ML17272A019
ML17272A019 | |
Person / Time | |
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Site: | Watts Bar ![]() |
Issue date: | 09/29/2017 |
From: | Simmons P Tennessee Valley Authority |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML17272A019 (3) | |
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Category:Letter
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Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML14163A6582014-09-18018 September 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML14212A6032014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule IR 05000391/19860602014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule ML14149A1502014-06-16016 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14133A5422014-05-23023 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13246A0222013-08-28028 August 2013 Submittal of Pre-op Test Instruction ML13178A2812013-06-26026 June 2013 10 CFR 50.59 Summary Report Supplement ML13144A5762013-05-22022 May 2013 Watt Bar, Units 1 & 2, Report of Drug Testing Error in Accordance with 10 CFR 26.719(c)(1) ML13126A2942013-04-29029 April 2013 10 CFR 50.59 Summary Report ML13121A0602013-04-29029 April 2013 Commitment Summary Report ML13080A3632013-03-18018 March 2013 Enclosure 3, Summer 2011 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A3662013-03-18018 March 2013 Enclosure 1, Summer 2010 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A0732013-03-12012 March 2013 Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation.. ML13175A1352013-03-0505 March 2013 2-PTI-092-03, Revision 0, Nuclear Instrumentation Source Range Noise Checks During Hot Functional Testing. ML12356A3172012-12-17017 December 2012 Submittal of Pre-op Test Instruction, 2-PTI-063-06, Revision 0, Safety Injection System Check Valve Test. ML12335A3402012-11-27027 November 2012 Tennessee Valley Authority - Fleet Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Flooding Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of ML13108A2842012-11-12012 November 2012 Unit 1, Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML13175A1362012-11-0808 November 2012 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification. ML13175A1342012-11-0101 November 2012 2-PTI-082-02, Revision 0, Rod Control - Non Hft. ML13175A1332012-10-22022 October 2012 2-PTI-085-01, Revision 0, Rod Control Functional Test. ML12236A1642012-07-19019 July 2012 Enclosure 1 Evaluation of Proposed Changes Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 ML12223A1832012-03-29029 March 2012 Environmental Protection Agency 2012 - Facility Detail Report - Environmental Facts Warehouse Fii - Moccasin Bend Wwtp ML11362A0562011-12-20020 December 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 7 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 7 ML11341A1572011-11-30030 November 2011 Attachments 7 Through 9, WNA-CN-00157-WBT-NP, Revision 1, CAW-11-3316, and WBT-D-3566 Np, Incore Instrument System Signal Processing System Isolation Requirement ML11326A2842011-11-18018 November 2011 Commitment Summary Report ML11257A0502011-08-31031 August 2011 Attachment 7, WCAP-17427-NP, Rev. 1, Watts Bar Nuclear Plant Unit 2 Common Q Post Accident Monitoring System Computer Security Assessment, Attachment 8, Application for Withholding Proprietary Information from Public Disclosure and Attachme ML1104003852011-02-0707 February 2011 Enclosure 2, Appendix a, Hydrothermal Effects on the Ichthyhoplankton from the Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir ML1104003842011-02-0707 February 2011 Enclosure 1, Hydrothermal Effects on the Ichthyoplankton from Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir 2024-01-03 |
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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381 September 29,2017 10 cFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (PAMS) Report The program requirements for the Watts Bar Nuclear Plant (WBN) Post Accident Monitoring System (PAMS) requires a report to be submitted within 14 days when Condition B of Technical Specification (TS) Limiting Condition for Operation 3.3.3, "Post Accident Monitoring (PAM) lnstrumentation," is entered. On August 16,2017, containment high range radiation monitor 1-RM-90-272 was declared inoperable. On September 15, 2017, WBN entered TS 3.3.3 Condition B for this event when the inoperable condition had been present for 30 days, requiring a Special Report to the NRC. This special report is provided in the Enclosure.
There are no new regulatory commitments in this letter. Please direct any questions concerning this matter to Kim Hulvey, WBN Licensing Manager, at (423) 365-7720.
Respectfully, Paul Simmons Site Vice President Watts Bar Nuclear Plant Enclosure cc: See Page 2
U.S. Nuclear Regulatory Commission Page 2 September 29,2017 cc (Enclosure):
NRC Regional Administrator - Region Il NRC Senior Resident lnspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant
Enclosure Technical Specification 5.9.8 PAMS Report Backqround The Watts Bar Nuclear Plant (WBN) Technical Specification (TS) 3.3.3, "Post Accident Monitoring (PAM) lnstrumentation," specifies the operability requirements for PAM instrumentation. TS Table 3.3.3-1, Function l2, "Containment Radiation (High Range),"
requires two monitors for upper containment and two monitors for lower containment. On August 16,2017, 1-RM-90-272, one of the two upper containment area radiation monitors was declared inoperable when its green operable light would not remain lit.
TS 3.3.3 Limiting Condition for Operation (LCO) Condition A allows a single indication channel to be inoperable for 30 days. lf the indication channel is not restored within 30 days, LCO Condition B is entered, which requires action in accordance with TS 5.9.8 to be taken immediately. TS 5.9.8 requires a report to be submitted to the Nuclear Regulatory Commission within 14 days.
On-line efforts to repair this indication were unsuccessful prior to exceeding the 30 day period of inoperability specified by TS 3.3.3. Parts to correct this issue were obtained after the 30 day period expired.
This report outlines the preplanned alternate method of monitoring, the cause of inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
Preplanned Alternate Method of Monitorino A prompt determination of operability performed by site engineering determined the monitor will perform its safety function with the green operational light not in service provided that the integrated computer system (lCS) alarm setpoint for 1-RM-90-272is active (audible) for Operations response. ln addition, a second upper containment high range radiation monitor remains operable and capable of providing indication during an accident.
Gause of lnoperabilitv The issue is associated with a failed subcomponent within the ratemeter for 1-RM-90-272.
Actions and Schedule to Restore lnstrumentation Function to Ooerable Condition Repairs to 1-RM-90-272were performed and this containment radiation monitor was returned to a fully operable status on September 28, 2017.