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| {{#Wiki_filter:ACCESS IUM VoR F AC IL:50 259 SO-2bo 50-296 A VT H~iVAi~E P AUL i T.,~.HORN g.S~ELYpO~REC IP~"f 4."IE OENTOV,t~.R. | | {{#Wiki_filter:REGULA'IJRY 0I 0 VFOR~ATI J'1 OISTRIBUTIO'4 SYSTE'H (R IOS) |
| 0 0 REGULA'I JRY I VFOR~ATI J'1 OISTRIBUTIO'4 SYSTE'H (R IOS): 80111202'30 OOC~OA TE: 80/10/28 4OTARIZEO:
| | ACCESS IUM VoR : 80111202'30 OOC ~ OA TE: 80/10/28 4OTARIZEO: '40 OOCKET F AC IL:50 259 3rowns Ferry Vucl.ear ~ower Stations Jnit lg Tennessee 05000259 SO-2bo 3ro~ns Ferry Vuclear Power Stations Unit 2i lennessee 0 50-296 Brawls Ferry .'Nuclear Power Station< Jnit 3i Tennessee 000296 A VT H ~ iVAi~E AU'TtjQR AFF IL [AT IQ'V P AUL i T.,~. Safe Energy Al i ance 1 |
| '40 3rowns Ferry Vucl.ear~ower Stations Jnit lg Tennessee 3ro~ns Ferry Vuclear Power Stations Unit 2i lennessee Brawls Ferry.'Nuclear Power Station<Jnit 3i Tennessee AU'TtjQR AFF IL[AT IQ'V Safe Energy Al 1 i ance Safe Energy A 1 1 i ance Safe Energy Alliance RECIPIENT I AFFILI A I ION Office of nuclear Reactor Regulationi director OOCKET 05000259 0 000296 DISTR IHUT IOV CDOE: XE03S TITLE: 2.206 Filings VOTES: SU8JECT: Requests reconsideration of QRC issuance of Amenas 60g55 32 to.Licenses OPR 35iOPN 52*OPR 68'mends authorize tempo,rary storage of low level radwaste in oavilions not designed to withstand winds over 80 mohan COP IES RECEI'VEO:LTR E'lCL SIZE: O RECIPIENT IO CANOE/VA wE ACTION'4: IPPOLI T'Jp T~CLARKgR~J~Ii'>TER>AL; 9 I REC TOR'ERR~lURRAY~J~'OELD PUHPLEgR, EXTERN')AL: | | HORN g.S ~ Safe Energy A i ance 1 1 ELYpO ~ Safe Energy Alliance REC IP ~ "f 4."IE RECIPIENT I AFFILIA I ION OENTOV,t~.R. Office of nuclear Reactor Regulationi director mohan SU8JECT: Requests reconsideration of QRC issuance of Amenas 60g55 32 to. Licenses OPR 35iOPN 52 |
| LPOR-COPIES LTT<E~VCL RECIPIENT I O COOL,/V A'4E iVOR R I S g S~CLARKeR~ERTTERrG~ARC POR PP.AS 4 F/ORIG COPIES LTTR EV L ey>>ts8O TOTAL AUNUER OF COPIES REQJIREO: LTTR 13 EVCL 13 Ik | | * OPR 68 'mends authorize tempo,rary storage of low level radwaste in oavilions not designed to withstand winds over 80 DISTR IHUT IOV CDOE: XE03S COP IES RECEI'VEO:LTR E'lCL O SIZE: |
| ~A October 28, 1980 Safe Energy Alliance of Alabama Huntsville Chapter Suite 407, Terry Hutchins Blvd.102 Clinton Ave.Huntsville, AL.35801 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Dear Mr.Denton;This letter is a request for reconsideration of the issuance, by the NRC, of amendments No.'s.60, 55 8e 32 to Facility Licenses No's.DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant, units No's.1, 2, 8c 3 dated March 17, 1980.These amendments authorize the temporary storage of low-level radioactive waste in an existing covered pavilion situated'n the site of BFNP.This request for reconsideration is motivated by the fact that the approved temporary Low Level Naste Storage (LLNS)pavilion is not designed to withstand tornado winds of over 80 mph velocities.
| | TITLE: 2.206 Filings VOTES: |
| BFNP is located in an area of North Alabama that has come to be known as"Tornado Alley".On April 3rd and 0th 1974 a series of tornadoes associated'ith a storm that caused 315 deaths and more than$600 million in damage passed within 2 miles of BFNP.Fifty-eight (58)500 KV linetransmission towers earring power from BFNP were snapped causing over a million dollars worth of damage As a result of the loss of these power lines unit one@BFNP was forced to shut down due to the sudden drop in demand the tornadoe's destructive activity had'brought about.Despite this history of very recent serious tornado activity, TVA, in the application for an amendment to BFNP's operating license which would allow the Agency to Store LLRN onsite, clearly states that the probability of a destructive tornado occuring at this facility was considered to be so small.as to be negligable.
| | RECIPIENT -COPIES RECIPIENT COPIES IO CANOE/VA wE LTT< E~VCL I O COOL,/V A'4E LTTR EV L ACTION'4: IPPOLI T'Jp T ~ |
| 0 Mr.Harold R.Denton, Director October,28, 1980 Edward Epstein the associate administrator for Environmental Monitoring 8c Predication of National Oceanic 8c Atmospheric Administration.
| | iVOR R IS g S ~ |
| on a field visit to North Alabama after the April 1974 tornadoes estimated that the rotational speed of such tor-nadoes was between 200 and 250 mph.This dismissal of the need to design.LLRN structures capable of withstanding tornado winds in an area that has recently suffered from a devasting tornado puts TVA in direct conflict with the Code of Federal Regulations Title 10 Chapter 1, Part 50, Appendix A., P.361 Criterion 2 Desi n Basis for Protection A ainst Natural Phenomena which states~Structures, systems, and components important to safety shall be designed'o withstand.
| | CLARKgR ~ J ~ CLARKeR ~ |
| the effects of natural.phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions.
| | Ii'>TER>AL; 9 I REC TOR 'ERR ERTTERrG ~ |
| The design bases for th'ese structures, systems, and components shall reflects (1)Appropriate consideration of the most severe of the natural phenomena-that have been historically reported for the site and surround-ing area, with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data'ave been accumulated.
| | ~lURRAY~J ~ ARC POR |
| (2)appropriate combinations of the effects of normal and accident conditions with the effects of the natural phenomena and.(3)the importance of the safety functions to be performed.
| | 'OELD PP.AS PUHPLEgR, 4 F /ORIG EXTERN')AL: LPOR ey>> ts8O TOTAL AUNUER OF COPIES REQJIREO: LTTR 13 EVCL 13 |
| Despite later claims to have adhered to the CFR noted above, TVA in its Plan for Temporary Onsite Storage of Low-Level Radio-active Waste@BFNP Units 1, 2, 3 dated January 21, 1980 in Section 0 General Considerations Part G Sub 2 states: "The probability of a tornado with maximum wind speeds higher than the 95 mph value striking the plant in any one year is 7 x 10 This is considered to be small enough to be neglected."
| |
| ib~I Mr.Harold R.Denton, Director October 28, 1980'n effect TVA has chosen to neglect the possibility of a tornado re-occurring in an area that has already suffered severe damage from a series of tornados with wind velocities more than twice those that TVA has planned for.TVA is gambling on the possibility that another severe storm will not strike BFNP or its environs.The people of North Alabama will suffer the consequences of such negligence and it is for this reason that we request the NRC to direct TVA to adhere to the CFR which calls on them to be prepared for the"most severe of the natural phenomena that have been historically reported for the site and surrounding area." Sincerely yours, Thomas W.Paul tewart Horn cj;David, Ely The Safe Ener y Alliance of Alabama, Huntsville Chapter
| |
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| |
|
| Docket No.50 259 50-260 and 50-296~UNITED STATES NUCLEAR'REGULATORY COMMISSION WASHINGTON D.G.20555 November 3, 1980 See attached lfst of addressees.
| | Ik October 28, 1980 Safe Energy Alliance of Alabama Huntsville Chapter Suite 407, Terry Hutchins Blvd. |
| subject: Brotfns Ferr Nuclear Poorer Statfon Vnfts 1.2, and 3 Tennessee Va ey Atithorfty The following documents concerning our review of the subject facility are transmitted for your information: | | 102 Clinton Ave. |
| G Notice of Receipt of Application. | | Huntsville, AL. 35801 |
| Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application for Construction. | | ~ A Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D .C . 20555 Dear Mr. Denton; This letter is a request for reconsideration of the issuance, by the NRC, of amendments No.'s. 60, 55 8e 32 to Facility Licenses No's. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant, units No's. 1, 2, 8c 3 dated March 17, 1980. These amendments authorize the temporary storage of low-level radioactive waste in an existing covered pavilion situated'n the site of BFNP . |
| Permit.1 Notice of Constderation of Issuance of Facility Operating License.Application and Safety Analysis Report, Vol.Amendment No.to Application/SAR, dated Construction Permit No.CPPR-,date Facility Operating License No.DPR-, NPF-, date C3 Amendment No.to CPPR-or DRR-,dated er 1980. | | This request for reconsideration is motivated by the fact that the approved temporary Low Level Naste Storage (LLNS) pavilion is not designed to withstand tornado winds of over 80 mph velocities. |
| | BFNP is located in an area of North Alabama that has come to be known as "Tornado Alley". On April 3rd and 0th 1974 a series of tornadoes associated'ith a storm that caused 315 deaths and more than $ 600 million in damage passed within 2 miles of BFNP . |
| | Fifty-eight (58) 500 KV linetransmission towers earring power from BFNP were snapped causing over a million dollars worth of damage As a result of the loss of these power lines unit one |
| | @ BFNP was forced to shut down due to the sudden drop in demand the tornadoe's destructive activity had 'brought about. |
| | Despite this history of very recent serious tornado activity, TVA, in the application for an amendment to BFNP's operating license which would allow the Agency to Store LLRN onsite, clearly states that the probability of a destructive tornado occuring at this facility was considered to be so small. as to be negligable. |
| | |
| | 0 Mr. Harold R. Denton, Director October,28, 1980 Edward Epstein the associate administrator for Environmental Monitoring 8c Predication of National Oceanic 8c Atmospheric Administration. on a field visit to North Alabama after the April 1974 tornadoes estimated that the rotational speed of such tor-nadoes was between 200 and 250 mph. |
| | This dismissal of the need to design. LLRN structures capable of withstanding tornado winds in an area that has recently suffered from a devasting tornado puts TVA in direct conflict with the Code of Federal Regulations Title 10 Chapter 1, Part 50, Appendix A ., |
| | P. 361 Criterion 2 Desi n Basis for Protection A ainst Natural Phenomena which states~ |
| | Structures, systems, and components important to safety shall be designed'o withstand. the effects of natural .phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions. The design bases for th'ese structures, systems, and components shall reflects (1) Appropriate consideration of the most severe of the natural phenomena-that have been historically reported for the site and surround-ing area, with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data been accumulated. (2) appropriate combinations of the 'ave effects of normal and accident conditions with the effects of the natural phenomena and.(3) the importance of the safety functions to be performed. |
| | Despite later claims to have adhered to the CFR noted above, TVA in its Plan for Temporary Onsite Storage of Low-Level Radio-active Waste @ BFNP Units 1, 2, 3 dated January 21, 1980 in Section 0 General Considerations Part G Sub 2 states: "The probability of a tornado with maximum wind speeds higher than the 95 mph value striking the plant in any one year is 7 x 10 This is considered to be small enough to be neglected." |
| | |
| | ib ~I Mr. Harold R. Denton, Director October 28, 1980 |
| | 'n effect TVA has chosen to neglect the possibility of a tornado re-occurring in an area that has already suffered severe damage from a series of tornados with wind velocities more than twice those that TVA has planned for. TVA is gambling on the possibility that another severe storm will not strike BFNP or its environs. The people of North Alabama will suffer the consequences of such negligence and it is for this reason that we requestto the NRC to direct TVA to adhere to the CFR which calls on them be prepared for the "most severe of the natural phenomena that have been historically reported for the site and surrounding area." |
| | Sincerely yours, Thomas W. Paul tewart Horn cj; David, Ely The Safe Ener y Alliance of Alabama, Huntsville Chapter |
| | |
| | UNITED STATES NUCLEAR'REGULATORY COMMISSION WASHINGTON D.G. 20555 November 3, 1980 Docket No. 50 259 50-260 and 50-296~ |
| | See attached lfst of addressees. |
| | subject: Brotfns Ferr Nuclear Poorer Statfon Vnfts 1 .2, and 3 Tennessee Va ey Atithorfty The following documents concerning our review of the subject facility are transmitted for your information: |
| | G Notice of Receipt of Application. |
| | Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application for Construction. Permit. |
| | 1 Notice of Constderation of Issuance of Facility Operating License. |
| | Application and Safety Analysis Report, Vol. |
| | Amendment No. to Application/SAR, dated Construction Permit No. CPPR- ,date Facility Operating License No. DPR-, NPF- , date C3 Amendment No. to CPPR- or DRR-,dated er 1980. |
| | Office of Nuclear Reactor Regulation ORB 82 |
|
| |
|
| ==Enclosures:== | | ==Enclosures:== |
| | DL As stated cc; OFFICE p-suANAME ~ |
| | DATE ~ |
| | ti RC-2 I (6.76) |
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|
| As stated Office of Nuclear Reactor Regulation ORB 82 DL cc;OFFICE p-suANAME~DATE~ti RC-2 I (6.76) 5~-3 C 8 C Docket, No.50-259 50-260.and.50-296~UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D.C.20555 October 31, 1980 s teikution:
| | 5~ |
| t ORB III2 See attached 1fst of addressees.
| | -3 8 C C |
| subject: Brogans Ferr Nucl'ear Power Station Units 1, 2 and 3 Tennessee a ey ut or ty The following documents concerning our review of the subject facility are transmitted for., your information: | | |
| Notice of Receipt of Application. | | s teikution: |
| Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application. | | t ORB III2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20555 October 31, 1980 Docket, No. 50-259 50-260 |
| for Construction Permit.Notice of Consideration of Issuance of Facility Operating License.Cl Application and Safety Analysis Report, Vol'.Amendment No.to Application/SAR, dated Construction Permit No.CPPR-,date Facility Operating License Nn.DPR-', NPF-, date Amendment No.to CPPR=or DRR-,dated l3 Other: disposal semiannual report for 1978.nW<aste | | . and. 50-296~ |
| | See attached 1fst of addressees. |
| | subject: Brogans Ferr Nucl'ear Power Station Units 1, 2 and 3 Tennessee a ey ut or ty The following documents concerning our review of the subject facility are transmitted for., your information: |
| | Notice of Receipt of Application. |
| | Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application. for Construction Permit. |
| | Notice of Consideration of Issuance of Facility Operating License. |
| | Cl Application and Safety Analysis Report, Vol'. |
| | Amendment No. to Application/SAR, dated Construction Permit No. CPPR- ,date Facility Operating License Nn. DPR- ', NPF-, date Amendment No. to CPPR= or DRR-,dated l3 Other: nW<aste disposal semiannual report for 1978. |
| | Office of Nuclear Reactor Regulation ORB 02 |
|
| |
|
| ==Enclosures:== | | ==Enclosures:== |
| | DL As stated cc: |
| | ~ ORB j/2 OFFICE SURNAME SNorris:kf DATE ~ 4 ttg/80 Fg RC 2t (6-16) |
| | |
| | la 0' |
| | C- I l1 |
| | 'E e ~ s I t. |
| | C, -' |
| | r |
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| As stated Office of Nuclear Reactor Regulation ORB 02 DL cc: Fg RC 2t (6-16)OFFICE~SURNAME DATE~ORB j/2 SNorris:kf 4 ttg/80 la 0'C-I l1'E e~s I C,-'t.r UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D.C.20555 October 30, 1980 Docket No.50-259 5>>2t2 and 50-296 See attached 1ist of addressees.
| | istribution:~ |
| istribution:
| | QDOsCket s |
| s~QDOsCket ORB.b2
| | ORB. b2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20555 October 30, 1980 Docket No. 50-259 5>>2t2 and 50-296 See attached 1ist of addressees. |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Brot<ns Ferr Nuclear Potier Station Units 1'2 and 3 Tennessee a ey Aut or ty The following documents concerning our review of the subject fa'cility are transmitted for your information: | | Brot<ns Ferr Nuclear Potier Station Units 1 '2 and 3 Tennessee a ey Aut or ty The following documents concerning our review of the subject fa'cility are transmitted for your information: |
| Q Notice of Receipt of Application. | | Q Notice of Receipt of Application. |
| Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application for Construction Permit.Notice of Consideration of Issuance of Facility Operating License.Application and Safety Analysis Report, Vol.CI Amendment No.to Application/SAR, dated'Construction Permit No.CPPR-,date Facility Opcratinp License No.DPR-, NPF-, date Amendment No.to CPPR-or DRR-,dated H Other: pBFilkIJl~ | | Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application for Construction Permit. |
| 80. | | Notice of Consideration of Issuance of Facility Operating License. |
| | Application and Safety Analysis Report, Vol. |
| | CI Amendment No. to Application/SAR, dated |
| | 'Construction Permit No. CPPR- ,date Facility Opcratinp License No. DPR-, NPF-, date Amendment No. to CPPR- or DRR-,dated H Other: pBFilkIJl~ 80. |
| | Office of Nuclear Reactor Regulation ORB 4'2 |
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| |
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| ==Enclosures:== | | ==Enclosures:== |
| | DL As stated cc: |
| | ORB 02 OFI:K,'E p SNonrTs:kf suRNAM6 oArc ~ ] ~3-88~- |
| | NRC 2I (676) |
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| As stated Office of Nuclear Reactor Regulation ORB 4'2 DL cc: OFI:K,'E p suRNAM6 ORB 02 SNonrTs:kf NRC 2I (676)oArc~]~3-88~-
| | iS Ig I |
| iS Ig I C, r P 1 e}} | | C, r P 1 e}} |
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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:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20247Q4691989-08-0808 August 1989
Expresses Concerns Re Installation of RWCU Sys Sample Panel & Relation of Radioactive Water Flowing Through RWCU Sample Panel to Plant
ML20245F4731989-07-0909 July 1989
Requests Assistance in Determining Why Util Mgt Does Not Want Author to See Proposed Corrective Actions for Four Condition Adverse to Quality Repts Issued While Employed at Facility
ML20246J9851989-06-17017 June 1989
Expresses Concern Re Potential Industrial Safety Hazard Resulting from Inclusion of Glass Rotameter in RWCU Sample Line at Plant
ML20245B3981989-05-0808 May 1989
Discusses Technical & Safety Concerns Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels at Plant
ML20245B4081989-03-10010 March 1989
Requests Response to 881014 & 890119 & 23 Ltrs Re Technical & Safety Concerns at Plant
ML20244B0011989-03-0808 March 1989
Lists Facts to Consider for Action to Fix or Close GE Reactors Once & for All
ML20245B4091989-01-23023 January 1989
Refers to Re Corrosion Inhibitors in Closed Water Sys at Plant.Last Sentence on First Page of Ltr Should Be Changed to Read One Example Is Loss of Air Cooling to Shutdown Board Rooms at Sequoyah
ML20245B4101989-01-19019 January 1989
Requests That Jg Partlow Pursue Completion of Engineering Assignment of ED Buggs at Plant Concerning Corrosion Inhibitors for Closed Water Sys.Draft Engineering Rept Recommending Corrosion Inhibitors for Closed Water Sys Encl
ML20245B4121988-10-14014 October 1988
Informs of Several Technical Concerns Expressed While at Util & Requests That Jg Partlow Pursue Resolution of Listed Concerns
ML20238B7731987-08-0707 August 1987
FOIA Request for Records Explaining Status of Listed LERs Omitted from List,Previously Received from Nrc,Of LERs Filed by Commercial Nuclear Power Plant Licensees for Operating Year 1986
ML20197C4281986-08-22022 August 1986
FOIA Request for Eight Categories of Documents,Including Current Timetable for Correcting Technical & Engineering Problems & Expected Annual Costs for Operating & Maint of Facilities
ML20211A0111986-08-22022 August 1986
FOIA Request for Records on Browns Ferry & Sequoyah, Including Current Timetable for Correcting Technical & Engineering Problems & Expected Annual Costs for Capital Improvements
ML20204G0941986-07-10010 July 1986
Submits Complaint on TVA Refusal to Rehire Author Due to Age Discrimination as Well as Reporting Violations at Facility to NRC
ML20128P8031985-04-0808 April 1985
FOIA Request for Access to or Records Re Potential Environ Impact Associated W/Fuel Loading &/Or Low Power Testing at Diablo Canyon & AEOD Sept 1980 Rept on Browns Ferry Interim Equipment to Detect Water in Discharge
ML20077A8071983-07-15015 July 1983
Comments on Bangor Daily News & MTV Repts of NRC Order to Shut Down Five Facilities for Insp of Cooling Pipes. Subsequent Rescission Considered Under Pressure from Private Owners of Plants.Requests Stronger Enforcement
ML20073B4531983-01-27027 January 1983
FOIA Request for Documents Re Leaks Discovered on 830116 in Facility Primary Cooling Sys
ML20039D2321981-12-11011 December 1981
Responds to Rept Re Investigative Findings at Facility. Forwards EP Hofstadter Affidavit
ML18025B3421981-02-0202 February 1981
Forwards Petition to Intervene & Request for Hearing. Requests Name Be Added to List to Receive All Correspondence
ML18025B3331981-01-27027 January 1981
Requests NRC Perform EIS on Low Level Radwaste Mgt for Facilities.Ltr to TVA Chairman D Freeman Also Submitted
ML18025B2941981-01-21021 January 1981
Requests to Make Limited Appearance Statement & to Receive EIS on Proposed Low Level Radwaste Storage Project
ML18025B1831980-10-28028 October 1980
Requests Reconsideration of NRC Issuance of Amends 60,55 & 32 to Licenses DPR-33,DPR-52 & DPR-68 Respectively.Amends Authorize Temporary Storage of Low Level Radwaste in Pavilions Not Designed to Withstand Winds Over 80 Mph
ML19347A8271980-09-24024 September 1980
Questions Safety Design of Facilities
ML19347A8291980-09-24024 September 1980
Informs of Unreported RO at Facility Re High Radiation in Offgas Sys
ML19347A8251980-08-0808 August 1980
Alleges Cheating on NRC OL Exams at Facility.Ltr to Hj Green Offering to Expose Cheating Encl
ML18025A9631980-07-0909 July 1980
Expresses Concern Re Plans to Construct Low Level Waste Storage & Incineration Facility.Proposed Facility Would Present Significant Health Risks to Highly Populated Area. Requests Public Hearing & EIS
ML19309F7061980-04-22022 April 1980
Requests That Public Hearing & EIS Be Required for Proposed Low Level Waste Compaction & Incineration Facility at Site
1989-08-08
[Table view] |
Text
REGULA'IJRY 0I 0 VFOR~ATI J'1 OISTRIBUTIO'4 SYSTE'H (R IOS)
ACCESS IUM VoR : 80111202'30 OOC ~ OA TE: 80/10/28 4OTARIZEO: '40 OOCKET F AC IL:50 259 3rowns Ferry Vucl.ear ~ower Stations Jnit lg Tennessee 05000259 SO-2bo 3ro~ns Ferry Vuclear Power Stations Unit 2i lennessee 0 50-296 Brawls Ferry .'Nuclear Power Station< Jnit 3i Tennessee 000296 A VT H ~ iVAi~E AU'TtjQR AFF IL [AT IQ'V P AUL i T.,~. Safe Energy Al i ance 1
HORN g.S ~ Safe Energy A i ance 1 1 ELYpO ~ Safe Energy Alliance REC IP ~ "f 4."IE RECIPIENT I AFFILIA I ION OENTOV,t~.R. Office of nuclear Reactor Regulationi director mohan SU8JECT: Requests reconsideration of QRC issuance of Amenas 60g55 32 to. Licenses OPR 35iOPN 52
- OPR 68 'mends authorize tempo,rary storage of low level radwaste in oavilions not designed to withstand winds over 80 DISTR IHUT IOV CDOE: XE03S COP IES RECEI'VEO:LTR E'lCL O SIZE:
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Ik October 28, 1980 Safe Energy Alliance of Alabama Huntsville Chapter Suite 407, Terry Hutchins Blvd.
102 Clinton Ave.
Huntsville, AL. 35801
~ A Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D .C . 20555 Dear Mr. Denton; This letter is a request for reconsideration of the issuance, by the NRC, of amendments No.'s. 60, 55 8e 32 to Facility Licenses No's. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant, units No's. 1, 2, 8c 3 dated March 17, 1980. These amendments authorize the temporary storage of low-level radioactive waste in an existing covered pavilion situated'n the site of BFNP .
This request for reconsideration is motivated by the fact that the approved temporary Low Level Naste Storage (LLNS) pavilion is not designed to withstand tornado winds of over 80 mph velocities.
BFNP is located in an area of North Alabama that has come to be known as "Tornado Alley". On April 3rd and 0th 1974 a series of tornadoes associated'ith a storm that caused 315 deaths and more than $ 600 million in damage passed within 2 miles of BFNP .
Fifty-eight (58) 500 KV linetransmission towers earring power from BFNP were snapped causing over a million dollars worth of damage As a result of the loss of these power lines unit one
@ BFNP was forced to shut down due to the sudden drop in demand the tornadoe's destructive activity had 'brought about.
Despite this history of very recent serious tornado activity, TVA, in the application for an amendment to BFNP's operating license which would allow the Agency to Store LLRN onsite, clearly states that the probability of a destructive tornado occuring at this facility was considered to be so small. as to be negligable.
0 Mr. Harold R. Denton, Director October,28, 1980 Edward Epstein the associate administrator for Environmental Monitoring 8c Predication of National Oceanic 8c Atmospheric Administration. on a field visit to North Alabama after the April 1974 tornadoes estimated that the rotational speed of such tor-nadoes was between 200 and 250 mph.
This dismissal of the need to design. LLRN structures capable of withstanding tornado winds in an area that has recently suffered from a devasting tornado puts TVA in direct conflict with the Code of Federal Regulations Title 10 Chapter 1, Part 50, Appendix A .,
P. 361 Criterion 2 Desi n Basis for Protection A ainst Natural Phenomena which states~
Structures, systems, and components important to safety shall be designed'o withstand. the effects of natural .phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions. The design bases for th'ese structures, systems, and components shall reflects (1) Appropriate consideration of the most severe of the natural phenomena-that have been historically reported for the site and surround-ing area, with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data been accumulated. (2) appropriate combinations of the 'ave effects of normal and accident conditions with the effects of the natural phenomena and.(3) the importance of the safety functions to be performed.
Despite later claims to have adhered to the CFR noted above, TVA in its Plan for Temporary Onsite Storage of Low-Level Radio-active Waste @ BFNP Units 1, 2, 3 dated January 21, 1980 in Section 0 General Considerations Part G Sub 2 states: "The probability of a tornado with maximum wind speeds higher than the 95 mph value striking the plant in any one year is 7 x 10 This is considered to be small enough to be neglected."
ib ~I Mr. Harold R. Denton, Director October 28, 1980
'n effect TVA has chosen to neglect the possibility of a tornado re-occurring in an area that has already suffered severe damage from a series of tornados with wind velocities more than twice those that TVA has planned for. TVA is gambling on the possibility that another severe storm will not strike BFNP or its environs. The people of North Alabama will suffer the consequences of such negligence and it is for this reason that we requestto the NRC to direct TVA to adhere to the CFR which calls on them be prepared for the "most severe of the natural phenomena that have been historically reported for the site and surrounding area."
Sincerely yours, Thomas W. Paul tewart Horn cj; David, Ely The Safe Ener y Alliance of Alabama, Huntsville Chapter
UNITED STATES NUCLEAR'REGULATORY COMMISSION WASHINGTON D.G. 20555 November 3, 1980 Docket No. 50 259 50-260 and 50-296~
See attached lfst of addressees.
subject: Brotfns Ferr Nuclear Poorer Statfon Vnfts 1 .2, and 3 Tennessee Va ey Atithorfty The following documents concerning our review of the subject facility are transmitted for your information:
G Notice of Receipt of Application.
Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application for Construction. Permit.
1 Notice of Constderation of Issuance of Facility Operating License.
Application and Safety Analysis Report, Vol.
Amendment No. to Application/SAR, dated Construction Permit No. CPPR- ,date Facility Operating License No. DPR-, NPF- , date C3 Amendment No. to CPPR- or DRR-,dated er 1980.
Office of Nuclear Reactor Regulation ORB 82
Enclosures:
DL As stated cc; OFFICE p-suANAME ~
DATE ~
ti RC-2 I (6.76)
5~
-3 8 C C
s teikution:
t ORB III2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20555 October 31, 1980 Docket, No. 50-259 50-260
. and. 50-296~
See attached 1fst of addressees.
subject: Brogans Ferr Nucl'ear Power Station Units 1, 2 and 3 Tennessee a ey ut or ty The following documents concerning our review of the subject facility are transmitted for., your information:
Notice of Receipt of Application.
Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application. for Construction Permit.
Notice of Consideration of Issuance of Facility Operating License.
Cl Application and Safety Analysis Report, Vol'.
Amendment No. to Application/SAR, dated Construction Permit No. CPPR- ,date Facility Operating License Nn. DPR- ', NPF-, date Amendment No. to CPPR= or DRR-,dated l3 Other: nW<aste disposal semiannual report for 1978.
Office of Nuclear Reactor Regulation ORB 02
Enclosures:
DL As stated cc:
~ ORB j/2 OFFICE SURNAME SNorris:kf DATE ~ 4 ttg/80 Fg RC 2t (6-16)
la 0'
C- I l1
'E e ~ s I t.
C, -'
r
istribution:~
QDOsCket s
ORB. b2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20555 October 30, 1980 Docket No. 50-259 5>>2t2 and 50-296 See attached 1ist of addressees.
Subject:
Brot<ns Ferr Nuclear Potier Station Units 1 '2 and 3 Tennessee a ey Aut or ty The following documents concerning our review of the subject fa'cility are transmitted for your information:
Q Notice of Receipt of Application.
Draft/Final Environmental Statement, dated Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application for Construction Permit.
Notice of Consideration of Issuance of Facility Operating License.
Application and Safety Analysis Report, Vol.
CI Amendment No. to Application/SAR, dated
'Construction Permit No. CPPR- ,date Facility Opcratinp License No. DPR-, NPF-, date Amendment No. to CPPR- or DRR-,dated H Other: pBFilkIJl~ 80.
Office of Nuclear Reactor Regulation ORB 4'2
Enclosures:
DL As stated cc:
ORB 02 OFI:K,'E p SNonrTs:kf suRNAM6 oArc ~ ] ~3-88~-
NRC 2I (676)
iS Ig I
C, r P 1 e
