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| {{#Wiki_filter:ACCESSION NBR FAC IL: 50-259 50-2ba.50-29b AUTH.NAME QRIDLEYi R.RECIP.NAME MULLER>D.R.I REGULATORY I RMATION DISTRIBUTION SYS (BIDS)8b04080228 DOC.DATE: 8b/03/2b NOTARIZED: | | {{#Wiki_filter:I REGULATORY I RMATION DISTRIBUTION SYS (BIDS) |
| NO DOCKET 0 Browns Ferry Nuclear Power Station.Unit ii Tennessee 05000259 Browns Ferry Nuclear Power St'ationi Unit 2E Tennessee 050002ba Browns Ferry Nuclear Power Stationi Unit 3i Tennessee 0500029b AUTHOR AFFILIATION Tennessee Valley Authority REC I P I ENT*FF I L I ATI ON HWR Prospect Directorate 2 | | ACCESSION NBR 8b04080228 DOC. DATE: 8b/03/2b NOTARIZED: NO DOCKET 0 FAC IL: 50-259 Browns Ferry Nuclear Power Station. Unit ii Tennessee 05000259 50-2ba Browns Ferry Nuclear Power St'ationi Unit 2E Tennessee 050002ba |
| | .50-29b Browns Ferry Nuclear Power Stationi Unit 3i Tennessee 0500029b AUTH. NAME AUTHOR AFFILIATION QRIDLEYi R. Tennessee Valley Authority RECIP. NAME REC I P I ENT *FF I L I ATION MULLER> D. R. HWR Prospect Directorate 2 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Responds to 851007 request for addi info re NUREG-0737'tem II'.K.3.18'Mods to Automatic Depressuri xation Sgs (ADS)Logic." No design basis requirement or increase in safety associated w/requested ADS logic mod.Present ADS adequate.DISTRIBUTION CODE: 104bD COPIES RECEIVED: LTR j ENCL g SIZE: TITLE: OR Submittal: | | Responds to 851007 request for addi info re NUREG-0737'tem II'. K. 3. 18'Mods to Automatic Depressuri xation Sgs (ADS) |
| TMI Action Plan Rgmt NUREG-0737 5 NUREG-obba NOTES: NMSS/FC*F 1 c g.1 c g NMSS/FCAF/PM.
| | Logic. " No design basis requirement or increase in safety associated w/requested ADS logic mod. Present ADS adequate. |
| OIA 1 c g.NMSS/FCAF 1cg.ice NMSS/FCAF/PM. | | DISTRIBUTION CODE: 104bD TITLE: OR Submittal: TMI COPIES RECEIVED: LTR Action Plan j ENCL g SIZE: |
| OI*icy.NMSS/FCAF icy.icy NMSS/FCAF/PM. | | Rgmt NUREG-0737 5 NUREG-obba NOTES: NMSS/FC*F 1 c g. 1 c g NMSS/FCAF/PM. OIA 1 c g. 05000259 NMSS/FCAF 1cg. ice NMSS/FCAF/PM. OI* icy. a5ooo2bo NMSS/FCAF icy. icy NMSS/FCAF/PM. OIA icy. 050002'Pb RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL BWR ADTS 1 1 HWR EH 1 1 HWR EICSB 2 2 BWR FOB 1 HWR PD2 PD 01 5 5 CLARK> R 1 1 BWR PSB 1 1 BWR RSB 1 1 INTERNAL: ACRS 34 10 10 *DM/LFMB 1 0 ELD/HDS4 1 a IE/DEPER DIR 33 1 1 IE/DEPER/EPB 3 NRR HWR ADTS 1 1 NRR'AULSONa W 1 NRR PWR-A ADTS 1 1 NRR PWR-B ADT8 1 1 1 1 NRR/DSRO EMRI T 1 1 G F LE 04 1 1 RGN2 1 1 EXTERNAL: 24X 1 LPDR 03 1 1 NRC PDR 1 1 NSIC 05 1 NOTES: 3 3 TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 42 |
| OIA icy.05000259 a5ooo2bo 050002'Pb RECIPIENT ID CODE/NAME BWR ADTS HWR EICSB HWR PD2 PD 01 BWR PSB COPIES LTTR ENCL 1 1 2 2 5 5 1 1 RECIPIENT ID CODE/NAME HWR EH BWR FOB CLARK>R BWR RSB COPIES LTTR ENCL 1 1 1 1 1 1 1 INTERNAL: ACRS ELD/HDS4 IE/DEPER/EPB NRR'AULSONa W NRR PWR-B ADT NRR/DSRO EMRI RGN2 34 10 1 3 1 8 1 T 1 1 10 a 1 1 1*DM/LFMB IE/DEPER DIR 33 NRR HWR ADTS NRR PWR-A ADTS G F LE 04 1 0 1 1 1 1 1 1 1 1 1 1 EXTERNAL: 24X NRC PDR NOTES: 1 1 1 3 3 LPDR NSIC 03 05 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 42 95829Af79~ | |
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| i',I 8;i Pt>'7 QQ'y$))/Q A aAAA)')GBB'33 I'RQO)3" 13'P 1J (>TABS"SI;.)>8.3)']AYih HQ>)..i Q I i"~'('l'A H~''3 RW'z L0 G i~G1 f)N")()l4l 0 I F v 01 4h C 8 7 RC".'3 I<.~k.HA~1 DA TENNESSEE VALLEY AUTHORITY 5N 157B Lookout Place March 26, 1986 Director of Nuclear Reactor Regulation Attention:
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| Mr.D.R.Muller, Project Director BWR Project Directorate No.2 Division of Boiling Water Reactor Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555
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| ==Dear Mr.Muller:== | | ;.'h'~.'lu! ) 6"."%CO~.PN ."",,V. Df G 8~~.,'<<'20K ~~~a 95829Af79~ "lnl) i" oz,'e8B l - z";r~elauN y-., ~ <<'1 at >naG |
| In the Matter of the Tennessee Valley Authority Docket Nos.50-2S9 50-260 50-296 By letter from D.B.Vassallo to H.G.Parris dated October 7, 1985, we received a request for additional information regarding NUREG-0737, Item II.K.3.18, Modifications to Automatic Depressurization System Logic, for the Browns Ferry Nuclear Plant.Specifically requested was that.we inform NRC of our plans and schedule for implementing one of the NRC-approved modifications. | | '3 + 2 9 l')l7'3 " |
| We continue to maintain our position that there is no design basis requirement or a significant increase in safety associated with the ADS logic modification requested by NRC.The current ADS initiation logic is designed to mitigate intermediate and small breaks in the primary system boundary, assuming no HPCI injection and taking no credit for operator action.The requested modification appears to go beyond this basis by requiring that operator action also be excluded from other analyses, such as stuck open relief valve with HPCI failure, although it can be shown that time is available for manual depressurization (greater than 10 minutes).It is also not clear that the increase in safety by further assuring a reactor depressurization for certain events outweighs the decrease in safety due to inadvertent actuation in certain other events such as instrument malfunction. | | f EAU ~~7<<;:.)i.~fir. )'P~i 'a'GQL 34N ] " 'f') 1 |
| For primary system isolation events with the loss of high pressure makeup systems, the BWR Owners'roup analysis has shown that the operator has at least 30 to 40 minutes to initiate the ADS and prevent excessive fuel cladding heatup.Based on the BWR Owners'roup analysis and an Oak Ridge Laboratory study concerning loss of control air we have concluded that automatic ADS actuation would most likely occur without operator action within about 10 minutes after reactor pressure vessel level decreases to level 1 even for events which do not directly pressurize the drywall.In these events, the drywell becomes indirectly pressurized since reaching level 1 will cause containment isolation and a subsequent heatup and pressurization of the drywell due to the loss of drywell cooling.This heatup and pressurization will most likely result in ADS actuation within about, 10 minutes after the RPV water level decreasos to level 1.8604080229 860326 PDR ADOCK 05000259 P PDR An Equal Opportunity Employer | | '~i" ~4 <8 6" 'f ~ t>U <i".o;:i" t~f 8 "r.)iso< 'vs>>e I,) vN |
| 'N N Director of Nuclear Reactor Regulation March 26, 1986 For small break LOCA events with no high pressure makeup, analyses have shown successful accident mitigation with no operator action fox the first 10 minutes and a complete failure of the ADS logic.Analyses prepared by the General Electric Company for BFN units 1, 2, and 3 examine primary system breaks ranging in size from 0.05 ft through 0.50 ft with a complete loss of the ADS logic function.This analysis is enclosed.These scenarios assume actuation of four main steam relief valves 10 minutes after the break.It can be concluded that with total failure of ADS initiation logic and no operator actions within 10 minutes, adequate core cooling can be maintained with a primary system break equivalent to a stuck open relief valve and no high pressure makeup.The intent of NUREG-0737, Item II.K.3.18, is to provide additional assurance of adequate coxe cooling for transient and accident events which do not produce a high drywell pressuxe signal and are degraded by a loss of all high pressure coolant systems.Based upon our earlier submittals in which reliance was placed on use of symptom-oriented emergency procedure guidelines and with the additional analyses intxoduced in this submittal, TVA concludes that the existing ADS is adequate.Very truly yours, TENNESSEE VALLEY AUTHORITY Enclosure cc (Enclosure): | | : c. 9 Off ~ |
| Mr.R.J.Clax'k U.S.Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue Bethesda, Maryland 20814~~R.ridley Manager of icensing U.S.Nuclear Regulatory Commission Region II ATTN: Dr.J.Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 II I II J I II}} | | 9'iPI TAI,.il 1 1A "~'.~H1'VR u5'x vvrl5<,~'~ '~;~lI~-V ~a~a<a.;r) '~'i W;i 'i TA 3 j'-'>"-1A ') N:9I ) I;,) i- |
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| | TENNESSEE VALLEY AUTHORITY 5N 157B Lookout Place March 26, 1986 Director of Nuclear Reactor Regulation Attention: Mr. D. R. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
| | |
| | ==Dear Mr. Muller:== |
| | |
| | In the Matter of the Docket Nos. 50-2S9 Tennessee Valley Authority 50-260 50-296 By letter from D. B. Vassallo to H. G. Parris dated October 7, 1985, we received a request for additional information regarding NUREG-0737, Item II.K.3.18, Modifications to Automatic Depressurization System Logic, for the Browns Ferry Nuclear Plant. Specifically requested was that. we inform NRC of our plans and schedule for implementing one of the NRC-approved modifications. |
| | We continue to maintain our position that there is no design basis requirement or a significant increase in safety associated with the ADS logic modification requested by NRC. The current ADS initiation logic is designed to mitigate intermediate and small breaks in the primary system boundary, assuming no HPCI injection and taking no credit for operator action. The requested modification appears to go beyond this basis by requiring that operator action also be excluded from other analyses, such as stuck open relief valve with HPCI failure, although it can be shown that time is available for manual depressurization (greater than 10 minutes). It is also not clear that the increase in safety by further assuring a reactor depressurization for certain events outweighs the decrease in safety due to inadvertent actuation in certain other events such as instrument malfunction. |
| | For primary system isolation events with the loss of high pressure makeup systems, the BWR Owners'roup analysis has shown that the operator has at least 30 to 40 minutes to initiate the ADS and prevent excessive fuel cladding heatup. Based on the BWR Owners'roup analysis and an Oak Ridge Laboratory study concerning loss of control air we have concluded that automatic ADS actuation would most likely occur without operator action within about 10 minutes after reactor pressure vessel level decreases to level 1 even for events which do not directly pressurize the drywall. In these events, the drywell becomes indirectly pressurized since reaching level 1 will cause containment isolation and a subsequent heatup and pressurization of the drywell due to the loss of drywell cooling. This heatup and pressurization will most likely result in ADS actuation within about, 10 minutes after the RPV water level decreasos to level 1. |
| | 8604080229 860326 PDR ADOCK 05000259 P PDR An Equal Opportunity Employer |
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| | 'N N |
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| | Director of Nuclear Reactor Regulation March 26, 1986 For small break LOCA events with no high pressure makeup, analyses have shown successful accident mitigation with no operator action fox the first 10 minutes and a complete failure of the ADS logic. Analyses prepared by the General Electric Company for BFN units 1, 2, and 3 examine primary system breaks ranging in size from 0.05 ft through 0.50 ft with a complete loss of the ADS logic function. This analysis is enclosed. These scenarios assume actuation of four main steam relief valves 10 minutes after the break. It can be concluded that with total failure of ADS initiation logic and no operator actions within 10 minutes, adequate core cooling can be maintained with a primary system break equivalent to a stuck open relief valve and no high pressure makeup. |
| | The intent of NUREG-0737, Item II.K.3.18, is to provide additional assurance of adequate coxe cooling for transient and accident events which do not produce a high drywell pressuxe signal and are degraded by a loss of all high pressure coolant systems. Based upon our earlier submittals in which reliance was placed on use of symptom-oriented emergency procedure guidelines and with the additional analyses intxoduced in this submittal, TVA concludes that the existing ADS is adequate. |
| | Very truly yours, TENNESSEE VALLEY AUTHORITY R. ridley |
| | ~ |
| | ~ |
| | Manager of icensing Enclosure cc (Enclosure): |
| | Mr. R. J. Clax'k U.S. Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue Bethesda, Maryland 20814 U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 |
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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
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
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
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
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
ML18039A7931999-06-0101 June 1999
Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage
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
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
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
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
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
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.
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
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
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
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
ML20212F7751999-09-22022 September 1999
Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses
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
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
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)
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
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
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
ML18039A7931999-06-0101 June 1999
Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage
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
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
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
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
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
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.
ML20206C8591999-04-23023 April 1999
Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a)
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
ML20206C1241999-04-21021 April 1999
Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits
ML20205T0971999-04-15015 April 1999
Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6)
ML18039A7441999-04-0707 April 1999
Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments
ML18039A7431999-03-30030 March 1999
Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs.
ML18039A7421999-03-30030 March 1999
Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214
ML18039A7411999-03-30030 March 1999
Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days
ML18039A7371999-03-26026 March 1999
Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval
ML18039A7331999-03-26026 March 1999
Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles
ML18039A7291999-03-22022 March 1999
Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors
ML20204G8471999-03-19019 March 1999
Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl
ML20207M0611999-03-11011 March 1999
Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524
ML18039A6971999-02-22022 February 1999
Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation
ML18039A6961999-02-19019 February 1999
Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented
ML18039A6911999-02-19019 February 1999
Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation
ML20203B6031999-02-0404 February 1999
Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521
ML18039A6741999-01-21021 January 1999
Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA
ML20199F6951999-01-0808 January 1999
Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months
1999-09-09
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059L5741990-09-19019 September 1990
Forwards Rev 2 to Browns Ferry Nuclear Plant Cable Issues Supplemental Rept Corrective Actions,Sept 1990. Rept Revised to Clarify Cable Bend Radius & Support of Vertical Cable & Document Resolution of Jamming Issues
ML20064A6871990-09-18018 September 1990
Requests Closure of Confirmatory Order EA-84-054 Re Regulatory Performance Improvement Program
ML20059L4931990-09-17017 September 1990
Provides Addl Info Re 900713 Tech Spec Change 290 Concerning Hpci/Rcic Steam Line Space Temp Isolations,Per Request
ML18033B5171990-09-17017 September 1990
Forwards Addl Info Re 900524 Tech Spec Change 287 on Reactor Pressure Instrument Channel.Schematic Diagrams Provided in Encl 2
ML20064A6851990-09-17017 September 1990
Responds to NRC Recommendations Re Primary Containment Isolation at Facility.Background Info & Responses to Each Recommendation Listed in Encl 1
ML20059K2971990-09-14014 September 1990
Responds to NRC 900208 SER Re Conformance to Reg Guide 1.97, Rev 3, Neutron Flux Monitoring Instrumentation. TVA Endorses BWR Owners Group Appealing NRC Position Directing Installation of Upgraded Neutron Flux Sys
ML20059H3861990-09-10010 September 1990
Forwards Corrective Actions Re Radiological Emergency Plan, Per Insp Repts 50-259/89-41,50-260/89-41 & 50-296/89-41. Corrective Action:Plant Manager Instruction 12.12,Section 4.11.3.1 Revised
ML18033B5031990-08-31031 August 1990
Forwards Financial Info Required to Assure Retrospective Premiums,Per 10CFR140 & 771209 Ltr
ML20059E1741990-08-31031 August 1990
Informs That Plant Restart Review Board & Related Functions Will Be Phased Out on Date Fuel Load Commences
ML20059D7061990-08-28028 August 1990
Requests That Sims Be Updated to Reflect Implementation of Program to Satisfy Requirements of 10CFR50,App J.Changes & Improvements Will Continue to Be Made to Reflect Plant Mods, Tech Spec Amends & Recommendations from NRC
ML18033B4931990-08-20020 August 1990
Suppls Response to Violations Noted in Insp Repts 50-259/90-14,50-260/90-14 & 50-296/90-14.Corrective Actions: TVA Developed Corporate Level std,STD-10.1.15 Re Independent Verification
ML20063Q2431990-08-20020 August 1990
Responds to 900807 Telcon Re Rev to Commitment Due Date Per Insp Rept 50-260/89-59 Re Electrical Issues Program
ML20063Q2451990-08-17017 August 1990
Provides Revised Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants & Notification of Commitment Completion
ML20063Q2441990-08-17017 August 1990
Advises That IE Bulletin 80-11 Re Masonry Wall Design Implemented at Facilities.Design Finalized,Mods Completed, Procedures Issued & Necessary Training Completed.Sims Data Base Should Be Updated to Show Item Being Implemented
ML20059A4861990-08-16016 August 1990
Responds to Verbal Commitment Made During 900801 Meeting W/Nrc Re Control Room Habitability.Calculations Performed to Support Util 900531 Submittal Listed in Encls 1 & 2
ML20059A5141990-08-16016 August 1990
Provides Response to NRC Bulletin 88-008,Suppl 3 Re Thermal Stresses in Piping Connected to Rcs.Util Does Not Anticipate Thermal Cyclic Fatique Induced Piping,Per Suppl 3 to Occur in Plant.Ltr Contains No Commitment
ML18033B4821990-08-14014 August 1990
Submits Revised Response to Violations Noted in Insp Repts 50-259/89-16,50-260/89-16 & 50-296/89-16.Extends Completion Dates for Commitments to 901203
ML18033B4831990-08-13013 August 1990
Responds to NRC 900713 Ltr Re Violations & Deviations Noted in Insp Repts 50-259/90-18,50-260/90-18 & 50-296/90-18. Corrective Actions:Craft Foreman Suspended for Three Days & Relieved of Duties as Foreman
ML18033B4811990-08-10010 August 1990
Responds to NRC 900710 Ltr Re Power Ascension Testing Program.Four Hold Points Selected by NRC Added to Unit 2 Restart Schedule
ML18033B4801990-08-0808 August 1990
Forwards Response to SALP Repts 50-259/90-07,50-260/90-07 & 50-296/90-07 for Jul 1989 - Mar 1990
ML20044B2121990-07-13013 July 1990
Clarifies Util Position on Two Items from NRC 891221 Safety Evaluation Re TVA Supplemental Response to Generic Ltr 88-01 Concerning IGSCC in BWR Stainless Steel Piping.Insp Category for Nine Welds Will Be Changed from Category a to D
ML18033B4371990-07-13013 July 1990
Forwards Corrected Tech Spec Page 3.2/4.2-45 to Util 900706 Application for Amend to License DPR-52 Re ADS
ML18033B4331990-07-13013 July 1990
Requests Temporary Exemption from Simulator Certification Requirements of 10CFR55.45(b)(2)(iii)
ML20055F6091990-07-12012 July 1990
Provides Response to NRC Bulletin 88-003 Re Insp Results. No Relays Found to Have Inadequate Latch Engagements. Therefore,No Corrective Repairs or Replacement of Relays Required
ML18033B4251990-07-10010 July 1990
Forwards Cable Installation Supplemental Rept,In Response to NRC Request During 900506 Telcon.Rept Contains Results of Walkdowns & Testing Except Work on Ongoing Cable Pullby Issue
ML18033B4241990-07-0606 July 1990
Advises That Util Expects to Complete Implementation of Rev 4 to Emergency Procedure Guidelines by Mar 1991.Response to NRC Comments on Draft Emergency Operating Instructions Encl
ML18033B4201990-07-0505 July 1990
Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3. Util Has Concluded That Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issue,Subj to Listed Conditions
ML18033B4091990-07-0202 July 1990
Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-259/89-53,50-260/89-53 & 50-296/89-53.Corrective Actions: Condition Adverse to Quality Rept Initiated & Issued to Track Disposition of Deficiency in Chilled Water Flow Rates
ML20043G4901990-06-14014 June 1990
Forwards Tabs for Apps a & B to Be Inserted Into Util Consolidated Nuclear Power Radiological Emergency Plan
ML20043H3511990-06-14014 June 1990
Forwards Corrected Pages to Rev 15 to Physical Security Contingency Plan,As Discussed During 900606 Telcon.Encl Withheld (Ref 10CFR73.21)
ML20043F4951990-06-11011 June 1990
Advises That Facilities Ready for NRC Environ Qualification Audit.Only Remaining Required Binder in Review Process & Will Be Completed by 900615
ML18033B3651990-06-0808 June 1990
Forwards Revised Page 3.2/4.2-13 & Overleaf Page 3.2/4.2-12 to Tech Spec 289, RWCU Sys Temp Loops.
ML18033B3391990-06-0404 June 1990
Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-259/90-08,50-260/90-08 & 50-296/90-08.Corrective Actions: Individual Involved Counseled on Importance of Complying W/Approved Plant Procedures When Performing Assigned Tasks
ML20043D3251990-06-0101 June 1990
Responds to NRC 900502 Ltr Re Notice of Violation & Proposed Imposition of Civil Penalty.Corrective Actions:Snm Program Action Plan Being Developed & Implemented,Consisting of Improved Training for Control Personnel & Accountability
ML18033B3551990-05-31031 May 1990
Forwards Response to 891219 Request for Addl Info on Hazardous Chemicals Re Control Room Habitability
ML20043C1951990-05-30030 May 1990
Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues
ML20043C0601990-05-29029 May 1990
Forwards Response to Violations Noted in Insp Repts 50-259/90-12,50-260/90-12 & 50-296/90-12.Util Admits Violation Re Access Control to Vital Areas,But Denies Violation Re Backup Ammunicition for Responders
ML18033B3351990-05-25025 May 1990
Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability. Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issues Subj to Listed Conditions
ML18033B3221990-05-21021 May 1990
Forwards Rev 1 to ED-Q2000-870135, Cable Ampacity Calculation - V4 & V5 Safety-Related Trays for Unit 2 Operation, as Followup to Electrical Insp Rept 50-260/90-13 Re Ampacity Program
ML18033B3101990-05-18018 May 1990
Responds to NRC 900417 Ltr Re Violations Noted in Insp Repts 50-259/90-05,50-260/90-05 & 50-296/90-05.Corrective Action: Senior Reactor Operator Assigned to Fire Protection Staff for day-to-day Supervision of Fire Protection Program
ML20043A6101990-05-15015 May 1990
Forwards Rev 16 to Security Personnel Training & Qualification Plan.Rev Withheld (Ref 10CFR2.790)
ML20043A4091990-05-14014 May 1990
Forwards Rev 14 to Physical Security/Contingency Plan.Rev Withheld (Ref 10CFR73.21)
ML20043A4081990-05-14014 May 1990
Forwards Rev 15 to Physical Security/Contingency Plan, Consisting of Changes for Provision of Positive Access Control During Major Maint & Refueling Operations to One of Two Boundaries.Rev Withheld (Ref 10CFR73.21)
ML18033B2921990-05-0909 May 1990
Provides Info for NRC Consideration Re Plant Performance for Current SALP Rept Period of Jan 1989 - Mar 1990.Util Believes Corrective Actions Resulted in Positive Individual Changes & Programmatic Upgrades
ML20042F7401990-05-0404 May 1990
Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' TVA Will Finalize Calculations for Switch Setpoints Prior to Units Restart
ML20042F7701990-05-0404 May 1990
Provides Results of Review of Util 890418 Submittal Re Supplemental Implementation of NUMARC 87-00 on Station Blackout.Implementation of 10CFR50.63 Consistent W/Guidance Provided by NUMARC 87-00
ML20042F3721990-05-0202 May 1990
Forwards Corrected Monthly Operating Repts for Jan-June 1989 & Aug 1989 - Jan 1990.Discrepancies Involve Cumulative Unit Svc Factors & Unit Availability Capacity Factors
ML18033B2631990-04-12012 April 1990
Forwards Response to NRC 900212 Request for Info Re Power Ascension & Restart Test Program at Unit 2.Util Has Refined Power Ascension Program to Be More Integrated & Comprehensive
ML18033B2551990-04-0909 April 1990
Responds to NRC 900309 Ltr Re Violations Noted in Insp Repts 50-259/89-16,50-260/89-16 & 50-296/89-16.Corrective Actions: Contractor Will Perform Another Check Function Review for Mechanical Calculations & Area Walkdowns Will Be Conducted
ML18033B2431990-04-0202 April 1990
Responds to NRC 900302 Ltr Re Violations Noted in Insp Repts 50-259/89-43,50-260/89-43 & 50-296/89-43.Corrective Action: Surveillance Insp Revised to Prevent Removal of All Eight Emergency Equipment Cooling Water Pumps from Water
1990-09-19
[Table view] |
Text
I REGULATORY I RMATION DISTRIBUTION SYS (BIDS)
ACCESSION NBR 8b04080228 DOC. DATE: 8b/03/2b NOTARIZED: NO DOCKET 0 FAC IL: 50-259 Browns Ferry Nuclear Power Station. Unit ii Tennessee 05000259 50-2ba Browns Ferry Nuclear Power St'ationi Unit 2E Tennessee 050002ba
.50-29b Browns Ferry Nuclear Power Stationi Unit 3i Tennessee 0500029b AUTH. NAME AUTHOR AFFILIATION QRIDLEYi R. Tennessee Valley Authority RECIP. NAME REC I P I ENT *FF I L I ATION MULLER> D. R. HWR Prospect Directorate 2
SUBJECT:
Responds to 851007 request for addi info re NUREG-0737'tem II'. K. 3. 18'Mods to Automatic Depressuri xation Sgs (ADS)
Logic. " No design basis requirement or increase in safety associated w/requested ADS logic mod. Present ADS adequate.
DISTRIBUTION CODE: 104bD TITLE: OR Submittal: TMI COPIES RECEIVED: LTR Action Plan j ENCL g SIZE:
Rgmt NUREG-0737 5 NUREG-obba NOTES: NMSS/FC*F 1 c g. 1 c g NMSS/FCAF/PM. OIA 1 c g. 05000259 NMSS/FCAF 1cg. ice NMSS/FCAF/PM. OI* icy. a5ooo2bo NMSS/FCAF icy. icy NMSS/FCAF/PM. OIA icy. 050002'Pb RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL BWR ADTS 1 1 HWR EH 1 1 HWR EICSB 2 2 BWR FOB 1 HWR PD2 PD 01 5 5 CLARK> R 1 1 BWR PSB 1 1 BWR RSB 1 1 INTERNAL: ACRS 34 10 10 *DM/LFMB 1 0 ELD/HDS4 1 a IE/DEPER DIR 33 1 1 IE/DEPER/EPB 3 NRR HWR ADTS 1 1 NRR'AULSONa W 1 NRR PWR-A ADTS 1 1 NRR PWR-B ADT8 1 1 1 1 NRR/DSRO EMRI T 1 1 G F LE 04 1 1 RGN2 1 1 EXTERNAL: 24X 1 LPDR 03 1 1 NRC PDR 1 1 NSIC 05 1 NOTES: 3 3 TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 42
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TENNESSEE VALLEY AUTHORITY 5N 157B Lookout Place March 26, 1986 Director of Nuclear Reactor Regulation Attention: Mr. D. R. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Muller:
In the Matter of the Docket Nos. 50-2S9 Tennessee Valley Authority 50-260 50-296 By letter from D. B. Vassallo to H. G. Parris dated October 7, 1985, we received a request for additional information regarding NUREG-0737, Item II.K.3.18, Modifications to Automatic Depressurization System Logic, for the Browns Ferry Nuclear Plant. Specifically requested was that. we inform NRC of our plans and schedule for implementing one of the NRC-approved modifications.
We continue to maintain our position that there is no design basis requirement or a significant increase in safety associated with the ADS logic modification requested by NRC. The current ADS initiation logic is designed to mitigate intermediate and small breaks in the primary system boundary, assuming no HPCI injection and taking no credit for operator action. The requested modification appears to go beyond this basis by requiring that operator action also be excluded from other analyses, such as stuck open relief valve with HPCI failure, although it can be shown that time is available for manual depressurization (greater than 10 minutes). It is also not clear that the increase in safety by further assuring a reactor depressurization for certain events outweighs the decrease in safety due to inadvertent actuation in certain other events such as instrument malfunction.
For primary system isolation events with the loss of high pressure makeup systems, the BWR Owners'roup analysis has shown that the operator has at least 30 to 40 minutes to initiate the ADS and prevent excessive fuel cladding heatup. Based on the BWR Owners'roup analysis and an Oak Ridge Laboratory study concerning loss of control air we have concluded that automatic ADS actuation would most likely occur without operator action within about 10 minutes after reactor pressure vessel level decreases to level 1 even for events which do not directly pressurize the drywall. In these events, the drywell becomes indirectly pressurized since reaching level 1 will cause containment isolation and a subsequent heatup and pressurization of the drywell due to the loss of drywell cooling. This heatup and pressurization will most likely result in ADS actuation within about, 10 minutes after the RPV water level decreasos to level 1.
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Director of Nuclear Reactor Regulation March 26, 1986 For small break LOCA events with no high pressure makeup, analyses have shown successful accident mitigation with no operator action fox the first 10 minutes and a complete failure of the ADS logic. Analyses prepared by the General Electric Company for BFN units 1, 2, and 3 examine primary system breaks ranging in size from 0.05 ft through 0.50 ft with a complete loss of the ADS logic function. This analysis is enclosed. These scenarios assume actuation of four main steam relief valves 10 minutes after the break. It can be concluded that with total failure of ADS initiation logic and no operator actions within 10 minutes, adequate core cooling can be maintained with a primary system break equivalent to a stuck open relief valve and no high pressure makeup.
The intent of NUREG-0737, Item II.K.3.18, is to provide additional assurance of adequate coxe cooling for transient and accident events which do not produce a high drywell pressuxe signal and are degraded by a loss of all high pressure coolant systems. Based upon our earlier submittals in which reliance was placed on use of symptom-oriented emergency procedure guidelines and with the additional analyses intxoduced in this submittal, TVA concludes that the existing ADS is adequate.
Very truly yours, TENNESSEE VALLEY AUTHORITY R. ridley
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Manager of icensing Enclosure cc (Enclosure):
Mr. R. J. Clax'k U.S. Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue Bethesda, Maryland 20814 U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
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