Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML070370281, ML073100027, ML073510180, ML080360067, ML080430700, ML080500171, ML080530256, ML081010450, ML081010451, ML081120502, ML081700294, ML081720078, ML081760295, ML082040065, ML082050462, ML082100425, ML082810470, ML083120308, ML083240224, ML083250083, ML090130718, ML090340528, ML090720951, ML090760630, ML091320366, ML092020345, ML092430520, ML092440518, ML092460495, ML092460496, ML092460497, ML092460498, ML092460500, ML092540483, ML092680057, ML12319A076, ML13044A498
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MONTHYEARML0711503712007-04-24024 April 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Steam Dryer Evaluations Project stage: Request ML0712905652007-05-16016 May 2007 Withholding Information from Public Disclosure, Response to Nuclear Regulatory Commission (NRC) Request for Additional Information - Round 12 for Browns Ferry EPU: Supplemental to SBWB-64 Project stage: RAI ML0716303492007-06-15015 June 2007 Meeting with the Tennessee Valley Authority Concerning the Status of Browns Ferry Nuclear Plant, Units 1, 2 and 3, Steam Dryer Review Project stage: Meeting ML0718700242007-07-0303 July 2007 Technical Specifications (TS) Change TS-461 - Modification of Restart Large Transient Testing License Condition 2. (G) 2 - Supplement 1 Project stage: Request ML0717801902007-07-0505 July 2007 Request for Additional Information for Extended Power Uprate - Round 13 (TS-431 and TS-418 (TAC Nos. MD5262, MD5263, and MD5264) Project stage: RAI ML0719004762007-07-10010 July 2007 Meeting with the Tennessee Valley Authority (TVA) Concerning the Pending ACRS Meeting on the Browns Ferry Extended Power Uprate Project stage: Meeting ML0721501562007-07-18018 July 2007 Slides from Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation Project stage: Meeting ML0721303712007-07-27027 July 2007 Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate - Steam Dryer Evaluations Project stage: Request ML0721400442007-08-0808 August 2007 Summary of Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation Project stage: Meeting ML0724805472007-08-31031 August 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure Project stage: Request ML0727606602007-10-0909 October 2007 Request for Additional Information for Extended Power Uprate - Round 14 (TS-418) Project stage: RAI ML0728902372007-10-18018 October 2007 Request for Withholding Information from Public Disclosure Concerning Round 13 Request for Additional Information for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263 and MD5264) Project stage: RAI ML0729603112007-10-22022 October 2007 Technical Specification (TS) Changes TS-431 & TS-418, Extended Power Uprate - EPU Large Transient Testing Project stage: Request ML0731000272007-11-0909 November 2007 Request for Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418-S) Project stage: Other ML0732303482007-11-15015 November 2007 Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure APLA-35/37 Project stage: Request ML0733304832007-11-21021 November 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Preliminary Findings on Steam Dryer Stress Analysis Project stage: Request ML0735101802007-12-14014 December 2007 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Schedule Regarding Analysis for Steam Dryers Project stage: Other ML0734607572007-12-19019 December 2007 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac No. MD5262, MD5263 and MD5264) Project stage: Withholding Request Acceptance ML0735400102008-01-25025 January 2008 Summary of Meeting with Tennessee Valley Authority on Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264), Browns Ferry Units 1, 2, and 3 Project stage: Meeting ML0801504182008-01-25025 January 2008 Plants, Units 1, 2, and 3 - (Public Version) - Summary of December 10, 2007 Meeting with TVA on Steam Dryer Portion of the Extended Power Uprate Review Project stage: Meeting ML0803205212008-01-25025 January 2008 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) Response to Round 15 Request for Additional Information (RAI) - APLA-38/40, SRXB-71, and SRXB-72 Project stage: Request ML0803600672008-01-25025 January 2008 Steam Dryer RAI 15 Status, Slides Project stage: Other ML0802501652008-01-30030 January 2008 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263, and MD5264) Project stage: Withholding Request Acceptance ML0803805602008-01-31031 January 2008 Technical Specifications (TS) Change TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 Request for Additional Information (RAI) Regarding Steam Dryer Analyses Project stage: Request ML0804307002008-02-11011 February 2008 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Schedule Regarding EPU Project stage: Other ML0803503812008-02-14014 February 2008 Summary of Meeting with Tennessee Valley Authority - on Extended Power Uprate Review Project stage: Meeting ML0805302562008-02-21021 February 2008 Unit 1 - Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Fuels Methods Commitments Project stage: Other ML0806501012008-02-21021 February 2008 Response to Round 16 Request for Additional Information SRXB-73 Project stage: Request ML0804506472008-02-27027 February 2008 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0803506982008-02-29029 February 2008 Request for Additional Information for Extended Power Uprate - Round 16 (TS-431 and TS-418) (TACs MD5262, MD5263, MD5264) Project stage: RAI ML0807104982008-03-0606 March 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Change TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 16 Request for Additional Information (RAI) - SRXB-74/86 and SRXB-87 Through SRXB-90 Project stage: Request ML0811205102008-03-20020 March 2008 Summary of March 20, 2008, Meeting with Tennessee Valley Authority Regarding Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264) - Slides Project stage: Meeting ML0810104512008-04-0404 April 2008 Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) BFN Steam Monitoring Plan Project stage: Other ML0810104502008-04-0404 April 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 and Round 16 Requests for Additional Information (RAI) Regarding Steam Dryer Analyses Project stage: Other ML0817602952008-04-0909 April 2008 Units 1, 2, & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Confirmation of Commitment Completions Project stage: Other ML0811205022008-04-16016 April 2008 CDI Incoming Letter Dated April 16, 2008 Regarding NRC Presentation Entitled, Tennessee Valley Authority Browns Ferry Nuclear Plant - Extended Power Uprate Steam Dryers. Project stage: Other ML0811302312008-04-17017 April 2008 Public Slides - Summary of April 17, 2008, Meeting Regarding Steam Dryer Portion of the Extended Power Uprate Review, Project stage: Meeting ML0811200332008-04-30030 April 2008 Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Withholding Information from Public Disclosure for Round 15 Fuels Responses Project stage: Withholding Request Acceptance ML0812806272008-05-0101 May 2008 Technical Specifications Change TS-418, Extended Power Uprate Supplemental Response to Round 16 Request for Additional Information - SRXB-87 & SRXB-89 Project stage: Supplement ML0813502222008-05-0202 May 2008 Request for Additional Information for Extended Power Uprate - Round 17 (TS-431 and TS-410) Project stage: RAI ML0805001712008-05-0202 May 2008 - Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418) Project stage: Other ML0812804712008-05-0202 May 2008 Request for Additional Information for Extended Power Uprate - Round 17 Project stage: RAI ML0813602912008-05-22022 May 2008 Summary of April 17, 2008, Meeting Regarding Steam Dryer Portion of the Extended Power Uprate Review Project stage: Meeting ML0815805532008-05-22022 May 2008 Summary of 5/22/08 Meeting Regarding Containment Overpressure Portion of the Extended Power Uprate Review - Browns Ferry - Handouts Project stage: Meeting ML0810604452008-06-0202 June 2008 Request for Withholding Information from Public Disclosure for Partial Round 13 Responses (Tacs. MD5262, MD5263 and MD5264) Project stage: Withholding Request Acceptance ML0810606162008-06-0202 June 2008 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant Project stage: Withholding Request Acceptance ML0810607222008-06-0202 June 2008 Request for Withholding Information from Public Disclosure for Partial Response to Round 13 Project stage: Withholding Request Acceptance ML0816403252008-06-0303 June 2008 Units 2 & 3 - Technical Specifications Change TS-418 - Extended Power Uprate - Supplemental Response to Round 16 Request for Additional Information - SRXB-88 Project stage: Supplement ML0812607122008-06-0505 June 2008 Summary of Meeting with TVA Steam Dryer Portion of the Extended Power Uprate Review Project stage: Meeting ML0817002942008-06-12012 June 2008 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to ACRS Conclusions and Recommendations Regarding Containment Overpressure Credit Project stage: Other 2008-01-30
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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
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Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 August 28, 2009 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Response to Round 24 Request for Additional Information (RAI) EMCB.208 Regarding Steam Dryer Analyses (TAC NO. MD5262)
References:
- 1. Letter from TVA to NRC, "Browns Ferry Nuclear Plant (BFN) -
Unit 1 - Proposed Technical Specifications (TS) Change TS - 431 -
Request for License Amendment - Extended Power Uprate (EPU)
Operation," dated June 28, 2004
- 2. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Unit 1 -
Request for Additional Information for Extended Power Uprate -
Round 24," dated June 9, 2009
- 3. Letter from TVA to NRC, "Browns Ferry Nuclear Plant (BFN) -
Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 24 Request for Additional Information (RAI) EMCB.209 Regarding Steam Dryer Analyses," dated May 29, 2009 The Tennessee Valley Authority (TVA) submitted a license amendment application to NRC for the EPU of BFN Unit 1 on June 28, 2004 (Ref. 1). The proposed amendment would modify the operating license to increase the maximum authorized core thermal power level by approximately 14 percent to 3952 megawatts.
NRC issued a Round 24 RAI regarding the EPU steam dryer analyses on June 9, 2009 (Ref. 2) and indicated that TVA had agreed to provide the requested additional information by June 5, 2009. TVA provided the response to RAI EMCB.209 on May 29, 2009 (Ref. 3). Subsequently, TVA representatives discussed plans for addressing RAI EMCB.208 with the NRC Project Manager for the BFN. Enclosure 1 1o3172r-,
Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 August 28, 2009 provides the response for RAI EMCB.208 which completes the responses to the Round 24 RAI.
As discussed during the meeting with the NRC staff on August 11, 2009, TVA is revising the stress analysis for the BFN Unit 1 steam dryer to not credit low flow noise removal. The revised steam dryer stress analysis will show that the BFN Unit 1 steam dryer meets acceptable stress criteria at EPU conditions with the added planned modifications. Also, a steam dryer stress analysis has been performed that shows the BFN Unit 1 steam dryer meets acceptable stress criteria at 110% of original licensed power (OLTP) with the currently modified BFN Unit 1 steam dryer. This analysis was performed to support 110% OLTP operation (approximately 5% increase from current licensed power level) prior to the implementation of the planned steam dryer modifications needed for EPU operation. The steam dryer stress analyses are further discussed in the response to RAI EMCB.208 in Enclosure 1. The revised BFN Unit 1 steam dryer reports for 110% OLTP conditions are provided in Enclosures 2, 3, and 4.
TVA is finalizing the revised steam dryer reports for EPU conditions (i.e., 120% OLTP) and plans to submit these reports by August 31, 2009.
Note that Enclosures 1, 2, 3, and 4 contain information that Continuum Dynamics, Inc.
(CDI) considers to be proprietary in nature and subsequently, pursuant to 10 CFR 2.390(a)(4), CDI requests that such information be withheld from public disclosure. provides an affidavit from CDI supporting this request. Enclosures 5, 6, 7, and 8 contain the redacted versions of the proprietary enclosures with the CDI proprietary material removed, which are suitable for public disclosure.
TVA has determined that the additional information provided by this letter does not affect the no significant hazards considerations associated with the proposed TS change. The proposed TS change still qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9).
No new regulatory commitments are made in this submittal. Please direct any questions concerning this matter to J. D. Wolcott at (256) 729-2495.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 2 8 th day of August, 2009.
Respectfully, R. M. Krich Vice President Nuclear Licensing
Enclosures:
Enclosure 1 - Response to Round 24 Request for Additional Information (RAI) EMCB.208 Regarding Steam Dryer Analyses (Proprietary Version)
U.S. Nuclear Regulatory Commission Page 3 August 28, 2009 Enclosure 2 - CDI Report No.09-24P, "Stress Assessment of Browns Ferry Nuclear Unit 1 Steam Dryer to 110% OLTP Power Level," Revision 0 (Proprietary Version)
Enclosure 3 - CDI Report No.09-22P, "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level to 110%
OLTP Power Level on Browns Ferry Nuclear Unit 1 Steam Dryer to 250 Hz," Revision 0 (Proprietary Enclosure 4 - Version)
CDI Technical Note No. 09-11 P, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension to 110% OLTP at Browns Ferry Nuclear Unit 1," Revision 0 (Proprietary Enclosure 5 - Version)
Response to Round 24 Request for Additional Information (RAI) EMCB.208 Regarding Steam Dryer Enclosure 6 - Analyses (Non-proprietary Version)
CDI Report No. 09-24NP, "Stress Assessment of Browns Ferry Nuclear Unit 1 Steam Dryer to 110%
OLTP Power Level," Revision 0 (Non-proprietary Enclosure 7 - Version)
CDI Report No. 09-22NP, "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level to 110%
OLTP Power Level on Browns Ferry Nuclear Unit 1 Steam Dryer to 250 Hz," Revision 0 (Non-proprietary Enclosure 8 - Version CDI Technical Note No. 09-11 NP, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension to 110% OLTP at Browns Ferry Nuclear Unit 1," Revision 0 Enclosure 9 - (Non-proprietary Version)
CDI Affidavit cc (Enclosures):
Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer - Alabama Department of Public Health
PROPRIETARY INFORMATION ENCLOSURE I TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT I TECHNICAL SPECIFICATIONS (TS) CHANGE TS-431 EXTENDED POWER UPRATE (EPU)
RESPONSE TO ROUND 24 REQUEST FOR ADDITIONAL INFORMATION (RAI) EMCB.208 REGARDING STEAM DRYER ANALYSES (PROPRIETARY VERSION)
Attached is the proprietary version of the Response to Round 24 RAI EMCB.208 Regarding Steam Dryer Analyses.
CDI proprietary information is identified by double square brackets. TVA has added superscript notation "(3),, to the applicable text of NRC RAI EMCB.208 in accordance with 10 CFR 2.390(b)(1)(i)(B). In each case, the superscript notation ,(3), refers to Paragraph (3) of the.
affidavit provided, which documents the basis for the proprietary determination. ((This sentence is an example.(3))) Specific information that is not so marked is not considered to be CDI proprietary information.
An affidavit attesting to the proprietary nature of this enclosure is contained in Enclosure 9.
PROPRIETARY INFORMATION NRC RAI EMCB.208 (Unit 1)
It appears that the main steam line (MSL) strain gage measurements in Unit 1 were reduced by subtracting:
((1. Electrical interference check signals measured at low input voltages to the strain gage arrays;
- 2. 'exclusion' tones caused by plant machinery, such as pumps;
- 3. the incoherent portion of the signals between upper and lower arrays, where coherence is adjusted using the methodology described in Chapter 7 of CDI Report 07-09P, Rev. 0; and,
- 4. data acquired at Low Flow (LF) conditions in the Unit 1 plant. (3)))
In Enclosure 3 of a letter dated July 27, 2007, the licensee provide acoustic circuit model (ACM), Rev. 4 (described in CDI Report 07-09P, Rev. 0) which was benchmarked using Quad Cities 2 (QC2) MSL and steam dryer measurements. The licensee used the QC2 benchmark data to compute the frequency dependent bias errors and uncertainties for Unit 1. ((However, the MSL strain gage measurements used for the QC2 benchmark were only adjusted using items 1-3 in the list above. No LF data was subtracted from the MSL QC2 benchmark measurements. (3)))
Address the apparent inconsistency with the conclusion that the CDI 07-09 bias and uncertainties are conservative ((given that the benchmarked code (QC2) did not subtract the LF data. Demonstrate by analyses that the bias and uncertainties assumed in CDI Report 07-09P are applicable to Unit 1 when LF is subtracted. (3)))
TVA Response to EMCB.208 (Unit 1)
The benchmarking of ACM Rev. 4 was performed by comparing predicted pressure loads based upon QC MSL measurements against actual pressure measurements on the QC dryers. No signal conditioning was performed by CDI on either the MSL data or the steam dryer pressure data. However, it is apparent from examination of the data plots in CDI Report No.07-09P that a 60 Hertz notch filter was present on both sets of data. The presence of noise in each of the signals would have opposite effects on the benchmarking bias and uncertainty values.
Depending on the relative magnitude of noise in the data sets, the effect of low flow noise could increase or decrease the conservatism of the pressure load prediction. Determining the effect of signal noise on the conservatism of the pressure load prediction would involve analysis of additional low flow data from an instrumented steam dryer.
To facilitate the review and approval of EPU for BFN Unit 1, TVA has designed additional modifications that will allow the steam dryer to meet the alternating stress ratio (SR-a) criteria of SR-a > 2.0 at EPU conditions without crediting low flow noise removal. TVA is finalizing the revised steam dryer reports for EPU conditions and plans to submit these reports by August 31,
- 2009, The planned steam dryer modifications to support EPU operation will require vessel disassembly and, thus, will be scheduled to be implemented during the next refueling outage currently scheduled for Fall 2010. TVA anticipates that approval of the EPU license amendment for Unit 1 could be obtained in advance of the next refueling outage (contingent on NRC staff review). Accordingly, TVA has performed an additional Unit 1 steam dryer stress analysis El-1
PROPRIETARY INFORMATION based on the currently modified steam dryer at 110% original licensed thermal power (OLTP) which meets the criteria of SR-a > 2.0 without crediting low flow noise removal. This analysis supports operation of Unit 1 at 110% OLTP (approximately 105% of current licensed thermal power (CLTP)) prior to the completion of the additional steam dryer modifications which would be implemented during the refueling outage.
The 110% OLTP steam dryer analysis, CDI Report No.09-24P, "Stress Assessment of Browns Ferry Nuclear Unit 1 Steam Dryer to 110% OLTP Power Level," is provided in Enclosure 2 and includes the following aspects:
- Steam dryer finite element model is based upon the current modified steam dryer.
" No credit is taken for low flow noise removal in determining the steam dryer stress results.
- Bump-up factors associated with 110% OLTP are used in determining stress results at 110% OLTP.
The Unit 1 results based on the above changes indicate a minimum SR-a with frequency shifts and no credit for low flow noise removal of SR-a = 2.33 at CLTP and SR-a = 2.01 at 110%
OLTP with bump-up factors applied. provides the associated load report, CDI Report No.09-22P, "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level to 110% OLTP Power Level on Browns Ferry Nuclear Unit 1 Steam Dryer to 250 Hz," and Enclosure 4 provides the associated limit curve report, CDI Technical Note 09-11 P, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension to 110% OLTP at Browns Ferry Nuclear Unit 1."
E1-2
ENCLOSURE 5 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT I TECHNICAL SPECIFICATIONS (TS) CHANGE TS-431 EXTENDED POWER UPRATE (EPU)
RESPONSE TO ROUND 24 REQUEST FOR ADDITIONAL INFORMATION (RAI) EMCB.208 REGARDING STEAM DRYER ANALYSES (NON-PROPRIETARY VERSION)
Attached is the non-proprietary version of the Response to Round 24 RAI EMCB.208 Regarding Steam Dryer Analyses.
NON-PROPRIETARY INFORMATION NRC RAI EMCB.208 (Unit 1)
It appears that the main steam line (MSL) strain gage measurements in Unit 1 were reduced by subtracting:
In Enclosure 3 of a letter dated July 27, 2007, the licensee provide acoustic circuit model (ACM), Rev. 4 (described in CDI Report 07-09P, Rev. 0) which was benchmarked using Quad Cities 2 (QC2) MSL and steam dryer measurements. The licensee used the QC2 benchmark data to compute the frequency dependent bias errors and uncertainties for Unit 1. ((
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Address the apparent inconsistency with the conclusion that the CDI 07-09 bias and uncertainties are conservative ((
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TVA Response to EMCB.208 (Unit 1)
The benchmarking of ACM Rev. 4 was performed by comparing predicted pressure loads based upon QC MSL measurements against actual pressure measurements on the QC dryers. No signal conditioning was performed by CDI on either the MSL data or the steam dryer pressure data. However, it is apparent from examination of the data plots in CDI Report No.07-09P that a 60 Hertz notch filter was present on both sets of data. The presence of noise in each of the signals would have opposite effects on the benchmarking bias and uncertainty values.
Depending on the relative magnitude of noise in the data sets, the effect of low flow noise could increase or decrease the conservatism of the pressure load prediction. Determining the effect of signal noise on the conservatism of the pressure load prediction would involve analysis of additional low flow data from an instrumented steam dryer.
To facilitate the review and approval of EPU for BFN Unit 1, TVA has designed additional modifications that will allow the steam dryer to meet the alternating stress ratio (SR-a) criteria of SR-a > 2.0 at EPU conditions without crediting low flow noise removal. TVA is finalizing the revised steam dryer reports for EPU conditions and plans to submit these reports by August 31, 2009.
The planned steam dryer modifications to support EPU operation will require vessel disassembly and, thus, will be scheduled to be implemented during the next refueling outage currently scheduled for Fall 2010. TVA anticipates that approval of the EPU license amendment for Unit 1 could be obtained in advance of the next refueling outage (contingent on NRC staff review). Accordingly, TVA has performed an additional Unit I steam dryer stress analysis E5-1
NON-PROPRIETARY INFORMATION based on the currently modified steam dryer at 110% original licensed thermal power (OLTP) which meets the criteria of SR-a > 2.0 without crediting low flow noise removal. This analysis supports operation of Unit 1 at 110% OLTP (approximately 105% of current licensed thermal power (CLTP)) prior to the completion of the additional steam dryer modifications which would be implemented during the refueling outage.
The 110% OLTP steam dryer analysis, CDI Report No.09-24P, "Stress Assessment of Browns Ferry Nuclear Unit 1 Steam Dryer to 110% OLTP Power Level," is provided in Enclosure 2 and includes the following aspects:
- Steam dryer finite element model is based upon the current modified steam dryer.
- No credit is taken for low flow noise removal in determining the steam dryer stress results.
- Bump-up factors associated with 110% OLTP are used in determining stress results at 110% OLTP.
The Unit 1 results based on the above changes indicate a minimum SR-a with frequency shifts and no credit for low flow noise removal of SR-a = 2.33 at CLTP and SR-a = 2.01 at 110%
OLTP with bump-up factors applied. provides the associated load report, CDI Report No.09-22P, "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level to 110% OLTP Power Level on Browns Ferry Nuclear Unit 1 Steam Dryer to 250 Hz," and Enclosure 4 provides the associated limit curve report, CDI Technical Note 09-11 P, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension to 110% OLTP at Browns Ferry Nuclear Unit 1."
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