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| =Text= | | =Text= |
| {{#Wiki_filter:l June 26,1997 1 Mr. Oliver D. Kingsley, Jr. l President, TVA Nuclear and Chief Nuclear Officer Tennessee Valley Authority 6A Lookout Place 1101 Market Street I Chattanooga, TN 37402-2801 | | {{#Wiki_filter:June 26,1997 1 |
| | Mr. Oliver D. Kingsley, Jr. |
| | President, TVA Nuclear and Chief Nuclear Officer Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. M97412, M97413, AND M97414) l (TS 386) l | | BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. M97412, M97413, AND M97414) |
| | (TS 386) |
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| ==Dear Mr. Kingsley:== | | ==Dear Mr. Kingsley:== |
| | | On December 11, 1996, the Tennessee Valley Authority (TVA) requested amendments to the operating licenses for the Browns Ferry Nuclear Plant (BFN) |
| 1 On December 11, 1996, the Tennessee Valley Authority (TVA) requested amendments to the operating licenses for the Browns Ferry Nuclear Plant (BFN)
| | Units 1, 2, and 3. |
| Units 1, 2, and 3. This request proposed changing technical'. specifications (TS) for the as-found setpoint tolerance for the main steam safety / relief valves from fl% to i3%. The U.S. Nuclear Regulatory Commission (NRC) staff ) | | This request proposed changing technical'. specifications (TS) for the as-found setpoint tolerance for the main steam safety / relief valves from fl% to i3%. |
| has determined that additional information will be requiredito complete its l review of TVA's request. The additional information requested is described in l the enclosure.- , | | The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information will be requiredito complete its review of TVA's request. |
| The NRC staff understands that TVA has not established a schedule for BFN Unit I restart. TVA stated that analyses required for the increased setpoint tolerance will be performed prior to BFN Unit I restart. TVA also noted that the increased setpoint tolerance had been incorporated into the proposed BFN improved technical specification (ITS) conversion submitted on September 6, 1996. Since the BFN Unit 1 proposed ITS include the. change in tolerance, there is no need to track this change for the current BFN Unit 1 TS. | | The additional information requested is described in the enclosure.- |
| Therefore, the staff intends to deny the amendment requested on December 11, 1996 for BFN Unit 1. This denial will be documented in separate correspondence. | | The NRC staff understands that TVA has not established a schedule for BFN Unit I restart. |
| | TVA stated that analyses required for the increased setpoint tolerance will be performed prior to BFN Unit I restart. TVA also noted that the increased setpoint tolerance had been incorporated into the proposed BFN improved technical specification (ITS) conversion submitted on September 6, 1996. |
| | Since the BFN Unit 1 proposed ITS include the. change in tolerance, there is no need to track this change for the current BFN Unit 1 TS. |
| | Therefore, the staff intends to deny the amendment requested on December 11, 1996 for BFN Unit 1. |
| | This denial will be documented in separate correspondence. |
| Please contact me at (301)415-1470 if you have any questions on this topic. | | Please contact me at (301)415-1470 if you have any questions on this topic. |
| Sincerely, 30 W. CEMER CM WRlMfiffah.eroJectMana9er Project Directorate 11-3 9706300186 970626 Division of Reactor Projects - I/II PDR P | | Sincerely, 30 W. CEMER CM WRlMfiffah.eroJectMana9er Project Directorate 11-3 9(b \\ |
| ADOCK 05000259 PDR Office of Nuclear Reactor Regulation 9(b \ | | 9706300186 970626 Division of Reactor Projects - I/II PDR ADOCK 05000259 Office of Nuclear Reactor Regulation P |
| Docket Nos. 50-259, 50-260, and 50-296 | | PDR Docket Nos. 50-259, 50-260, and 50-296 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request For Additional Ei_stribution \ | | Request For Additional Ei_stribution |
| Information Docket File GHammer PUBLIC GGolub l cc w/ | | \\ |
| | Information Docket File GHammer PUBLIC GGolub l |
| | cc w/ |
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| ==Enclosure:== | | ==Enclosure:== |
| See next page BFN Rdg. BMozafari SVarga JJohnson, RII DOCUMENT NAME: G:\BFN\M97412.RAI OGC ACRS To receive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" = No copy 0FFICE PDII-3/PM /,1 lf PDII-3/LA _4/ lC PDII-3/D f4 / pox l1 l NAME JWilliams /hS/ BClayton A9~' FHebdon/f' Ay1/ | | See next page BFN Rdg. |
| DATE 06/fp /97 F 06/-) te/97 06/ A /97 0FFICIAL RECORD COPY | | BMozafari SVarga JJohnson, RII DOCUMENT NAME: |
| - - _ - - - - - c 2 02 Tl
| | G:\\BFN\\M97412.RAI OGC ACRS To receive a copy of this document, indicate in the box: |
| | "C" - Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" = No copy 0FFICE PDII-3/PM /,1 lf PDII-3/LA |
| | _4/ lC PDII-3/D f4 / pox l1 l |
| | NAME JWilliams /hS/ |
| | BClayton A9~' |
| | FHebdon/f' Ay1/ |
| | DATE 06/fp /97 F 06/-) te/97 06/ A /97 0FFICIAL RECORD COPY |
| | - - - - - c 2 02 Tl |
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| 1 l , | | 1 l |
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| l Mr. Ol'iver D. Kingsley, Jr. BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority l | | l Mr. Ol'iver D. Kingsley, Jr. |
| ! l cc l Mr. O. J. Zeringue, Sr. Vice President Mr. Timothy E. Abney, Manager Nuclear Operations Licensing and Industry Affairs
| | BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority l |
| ; Tennessee Valley Authority Browns Ferry Nuclear Plant
| | cc l |
| ! 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 l ,
| | Mr. O. J. Zeringue, Sr. Vice President Mr. Timothy E. Abney, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 l |
| 1 Mr. Jack A. Bailey, Vice President Regional Administrator { | | 1 Mr. Jack A. Bailey, Vice President Regional Administrator Engineering & Technical Services U.S. Nuclear Regulatory Commission Tennessee Valley Authority Region II 6A Lookout Place 61 Forsyth Street, SW., Suite 23T85 1101 Market Street Atlanta, GA 30303-3415 Chattanooga, TN 37402-2801 Mr. Leonard D. Wert Mr. C. M. Crane, Site Vice President Senior Resident Inspector Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 10833 Shaw Road Decatur, AL 35609 Athens, AL 35611 i |
| Engineering & Technical Services U.S. Nuclear Regulatory Commission ! | | General Counsel Chairman Tennessee Valley Authority Limestone County Commission ET 10H 310 West Washington Street 400 West Summit Hill Drive Athens, AL 35611 Knoxville, TN 37902 State Health Officer Mr. Raul R. Baron, General Manager Alabama Department of Public Health Nuclear Assurance and Licensing 434 Monroe Street Tennessee Valley Authority Montgomery, AL 36130-1701 4J Blue Ridge 8 |
| Tennessee Valley Authority Region II 6A Lookout Place 61 Forsyth Street, SW., Suite 23T85 1101 Market Street Atlanta, GA 30303-3415 ) | | 1101 Market Street Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Pedro Salas, Manager Licensing and Industry Affairs Tennessee Valley Authority 4J Blue Ridge j |
| Chattanooga, TN 37402-2801 Mr. Leonard D. Wert Mr. C. M. Crane, Site Vice President Senior Resident Inspector Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority ' | | l 1101 Market Street l |
| U.S. Nuclear Regulatory Commission P.O. Box 2000 10833 Shaw Road Decatur, AL 35609 Athens, AL 35611 i | | Chattanooga, TN 37402-2801 |
| General Counsel Chairman Tennessee Valley Authority Limestone County Commission ET 10H 310 West Washington Street 400 West Summit Hill Drive Athens, AL 35611 Knoxville, TN 37902 State Health Officer Mr. Raul R. Baron, General Manager Alabama Department of Public Health Nuclear Assurance and Licensing 434 Monroe Street Tennessee Valley Authority Montgomery, AL 36130-1701 4J Blue Ridge 8 1101 Market Street Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Pedro Salas, Manager Licensing and Industry Affairs , | | / |
| Tennessee Valley Authority i 4J Blue Ridge j l 1101 Market Street ! | |
| l Chattanooga, TN 37402-2801
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| l REQUEST FOR ADDITIONAL INFORMATION l T - | | l REQUEST FOR ADDITIONAL INFORMATION l T BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 l |
| l BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 l ,
| | l INCREASED MAIN STEAM SAFETY / RELIEF VALVE SETPOINT TOLERANCE |
| INCREASED MAIN STEAM SAFETY / RELIEF VALVE SETPOINT TOLERANCE l l | | : 1., page 13 of the December 11, 1996 submittal states that the hydrodynamic main steam safety / relief valves (S/RVs) loads resulting from the 3% setpoint tolerance are less than 1% higher than the " loads l |
| l
| | used in design." However, it is the NRC staff's experience via review l |
| : 1. Enclosure 5, page 13 of the December 11, 1996 submittal states that the hydrodynamic main steam safety / relief valves (S/RVs) loads resulting from the 3% setpoint tolerance are less than 1% higher than the " loads l used in design." However, it is the NRC staff's experience via review l of other analyses, such as those supporting power uprate at several , | | of other analyses, such as those supporting power uprate at several boiling water reactors that the loads vary almost linearly with respect t |
| t boiling water reactors that the loads vary almost linearly with respect I to opening pressure of the S/RVs. Therefore, it is expected that an '
| | to opening pressure of the S/RVs. |
| increase in the S/RV setpoints to 3% would result in a 3% increase in ! | | Therefore, it is expected that an increase in the S/RV setpoints to 3% would result in a 3% increase in the S/RV hydrodynamic loads. |
| the S/RV hydrodynamic loads. I | | a. |
| : a. What S/RV setpoints and setpoint tolerances were assumed for developing the above " loads used in design"?
| | What S/RV setpoints and setpoint tolerances were assumed for developing the above " loads used in design"? |
| : b. Describe the methodology for determining the S/RV hydrodynamic loads and the analysis results which indicate only a 1% load increase for the 3% setpoint tolerance. l l .
| | b. |
| It is also stated that the resulting 1% increase in the loads is negligible when combined with other combined loads; therefore, the effect of the load increases on the plant structures were not evaluated. | | Describe the methodology for determining the S/RV hydrodynamic loads and the analysis results which indicate only a 1% load increase for the 3% setpoint tolerance. |
| What is the available structural margin such that these load c. | | l It is also stated that the resulting 1% increase in the loads is negligible when combined with other combined loads; therefore, the effect of the load increases on the plant structures were not evaluated. |
| increases are negligible? | | c. |
| : 2. Enclosure 5, page 13 of the December 11, 1996 submittal states that the maximum differential pressure due to the increased S/RV setpoint 4 tolerance was evaluated for valves in the Generic Letter 89-10 program. | | What is the available structural margin such that these load increases are negligible? |
| Please verify that the calculations which demonstrate the capability of ' | | : 2., page 13 of the December 11, 1996 submittal states that the maximum differential pressure due to the increased S/RV setpoint 4 |
| these valves to function adequately have been revised for these i differential pressures. ; | | tolerance was evaluated for valves in the Generic Letter 89-10 program. |
| 1
| | Please verify that the calculations which demonstrate the capability of these valves to function adequately have been revised for these differential pressures. |
| : 3. What is the basis for the high-pressure coolant injection (HPCI) and I reactor core isolation cooling (RCIC) design requirement to provide design flow to the reactor vessel at pressures up to 1120 psig? In other words, how was the 1120 psig value originally determined?
| | 3. |
| : 4. The engineering analysis describes the calculations performed to determine the required additional flow, power, and rpm needed for HPCI and RCIC.
| | What is the basis for the high-pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) design requirement to provide design flow to the reactor vessel at pressures up to 1120 psig? |
| : a. Do the HPCI and RCIC turbines have a maximum allowable pressure?
| | In other words, how was the 1120 psig value originally determined? |
| , b. If so, what is the value and is the value exceeded due to l , increased S/RV tolerance?
| | 4. |
| /
| | The engineering analysis describes the calculations performed to determine the required additional flow, power, and rpm needed for HPCI and RCIC. |
| | a. |
| | Do the HPCI and RCIC turbines have a maximum allowable pressure? |
| | b. |
| | If so, what is the value and is the value exceeded due to l |
| | increased S/RV tolerance? |
| | / |
| Enclosure l | | Enclosure l |
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| 1 | | 1 5. |
| . 5. TVA's submittal includes plant-specific analyses supporting the increase S/RV setpoint tolerance for Unit 2. The cover letter states that analyses supporting the increased S/RV setpoint tolerance is being )
| | TVA's submittal includes plant-specific analyses supporting the increase S/RV setpoint tolerance for Unit 2. |
| performed for the next Unit 3 reload cycle. | | The cover letter states that analyses supporting the increased S/RV setpoint tolerance is being |
| l
| | ) |
| ! a. Verify that the necessary plant-specific analyses have been completed for the current Unit 3 operating cycle. l I
| | l performed for the next Unit 3 reload cycle. |
| : b. Confirm that any differences between Units 2 and 3 that exist in i approved alternative operating modes (e.g., increased core flow, extended load line limit, or final feedwater temperature reduction) have been addressed for Unit 3.
| | a. |
| : c. Describe how TVA will ensure that the increased setpoint tolerance will be reflected in future operating cycles for each unit.
| | Verify that the necessary plant-specific analyses have been completed for the current Unit 3 operating cycle. |
| I l
| | b. |
| | Confirm that any differences between Units 2 and 3 that exist in i |
| | approved alternative operating modes (e.g., increased core flow, extended load line limit, or final feedwater temperature reduction) have been addressed for Unit 3. |
| | c. |
| | Describe how TVA will ensure that the increased setpoint tolerance will be reflected in future operating cycles for each unit. |
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Letter Sequence RAI |
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MONTHYEARML20141E0011997-06-26026 June 1997
Forwards RAI Re Licensee 961211 Request for Amends to Licenses DPR-33,DPR-52 & DPR-68.Request Proposed Changing TS for as-found Setpoint Tolerance for Main Steam Safety/Relief Valves
Project stage: RAI
ML20198P6161997-11-0303 November 1997
Forwards Response to RAI Re TS Change TS-386,which Increases Main Steam Safety/Relief Valve Setpoint Tolerance
Project stage: Response to RAI
1997-11-03
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999
Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event
ML20217E0711999-10-14014 October 1999
Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to
ML18039A8961999-10-14014 October 1999
Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event
ML20217F7751999-10-0808 October 1999
Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues
ML20217D3261999-10-0808 October 1999
Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3
ML18039A8881999-10-0808 October 1999
Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.
ML18039A8931999-10-0808 October 1999
Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr
ML20217B5481999-10-0101 October 1999
Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR
ML20212M1481999-09-28028 September 1999
Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl
ML20212F7751999-09-22022 September 1999
Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses
ML20212D3651999-09-20020 September 1999
Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program
ML18039A8721999-09-10010 September 1999
Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks
ML20211Q5731999-09-0909 September 1999
Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl
ML20211G6491999-08-26026 August 1999
Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance
ML20210Q6931999-08-0909 August 1999
Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants
ML18039A8371999-08-0606 August 1999
Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept
ML20210Q4421999-08-0505 August 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date
ML20210N1051999-08-0202 August 1999
Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3
ML20210G8991999-07-28028 July 1999
Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl
ML18039A8181999-07-26026 July 1999
Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B)
ML20210G8051999-07-22022 July 1999
Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties
ML20210F3031999-07-22022 July 1999
Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630
ML20209J0251999-07-16016 July 1999
Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi,
ML20210B2671999-07-14014 July 1999
Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance
ML20209E5511999-07-0707 July 1999
Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179
ML20209E3421999-07-0707 July 1999
Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance
ML20196J3531999-06-30030 June 1999
Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN
ML20196G9111999-06-28028 June 1999
Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits
ML18039A8081999-06-28028 June 1999
Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF
ML18039A8111999-06-25025 June 1999
Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05
ML20196F8741999-06-23023 June 1999
Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20196F8131999-06-22022 June 1999
Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld
ML18039A8051999-06-22022 June 1999
Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept
ML18039A8031999-06-18018 June 1999
Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days
ML20195D3321999-06-0101 June 1999
Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21
ML18039A7931999-06-0101 June 1999
Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage
ML18039A7891999-05-24024 May 1999
Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509
ML18039A7911999-05-24024 May 1999
Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training
ML20195B9361999-05-24024 May 1999
Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License
ML20206U6551999-05-14014 May 1999
Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521
ML20206Q8421999-05-10010 May 1999
Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6)
ML18039A7771999-05-0606 May 1999
Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments
ML20206G6611999-05-0404 May 1999
Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3
ML18039A7741999-04-30030 April 1999
Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval
ML20206H5901999-04-30030 April 1999
Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413
ML18039A7591999-04-27027 April 1999
Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302
ML18039A7651999-04-27027 April 1999
Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr.
ML18039A7681999-04-27027 April 1999
Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval
ML18039A7541999-04-23023 April 1999
Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping
ML18039A7581999-04-23023 April 1999
Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177
1999-09-09
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217E0711999-10-14014 October 1999
Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to
ML20217D3261999-10-0808 October 1999
Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3
ML20217F7751999-10-0808 October 1999
Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues
ML20212M1481999-09-28028 September 1999
Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl
ML20212D3651999-09-20020 September 1999
Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program
ML20211G6491999-08-26026 August 1999
Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance
ML20210Q4421999-08-0505 August 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date
ML20210N1051999-08-0202 August 1999
Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3
ML20210G8991999-07-28028 July 1999
Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl
ML20210G8051999-07-22022 July 1999
Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties
ML20209J0251999-07-16016 July 1999
Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi,
ML20210B2671999-07-14014 July 1999
Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance
ML20209E3421999-07-0707 July 1999
Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance
ML20209E5511999-07-0707 July 1999
Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179
ML20196J3531999-06-30030 June 1999
Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN
ML20196G9111999-06-28028 June 1999
Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits
ML20196F8741999-06-23023 June 1999
Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20206G6611999-05-0404 May 1999
Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3
ML20205M0431999-04-13013 April 1999
Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR
ML20205T3771999-04-0909 April 1999
Informs That on 990317,R Champion & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Are Wks of 000612 & 26 for Approx 16 Candidates
ML20205J2521999-04-0505 April 1999
Informs That Effective 990328,A De Agazio Assigned as Project Manager for Browns Ferry Nuclear Plant,Units 1,2 & 3
ML20205F9231999-04-0101 April 1999
Forwards SE Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST, Valve Program for Plant,Units 1,2 & 3
ML20205B9601999-03-24024 March 1999
Seventh Partial Response to FOIA Request for Documents. Records in App N Already Available in Pdr.App O Records Being Released in Entirety & App P Records Being Withheld in Part (Ref FOIA Exemptions 7C,2 & 5)
ML20205A1821999-03-19019 March 1999
Discusses Plant Performance Review of Browns Ferry NPP Completed on 990208.Determined Overall Performance to Be Acceptable.Security,Fire Protection,Radiation Protection & Plant Chemistry Continued to Be Effective
ML20203B9001999-02-0808 February 1999
First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6)
ML20203G4971999-02-0505 February 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam
ML20199B0811999-01-12012 January 1999
Forwards Request for Addl Info Re GL 96-05, Periodic Verification Design-Basis Capability of Safety-Related Motor-Operated Valves, to Request That NPP Licensees Establish Program Effectiveness of Current Program
ML20199E3791998-12-23023 December 1998
Discusses Training Managers Conference Conducted at RB Russell Bldg on 981105.Agenda Used for Conference,List of Attendees,Slide Presentation & Preliminary Schedule for FY99 & FY00 Encl
ML20198N8111998-12-18018 December 1998
Discusses Open Mgt Meeting Conducted on 981217 in Region II Ofc to Present self-assessment of Util Performance.List of Attendees & Copy of Presentation Handout Encl
ML20198N7481998-12-14014 December 1998
Discusses DOL Case 98-ERA-34,DC Smith Vs Tva.Forwards Synopsis of OI Rept 2-1998-011,completed on 981030
ML20197H4421998-12-0202 December 1998
First Final Response to FOIA Request for Documents.Records Listed in App a Already Available in Pdr.App B Records Placed in Pdr.Portions of App C Records Withheld & App D Records Being Withheld in Entirety (FOIA Exemption 5)
ML20196B0011998-11-23023 November 1998
Forwards Emergency Response Data Sys Implementation Documents,Which Include Data Point Library Updates for Listed Plants.Changes Should Be Made to Data Base as Soon as Possible.Without Encl
ML20196D1031998-11-16016 November 1998
Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plans Through March 1999 & Historical Listing of Plant Issues,Called Plant Issues Matrix Encl
ML20196C9651998-11-13013 November 1998
Forwards Copy of Answer Key & Master Bwr/Pwr GFE Sections of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl
ML20195B9211998-11-12012 November 1998
Forwards Staff Assessment of Fatigue Evaluation,Accepting Licensee 980919 Response to NRC 980916 Request for Certain Plant Specific Design & Installation Details Re Insp & Repair of Plant,Unit 3 Core Spray Sys Piping Internal to Rv
ML20195B9291998-11-10010 November 1998
Forwards Transcript of 981026,informal Hearing on 2.206 Petition Filed by Union of Concerned Scientists
ML20195H4501998-11-0909 November 1998
Summarizes 981105 Open Mgt Meeting in Atlanta,Ga Re Site Engineering Performance.List of Attendees & License Presentation Handouts Encl
ML20195C4631998-11-0909 November 1998
Informs That Effective 981105,L Raghavan Was Assigned Project Manager for Plant,Units 1,2 & 3
ML20155H4481998-11-0404 November 1998
Informs That on 981005 TVA Informed Staff That Amend Proposed by TVA Application & Revised on 970306 No Longer Needed.Notice of Withdrawal of Application for Amend to FOL Filed with Ofc of Fr
ML20155H4131998-11-0404 November 1998
Informs That on 981013,TVA Informed Staff That Amend Proposed by TVA Application No Longer Needed. Commission Has Filed Encl Notice of Withdrawal of Application for Amend to FOL with Ofc of Fr
ML20155A5031998-10-23023 October 1998
Informs of Withdrawal of TS Change 356,submitted on 951222. Federal Register Notice Re Withdrawal Will Not Be Published, Due to Staff Failure to Issue Notice,Per 10CFR50.91(a)(2) (I)
ML20155H1211998-10-21021 October 1998
Confirms 981021 Telcon Between T Abney & T Morrissey Re Mgt Meeting Scheduled for 981105 in Atlanta,Ga to Discuss Recent Browns Ferry Nuclear Plant Engineering Performance & on-going Site Activities
ML20155B6861998-10-0909 October 1998
Extends Invitation to Attend Training Manager Conference to Be Held in Atlanta,Ga on 981105.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators
ML20154J6231998-10-0808 October 1998
Forwards Notice of Withdrawal of 971230 Application for Amend to Browns Ferry Nuclear Plant,Units 1,2 & 3 Custom TSs to Remove Identified non-conservatism Re Number of RHRSW Pumps Required for multi-unit Operation
ML20154J8181998-10-0707 October 1998
Discusses Closure of TAC Numbers M92757,M92758 & M92759. Notice of Withdrawal of Application for Amend to Licenses DPR-33,DPR-52 & DPR-69 Encl
ML20155A6561998-10-0202 October 1998
Confirms 980929 Telcon Between T Abney & H Christensen Re Mgt Meeting at Licensee Request Scheduled for 981217 in Atlanta,Ga to Discuss Recent Plant Performance & on-going Site Activities
ML20154A4991998-09-30030 September 1998
Ltr Contract:Task Order 25, Browns Ferry Safety Sys Engineering Insp (Ssei), Under Contract NRC-03-98-021
ML20153H3041998-09-28028 September 1998
Forwards SE Accepting Util Proposed Alternatives Contained in Requests for Relief 3-SPT-3 & 3-SPT-4 for Second Interval Per 10CFR50.55(a)(3)(i) & Code Case N-546.INEEL TER in Support of Relief Requests Also Encl
ML20155B4421998-09-22022 September 1998
Announces Plans to Conduct Ssei at Bfnp on 981116-20 & 981130-1204.Insp Objective Will Be to Evaluate Capability of High Pressure Coolant Injection Sys to Perform Safety Functions Required by Design Basis
ML20153B6351998-09-18018 September 1998
Requests That Util Assess Impacts of New Rocket Booster Plant to Be Located within 10 Mile EPZ of Plant Site & May Be as Close as 2 to 5 Miles from Site
1999-09-28
[Table view] |
Text
June 26,1997 1
Mr. Oliver D. Kingsley, Jr.
President, TVA Nuclear and Chief Nuclear Officer Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. M97412, M97413, AND M97414)
(TS 386)
Dear Mr. Kingsley:
On December 11, 1996, the Tennessee Valley Authority (TVA) requested amendments to the operating licenses for the Browns Ferry Nuclear Plant (BFN)
Units 1, 2, and 3.
This request proposed changing technical'. specifications (TS) for the as-found setpoint tolerance for the main steam safety / relief valves from fl% to i3%.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information will be requiredito complete its review of TVA's request.
The additional information requested is described in the enclosure.-
The NRC staff understands that TVA has not established a schedule for BFN Unit I restart.
TVA stated that analyses required for the increased setpoint tolerance will be performed prior to BFN Unit I restart. TVA also noted that the increased setpoint tolerance had been incorporated into the proposed BFN improved technical specification (ITS) conversion submitted on September 6, 1996.
Since the BFN Unit 1 proposed ITS include the. change in tolerance, there is no need to track this change for the current BFN Unit 1 TS.
Therefore, the staff intends to deny the amendment requested on December 11, 1996 for BFN Unit 1.
This denial will be documented in separate correspondence.
Please contact me at (301)415-1470 if you have any questions on this topic.
Sincerely, 30 W. CEMER CM WRlMfiffah.eroJectMana9er Project Directorate 11-3 9(b \\
9706300186 970626 Division of Reactor Projects - I/II PDR ADOCK 05000259 Office of Nuclear Reactor Regulation P
PDR Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
Request For Additional Ei_stribution
\\
Information Docket File GHammer PUBLIC GGolub l
cc w/
Enclosure:
See next page BFN Rdg.
BMozafari SVarga JJohnson, RII DOCUMENT NAME:
G:\\BFN\\M97412.RAI OGC ACRS To receive a copy of this document, indicate in the box:
"C" - Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" = No copy 0FFICE PDII-3/PM /,1 lf PDII-3/LA
_4/ lC PDII-3/D f4 / pox l1 l
NAME JWilliams /hS/
BClayton A9~'
FHebdon/f' Ay1/
DATE 06/fp /97 F 06/-) te/97 06/ A /97 0FFICIAL RECORD COPY
- - - - - c 2 02 Tl
1 l
i i (
l Mr. Ol'iver D. Kingsley, Jr.
BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority l
cc l
Mr. O. J. Zeringue, Sr. Vice President Mr. Timothy E. Abney, Manager Nuclear Operations Licensing and Industry Affairs Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 l
1 Mr. Jack A. Bailey, Vice President Regional Administrator Engineering & Technical Services U.S. Nuclear Regulatory Commission Tennessee Valley Authority Region II 6A Lookout Place 61 Forsyth Street, SW., Suite 23T85 1101 Market Street Atlanta, GA 30303-3415 Chattanooga, TN 37402-2801 Mr. Leonard D. Wert Mr. C. M. Crane, Site Vice President Senior Resident Inspector Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 10833 Shaw Road Decatur, AL 35609 Athens, AL 35611 i
General Counsel Chairman Tennessee Valley Authority Limestone County Commission ET 10H 310 West Washington Street 400 West Summit Hill Drive Athens, AL 35611 Knoxville, TN 37902 State Health Officer Mr. Raul R. Baron, General Manager Alabama Department of Public Health Nuclear Assurance and Licensing 434 Monroe Street Tennessee Valley Authority Montgomery, AL 36130-1701 4J Blue Ridge 8
1101 Market Street Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Pedro Salas, Manager Licensing and Industry Affairs Tennessee Valley Authority 4J Blue Ridge j
l 1101 Market Street l
Chattanooga, TN 37402-2801
/
l 1
i l
l REQUEST FOR ADDITIONAL INFORMATION l T BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 l
l INCREASED MAIN STEAM SAFETY / RELIEF VALVE SETPOINT TOLERANCE
- 1., page 13 of the December 11, 1996 submittal states that the hydrodynamic main steam safety / relief valves (S/RVs) loads resulting from the 3% setpoint tolerance are less than 1% higher than the " loads l
used in design." However, it is the NRC staff's experience via review l
of other analyses, such as those supporting power uprate at several boiling water reactors that the loads vary almost linearly with respect t
to opening pressure of the S/RVs.
Therefore, it is expected that an increase in the S/RV setpoints to 3% would result in a 3% increase in the S/RV hydrodynamic loads.
a.
What S/RV setpoints and setpoint tolerances were assumed for developing the above " loads used in design"?
b.
Describe the methodology for determining the S/RV hydrodynamic loads and the analysis results which indicate only a 1% load increase for the 3% setpoint tolerance.
l It is also stated that the resulting 1% increase in the loads is negligible when combined with other combined loads; therefore, the effect of the load increases on the plant structures were not evaluated.
c.
What is the available structural margin such that these load increases are negligible?
- 2., page 13 of the December 11, 1996 submittal states that the maximum differential pressure due to the increased S/RV setpoint 4
tolerance was evaluated for valves in the Generic Letter 89-10 program.
Please verify that the calculations which demonstrate the capability of these valves to function adequately have been revised for these differential pressures.
3.
What is the basis for the high-pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) design requirement to provide design flow to the reactor vessel at pressures up to 1120 psig?
In other words, how was the 1120 psig value originally determined?
4.
The engineering analysis describes the calculations performed to determine the required additional flow, power, and rpm needed for HPCI and RCIC.
a.
Do the HPCI and RCIC turbines have a maximum allowable pressure?
b.
If so, what is the value and is the value exceeded due to l
increased S/RV tolerance?
/
Enclosure l
1 5.
TVA's submittal includes plant-specific analyses supporting the increase S/RV setpoint tolerance for Unit 2.
The cover letter states that analyses supporting the increased S/RV setpoint tolerance is being
)
l performed for the next Unit 3 reload cycle.
a.
Verify that the necessary plant-specific analyses have been completed for the current Unit 3 operating cycle.
b.
Confirm that any differences between Units 2 and 3 that exist in i
approved alternative operating modes (e.g., increased core flow, extended load line limit, or final feedwater temperature reduction) have been addressed for Unit 3.
c.
Describe how TVA will ensure that the increased setpoint tolerance will be reflected in future operating cycles for each unit.
l i
(
i
/
r
