ML18033A844: Difference between revisions

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=Text=
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 27, 2018 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 27, 2018 Mr. George A. Lippard, Ill Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P.O. Box 88, Mail Code 800 Jenkinsville, SC 29065  
& Gas Company Virgil C. Summer Nuclear Station P.O. Box 88, Mail Code 800 Jenkinsville, SC 29065  


==SUBJECT:==
==SUBJECT:==
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -CORRECTION TO AMENDMENT NO. 170 TO CORRECT A TYPOGRAPHICAL ERROR  
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -CORRECTION TO AMENDMENT NO. 170 TO CORRECT A TYPOGRAPHICAL ERROR  


==Dear Mr. Lippard:==
==Dear Mr. Lippard:==
 
By letter dated January 31, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 18031 A763), South Carolina Electric & Gas Company (SCE&G, the licensee) requested the U.S. Nuclear Regulatory Commission (NRC) approval of a correction of a typographical error in the Virgil C. Summer Nuclear Station (VCSNS), Unit No. 1, Technical Specifications (TS). The typographical error was inadvertently introduced during License Amendment No. 118 (ADAMS Accession No. ML012280053), and carried over into Amendment No. 170 (ADAMS Accession No. ML050130293).
By letter dated January 31, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 18031 A763), South Carolina Electric  
The typographical error was identified in TS Table 3.3-10, "Accident Monitoring Instrumentation," Item 7, "Reactor Coolant Inlet Temperature  
& Gas Company (SCE&G, the licensee) requested the U.S. Nuclear Regulatory Commission (NRC) approval of a correction of a typographical error in the Virgil C. Summer Nuclear Station (VCSNS),
-Tco1d -Wide Range Instrument Loop/Indicator." Specifically, the "ITE-430/ITR-41 O" entry was incorrectly labelled as "Channel E" rather than "Channel D" in the licensee's application dated December 17, 1993 (ADAMS Accession No. ML 18046A010) and was not in accordance with Regulatory Guide (RG) 1.97, Revision 3, "Instrumentation for light-water-cooled nuclear power plants to assess plant and environs conditions during and following an accident," dated May 1983 (ADAMS Accession No. ML003740282}.
Unit No. 1, Technical Specifications (TS). The typographical error was inadvertently introduced during License Amendment No. 118 (ADAMS Accession No. ML012280053),
and carried over into Amendment No. 170 (ADAMS Accession No. ML050130293).
The typographical error was identified in TS Table 3.3-10, "Accident Monitoring Instrumentation,"
Item 7, "Reactor Coolant Inlet Temperature  
-Tco1d -Wide Range Instrument Loop/Indicator."
Specifically, the "ITE-430/ITR-41 O" entry was incorrectly labelled as "Channel E" rather than "Channel D" in the licensee's application dated December 17, 1993 (ADAMS Accession No. ML 18046A010) and was not in accordance with Regulatory Guide (RG) 1.97, Revision 3, "Instrumentation for light-water-cooled nuclear power plants to assess plant and environs conditions during and following an accident,"
dated May 1983 (ADAMS Accession No. ML003740282}.
The NRC staff reviewed the information provided in the January 31, 2018, License Amendments No. 118 and No. 170, and RG 1.97 and conclude that TS Table 3.3-10, Item 7, was incorrectly labelled "Channel E ITE-430/ITR-41 O" and should be replaced with "Channel D ITE-430/ITR-41 O." Correction of the typographical error does not change the NRC conclusions provided in approval of Amendments No. 118 and No. 170 or the no significant hazards consideration as published in the Federal Register.
The NRC staff reviewed the information provided in the January 31, 2018, License Amendments No. 118 and No. 170, and RG 1.97 and conclude that TS Table 3.3-10, Item 7, was incorrectly labelled "Channel E ITE-430/ITR-41 O" and should be replaced with "Channel D ITE-430/ITR-41 O." Correction of the typographical error does not change the NRC conclusions provided in approval of Amendments No. 118 and No. 170 or the no significant hazards consideration as published in the Federal Register.
G. Lippard, Ill Enclosed is the corrected TS page for VCSNS Amendment No. 170. Please replace the affected page with the enclosed page. If you have any questions, please contact me at 301-415-1009.
G. Lippard, Ill Enclosed is the corrected TS page for VCSNS Amendment No. 170. Please replace the affected page with the enclosed page. If you have any questions, please contact me at 301-415-1009.
Line 40: Line 31:


As stated cc: Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 ATTACHMENT TO LICENSE AMENDMENT NO. 270 CORRECTION TO TYPOGRAPHICAL ERROR RENEWED FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following page of the Appendix "A" Technical Specifications (TSs) with the attached revised page. Remove TS TS 3/4 3-57 3/4 3-57 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION  
As stated cc: Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 ATTACHMENT TO LICENSE AMENDMENT NO. 270 CORRECTION TO TYPOGRAPHICAL ERROR RENEWED FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following page of the Appendix "A" Technical Specifications (TSs) with the attached revised page. Remove TS TS 3/4 3-57 3/4 3-57 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION  
(/) REQUIRED MINIMUM C NO.OF CHANNELS INSTRUMENT CHANNELS OPERABLE m ;;u 1. Reactor Building Pressure  
(/) REQUIRED MINIMUM C NO.OF CHANNELS INSTRUMENT CHANNELS OPERABLE m ;;u 1. Reactor Building Pressure -Narrow Range 2 1 C Instrument Loop/Indicator:
-Narrow Range 2 1 C Instrument Loop/Indicator:
z -; Channel D IPT-951/IPl-951  
z -; Channel D IPT-951/IPl-951  
...>. Channel B IPT-952/IPl-952  
...>. Channel B IPT-952/IPl-952  
: 2. Reactor Building Pressure  
: 2. Reactor Building Pressure -Wide Range 2 1 Instrument Loop/Indicator:
-Wide Range 2 1 Instrument Loop/Indicator:
Channel D IPT-954A/IPl-954A Channel E IPT-954B/IPl-954B  
Channel D IPT-954A/IPl-954A Channel E IPT-954B/IPl-954B  
: 3. Reactor Building Radiation Level -High Range 2 1 Instrument Loop/Indicator:
: 3. Reactor Building Radiation Level -High Range 2 1 Instrument Loop/Indicator:
Channel A RMG-18 (,) Channel B RMG-7 J;;: 4. Deleted <,.) I CJ1 -..J 5. Reactor Building/RHR Sump Level 2 1 Instrument Loop/Indicator:
Channel A RMG-18 (,) Channel B RMG-7 J;;: 4. Deleted <,.) I CJ1 -..J 5. Reactor Building/RHR Sump Level 2 1 Instrument Loop/Indicator:
Channel A ILT-1969/ILl-1969 Channel B ILT-1970/ILl-1970  
Channel A ILT-1969/ILl-1969 Channel B ILT-1970/ILl-1970  
: 6. Reactor Coolant Outlet Temperature  
: 6. Reactor Coolant Outlet Temperature -TH01-Wide Range 2 1 Instrument Loop/Indicator:  
-TH01-Wide Range 2 1 Instrument Loop/Indicator:  
)> Channel A ITE-413/ITl-413 3 Channel A ITE-423/ITl-423 (D ::I Channel E ITE-433/ITR-413  
)> Channel A ITE-413/ITl-413 3 Channel A ITE-423/ITl-423 (D ::I Channel E ITE-433/ITR-413  
: 0. 3 7. Reactor Coolant Inlet Temperature -T cold -Wide Range 2 1 (D ::I r-+ Instrument Loop/Indicator:
: 0. 3 7. Reactor Coolant Inlet Temperature -T cold -Wide Range 2 1 (D ::I r-+ Instrument Loop/Indicator:
Line 58: Line 46:


==SUBJECT:==
==SUBJECT:==
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -CORRECTION TO AMENDMENT NO. 170 TO CORRECT A TYPOGRAPHICAL ERROR DATED FEBRUARY 27, 2018 DISTRIBUTION:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -CORRECTION TO AMENDMENT NO. 170 TO CORRECT A TYPOGRAPHICAL ERROR DATED FEBRUARY 27, 2018 DISTRIBUTION:
PUBLIC RidsNrrPMSummer Resource RidsACRS_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrDorlLpl2-1 Resource RidsNrrLAKGoldstein Resource KWest, NRR ADAMS Accession No.: ML 18033A844 OFFICE DORL/LPL2-1  
PUBLIC RidsNrrPMSummer Resource RidsACRS_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrDorlLpl2-1 Resource RidsNrrLAKGoldstein Resource KWest, NRR ADAMS Accession No.: ML 18033A844 OFFICE DORL/LPL2-1  
/PM DORL/LPL2-1/LA DORL/LPL2-1/BC NAME SWilliams KGoldstein MMarkley DATE 02/12/2018 02/16/2018 02/26/2018 OFFICIAL RECORD COPY DORL/LPL2-1/PM SWilliams 02/27/2018}}
/PM DORL/LPL2-1/LA DORL/LPL2-1/BC NAME SWilliams KGoldstein MMarkley DATE 02/12/2018 02/16/2018 02/26/2018 OFFICIAL RECORD COPY DORL/LPL2-1/PM SWilliams 02/27/2018}}

Revision as of 02:59, 6 July 2018

Virgil C. Summer Nuclear Station, Unit 1 - Correction to Amendment No. 170 to Correct a Typographical Error
ML18033A844
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 02/27/2018
From: Williams S A
Plant Licensing Branch II
To: Lippard G A
South Carolina Electric & Gas Co
Williams S, NRR/DORL/LPLII-1
References
Download: ML18033A844 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 27, 2018 Mr. George A. Lippard, Ill Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P.O. Box 88, Mail Code 800 Jenkinsville, SC 29065

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -CORRECTION TO AMENDMENT NO. 170 TO CORRECT A TYPOGRAPHICAL ERROR

Dear Mr. Lippard:

By letter dated January 31, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 18031 A763), South Carolina Electric & Gas Company (SCE&G, the licensee) requested the U.S. Nuclear Regulatory Commission (NRC) approval of a correction of a typographical error in the Virgil C. Summer Nuclear Station (VCSNS), Unit No. 1, Technical Specifications (TS). The typographical error was inadvertently introduced during License Amendment No. 118 (ADAMS Accession No. ML012280053), and carried over into Amendment No. 170 (ADAMS Accession No. ML050130293).

The typographical error was identified in TS Table 3.3-10, "Accident Monitoring Instrumentation," Item 7, "Reactor Coolant Inlet Temperature

-Tco1d -Wide Range Instrument Loop/Indicator." Specifically, the "ITE-430/ITR-41 O" entry was incorrectly labelled as "Channel E" rather than "Channel D" in the licensee's application dated December 17, 1993 (ADAMS Accession No. ML 18046A010) and was not in accordance with Regulatory Guide (RG) 1.97, Revision 3, "Instrumentation for light-water-cooled nuclear power plants to assess plant and environs conditions during and following an accident," dated May 1983 (ADAMS Accession No. ML003740282}.

The NRC staff reviewed the information provided in the January 31, 2018, License Amendments No. 118 and No. 170, and RG 1.97 and conclude that TS Table 3.3-10, Item 7, was incorrectly labelled "Channel E ITE-430/ITR-41 O" and should be replaced with "Channel D ITE-430/ITR-41 O." Correction of the typographical error does not change the NRC conclusions provided in approval of Amendments No. 118 and No. 170 or the no significant hazards consideration as published in the Federal Register.

G. Lippard, Ill Enclosed is the corrected TS page for VCSNS Amendment No. 170. Please replace the affected page with the enclosed page. If you have any questions, please contact me at 301-415-1009.

Docket No. 50-395

Enclosure:

As stated cc: Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 ATTACHMENT TO LICENSE AMENDMENT NO. 270 CORRECTION TO TYPOGRAPHICAL ERROR RENEWED FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following page of the Appendix "A" Technical Specifications (TSs) with the attached revised page. Remove TS TS 3/4 3-57 3/4 3-57 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION

(/) REQUIRED MINIMUM C NO.OF CHANNELS INSTRUMENT CHANNELS OPERABLE m ;;u 1. Reactor Building Pressure -Narrow Range 2 1 C Instrument Loop/Indicator:

z -; Channel D IPT-951/IPl-951

...>. Channel B IPT-952/IPl-952

2. Reactor Building Pressure -Wide Range 2 1 Instrument Loop/Indicator:

Channel D IPT-954A/IPl-954A Channel E IPT-954B/IPl-954B

3. Reactor Building Radiation Level -High Range 2 1 Instrument Loop/Indicator:

Channel A RMG-18 (,) Channel B RMG-7 J;;: 4. Deleted <,.) I CJ1 -..J 5. Reactor Building/RHR Sump Level 2 1 Instrument Loop/Indicator:

Channel A ILT-1969/ILl-1969 Channel B ILT-1970/ILl-1970

6. Reactor Coolant Outlet Temperature -TH01-Wide Range 2 1 Instrument Loop/Indicator:

)> Channel A ITE-413/ITl-413 3 Channel A ITE-423/ITl-423 (D ::I Channel E ITE-433/ITR-413

0. 3 7. Reactor Coolant Inlet Temperature -T cold -Wide Range 2 1 (D ::I r-+ Instrument Loop/Indicator:

z Channel E ITE-410/ITl-410 j Channel E ITE-420/ITl-420 Channel D ITE-430/ITR-410

...>. -..J 0 G. Lippard, Ill

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 -CORRECTION TO AMENDMENT NO. 170 TO CORRECT A TYPOGRAPHICAL ERROR DATED FEBRUARY 27, 2018 DISTRIBUTION:

PUBLIC RidsNrrPMSummer Resource RidsACRS_MailCTR Resource RidsRgn2MailCenter Resource RidsNrrDorlLpl2-1 Resource RidsNrrLAKGoldstein Resource KWest, NRR ADAMS Accession No.: ML 18033A844 OFFICE DORL/LPL2-1

/PM DORL/LPL2-1/LA DORL/LPL2-1/BC NAME SWilliams KGoldstein MMarkley DATE 02/12/2018 02/16/2018 02/26/2018 OFFICIAL RECORD COPY DORL/LPL2-1/PM SWilliams 02/27/2018

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