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Category:Letter type:L
MONTHYEARL-20-006, Unit 2, Emergency Plan Implementing Procedure Revision2020-02-10010 February 2020
Unit 2, Emergency Plan Implementing Procedure Revision
L-12-001, Revised Response to NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2019-12-26026 December 2019
Revised Response to NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System
L-19-061, Unit 2 - Emergency Plan Implementing Procedure Revision2019-12-16016 December 2019
Unit 2 - Emergency Plan Implementing Procedure Revision
L-19-058, Statement of Payment of Civil Penalty2019-12-11011 December 2019
Statement of Payment of Civil Penalty
L-19-054, Unit 2 - Emergency Plan Implementing Procedure Revision2019-12-0505 December 2019
Unit 2 - Emergency Plan Implementing Procedure Revision
L-19-046, Notification of Readiness for NRC Independent Review to Confirm Chilling Effect Letter and Cross-Cutting Issue Closure Criteria Have Been Met2019-10-0303 October 2019
Notification of Readiness for NRC Independent Review to Confirm Chilling Effect Letter and Cross-Cutting Issue Closure Criteria Have Been Met
L-19-052, Revision 47 to Emergency Plan Implementing Procedure EPIP 12, Emergency Equipment and Supplies2019-09-30030 September 2019
Revision 47 to Emergency Plan Implementing Procedure EPIP 12, Emergency Equipment and Supplies
L-19-048, Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-0422019-09-12012 September 2019
Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-042
L-19-041, Cycle 2 Steam Generator Tube Inspection Report2019-08-27027 August 2019
Cycle 2 Steam Generator Tube Inspection Report
L-19-045, American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 2 Operation2019-08-14014 August 2019
American Society of Mechanical Engineers, Section XI, First 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 2 Operation
L-19-044, Unit 2 - Forward Emergency Plan Implementing Procedure Revisions2019-08-0808 August 2019
Unit 2 - Forward Emergency Plan Implementing Procedure Revisions
L-19-036, Notification of Readiness for NRC Inspection Procedure 95001 Inspection2019-06-20020 June 2019
Notification of Readiness for NRC Inspection Procedure 95001 Inspection
L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019
Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report
L-19-031, Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2019-02 - Preparation and Scheduling of Operator Licensing Examinations2019-05-15015 May 2019
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L-19-016, Annual Radiological Environmental Operating Report - 20182019-05-15015 May 2019
Annual Radiological Environmental Operating Report - 2018
L-19-029, Submittal of Revision 0 of Cycle 3 Core Operating Limits Report2019-04-24024 April 2019
Submittal of Revision 0 of Cycle 3 Core Operating Limits Report
L-19-015, Annual Non-Radiological Environmental Operating Report - 20182019-04-11011 April 2019
Annual Non-Radiological Environmental Operating Report - 2018
L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019
Revised Pressure and Temperature Limits Report (PTLR)
L-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual2019-03-19019 March 2019
Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
L-19-024, Unit 2 - Emergency Plan Implementing Procedures Revision2019-03-0707 March 2019
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L-19-019, Transmittal of 10 CFR 50.46 - 30-Day and Annual Report for Watts Bar Nuclear Plant, Units 1 and 22019-03-0707 March 2019
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L-19-011, Plant, Unit 1 - Revision 1 of the Cycle 16 Core Operating Limits Report (COLR)2019-01-29029 January 2019
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L-19-008, American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 15 Operation2019-01-24024 January 2019
American Society of Mechanical Engineers, Section Xl, Third 10-Year Inspection Interval, Inservice Inspection Owner'S Activity Report for Cycle 15 Operation
L-18-001, Notification of Readiness for NRC Inspection Procedure 95001 Inspection2018-11-26026 November 2018
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L-04-001, Completion of Action Required in Response to NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors2018-01-25025 January 2018
Completion of Action Required in Response to NRC Bulletin 2004-01: Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors
L-11-001, Submittal of 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2015-09-24024 September 2015
Submittal of 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.
L-11-011, Transmittal of Response to NRC Bulletin 2011-01, Mitigating Strategies.2015-06-29029 June 2015
Transmittal of Response to NRC Bulletin 2011-01, Mitigating Strategies.
L-88-017, Response Clarification to Generic Letter 88-0172013-08-13013 August 2013
Response Clarification to Generic Letter 88-017
L-03-004, Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 20032003-12-18018 December 2003
Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 2003
2020-02-10
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Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 August 13, 2013 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License No. NPF-90 Construction Permit No. CPPR-92 NRC Docket Nos. 50-390 and 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) UNITS I AND 2 - GENERIC LETTER (GL) 88 RESPONSE CLARIFICATION
References:
- 1. TVA letter to NRC dated February 9, 1998, "Watts Bar Nuclear Plant (WBN)
Unit 1 - 10 CFR 50.59(b)(2), Changes, Tests and Experiments Summary Report"
- 2. NRC letter to TVA dated March 8, 1995, "Watts Bar Unit 1 - Revised Response to Generic Letter 88-17 Regarding Loss of Decay Heat Removal (TAC M69792)"
- 3. TVA letter to NRC dated February 7, 1995, "Watts Bar Nuclear Plant (WBN)
Unit 1 and 2 - Generic Letter 88-17, Loss of Decay Heat Removal - Revised Response to Item 4 (TAC No. M69792)"
This letter revises one of the two methods TVA will use to provide reactor coolant system (RCS) narrow range water level indications during reduced inventory conditions.
In the revised response to GL 88-17 (Reference 3), TVA stated the following:
"NarrowRange Level Indication - Two independent,RCS waterlevel indications will be used whenever the RCS is in a reduced inventory condition. An ultrasonic level measurement system (ULMS) and a differential pressure type level instrument loop will be utilized. Both instruments will have a range of indicationthat encompasses the inside diameter of the hot leg pipe. Indication with visible and audible alarms will be provided in the main control room for the differential pressure type level instrument loop. The ULMS
U.S. Nuclear Regulatory Commission Page 2 August 13, 2013 will have indication with visible and audible alarm capability in the Main Control Room on the emergency response facility data system computer."
NRC accepted this approach in Reference 2.
However, in 1997, Unit 1, under 10 CFR 50.59 (Summary Report provided by Reference 1), switched from the ULMS to a portable reactor vessel level monitoring system (Mansell Level Monitoring System [MLMS]). The MLMS utilizes redundant pressure transducers mounted at a reference location (pressurizer vent and reactor head vent) and at a liquid head location (loop #1 crossover leg drain line). The pressure information from these points is transmitted to the Control Room, processed by a computer dedicated to the MLMS, and displayed to the Control Room operators in FEET and INCHES to a resolution of 0.1 inches of water. The display system also provides an operator interface where the required information can be entered to set the proper zero range, level alarm setpoints, temperature, and boron concentration. This system has been proven to be a more accurate and reliable system than the ultrasonic system.
For WBN Unit 2, instead of completing the originally planned ULMS, TVA will utilize the same type of MLMS as Unit 1. The MLMS is installed in the Control Room prior to going into reduced inventory operations. Installation, use, and removal of the MLMS is performed in accordance with General Operating Procedure GO-10, "Reactor Coolant System Drain and Fill Operations." The MLMS provides narrow range level indication and alarms in the Control Room. The alarm setpoints for the MLMS are set in accordance with GO-10 and are dependent on the plant evolution in progress. This change is reflected in Amendment 110 of the Unit 2 Final Safety Analysis Report (FSAR) being submitted by separate correspondence.
The enclosure provides the commitment made in this letter.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1 3 th day of August, 2013.
If you have any questions, please contact me at (423) 365-1260 or Gordon Arent at (423) 365-2004.
Respectfully, Raymond A. Hruby, Jr.
General Manager, Technical Services Watts Bar Unit 2
U.S. Nuclear Regulatory Commission Page 3 August 13, 2013
Enclosure:
- 1. List of Commitments cc (Enclosure):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 1 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
WATTS BAR NUCLEAR PLANT (WBN) UNITS I AND 2 GENERIC LETTER (GL) 88 RESPONSE CLARIFICATION LIST OF COMMITMENTS
- 1. Each WBN unit will update their respective Safety Analysis Report (i.e., UFSAR for Unit 1 and FSAR for Unit 2) to reflect this different means of providing two different monitoring systems.
