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| | number = ML11118A154 | | | number = ML11118A154 |
| | issue date = 05/06/2011 | | | issue date = 05/06/2011 |
| | title = Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Request for Additional Information Regarding Completion Time Extension for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D (TAC No. ME5036, ME5037, and | | | title = Request for Additional Information Regarding Completion Time Extension for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D (TAC No. ME5036, ME5037, and ME5038) |
| | author name = Gratton C | | | author name = Gratton C |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
Letter Sequence RAI |
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MONTHYEARML1032103342010-11-12012 November 2010 Revised Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, & 3D Project stage: Request ML1101100102010-12-17017 December 2010 Email - Acceptance of Requested Licensing Action Request to Extend Completion Time for TS 3.8.1 Required Action B.4.(TAC No(S). ME5036-8) Project stage: Acceptance Review ML1101403192011-01-19019 January 2011 Request for Additional Information Regarding Amendment Request to Extend Completion Time for Technical Specification 3.8.1 Required Action B.4 Project stage: RAI ML1104502562011-02-0808 February 2011 Response to NRC Request for Additional Information Regarding Extending Completion Times for Technical Specification 3.8.1 Project stage: Response to RAI ML11118A1542011-05-0606 May 2011 Request for Additional Information Regarding Completion Time Extension for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D (TAC No. ME5036, ME5037, and ME5038) Project stage: RAI ML11171A2092011-06-15015 June 2011 Revision to Response to NRC Request for Additional Information Regarding Extending Completion Times for Technical Specification 3.8.1, TS-468 Project stage: Response to RAI ML11234A1772011-08-19019 August 2011 Supplemental Information Regarding Extending Completion Times for Technical Specification 3.8.1 Dated January 19, 2011 Project stage: Supplement ML11227A2582011-10-0505 October 2011 Issuance of Amendments to Revise the Technical Specifications to Extend the Emergency Diesel Generator Allowed Outage Time (TAC ME5036, ME5037, and ME5038) (TS-468) Project stage: Approval 2011-10-05
[Table View] |
Request for Additional Information Regarding Completion Time Extension for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D (TAC No. ME5036, ME5037, and ME5038)ML11118A154 |
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Site: |
Browns Ferry |
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Issue date: |
05/06/2011 |
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From: |
Gratton C Plant Licensing Branch II |
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To: |
Krich R M Tennessee Valley Authority |
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Gratton C |
References |
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TAC ME5036, TAC ME5037, TAC ME5038 |
Download: ML11118A154 (6) |
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Category:Letter
MONTHYEARCNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24190A1292024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints ML24185A1512024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24176A1022024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A2462024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision ML24115A1652024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24108A1832024-04-17017 April 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML24106A2632024-04-16016 April 2024 Ltr to State Recognized Tribes-Hamilton, Cher-O-Creek Intra Tribal Indians ML24106A2572024-04-16016 April 2024 Ltr to Federally Recognized Tribes-Yahola, Kialegee Tribal Town 2024-09-03
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24255A5822024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 ML24255A5802024-09-10010 September 2024 SLRA - Requests for Additional Information - Set 1 - Email from Jessica Hammock to James Barstow ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A0272024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23332A0042023-11-27027 November 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47 ML23243A9892023-08-29029 August 2023 Inspection Information Request ML23124A0082023-05-0303 May 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML23041A0022023-02-0909 February 2023 NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025) ML22299A0292022-10-26026 October 2022 NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage ML22292A2722022-10-19019 October 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) ML22174A2722022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML21343A4232021-12-0909 December 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI) ML21173A1042021-06-21021 June 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to TS 3.8.6 ML21041A5422021-02-10010 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt 10 CFR 50.69 ML21041A5432021-02-0505 February 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Draft Request for Additional Information Regarding 10 CFR 50.69 LAR ML21026A1652021-01-26026 January 2021 Document Request for Browns Ferry Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-02 ML20297A3012020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt TSTF-425 ML20296A3782020-10-22022 October 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Incorporate TMRE ML20294A3762020-09-23023 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Adopt TSTF-425 ML20266G4472020-09-22022 September 2020 Notification of Inspection and Request for Information ML20224A4732020-08-11011 August 2020 Requalification Program Inspection Browns Ferry Nuclear ML20195B1302020-07-13013 July 2020 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Alternative Request No. 0-ISI-47 ML20149K3212020-05-27027 May 2020 RP Inspection Document Request, Browns Ferry 2020-003 ML20254A3032020-05-13013 May 2020 Request for Supporting Information for the Browns Ferry, Units 1, 2, and 3 Seismic Probabilistic Risk Assessment Audit Review ML20054B8592020-02-20020 February 2020 Emergency Preparedness Program Inspection Request for Information ML20014E6552020-01-14014 January 2020 01 RP Inspection Document Request ML19196A0752019-07-12012 July 2019 NRR E-mail Capture - Final RAIs Browns Ferry Nuclear, Units 1, 2, 3 - Application to Revise Technical Specifications to Adopt TSTF-542 Revision 2, Reactor Pressure Vessel Water Inventory Control ML19116A0712019-06-0303 June 2019 Request for Additional Information Related Resubmittal of Proposed Alternative Request No. 1-ISI-27 for the Period of Extended Operation ML18331A5442018-12-0606 December 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - (Non-Proprietary) ML18317A1642018-11-20020 November 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - Non-Proprietary ML18263A1412018-09-11011 September 2018 NRR E-mail Capture - Browns Ferry Unit 1: RAI Associated with Relief Request 1-ISI-28 ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18108A1872018-04-18018 April 2018 Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000259/2018411, 05000260/2018411, and 05000296/2018411 ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17216A0062017-08-18018 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to LAR to Revise Modifications and Implementations Related to NFPA 805 for Fire Protection for Light Water Reactor Generating Plants (CAC Nos. MF9814-MF9816) ML17163A0502017-06-0808 June 2017 NRR E-mail Capture - RAI for Browns Ferry RR 3-ISI-28 CAC No. MF9257 ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML16288A0182016-10-27027 October 2016 Browns Ferry Nuclear Plant, Units 2 and 3 - RAI Related to Relief Request for the Use of Alternatives to Certain American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI Requirements (CAC Nos. MF7795 and MF7796) ML16236A0732016-08-31031 August 2016 Request for Additional Information Related to License Amendment Request to Add New Technical Specification 3.3.8.3 ML16203A0272016-07-25025 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (CAC Nos. MF6738, MF6739, and MF6740) ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16187A2932016-07-21021 July 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743) ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate 2024-09-10
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 6,2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 BROWNS FERRY NUCLEAR PLANT, UNIT 1, 2, AND 3 -REQUEST FOR ADDITIONAL INFORMATION REGARDING COMPLETION TIME EXTENSION FOR TS 3.8.1 REQUIRED ACTION B.4 -EMERGENCY DIESEL GENERATORS A, B, C, D, 3A, 3B, 3C, AND 3D (TAC NOS. ME5036, ME5037, AND ME5038)
Dear Mr. Krich:
By letter dated November 12, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 103210334), as supplemented on February 8,2011 (ADAMS Accession No. ML 110450256), Tennessee Valley Authority (the licensee) submitted a request for a Technical Specification change to extend the completion time for one diesel generator inoperable from 7 to 14 days. Based on our review of your submittal and supplement, the U. S. Nuclear Regulatory Commission (NRC) staff finds that a response to the enclosed request for additional information is needed before we can complete the review. A draft of the enclosed questions was sent to the licensee on March 31,2011. This request was discussed with Mr. Tom Mathews of your staff on April 27, 2011, and it was agreed that a response would be provided within 30 days from this date. During the call, the NRC staff identified an additional question regarding the manning of the temporary emergency diesels was not part of the March 31, 2011, draft. Question 2 has been modified to include a request for this additional information.
Mr. R. Krich If you have any questions, please contact me at (301) 415-1055.
Sincerely, Christopher Gratton, Senior Project Plant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor Docket No. 50-259, 50-260, and
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR EXTENSION OF THE COMPLETION TIME FOR INOPERABLE DIESEL GENERATORS TENNESSEE VALLEY AUTHORITY BROWNS FERRY UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, 50-296 On January 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No.11 0140319), the Nuclear Regulatory Commission (NRC) staff requested additional information from Tennessee Valley Authority (TVA) regarding its November 12, 2010 (ADAMS) Accession No, ML 103210334), amendment application.
The following questions pertain to TVA's response dated February 8, 2011 (ADAMS Accession No, ML 110450256).
- 1. Staff question to TVA Response to Electrical Question 3a The licensee stated that "Achieving a cold shutdown condition during an SBO [station blackout]
is not part of the plant's accepted SBO licensing basis ...therefore the loads assigned to the TDGs [temporary diesel generators]
are those needed to achieve HOT SHUTDOWN conditions." The NRC staff is not evaluating the licensee's compliance with Title 10 of the Code of Federal Regulations (10 CFR), Section 50.63. The SBO analysis demonstrated the plant's capability to maintain HOT SHUTDOWN conditions for an extended duration.
The staffs objective of requiring an extra power source for an inoperable emergency diesel generator (EDG) is to avoid a potential prolonged SBO event during the period of extended allowed outage time (AOT). The staff has limited granting AOT extensions to those licensees who have installed a supplemental alternating current (AC) power source (i.e., additional diesels, gas turbines, or other power sources) that can be substituted for an inoperable EDG in the event of an extended loss-of-offsite power (LOOP). It is the staffs position that the supplemental AC source should have enough capacity to carry all LOOP loads to bring the unit to a cold shutdown and perform the EDG's original licensing basis functions on a multi-unit site. The supplemental AC source should be able to be manually aligned to the safety busses within one to two hours to replace the inoperable diesel generator and prevent SBO conditions for an extended duration.
The SBO analysis may be used to provide assurance about the capability of the plant to maintain shutdown conditions during the time it takes to restore AC power from the supplemental source. While the supplemental AC source is intended to be used during a prolonged SBO event, it is not intended to maintain compliance with SBO licensing basis. The staff considers it essential for the supplemental AC source to have adequate capacity to bring the plant to cold shutdown for the following reasons: The design requirements of the onsite and offsite power sources ensure that the plant is capable of achieving cold shutdown following postulated accidents and anticipated operational occurrences.
The supplemental AC source is needed to replace an existing Enclosure
-2 source that has the capacity to support cold shutdown loads to maintain the defense-in-depth philosophy.
An accident is not postulated. Technical Specification (TS) 3.8.1.1 requires the plant to be in cold shutdown if the limiting condition for operation is not met within the allotted time. In addition, TS 3.8.1.J requires entry into Limited Condition for Operation (LCO) 3.0.3 if a combination of onsite and offsite sources are not available.
The supplemental source is expected to have adequate capacity to enable the plant to satisfy the requirements of LCO 3.0.3, if needed. Other regulatory requirements, such as a responding to a serious fire, may require plant shutdown and transition to cold shutdown.
The supplemental AC source should have adequate capacity to bring the plant to a cold shutdown as required by 10 CFR Part 50, Appendix R. To maintain the defense-in-depth philosophy for the proposed plant configuration, provide details about the capability of the supplemental power source to bring the plant to a cold shutdown.
- 2. Staff question to TVA Response to Electrical Question 3b The licensee stated that TOG load testing will use a resistive load bank, and connection to a safety-related motor. The connection of a safety-related motor or other operable safety-related component to the nonsafety-related TOG(s) could cause the connected component, and any electrically interconnected components, to become inoperable, with respect to the TSs, during the test. The NRC staffs expectation is that, as a minimum, the TOGs have a demonstrated capability for supplying large reactive power required during starting of the largest motor and steady state power requirements for expected loads to be connected to TOGs. The testing may be conducted at the TOG vendor/supplier's facility and the use of resistive load for demonstrating the kilowatt rating of the machine is acceptable.
Please describe the planned method of verifying the reactive power capability of the proposed TOG. In addition, please describe the operator manning requirements for the TOGs. Confirm that the TOGs will be continuously manned during any period that they are required to operate while an EOG is in extended period of AOT to ensure reliable operation and equal load sharing between the two TOGs, or provide a justification why continuous manning during operation is not required.
- 3. Staff question to TVA Response to Electrical Question 3c The licensee stated that during TOG load test, it will be ensured that the resistive load will be equally shared between the two TOGs. The NRC staff is concerned about the resistive and reactive load sharing of the TOGs. The loads between the two TOGs will tend to become unequal (load drifting from one TOG to another TOG) due to any minor differences between the deSign and operating characteristics of the two TOGs. Provide details on the design features of the proposed TOGs that will ensure that the load sharing will be maintained in a balanced condition between the generators.
-3 Staff question to TVA Response to Supplementary Question 1 (See January 19, 2011, cover letter) The licensee has considered the potential unavailability of the TOG during the extended allowed outage time of an EOG under maintenance.
The proposed TS allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore an inoperable TOG from the point of discovery of an unavailable TOG if the unavailability was discovered after 4 days of continuous OG inoperability.
In the event that the unavailability of the TOG was discovered on day 11 of the outage, there may be no incentive to restore the TOG. The intent of extending the completion time for TS 3.8.1 is to accommodate preplanned maintenance activities for EOGs. The TOG is expected to be available at the beginning of the preplanned activity.
The NRC staffs position is that the TOGs must be available during the entire period of extended outage time, since availability of TOGs is a primary consideration for allowing extended outage time. Please revise the Required Action 8.5 Completion Time for an unavailable TOG(s) based on above considerations.
Mr. R. Krich -If you have any questions, please contact me at (301) 415-1055.
Sincerely, IRA! Christopher Gratton, Senior Project Manager Plant licensing Branch 11-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-259, 50-260, and 50-296
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Distribution:
PUBLIC LPLlI-2 RIF RidsNrrAcrsAcnwMailCenter SMatharu, NRR RidsNrrDorlLpl2-2 RidsNrrLABClayton RidsNrrPMBrownsFerry RMathews, NRR RidsOgcRp RidsNrrDorlDpr RidsRgn2MailCenter SSom,NRR ADAMS Accession No'.. ML 11118A 154 OFFICE LPL2-2/PM LPL2-2/LA EEEB/BC LPL2-2/BC NAME CGratton BClavton (RSola for) LLund DBroaddu$
DATE 04/29/11 05/03/11 04/29/11 05/06/11 OFFICIAL RECORD COPY