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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 - 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) 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) ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16146A6352016-06-13013 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate ML16145A1582016-06-0303 June 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (SBPB-RAI 4) (CAC Nos. 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] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 28, 2016 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF4851, MF4582, AND MF4853)
Dear Mr. Shea:
By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN),
Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On January 15, 2016, the NRC staff forwarded, by electronic mail, a draft request for additional information (RAI) to TVA. On January 21, 2016, the NRC staff held a conference call to provide the licensee with an opportunity to clarify any portion of the draft RAI and discuss the timeframe for which TVA may provide the requested information. The RAI is enclosed. As agreed by the NRC and TVA staff during the conference call, TVA will respond to this RAI by February 16, 2016.
J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT. UNITS 1. 2. AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN),
Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.
The U.S. Nuclear Regulatory Commission (NRC) staff from the Electrical Engineering Branch (EEEB) and Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB),
Division of Engineering reviewed the information the licensee provided and determined that the following additional information is required in order to complete the evaluation.
EEEB-Reguest for Additional Information (RAI) 1 In Section 3.0 of Attachment 43, the licensee states:
The [TSS] study evaluated the performance of the 500 kV [kilovolt] and 161 kV offsite power systems during a DBE [design-basis event] under EPU [extended power uprate] conditions. Bus voltages observed during the simulation are compared to acceptance criteria to determine adequacy of the offsite power supply. The TSS considered a loss of the largest single supply to the grid, loss of the largest single load, loss of the nuclear unit, and loss of each bulk transmission line in the TVA transmission system, including all the lines coming into the BFN switchyard. The study used base cases from both 2015 (pre-EPU) and 2019 (post-EPU) to address the load flow analysis at EPU conditions.
A Provide the acceptable voltage range of BFN 500 kV and 161 kV offsite power acceptance criteria. Also, clarify whether the voltage criteria corresponding to post-EPU conditions has been agreed upon by the transmission system operator.
Enclosure
B. Provide a summary of the cases studied, with diagrams to verify that the voltage criteria is met under the following post-EPU conditions:
- i. loss of the largest load (identify the load),
ii. loss of the largest generator (identify the generator), and iii. loss of the most critical transmission line (identify the line).
EEEB-RAI 2 In Section 2.3.3.1 of Attachment 7, "Safety Analysis Report for Browns Ferry Nuclear Plant Units 1, 2, and 3 Extended Power Uprate," the licensee states:
The larger condensate pump motors {1,250 horsepower (hp)), CSP motors (3,000 hp) and reactor recirculation pump motors (8,657 hp) do not change the conclusions of the current Browns Ferry degraded voltage analysis. The analysis encompasses the safety-related 4.16 kV [kilovolts] buses and is independent of voltage profiles for the balance of plant buses [BOP].
Provide a summary of the degraded voltage analysis corresponding to post-EPU conditions.
Also, provide single line diagram(s) showing the safety-related 4.16 kV buses with their connected loads and power sources and the BOP buses with their connected loads and power sources.
EEEB-RAI 3 In Section 2.3.3.2 of Attachment 7, the licensee states:
The analytical electrical system computer model developed for Browns Ferry updated the main power transformer size to reflect the recent change of main power transformers and the proposed changes to the main generators and condensate pumps.
Provide a description of the proposed changes, including the ratings, to the main generators.
EEEB-RAI 4 In Section 2.3.2.2 of Attachment 7, the licensee states:
The Unit 1, Unit 2 and Unit 3 isolated phase bus (IPB) duct work, cooling coils and fans have been modified to increase the continuous current rating to provide for operation at EPU output.
Provide the IPB duct current rating and the continuous current requirement for EPU conditions to show the adequacy of the IPB duct to support operation under EPU conditions. Also, provide a description of the modifications made to the IPB duct, cooling coils, and fans, to increase the continuous current rating for operating at EPU conditions.
ESGB-RAI 1 In Section 10.3.6 of the Updated Final Safety Analysis Report, and in information provided in the supplemental letter dated December 15, 2015, it is indicated that a Boral neutron absorber monitoring program is used at BFN, Units 1, 2, and 3. The intent of the monitoring program is to manage potential reduction of neutron-absorbing capacity and loss of material due to general corrosion. However, in the sources mentioned, there is minimal information describing the Boral monitoring program. For this reason, please provide a brief description of the monitoring program. The information provided should include the following discussion:
A. If test specimens (i.e., coupons) are used:
- i. Define the periodicity for evaluation.
ii. Provide the number of coupons available.
iii. Describe any adverse conditions identified from coupon evaluation thus far.
iv. Discuss the ambient conditions for the coupons in the spent fuel pool (e.g.,
surrounded by freshly discharged spent fuel assemblies).
- v. Discuss whether coupons are returned to the spent fuel pool after inspection.
B. If coupons are not used, discuss the periodicity of surveillance.
C. Describe the types of tests performed during the periodic inspection.
- a. Describe the test procedure.
- b. Discuss whether neutron-attenuation testing is performed to determine the boron-1 O (B-10) areal density of the absorber material during periodic testing.
D. Define the acceptance criteria for the surveillance program, including what constitutes an adverse condition.
E. Describe those measures taken to address a failure to meet the acceptance criteria for either the surveillance program and/or the B-10 areal density.
F. Address any adverse conditions, other than identified corrosion, which may be identified during testing, and whether different acceptance criteria apply to those other adverse conditions.
J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
Sincerely, IRA/
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLABClayton SKrepel, NRR LPL2-2 R/F RidsACRS_MailCTR RidsNrrDeEsgb RidsNrrDorllpl2-2 RidsRgn2MailCenter RisdNrrDeEeeb KWood, NRR RidsNrrPMBrownsFerry ADAMS Access1on No.: ML16020A111 *b>Y memoran d um **b>Y e-ma1*1 OFFICE NRR/DORL/LPLll-2/PM NRR/DORL/LPLll-2/LA NRR/DE/EEEB/BC**
NAME FSaba (LRonewicz for) BClayton JZimmerman DATE 1/21/2016 1/22/2016 1/28/2016 OFFICE NRR/DE/ESGB/BC* NRR/DORL/LPLll-2/BC NRR/DORL/LPLll-2/PM NAME GKulesa BBeasley FSaba DATE 1/13/2016 1/28/2016 1/28/2016 OFFICIAL RECORD COPY