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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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
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23332A0042023-11-27027 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 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 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 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 - 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MF6741, MF6742, and MF6743) ML16144A6452016-06-0303 June 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Non-proprietary Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (EMCB-RAI) ML16119A1332016-05-0606 May 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (SNPB-RAI) (CAC Nos. MF6741, MF6742, and MF6743) 2023-08-29
[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