTR analysis parameters that are not discussed in SCE&G's LAR. Therefore, the NRC staff is requesting that a table be provided for the SGTR analysis that lists: (1) The parameters used in the SGTR dose analysis, (2) the current approved SGTR modeled value for each parameter listed in VCSNS Updated Final Safety Analysis Report, (3) the new modeled value for each parameter in the revised SGTR analysis, and (4) a description of the technical basis that explains why the new modeled value changed. "-(NOTE: Tables 9 through 14 in the LAR already provide items (1) and (3) above and could be revised to include items (2) and (4)). RAI No.2 Provide the RADTRAD input and output files for the new SGTR analysis.
RAI No.1 I
In application dated August 27, 2014, it stated:
New SGTR dose analyses are also performed by Westinghouse using, consistent with the Virgil C. Summer Licensing Basis, the RADTRAD computer program following the guidance of Regulatory Guide 1.183. Dose consequences are provided for the mass transfer input from the current licensing basis and new transient analyses.           -
During the review process the NRC staff noticed what appear to be some differences between the current license basis SGTR analysis parameters and the proposed SGTR analysis parameters that are not discussed in SCE&G's LAR. Therefore, the NRC staff is requesting that a table be provided for the SGTR analysis that lists: (1) The parameters used in the SGTR dose analysis, (2) the current approved SGTR modeled value for each parameter listed in VCSNS Updated Final Safety Analysis Report, (3) the new modeled value for each parameter in the revised SGTR analysis, and (4) a description of the technical basis that explains why the new modeled value changed.
(NOTE: Tables 9 through 14 in the LAR already provide items (1) and (3) above and could be revised to include items (2) and (4)).
RAI No.2 Provide the RADTRAD input and output files for the new SGTR analysis.
RAI No.3 As presented in LAR 12-04269, LOFTTR2 was used, per the methodology of WCAP:10698-P, to perform SGTR transient analyses for VCSNS. Does the version of LOFTTR2 used in the analysis presented in LAR 12-04269 contain any code modifications?
RAI No.3 As presented in LAR 12-04269, LOFTTR2 was used, per the methodology of WCAP:10698-P, to perform SGTR transient analyses for VCSNS. Does the version of LOFTTR2 used in the analysis presented in LAR 12-04269 contain any code modifications?
Enclosure   RAI No.4 The referenced Steam Generator Tube analysis methodology (WCAP-1 0698) contains a single failure analysis relative to margin to overfill.
Enclosure
When a new methodology is referenced by an applicant, exceptions to portions of the methodology typically require a technical basis. What is the technical basis for not considering a single failure?
January 9, 2015 Mr. Thomas D. (3atlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer NUclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SG 29065
 
==SUBJECT:==
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE BASIS CHANGES IN GENERATOR TUBE RUPTURE ANALYSIS (TAC NO. MF4699)
 
==Dear Mr. Gatlin:==
By letter dated August 27, 2014, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a license amendment request to revise Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requests approval to revise the licensing basis to incorporate a supplemental analysis to the steam generator tube rupture accident.
The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure.
We request that SCE&G respond to these RAis within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.
Docket No. 50-395


==Enclosure:==
RAI No.4 The referenced Steam Generator Tube analysis methodology (WCAP-1 0698) contains a single failure analysis relative to margin to overfill. When a new methodology is referenced by an applicant, exceptions to portions of the methodology typically require a technical basis. What is the technical basis for not considering a single failure?


Sincerely, /RAJ Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
ML14339A030 OFFICE     LPL2-1/PM           LPL2-1/LA             LPL2-1/BC             LPL2-1/PM NAME       SWilliams           SFigueroa             RPascarelli         SWilliams DATE       12/31/14             01/06/15               01/08/15             01/09/15}}
PUBLIC RidsNrrDoriDpr Resource RidsNrrLASFigueroa Resource LPL2-1 R/F RidsNrrDorllpl2-1 Resource RidsNrrDRA Resource RidsAcrsAcnw_MaiiCTR Resource RidsRgn2MaiiCenter Resource RidsNrrPMSummer Resource ADAMS Accession No.: ML 14339A030 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 12/31/14 01/06/15 01/08/15 01/09/15 OFFICIAL RECORD COPY}}

Latest revision as of 16:15, 5 February 2020

Request for Additional Information Regarding License Basis Changes in Steam Generator Tube Rupture Analysis
ML14339A030
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 01/09/2015
From: Shawn Williams
Plant Licensing Branch II
To: Gatlin T
South Carolina Electric & Gas Co
Williams S
References
TAC MF4699
Download: ML14339A030 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 9, 2015 Mr. Thomas D. Gatlin Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS (TAG NO. MF4699)

Dear Mr. Gatlin:

By letter dated August 27, 2014, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a license amendment request to revise Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit No. 1. The licensee requests approval to revise the licensing basis to incorporate a supplemental analysis to the steam generator tube rupture accident.

The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. We request that SCE&G respond to these RAis within 30 days of the date of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.

Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 .

Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

REQUESTS FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST LICENSE BASIS CHANGES IN STEAM GENERATOR TUBE RUPTURE ANALYSIS VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-395 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the Virgil C. Summer Nuclear Station License Amendment Request (LAR), LAR-12-04269, dated August 27, 2014, concerning the license basis changes required due to an update to the Steam Generator Tube Rupture (SGTR) analysis. The NRC staff has determined that the following request for additional information (RAJ) is required to complete its review.

RAI No.1 I

In application dated August 27, 2014, it stated:

New SGTR dose analyses are also performed by Westinghouse using, consistent with the Virgil C. Summer Licensing Basis, the RADTRAD computer program following the guidance of Regulatory Guide 1.183. Dose consequences are provided for the mass transfer input from the current licensing basis and new transient analyses. -

During the review process the NRC staff noticed what appear to be some differences between the current license basis SGTR analysis parameters and the proposed SGTR analysis parameters that are not discussed in SCE&G's LAR. Therefore, the NRC staff is requesting that a table be provided for the SGTR analysis that lists: (1) The parameters used in the SGTR dose analysis, (2) the current approved SGTR modeled value for each parameter listed in VCSNS Updated Final Safety Analysis Report, (3) the new modeled value for each parameter in the revised SGTR analysis, and (4) a description of the technical basis that explains why the new modeled value changed.

(NOTE: Tables 9 through 14 in the LAR already provide items (1) and (3) above and could be revised to include items (2) and (4)).

RAI No.2 Provide the RADTRAD input and output files for the new SGTR analysis.

RAI No.3 As presented in LAR 12-04269, LOFTTR2 was used, per the methodology of WCAP:10698-P, to perform SGTR transient analyses for VCSNS. Does the version of LOFTTR2 used in the analysis presented in LAR 12-04269 contain any code modifications?

Enclosure

RAI No.4 The referenced Steam Generator Tube analysis methodology (WCAP-1 0698) contains a single failure analysis relative to margin to overfill. When a new methodology is referenced by an applicant, exceptions to portions of the methodology typically require a technical basis. What is the technical basis for not considering a single failure?

ML14339A030 OFFICE LPL2-1/PM LPL2-1/LA LPL2-1/BC LPL2-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 12/31/14 01/06/15 01/08/15 01/09/15

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