Letter Sequence Other |
---|
|
|
MONTHYEARML20129K2101996-11-0404 November 1996 Provides Response to NRC Bulletin 96-003, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Bwrs Project stage: Other ML20134C2891997-01-29029 January 1997 Submits Response to NRC Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors, Project stage: Other ML20134N5801997-02-19019 February 1997 Clarifies NRC Staff Expectations Re Compensatory Measures Which May Be Used to Defer Actions Requested by NRC Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Bwrs Project stage: Approval ML20151K1111997-07-25025 July 1997 Provides Response Re Resolution of NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs Project stage: Other ML20210V2911997-09-16016 September 1997 Provides Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in BWRs Per Request During 970821 Meeting Project stage: Meeting ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor Project stage: Other 1997-02-19
[Table View] |
|
---|
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 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 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 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 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 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. 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 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 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, ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 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 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment 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 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 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 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 ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co 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 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 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 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 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 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 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 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 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co 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 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates 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 ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry 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 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 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 ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail 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 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 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 1999-09-28
[Table view] |
Text
.
~
l 'p+ o..g$% UNITED STATES
, g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30468 4 001 k*.... September 22, 1997 Mr. Oliver D. Kingsley, Jr.
President. TVA Nuclecr and Chief Nuclear Officer Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga. Tennessee 37402 2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT UNITS 1. 2. AND 3 - RESPONSE TO BULLETIN 96 03 (TAC NOS. M96135. M96136. AND M96137)
Dear Mr. Kingsley:
The Nuclear Regulatory Commission (NRC) staff has accepted deferral of com)letion of certain actions requested by Bulletin 96 03. " Potential Plugging of Emergency Core Cooling System (ECCS) Strainers by Debris in Boiling Water Reactors " for the Browns Ferry Nuclear Plant (BFN) Unit 2 until December 31.
1998, or until NRC approval and TVA implementation of a license amendment incorporating containment overpressure credit for ECCS pump net positive suction head (NPSH) into the licensing basis, whichever is first.
On July 25. 1997 the Tennessee Valley Authority (TVA) provided a supplemental response to B 96 03. BFN Units 1. 2. and 3. Based on its initial review of this supplemental response, the NRC staff determined that portions of TVA's response appear to constitute an unreviewed safety question under the provisions of 10 CFR 50.59. If an unreviewed safet staff review and approval of those portions of TVA'ysquestion responseexists. NRC is required prior to implementation.
Specifically. TVA's July 25, 1997 letter states that containment overpressure is being credited to ensure adequate NPSH for low pressure ECCS systems.
Containment overpressure credit for NPSH is not currently part of the BFN licensing or design basis. The NRC staff believes that incorporation of containment overpressure credit into the licensing basis increases the possibility of malfunction of equipment important to safety. In addition, the margin of safety implicit in the requirements for ECCS pump operability may be reduced. Therefore, the NRC staff considers credit for containment overpressure for ECCS pump NPSH to be an unreviewed safety question. This position is consistent with that expressed by the NRC staff in a meeting with the Boiling Water Reactors Owners Group on February 19, 1997. This position was verbally discussed with members of y a r staff shortly after NRC receipt of your July 25, 1997 letter. \gl'0I
/
On August 25, 1997. TVA pr posed to com)lete installation of the upgraded ECCS suction strainers during the upcoming B N Unit 2 refueling outage. TVA stated that it is preparing a license amendment to incorporate containment I
()
overpressure into the licensing basis. Review of this license amendment will provide for NRC approval of the unreviewed safety question prior to its implementation in the BFN licensing basis, 9710060221 970922 DR ADOCK 0500 9 ['
f pt
', . p '
.lLl ,llfill.ill. l.l.
1
.J
i
. f Mr. O. D. Kingsley 2- l TVA proposed to defer incorporstion of the containment overpressure credit '
until December 31, 1998, or until NRC staff approval of the associated license !
amendment, whichever is sooner. TVA committed to maintain its foreign i material exclusion program, to perform thorough inspections to ensure !
insulation is securely fixed and to verify that all foreign material has been !
removed from the dr pool if necessary. ywell and Deferral of suppression incorporation ofpool, and to desludge the containment the suppression overpressure credit permits restart of BFN Unit 2 from the upcoming refueling outage with the upgraded ECCS suction strainers under the current licensing basis.
t The NRC staff finds that installation of the new suction strainers substantially improves the ability of the plant to acconynodate debris .
blockage, and that TVA's compensatory measures provide assurance that-debris loading will be maintained as low as practical. Therefore, the NRC staff.
accepts deferral of updating the BFN Unit 2 licensing basis to incorporate the containment overpressure credit in NPSH calculations consistent with 8 96 03 Option 1 until December 31, 1998, or until NRC approval and TVA implementation of the associated license amendment, whichever is first. '
You should be aware that similar situations have been identified for other
- boiling water reactors which also require license amendments. The NRC staff believes that TVA should have been aware of these activities, and should have been prepared to provide a proposed license amendnent as part of its supplemental response to B 96 03. without being prompted by the staff.
Questions regarding the acceptability of. the proposed amendment and the ,
schedule for im)1ementation could also have been resolved in a more timely manner had TVA yeen able to maintain its oririnal May 1997 schedule for providing its B 96 03 supplemental response. -
TVA's license amendment request should includ4 information similar to that provided by the licensees for the Dresden Mcelcello, and Pilgrim plants. .
Items =of interest to the NRC staff include, bu' are not limited to, details of .
NPSH and minimum containment pressure calculations including all assumptions and models used, time dependent NPSH required vs. NPSH available, and performance of containment spray'or other pressure mitigating safeguards.
Please call me at (301)415 1470 if you have any questions regarding this topic, Sincerely, , ,
. m
/ Joseph ProjectF.Directorate Williams, Project 11 3 Manager-Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50 259, 50 260, and 50-296 cc: See next page
l Mr. Oliver D. Kingsley, Jr. P"0WNS FERRY NUCLEAR PLANT Tennessee Valley Authority CC Mr. O. J. Zeringue, Sr. Vice President Mr. Mark J. Burzynski, Managar Nuclear Operations Nuclear Licensing Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place 4J Blue Ridge 1101 Market Street -1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Jack A. Bailey, Vice President Mr. Timothy E. Abney, Manager Cngineering & Technical Services 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 37402-2801 Mr. C. M. Crane, Site Vice President Regional Administrator, Region 11 Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 61 Forsyth Street, SW., Suite 23T85 P.O. Box 2000 Atlanta, GA 30303-3415 Decatur, AL 35609 Mr. Leonard D. Wert General Counsel Senior Resident Inspector Tennessee Valley Authority U.S. Nuclear Regulatory Commission ET 10H Browns Ferry Nuclear Plant 400 West Summit Hill Drive 10833 Shaw Road Knoxville, TN 37902 Athens, AL 35611 Mr. Raul R. Baron, General Manager State Health Officer Nuclear Assurance Alabama Dept. of Public Health Tennessee Valle.1 Authority 434 Monroe Street 40 Blue Ridge Montgomery, AL 35130-1701 1101 Market Street Chattanooga, TN 37402-2801 Chairman Limestone County Commission Mr. Karl W. Singer, Plant Manager 310 West Washington Street Browns Ferry Nuclear Plant Athens, AL 35611 Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609
(
,Mr. O. D. Kingsley September 22, 1997 TVA proposed to defer incorporation of the containment overpressure credit until December 31. 1998, or until NRC staff approval of the associated license amendment, whichever is sooner. TVA committed to maintain its foreign material exclusion program, to perform thorough inspections to ensure insulation is securely fixed and to verify that all foreign material has been removed from the drywell and suppression pool, and to desludge the suppression pool if necessary. Deferral of incorporation of the containment overpressure credit permits restart of BFN Unit 2 from the upcoming refueling outage with the upgraded ECCS suction strainers under the current licensing basis.
}
The NRC staff finds that installation of the new suction strainers substantially improves the ability of the plant to accommodate debris blockage, and that TVA's compensatory measures provide assurance that debris loading will be maintained as low as aractical. Therefore the NRC staff accepts deferral of updating the BFN Jnit 2 licensing basis to incorporate the containment overpressure credit in NPSH calculations consistent with B 96-03 Option 1 until December 31, 1998, or until NRC approval and TVA implementation of the associated license ament.nent, whichever is first.
You should be aware that similar situations have been identified for other boiling water reactors which also require license amendments. The NRC staff believes that TVA should have been aware of these activities, and should have been prepared to provide a proposed license amendment as > art of its supplemental response to B 96-03 without being prompted )y the staff.
Questions regarding the acceptability of the proposed amendment and the schedule for im)1ementation could also have been resolved in a more timely manner had TVA )een able to maintain its original May 1997 schedule for providing its B 96-03 supplemental response.
TVA's license amendment request should include information similar to that provided by the licensees for the Dresden. Monticello, and Pilgrim plants.
Items of interest to the NRC staff include, but are not limited to details of NPSH and minimum containment pressure calculations, including all assumptions and models used, time-dependent NPSH-required vs. NPSH-available, and performance of containment spray or other pressure-mitigating safeguards.
Please call me at (301)415-1470 if you have any questions regarding this topic.
Sincerely.
Joseph F. Williams. Project Manager Project Directorate 11 3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-259. 50-260.
and 50-296 cc: See next page DISTRIBU.Il0N:
Docket File FHebdon ACRS RElliott BClayton PUBLIC KKavanagh JJohnson. Ril BFN Reading BBoger OGC DOCUMENT NAME: G:\BFN\M96135.US0 *see previous concurrence To receive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" - No copy OFFICE P0ll*3/PM /jp lC PDil*3/LA a. lCl SCSB l6 SRXB l C- 0:PDil*3 g) i NAME JWi t t isms t mw /W BClayt on 9'~ CBerlinger* TCottins* FMehdon i-f DATE 09/ 4 J97 /'/ 09/rW/97 '
09/12/97 09/17/97 09/11/97 0FFICIAL RECORD COPY