ML16042A471: Difference between revisions
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2016 Mr. George A. Lippard, Ill Vice President, Nuclear Operations South Carolina Electric | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2016 Mr. George A. Lippard, Ill Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065 | ||
& 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 (CAC NO. MF7085) | VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION (CAC NO. MF7085) | ||
==Dear Mr. Lippard:== | ==Dear Mr. Lippard:== | ||
By letter dated January 20, 2015, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a relief request for Virgil C. Summer, Unit 1, for the third ten-year inservice inspection interval. | |||
By letter dated January 20, 2015, the South Carolina Electric | |||
& Gas Company (SCE&G, the licensee) submitted a relief request for Virgil C. Summer, Unit 1, for the third ten-year inservice inspection interval. | |||
The licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell. The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. | The licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell. 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 RAls 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 RAls 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. | ||
Line 35: | Line 31: | ||
==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 REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NUMBER RR-111-12 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 SOUTH CAROLINA ELECTRIC | 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 REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NUMBER RR-111-12 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 SOUTH CAROLINA ELECTRIC & GAS COMPANY DOCKET NUMBER 50-395 By letter dated November 10, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15316A556), South Carolina Electric & Gas Company, the licensee, submitted relief request number RR-111-12 to the U.S. Nuclear Regulatory Commission (NRC) for the third ten-year inservice inspection interval of Virgil C. Summer Nuclear Station, Unit 1. In relief request RR-111-12, the licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell identified in the licensee's submittal. | ||
& GAS COMPANY DOCKET NUMBER 50-395 By letter dated November 10, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15316A556), | |||
South Carolina Electric | |||
& Gas Company, the licensee, submitted relief request number RR-111-12 to the U.S. Nuclear Regulatory Commission (NRC) for the third ten-year inservice inspection interval of Virgil C. Summer Nuclear Station, Unit 1. In relief request RR-111-12, the licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell identified in the licensee's submittal. | |||
These two welds are ASME Code, Section XI, Examination Category C-A welds, Item Nos. C1 .20. The licensee has determined that conformance with the examination requirements Section XI of the ASME Code for these welds is impractical. | These two welds are ASME Code, Section XI, Examination Category C-A welds, Item Nos. C1 .20. The licensee has determined that conformance with the examination requirements Section XI of the ASME Code for these welds is impractical. | ||
Title 1 O of the Code of Federal Regulations (1 O CFR), Part 50, Paragraph 50.55a(g)(5)(iii) requires the licensee to submit information to the NRC to support the determination of impracticality. | Title 1 O of the Code of Federal Regulations (1 O CFR), Part 50, Paragraph 50.55a(g)(5)(iii) requires the licensee to submit information to the NRC to support the determination of impracticality. | ||
The NRC staff has determined that the following request for additional information (RAI) is required to complete its review. RAI No. 1 Please discuss the ASME Code Section XI, Appendix I requirement from which procedure SCANA-UT-98-13 is based. If supplements apply, please discuss which supplements were used. RAI No. 2 Please discuss any plant-specific operating experience regarding potential degradation in welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, such as stress corrosion | The NRC staff has determined that the following request for additional information (RAI) is required to complete its review. RAI No. 1 Please discuss the ASME Code Section XI, Appendix I requirement from which procedure SCANA-UT-98-13 is based. If supplements apply, please discuss which supplements were used. RAI No. 2 Please discuss any plant-specific operating experience regarding potential degradation in welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, such as stress corrosion cracking, fatigue cracking, and general corrosion. | ||
Enclosure February 18, 2016 Mr. George A Lippard, Ill Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065 | |||
Enclosure February 18, 2016 Mr. George A Lippard, Ill 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 (CAC NO. MF7085) | VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION (CAC NO. MF7085) | ||
==Dear Mr. Lippard:== | ==Dear Mr. Lippard:== | ||
By letter dated January 20, 2015, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a relief request for Virgil C. Summer, Unit 1, for the third ten-year inservice inspection interval. | |||
By letter dated January 20, 2015, the South Carolina Electric | |||
& Gas Company (SCE&G, the licensee) submitted a relief request for Virgil C. Summer, Unit 1, for the third ten-year inservice inspection interval. | |||
The licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell. The NRC staff has determined that additional information is needed to continue the review as discussed in the Enclosure. | The licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell. 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 RAls 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 RAls 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. | ||
Line 61: | Line 49: | ||
Sincerely, IRA/ 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: | Sincerely, IRA/ 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: | ||
PUBLIC RidsNrrDorlDpr Resource RidsNrrLASFigueroa Resource | PUBLIC RidsNrrDorlDpr Resource RidsNrrLASFigueroa Resource DDijamco, NRR LPL2-1 R/F RidsNrrDorllpl2-1 Resource RidsNrrDRA Resource ADAMS A ccess1on N o.: ML 16042A471 | ||
* b *1 1yema1 OFFICE LPL2-1/PM LPL2-1/LA NRR/DE/EVIB/BC* | * b *1 1yema1 OFFICE LPL2-1/PM LPL2-1/LA NRR/DE/EVIB/BC* | ||
NAME SWilliams SFigueroa JMcHale* | NAME SWilliams SFigueroa JMcHale* DATE 2/18/2016 2/17/2016 2/10/2016 OFFICIAL RECORD COPY RidsAcrs_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrPMSummer Resource LPL2-1/BC LPL2-1/PM MMarkley SWilliams 2/18/2016 2/18/2016}} | ||
DATE 2/18/2016 2/17/2016 2/10/2016 OFFICIAL RECORD COPY RidsAcrs_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrPMSummer Resource LPL2-1/BC LPL2-1/PM MMarkley SWilliams 2/18/2016 2/18/2016}} |
Revision as of 16:11, 8 July 2018
ML16042A471 | |
Person / Time | |
---|---|
Site: | Summer ![]() |
Issue date: | 02/18/2016 |
From: | Williams S A Plant Licensing Branch II |
To: | Lippard G A South Carolina Electric & Gas Co |
Williams S A, NRR/DORL/LPLII-1 | |
References | |
CAC MF7085 | |
Download: ML16042A471 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2016 Mr. George A. Lippard, Ill 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 (CAC NO. MF7085)
Dear Mr. Lippard:
By letter dated January 20, 2015, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a relief request for Virgil C. Summer, Unit 1, for the third ten-year inservice inspection interval.
The licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell. 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 RAls 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:
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 REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NUMBER RR-111-12 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 SOUTH CAROLINA ELECTRIC & GAS COMPANY DOCKET NUMBER 50-395 By letter dated November 10, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15316A556), South Carolina Electric & Gas Company, the licensee, submitted relief request number RR-111-12 to the U.S. Nuclear Regulatory Commission (NRC) for the third ten-year inservice inspection interval of Virgil C. Summer Nuclear Station, Unit 1. In relief request RR-111-12, the licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell identified in the licensee's submittal.
These two welds are ASME Code,Section XI, Examination Category C-A welds, Item Nos. C1 .20. The licensee has determined that conformance with the examination requirementsSection XI of the ASME Code for these welds is impractical.
Title 1 O of the Code of Federal Regulations (1 O CFR), Part 50, Paragraph 50.55a(g)(5)(iii) requires the licensee to submit information to the NRC to support the determination of impracticality.
The NRC staff has determined that the following request for additional information (RAI) is required to complete its review. RAI No. 1 Please discuss the ASME Code Section XI, Appendix I requirement from which procedure SCANA-UT-98-13 is based. If supplements apply, please discuss which supplements were used. RAI No. 2 Please discuss any plant-specific operating experience regarding potential degradation in welds CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, such as stress corrosion cracking, fatigue cracking, and general corrosion.
Enclosure February 18, 2016 Mr. George A Lippard, Ill 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 (CAC NO. MF7085)
Dear Mr. Lippard:
By letter dated January 20, 2015, the South Carolina Electric & Gas Company (SCE&G, the licensee) submitted a relief request for Virgil C. Summer, Unit 1, for the third ten-year inservice inspection interval.
The licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 piping welds and ASME Code Class 2 vessel welds. The scope of this letter is for the two ASME Code Class 2 vessel welds, CGE-2-1110-1 B/1 and CGE-2-1110-1 B/2, in the residual heat removal heat exchanger shell. 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 RAls 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:
Sincerely, IRA/ 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:
PUBLIC RidsNrrDorlDpr Resource RidsNrrLASFigueroa Resource DDijamco, NRR LPL2-1 R/F RidsNrrDorllpl2-1 Resource RidsNrrDRA Resource ADAMS A ccess1on N o.: ML 16042A471
- b *1 1yema1 OFFICE LPL2-1/PM LPL2-1/LA NRR/DE/EVIB/BC*
NAME SWilliams SFigueroa JMcHale* DATE 2/18/2016 2/17/2016 2/10/2016 OFFICIAL RECORD COPY RidsAcrs_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrPMSummer Resource LPL2-1/BC LPL2-1/PM MMarkley SWilliams 2/18/2016 2/18/2016