CNL-17-093, Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS)
Letter Sequence Response to RAI | |
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CAC:MF8526, Steam Generator Tube Integrity, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Approved, Closed) CAC:MF8527, Steam Generator Tube Integrity, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Approved, Closed) | |
Initiation Administration | |
MONTHYEARULNRC-06174, Licensing Document Change Notice (LDCN)14-0014 Application to Revise TS to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2015-03-0909 March 2015
[Table View]Licensing Document Change Notice (LDCN)14-0014 Application to Revise TS to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process Project stage: Request ULNRC-06200, Supplement to Licensing Document Change Notice (LDCN)12-0014 Application to Revise Technical Specification to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated..2015-04-0808 April 2015 Supplement to Licensing Document Change Notice (LDCN)12-0014 Application to Revise Technical Specification to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated.. Project stage: Supplement ULNRC-06236, Additional Supplement to Licensing Document Change Notice 14-0014 TSTF-5102015-08-12012 August 2015 Additional Supplement to Licensing Document Change Notice 14-0014 TSTF-510 Project stage: Supplement ULNRC-06270, Final Supplement to Document Change Notice (LDCN) 14-0014 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using The..2015-12-10010 December 2015 Final Supplement to Document Change Notice (LDCN) 14-0014 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using The.. Project stage: Supplement ML15324A1142016-02-0202 February 2016 Issuance of Amendment No. 215, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Project stage: Approval CNL-16-141, Application to Modify Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System.2016-10-20020 October 2016 Application to Modify Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System. Project stage: Request ML16340A0402016-11-30030 November 2016 Acceptance for Review - Request to Modify TS 3.7.12 Auxiliary Building Gas Treatment System Project stage: Acceptance Review ML17076A0232017-03-16016 March 2017 NRR E-mail Capture - Watts Bar, Units 1 and 2 - Final Request for Additional Information Concerning Request to Amend ABGTS TS Project stage: RAI CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 22017-05-0505 May 2017 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2 Project stage: Response to RAI CNL-17-093, Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS)2017-07-21021 July 2017 Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS) Project stage: Response to RAI ML17236A0572017-10-17017 October 2017 Issuance of Amendments Regarding Auxiliary Building Gas Treatment System Project stage: Approval 2016-11-30 |
ML17205A322 | |
Person / Time | |
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Site: | Watts Bar |
Issue date: | 07/21/2017 |
From: | James Shea Tennessee Valley Authority |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
CAC MF8526, CAC MF8527, CNL-17-093 | |
Download: ML17205A322 (3) | |
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CNL-19-065, Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2019-07-15015 July 2019 Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors CNL-19-056, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602019-06-0707 June 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 CNL-19-033, Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2019-03-21021 March 2019 Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) CNL-18-121, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2018-11-0909 November 2018 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) CNL-18-128, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30)2018-11-0808 November 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30) CNL-18-116, Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)2018-10-11011 October 2018 Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) .2018-10-0404 October 2018 Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) ... CNL-18-104, Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals2018-07-30030 July 2018 Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals CNL-18-102, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ...2018-07-24024 July 2018 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ... 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NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-018, Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028)2018-02-15015 February 2018 Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) CNL-18-012, Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)2018-01-17017 January 2018 Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01) CNL-17-108, Response to Request for Additional Information Regarding Request to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation2017-08-31031 August 2017 Response to Request for Additional Information Regarding Request to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-093, Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS)2017-07-21021 July 2017 Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS) CNL-17-091, Response to Request for Additional Information Regarding Request for Approval of a Relief from the ASME Section XI Coverage Examinations for Preservice Inspection (PSI) - Number WBN-2/PSI-1, Revision 1, and Submittal of the Wbn..2017-07-14014 July 2017 Response to Request for Additional Information Regarding Request for Approval of a Relief from the ASME Section XI Coverage Examinations for Preservice Inspection (PSI) - Number WBN-2/PSI-1, Revision 1, and Submittal of the Wbn.. CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-071, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-06-30030 June 2017 Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNL-17-066, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17)2017-06-0909 June 2017 Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17) CNL-17-062, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications Regarding Ice Condenser Containment Ice Mass Requirements2017-05-19019 May 2017 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications Regarding Ice Condenser Containment Ice Mass Requirements 2024-08-19 |
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-17-093 July 21, 2017 10 CFR 50.90 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 Watts Bar Nuclear Plant, Unit 2 Facility Operating License No. NPF-96 NRC Docket No. 50-391
Subject:
Revised Response to Request for Additional Information Related to License Amendment Request To Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS), for Watts Bar Nuclear Plant, Units 1 and 2 (CAC Nos. MF8526 and MF8527)
Reference:
- 1. TVA Letter to NRC, CNL-16-141, Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (WBN-TS-16-19), dated October 20, 2016 (ML16294A551)
- 2. NRC Electronic Mail to TVA, Watts Bar, Units 1 and 2 - Final Request for Additional Information Concerning Request to Amend ABGTS TS (CAC Nos. MF8526 and MF8527), dated March 16, 2017
- 3. TVA Letter to NRC, CNL-17-044, Response to Request for Additional Information Related to License Amendment Request To Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS),
for Watts Bar Nuclear Plant, Units 1 and 2 (CAC Nos. MF8526 and MF8527), dated May 5, 2017 (ML17125A244)
In Reference 1, Tennessee Valley Authority (TVA) submitted a request for an amendment to the Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications (TS) to revise TS 3.7.12, Auxiliary Building Gas Treatment System (ABGTS), to provide an action when both trains of the ABGTS are inoperable due to the auxiliary building secondary containment
U.S. Nuclear Regulatory Commission CNL-17-093 Page 2 July 21, 2017 enclosure (ABSCE) boundary being inoperable. The proposed license amendment request (LAR) also adds a Note to the TS Limiting Condition for Operation (LCO) that allows the ABSCE boundary to be opened intermittently under administrative controls, consistent with NUREG-1431, Standard Technical Specifications - Westinghouse Plants. In Reference 2, the Nuclear Regulatory Commission (NRC) transmitted a request for additional information (RAI). In Reference 3, TVA submitted a response to the RAI.
In Reference 3, page E1-8, item 2, in response to NRC SPBP-RAI 1, TVA stated The steam generator replacement activity for WBN Unit 2 (as noted in the referenced letter this activity is tentatively scheduled during RFO 4 in 2022, but could occur as early as 2019 during RFO 2) will require a single breach manned for approximately one to two months. However, the breach (e.g., a roll-up door) will only be opened when needed to move equipment or personnel into the area.
TVA would like to clarify the above RAI response regarding the planned breach entries of the ABSCE boundary for the steam generator replacement project (SGRP) for WBN Unit 2.
The SGRP currently plans to have three breaches greater than the total allowable breach area for the ABSCE (i.e., upper and lower containment access through the air locks and the fabric door leading through penetration X-1). Administrative controls for these breaches will be established in accordance with TVA procedure TI-65, Breaching the Containment Annulus, ABSCE, or MCRHZ Pressure Boundaries (see item 1 on pages E1-4 and E1-5 of Reference 3), including having individuals stationed at these breaches in contact with the main control room (MCR). Furthermore, in accordance with TI-65, the breach opening closures would be accomplished within two minutes following notification from the MCR to ensure that the ABSCE boundary could be drawn down to the design parameters within four minutes.
As noted in References 1 and 3, the proposed LAR was intended to support normal operation, short duration events (e.g., door openings, fire damper testing and inspections, and damper strokes). However, for the SGRP activity and on a one-time basis, the breaches are planned to remain in the open position. TVA acknowledges that allowing the breach openings of the ABSCE on a continuous basis during the SGRP does not meet the intent of the proposed Note to TS 3.7.12 in Reference 3 that states The Auxiliary Building Secondary Containment Enclosure (ABSCE) boundary may be opened intermittently under administrative control that ensure the ABSCE can be closed consistent with the safety analysis.
Therefore, TVA plans to submit a separate LAR to support the SGRP to modify the proposed Note to TS 3.7.12 to allow a one-time exception for the ABSCE breaches to be opened continuously that are needed to support the SGRP, as described in the above paragraph. The LAR will include additional information about the breaches planned for the SGRP.
TVA requests that NRC continue with the approval of the LAR, as proposed in References 1 and 3, on schedule in order to support the upcoming WBN Unit 2 refueling outage in October 2017.
U.S. Nuclear Regulatory Commission CNL-17-093 Page 3 July 21, 2017 This revised RAI response does not change the no significant hazards considerations determination contained in Reference 1. There are no new regulatory commitments associated with this submittal. Please address any questions regarding th is response to Ed Schrull at 423-751-3850.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 21st day of July 2017.
Respectfully,
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J. W. Shea Vice President, Nuclear Regulatory Affairs and Support Services cc:
NRC Regional Administrator - Reg ion II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant