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| 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 | | 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 |
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| 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 | | 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}} |
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Revision as of 00:32, 18 May 2018
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Category:Letter
MONTHYEARML24278A2832024-11-0707 November 2024 Letter to E. Carr Environmental Impact Statement Scoping Summary Report for Virgil C. Summer Nuclear Station Unit 1 IR 05000395/20240032024-11-0606 November 2024 – Integrated Inspection Report 05000395/2024003 ML24305A1302024-10-31031 October 2024 Submittal of 30 Day Report Per 10 CFR 26.719(c) Blind Performance Testing ML24308A0052024-10-28028 October 2024 10-28-24 NRC V.C. Summer Nuclear Station SLR Cherokee Nation Letter to USNRC ML24308A0062024-10-25025 October 2024 Subsequent License Renewal Application Area of Potential Effect (Ape) Clarification Fairfield County, South Carolina SHPO Project No. 22-EJ0147 ML24302A1442024-10-24024 October 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 4 and Requested Information Formation in Response to Limited Aging Management Audit ML24256A2322024-10-22022 October 2024 Relief Request RR-5-P1 Charging/Safety Injection Pumps ML24255A3152024-10-22022 October 2024 Relief Request RR-5-V2 Regarding Pressure Isolation Valves ML24250A0782024-10-22022 October 2024 Relief Request RR-5-V1 Regarding Service Water Return Header Check Valves 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System2024-10-15015 October 2024 Loss of Control Room Emergency Filtration System ML24290A1052024-10-0707 October 2024 Core Operating Limits Report VCSNS Unit 1 Cycle 29, Revision 0 IR 05000395/20244042024-09-26026 September 2024 Cyber Security Inspection Report 05000395-2024404 - Public ML24274A1942024-09-26026 September 2024 (Vcsns), Unit 1 Subsequent License Renewal Application (SLRA) First 10 CFR 54.21(b) Annual Amendment ML24221A2112024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0552024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0642024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0592024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0542024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) IR 05000395/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000395/2024402 IR 05000395/20240052024-08-22022 August 2024 Updated Inspection Plan for Virgil C. Summer Nuclear Station - Report 05000395/2024005 ML24190A4012024-08-19019 August 2024 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Dominion Energy Letter Dated May 30, 2024 IR 05000395/20240022024-08-12012 August 2024 Integrated Inspection Report 05000395/2024002 ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24162A3292024-07-0505 July 2024 Letter to E Carr - V.C. Summer Unit 1 - Summary of the May 2024 Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension ML24185A1902024-06-25025 June 2024 Submittal of Updated Final Safety Analysis Report, Revision 24 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24143A1792024-05-22022 May 2024 Special Report 2024-001-01 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Waste Gas System Inoperability ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes IR 05000395/20240012024-05-10010 May 2024 Integrated Inspection Report 05000395/2024001 ML24129A2002024-05-0606 May 2024 Update to Subsequent License Renewal Application, Supplement 2 IR 05000395/20240402024-05-0101 May 2024 95001 Supplemental Inspection Report 05000395/2024040 and Follow-Up Assessment Letter ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24116A2052024-04-23023 April 2024 Annual Radioactive Effluent Release Report ML24109A1792024-04-19019 April 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24108A0392024-04-18018 April 2024 Letter to E Carr-V.C. Summer Unit 1- Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24108A0672024-04-17017 April 2024 Submittal of Summary for Condition of the Service Water Intake Structure Provided in Accordance with License Condition 2.C.5.d 05000395/LER-2024-001, (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator2024-04-17017 April 2024 (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator ML24100A7312024-04-0909 April 2024 Personnel Exposure and Monitoring Annual Report ML24095A2072024-04-0101 April 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. 2024-09-26
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML23137A1782023-05-22022 May 2023 – Correction to Issuance of Amendment to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML23012A0152023-02-21021 February 2023 Issuance of Amendment No. 224 to Change Nozzle Blockage Testing Requirement for Reactor Building Spray System ML22341A1972022-12-15015 December 2022 Extension of Steam Generator Primary Inlet Nozzle Dissimilar Metal Weld Inspection Interval ML22244A1722022-09-22022 September 2022 Issuance of Amendment No. 223 to Relocate Main Steam Isolation Valve Isolation Times to the Updated Final Safety Analysis Report ML22242A1632022-08-31031 August 2022 Correction to Issuance of Amendment to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML22160A3652022-08-16016 August 2022 Issuance of Amendment No. 222 to Relocate Selected Surveillance Frequencies to a Risk-Informed Licensee Controlled Program ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21319A2622021-12-28028 December 2021 Issuance of Amendment No. 220 to Relocate Unit Staff Qualifications from Technical Specification to Quality Assurance Program Description ML21112A1082021-06-30030 June 2021 Issuance of Amendment No. 219 to Modify Technical Specification 6.9.1.11, Core Operating Limits Report ML19276D3772019-12-11011 December 2019 Issuance of Amendment Revise Company Name to Dominion Energy South Carolina, Inc. ML19080A1032019-04-30030 April 2019 Issuance of Amendment No. 215 Technical Specification 3.8.2, D.C. Sources - Operating ML19074A2222019-04-10010 April 2019 Issuance of Amendment No. 214 Removes the Expired One-Time Extension to Surveillance Requirement 4.3.3.6 and Removes the Index from Technical Specifications ML19023A4202019-03-0707 March 2019 Issuance of Amendment Reactor Coolant System Operational Leakage Technical Specification Surveillance Requirement 4.4.6.2.2 ML19056A4062018-11-30030 November 2018 Virgil C. Summer Nuclear Station NPDES Permit No. SC0030856 Renewal Application, Thermal Mixing Zone Evaluation 2018 Water Quality Monitoring Report ML18253A1152018-10-0505 October 2018 Issuance of Amendment No. 212 Technical Specification Change Request for the Revision of the Surveillance Frequency of the Turbine Trip Functional Unit ML18260A0272018-09-25025 September 2018 Issuance of Exigent Amendment One Time Extension to the Surveillance Frequency 4.3.3.6 of the Core Exit Temperature Instrumentation ML18141A6682018-06-28028 June 2018 Issuance of Amendment No. 210, Revise Technical Specification 6.8.4.g for Integrated Leak Rate Test Peak Calculated Containment Internal Pressure Change ML18157A2122018-06-0707 June 2018 Correction to Amendment No. 199 to Correct an Administrative Error ML18108A1632018-04-20020 April 2018 Correction to Amendments Nos. 79 and 202, to Correct Typographical Errors ML18033A8442018-02-27027 February 2018 Correction to Amendment No. 170 to Correct a Typographical Error ML17206A4122017-10-0404 October 2017 Issuance of Amendment TSTF-411, Revision 1, Surveillance Test Interval Extensions for Components of the Reactor Protection System (WCAP-15376-P-A). ML17011A0502017-03-0909 March 2017 Issuance of Amendment to Revise Completion Date of Implementation Milestone 8 of the Cyber Security Plan ML16348A2002017-01-18018 January 2017 Issuance of Amendment to Revise Technical Specification 3.5.4 Limiting Condition for Operation Refueling Water Storage Tank ML16264A4112016-10-26026 October 2016 Issuance of Amendment to Revise Technical Specification 3/4.7.1.2, Emergency Feedwater System ML15231A6052016-05-16016 May 2016 Issuance of Amendment to Change Licensing Basis to Incorporate a Supplemental Analysis to the Steam Generator Tube Rupture Accident ML16104A2952016-05-0606 May 2016 Issuance of Amendment to Adopt TSTF-523, Revision 2 RC-16-0043, License Amendment Request Technical Specification 3/4.7.1.2, Emergency Feedwater System.2016-04-0707 April 2016 License Amendment Request Technical Specification 3/4.7.1.2, Emergency Feedwater System. ML16063A0902016-03-0909 March 2016 Issuance of Exigent Amendment Regarding Technical Specification 3.7.1.2 RC-16-0035, (VCSNS) Unit 1 - Exigent License Amendment Request - LAR (16-00848) Technical Specification Change Request for the Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B2016-03-0101 March 2016 (VCSNS) Unit 1 - Exigent License Amendment Request - LAR (16-00848) Technical Specification Change Request for the Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B ML15208A0292015-10-15015 October 2015 Issuance of Amendment ML15170A0872015-08-18018 August 2015 Issuance of Amendment to Revise the Radiation Emergency Plan ML15063A3552015-04-13013 April 2015 Issuance of Amendment to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6 ML14287A2892015-02-11011 February 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14122A3092014-05-29029 May 2014 Issuance of Amendment 198 Regarding the Cyber Security Plan Implementation Schedule Milestone 8 ML14030A3742014-03-11011 March 2014 Issuance of Amendment for Technical Specification Change Related to Control Room Emergency Filtration System ML14010A1822014-02-28028 February 2014 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-510 ML13354B6432014-02-0606 February 2014 Issuance of Amendment for the Technical Specification Change Related to Snubber Surveillance Requirements ML13326A2042014-02-0505 February 2014 Issuance of Amendment Extending Integrated Leak Rate Test Interval ML12292A0562012-12-21021 December 2012 Issuance of Amendment Regarding Deviation of Scope of the Cyber Security Plan Implementation and Facility Operating Condition 2.E ML12270A3012012-10-12012 October 2012 Issuance of Amendment ML12184A1352012-07-0909 July 2012 Issuance of Amendment ML12146A0172012-05-30030 May 2012 Issuance of Amendment on Beacon Core Monitoring and Operations Support System ML12121A0342012-05-0101 May 2012 Issuance of Amendment Extending Integrated Leak Rate Test ML11346A0062012-03-20020 March 2012 Issuance of Amendment Regarding Quality Assurance Program ML12047A1922012-03-0606 March 2012 Issuance of Amendment No. 187 Regarding Surveillance Frequency of Solids State Protection Westinghouse Type AR Relays 18 Months ML11326A2502012-02-22022 February 2012 Issuance of Amendment Regarding Reactor Coolant System Leakage Detection Systems ML11201A3122011-08-24024 August 2011 Issuance of Amendment 184 Regarding Cyber Security Plan 2024-08-05
[Table view] |
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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
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