ML20153F346

Responds to NRC 880622 Request to Verify Data Contained in Safety Issues Mgt Sys (Sims) for Plant.Sims Data for Units Encl

ML20153F346
Person / Time
Site:	Browns Ferry
Issue date:	09/02/1988
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
TAC-R00112, TAC-R112, NUDOCS 8809070231
Download: ML20153F346 (29)

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'f .& D TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ol SN 157B Lookout Place SEP 021988 U.S. Nuclear Regulatory Coumission ATTN: Document Control Desk Washington, D.C. 20555  ;

Centlemen: ,

i In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority' ) 50-260

• 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - VERIFICATION OF SAFETY ISSUES MANACEMENT SYSTEM (SIMS) MULTIPLANT ACTION (MPA) ITEMS This letter is to respond to the NRC request by letter dated June 22, 1987, to verify the data contained in the NRC SIMS tracking system for BFN. Extensive research into TVA current and historical files was conducted to verify this data. This research included investigation into NRC/TVA correspondence, internal correspondence, procedures, design documents, and modification workplans.

Enclosed in this letter are three attachments. Attachment 1 is SIMS data for BFN Unit 1, attachment 2 is SIMS data for BFN Unit 2, and attachment 3 is SIMS data for BFN Unit 3. In these attachments are columns for the NUREG-07'7 item number (THI Item), the MPA item number, the issue description, the imposition date, the implementation date, and a column for remarks. The imposition data is the date that NRC and TVA reached agreement for action on the issue either by a safety evaluation report (SER) or letter of agreement. If neither of these were found an imposition date was not listed. The implementation date is the date of the SER or the NRC letter accepting TVA's actions. If one of these two documents. could not be found, the implementation date is listed as l the completion date of an engineering change notice (ECN), procedure revision date, or the date of the TVA letter to NRC indicating completion of required actions.

l Some items have neither an imposition nor implementation date. If this is the case the item has been incorporated into another item or TVA has been advised by NRC staff that verification is not required for BFN.

In the cases where the item for unit 1, 2, or 3 is to be completed before restart or during a subsequent refuel cycle the word "restart" or "refuel" and the refuel number, will be listed under the implementation date.

poM 8809070231 800902 PDR ADOCK 05000259 ,

P PNU \

i An Equal Opportunity Employer

, <  :* . l 1

U.S. Nuclear Regulatory Commission SEP 021988 i i

According to research by TVA staff and TVA's understanding of the item, the attached dates are the most accurate that TVA could obtain. If you have any questions or need further information please contact J. L. Turner at (205) 729-2853.

Very truly yours, TEN E" EE 'Y AUTHORITY R. Gridley, M nager Nuclear Licensing and Regulatory Affairs Enclosures cc (Enclosures):

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. F. R. McCoy, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory CommisJ.on 4

Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12 Box 637 Athens, Alabama 35611

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• Page D. 1 BROWNS FERRY NUCLEAR PLANT (BFN)

C/29/88 AllACHMENT!

SAFETYISSUESMANA6EMENTSYSTEM UNif1 TM!liEM MPA I ISSUE IMPOSITION IMPLEMENTAi!0N REMARKS DATE DATE A-01 10CFR50.55A(6) - Intervice Restart inservice inspection for first inspection ten year interval mill be cospleted before restart according to TVA letter dated 03/01/88. Thisisanongoing effort.

A-02 10CFR50 App.!-RETSandREMS 02/05/97 02/05/97 A43 Securi'yPlan 02/23/79 02/23/79 A 04 Contsineent Leak Testing - 10CFR50 Restart App.J A45 Mark 1 Short Tere Progree 12/08/78 12/08/78 A46 RespiratoryProtectionPrograe 10/11/19 10/11/79 A48 LPC! Modifications 05/11/79 04/18/87 ECNcospleted 04/18/87.

A49 Reactor Vessel Beltline Material 02/06/81 02/06/81 NRR cloud this MPA by Surveillance internal NRC letter dated 05/19/80 withoutimposing requireeents. According to discussions with 6. 6 ears, aHndsent should be listed for impleeentation date.

A 10 Safeguards Contingency Plan Revies 06/19/81 06/19/81 A Il GuardTrainingPlanRevies 06/15/81 06/15/81 A 12 Vital Area Analysis N/A NRAclosedMPAin04/82.

A14 InservicePuesandValveTesting 03/25/98 Thistoplesentationdateis Progree based on the TV4 subsittal to WRCdated 03/25/98. Asalting technical Specification a w nd u nt free htC. This is an ongoing effort.

A 15 liesel 6enerator Fue! 01194 12/04/07 Last general revision of procedurethatassigneddiesel fuel oil a QA status is used at lealesentation date.

A 16 Personnel Ogatifications - 04/GC 03/17/82 03/17/82

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C/29/08 AffACHMENT 1 SArtif ISSUES MAM 6EMENT SYSTEM UNIT 1 TMIliEM MPA 0 ISSUE IMPOSli!ON IMPLEMENTATION REMARKS DATE DATE A 17 Instrueentation to Follos the Restart Course of an Accident R6 1.97 A 18 10CFR50.726.73 Reporting 05/30/84 05/30/84 Requireeents A!! HydrogenControl 02/12/88 Rntart A 20 10CFR50.62ATN8 Rutart I 01 Dinal 6enerator Lockout 07/15/82 07/15/82 3-05 Stress Corresion Cracking in DM Restart TechnicalSpecificationsutil RCS (NURE6 0313) be subsitted before restart accordingtoTVAletterdated 08/01/88.

I06 Safety /ReliefValveSurveillance N/A MR aborted MPA without leposing requireeents.

1 16 Energency Plan Revies N/A NRR tereinated MPA on 04/01/81. MPAl F 67 opened to continue work.

1 17 Hydraulic Snubbers 05/24/82 05/24/82 1 20 ContainuntLeakageDuetoSul 08/25/80 08/25/80 !spesitionandisslesentation Ceterteration dates based on internal MC seendated 08/18/86 shere MPAt 1 20 uns sade part of RPA4 B24.

1-21 Loss of 125V DC Bus and Annunciator 05/25/02 N/A MRcloudMPA.

Systu l 22 MechanicalSnubters 05/24/82 05/24/82 123 Degradationof6ridVoltage 09/03/81 09/03/81 Norkisfieldcoeplete.

This ites incorporated into i 124 Contaln unt Vent and Purge 07/01/95 07/01/85 liesll.E.4.2.6(RPA4Flf) 1 25 Futsater and CR0 Noaale Cracking 06/06/84 12/11/84 (CNcloud!!/11/84.

127 Ofign Espleston Prenstion 08/22/19 08/22/79 (IEl7803) t41 Fire Protectice - 10CFR50 App. R Restart

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C/29/00 ATTAChMENTI SAFEif ISSUES MANAGEMENT SYSTEM UNIT 1 TMIITEM MPAI IllVE IMPOSITION IMPLEMENTAi!ON REMARKS DATE DATE l42 TM! Folloa-Up Nork (IEl 79-04) 12/27/79 12/27/79 kcording to discussion eith

6. Sears, MPA 'overtalen' by NURE6-0737.

144 Dedicated Hydrogen Penetrations & N/A N/A According to discussion eith Recoebiner(2.1.5.AC) 6. Sears, MPA ' overtaken' by NURE60737.

1 144 Control Roon kcess, TSC, OSC N/A N/A kcording to discussion eith 1 (2.2.2) 6. Sears, MPA ' overtaken' by NURE6-0737.

3 44 High Range Radiation Monitors N/A N/A According to discussion with (2.1.9.Il G. Sears, MPA ' overtaken' by  ;

IsVREG-0737.

l 44 Post Accident Saeoling (2.1.1.A) N/A N/A kcording to discussion eith

6. Sears, MPA 'overtaien' by NURE6-0737.

l 44 Shielding Revies (2.1.6.3) N/A N/A kcording to discussion with

6. Gears, MPA ' overtaken' by NURE6-0737.

l44 CoreCoolingInstrueentation N/A N/A According to discussion eith (2.1.3.1) 6. 6 ears, MPA ' overtaken' by NURE60737.

1 44 Relief 6SafetyValveTesting N/A N/A k cording to discussion eith (2.1.2) 6. 6 ears, MPA ' overtaken' by NURE60737.

3 44 Diverse Containeent isolation N/A N/A According to discussion eith (2.1.4) 6. Sears, MPA ' overtaken' by .

NURE60737.

l 44 Shif t Supervisor Pesponsibilities, N/A N/A k cording to discussion with STA,TurnoverProcedures(2.2.1.A. 6. 6 ears, MPA ' overtaken' by 1,Cl NURE60737.

l44 leproved lodine Instrueentation N/A N/A Accordingtodiscussioneith (2.1.1.Cl 6. Sears, MPA ' overtaken' by i huRE60737.

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144 ValvePositionIndication(2.1.3.A)N/A N/A According to discussion eith ,

6.6 ears,PfA' overtaken'by l hutti0737.

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C/29/80 ATTACHMENT 1 SAFETY ISSUES MANAGEMENT SYSTEM UN!ii TM! ITER MPA 0 ISSUE IMPOSITION IMPLEMENTATION REMARKS DATE DATE I 44 Systes Integrity for High N/A N/A According to discussion eith Radioactivity (2.1.6.A) 6. Sears, MPA ' overtaken' by NUREG-0737.

1-45 PriearyCoolantSystesPressure 08/01/80 08/08/80

, IsolationValves

! I 46 EE Turbine Disk Analysis 05/16/80 N/A NRR aborted MPA sithout leposing requireeents.

t 3 40 Distribution Systes Adequacy 0701/0$ 9,/31/95 l50 Scras Discharge Voluu Capability Restart I 't Masonry Walt Design (IEl 80-111 06/27/04 Rutart I-60 ElofSafetyRelatedElectrical Rutart Equipeent 3 61 LossofNon-lt16CPowerEvaluation 07/26/02 Inspection report cloud for

(!El79-27) Units I and 3 only.

1 62 ESFResetControls(IEI10-06) Rutart 1-63 Station Blackout 12/02/11 12/02/11 3 65 Pipe truts in luR Scras Systes 01/03/16 01/03/06 l-70 MonitoringRCSFatigueTransient 05/25/12 N/A NRRclosedMPA.

Lleits I72 TM1TechnicalSpecifications 05/23/10 leoleuntationdateisthe datelastissueclosed.

I 76 Post frip Revin Progras (6l 13 21 06/17/05 06/l7/05 Ites!.1) 177 EquipuntClassification6 Vender 01/13/07 lepteuntation date based on Interf ace (6L 13 28 Ites 2.1) last general revision of PMP 0601.01.

I 71 Post Maintenance Testing 03/23/01 Rutart Procedurnivenser er.t,1311Itte 3.1.163 .2) 1 79 Post 4  : ,ofRPS 10/27/16 10/27/16 (6'

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C/29/II Aff4CHMENT1 SAFETYISSUESMANA6EMENTSYSTER UNIT 1 IMIITEM MPA4 ISSUE IMPOSITION IMPLEMENTAi!ON REMARKS DATE DATE I 83 NUREl 0737 Tuhaical Specifications Restart (R 13-36) 1 14 StainlessSteelPipeInspection 01/25/98 6eneric Lettu 1411 (R 14 111 supwceded by Generic Letter II-01. This ites incorporated into MPAl 3-05.

1 15 Post frip Revies Capability 06/12/05 06/12/05

( R 83 29 Ites 1.21 1 06 Equipeent Classification b Vendor 03/05/97 !apleoentation ba nd on TVA Intulace (R 83 21 Ites 2.2) lett w dated 03/05/07.

Aealting RAI or SER.

1 17 Post-Maintenance Testing (R 13-20 03/23/11 03/23/98 Ites3.2.163.2.2)

I 83 TechnicalSpecificationsfor 10/27/06 10/27/06 Post Maintenance festing (R 13 21 Ites3.2.3) 892 Reacter Trip festing (R 83 20 03/23/11 03/23/06 Ites4.5.1) l l l 93 R utter Trip Functional fest 09/02/06 lopleeentationdateforitse j (R 13 28 Itees 4.5.2 6 4.5.3) 4.5.2only. AnaltingRA!or l

SER (or ites 4.5.3.

C-02 ATWS Recirculation Pues Trip Restart I C 10 ControlofHeavyLeads-Phase! 06/06/04 Restart I

(NUREl-0612)

Cll RPSPcurSupply 06/27/05 06/27/95 Modificationcosplete.

Testing to be done af ter restut to support Technical Specificationsubelttal. ,

1 C 15 Control of Heavy Leads Phase !! 06/28/05 06/21/15 thVall0612)

D 01 Long fue Contaiennt Prograe 05/06/05 Rutut 011 Fission Product Release for High 10/13/71 N/A h8R aborted MPA. No turnupofLbRFuel requirenntsissued.

D 14 Reactor Vessel Atypical Weld N/A N/A hRC$1MSliststatesthisnas Material llW genuit concun. MPA sdsequentlyclosed.

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C /29/88 AfiACHMENT1 SAFEff ISSUES MANA6EMENT SYSTEM UNIT 1 TMIITEM MPA 0 ISSUE IMPOSli!0N IMPLEMENTAi!DN REMARKS DATE DATE D-15 HELI and Consequer.tial Systee 02/02/84 N/A mR cloud MPA.

Failure 0 16 Revite of Corporate Capabilities N/A NRR aborted MPA. Nochanges imposed on licsnin.

D17 Clarification of ' Operability' 02/06/81 02/06/81 D-19 Diesel Generator Reliability 08/19/88 Technical Specifications (SL 8415) 020 MarkiDrywellVacuusBreakers 11/25/86 Restart lapleoentationdatebasedon (6L 83-01) TVA letter dated 01/29/17.

E01 Spent Fuel Pool Espansion N/A NRCclosedMPAin'92.

E 03 Reload Aeendeent N/A WRC closed MPA in '12.

E04 SingleLoopOperation N/A NRR aborted MPA.

l.A.1.1.4 F-01 Long-TereSTARequirteents 01/15/82 01/15/82 1.A.I.3.1 F 02 Shift Overtise Lisits 02/26/86 02/26/86 1.A.2.1.4 F-03 Upgrading R0 and SR0 fraining 10/12/83 10/12/83 1.C.l.2.4 F 04 InadequateCoreCooling 02/09/83 06/07/84 Ongoingissuebeingaddressed byBWR06. !aposition U te accordingto$ERof6eneric Letter 1305.

1.C.1.2.1 F 05 Energency Operatirg Procedure 02/09/03 Restart leposition date according to

, Review SER of 6eneric Letter 13 05.

l.C.5 F-06 Operating Esperience Feef tack 12/09/11 12/01/11 Progras

!.C.6 F 07 0;erationalPerformance  !!/08/81 04/13/12 Verification l.D.1.1 F 01 CetailedControlPoosDesign Refuelll

, Revite Progras Plan I.D.I.2 F 71 tetailed Control Roce tesign 12/30/06 Revies lunary Report 1.0.2 F 09 lafetyParanterDisplaySystes Restart

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CD/29/II ATTACHMENT 1 SAFEtyIS$UESMANAGEMENTSYliEM UNiii TRIITER MPA 6 Illut IMPOSITION IMPLEMENT 4f104 RERARKS DATE DATE 11.1.1 F-10 RCS High Point Vents 08/02/02 06/02/12 ,

!!.l.2.2 F il Plant Shielding Modifications 03/08/03 03/08/03

!!.l.3.2 F-12 Post Accident laspling 05/27/87 Restart Modificati .a II.I.4.1 F-13 Training for Mitigating Core 10/12/83 10/12/13 .

Casage 11.9.1.2 F-14 ReliefValveandSafetyValve 09/01/03 09/01/13

Testing ll.E.4.1.2 F!I Dedicated Hydrogen Penetrations 05/23/10 05/23/88 TV4 understands this to be the dedicated hydrogen penetration single failure proof issue only.

1 II.E.4.2.6 Fit ContaineentIsolation 07/01/95 07/01/15 legendability

!!.F.1.1 F 20 Noble 6as Monitor Restart II.F.1.2 F-21 lodineandParticulateSaeoling Restart i ll.F.1.3 F 22 Costaln unt High Range Monitor Restart f

!!.F.1.4 F 23 Contalnunt Pressure 06/16/03 Restart Instrueentation

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!!.F.1.5 F-24 ContaineentNaterLevel 06/16/13 Restart j Instrueentation 1

!!.F.1.6 F 25 Containeent Hydrogen Ponitor 06/16/03 Restart

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!!.F.2.3 F 26 InadequateCoreCooling 11/11/86 Restart Instrueentation  !

i ll.K.3.3 F 38 Report on Relief and Safety Valve 03/31/12 05/30/14 ,

Failures II.K.3.13 F 43 HPCI and RCIC Initiation Levels 09/11/13 Restart

!!.K.3.ll F45 IsolationofHPCIandRCIC 06/30/12  !!/12/83

, ll.K.3.16 F 46 Relief Valves Cha!!enges and 11/13/84 03/16/85 Last ECN coesloted on j Falleres 03/16/05.

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'C/29/00 AliACHMEhi !

SAFETY ISSUES MANAGEMENT SYSTEM UNii l TMIITEM frA i IllVE IMPOSITION IMPLEMENTAi!ON REMAAtt DATE DATE

!!.K.3.17 F-47 feergency Core Cooling Systes 08/24/83 06/24/13 Outages ll.K.3.ll F 48 ADSActuationStudy Restart

!!.K.3.lt F 49 Recirculation Pues Interlock 04/22/83 DFu has jet pumps.

Modification.

II.K.3.21 F 50 PostartofCoreSprayandLPCI 10/26/82 07/29/83 lopleoentationdatebasedon Inspection Keport 13 23.

!!.K.3.22 F-51 RCIC luction Modifications 07/27/84 07/27/I4

!!.K.3.24 F-52 Adequcy of Space Cooling for 11/10/82  !!/10/12 HPCl/RCIC

!!.K.3.25 F 53 Peeer to Puep Suls 01/25/83 01/25/83 II.K.3.27 F-54 Caeson Reference Lnel 12/30/82 12/30/82 Incorporated into ! tee 1.0.1.

!!.K.3.21 F 35 QualificationofAccueulaterr, 07/24/85 Refuel 16

!!.K.3.30 F 57 $sallloreLOCAAnalysis 12/28/83 12/28/83

!!.K.3.31 F 58 Cospliance with 10 CFR 50.46 12/21/93 12/28/83 II.K.3.44 F-59 TransientswithSingleFailures 12/29/81  !!/29/91 II.K.3.45 F 60 PanualCepressuritation 05/ll/P3 07/29/83 lealesentationdatebasedon Inspection Report 13 23.

Confirsatory Order dated

!!!.A.I.2 F 63 Technical Support Center 06/12/14 Restart 06/12/14 isthebasisfor i facesittee date. This ites is coepleteenceptfor$PDS

! lepi m ntation.

!!!.A.I.! F 64 Operational Support Center 06/12/14 06/12/84 Confirsatory Order dated 06/12/14 is the basis for topositionandtopleoentation dates.

111.4.1.2 F 65 Energency Operations Facility 06/12/04 06/12/14 Confirsatory Order dated 06/12/14 lathebasisfor

incosition and lealesentation dates, i  !!!.A.2 F 66 haclearCataLint 04/15/13 This date is based on TVA letter dated 04/15/13.

Page C . 9 BROWNS FERRY NUCLEAR PLANT (BFN)

C/29/00 ATTACHMENT 1 SAFETYll8UESMANAGEMENTSYSTEM UNITI TMIITEM MPAi IllVE IMPOSITION IMPLEMENTATION REMARKS DATE DATE Ill.A.2.1 F 67 Energency Plan upgrade 05/11/13 05/11/83 111.A.2.2 F 68 PeteorologicalDataUpgrade 05/04/07 lapleoentationdatebasedon seeting with NRC and TVA staffs as reported in hRC letter dated 05/04/17.

!!!.D.3.3 F 69 Inplant Radiation Monitoring 02/22/12 02/22/12

!!!.D.3.4 F 70 Control Roos Habitability 08/30/12 04/30/12 i

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C/29/08 AliACHMENT 2 SAFETYISSUESMANA6EMENTSYSTEM im!T 2 TM!li[M MPA 6 ISSUE IMPOSITION IMPLEMENTAil04 REMARKS DATE DATE A-01 10CTR50.55A(6)-Inservice Restart Insuvice inspection for first inspection ten year intuval will be coepleted before restart according to TVA letter dated 03/01/88. This is an ongoing effort.

A-02 10CFR50 App.1 RETI and RERS 02/05/87 02/05/97 A-03 SecurityPlan 02/23/79 02/23/79 A-04 Containeent Leat Testing - Restart 10CFR50 App.J A05 Mark i Short fers Prograe 12/08/78 12/08/78 A-06 Respiratory Protection Progras 10/11/19 10/11/19 A08 LPCIModifications 05/11/79 04/18/87 ECNcospl'ted 04/18/87.

A-09 ReactorVesselGeltlineMaterial 02/06/81 02/06/81 NRRclosedthisMPAby Surveillance intunal hRC lettu dated 05/19/80 sithoutisposing requirteents. According to discussions eith 6. 6 ears, seendeentshouldbelistedfor lealesentationdate.

4 10 SafeguardsContingencyPlanRevies 06/19/81 06/19/81 A ll GuardTrainingPlanRevies 06/15/81 06/15/81 A12 Vital Area Analysis N/A hAR closed 19A in 04/82.

A 14 Intervice Puse and Valve festing 03/25/88 This lepleaentation date is Progras based on the TVA subelttal to 1

NRCdated 03/25/88. Assiting I

i fechnical Specification seendeent free hRC. Thisis an ongoing effort.

A15 Dinel 6enuator Fuel Oil GA 12/04/87 Last general revision of procedure that assigned die" :

' fuel oil a QA status is use!

l 4 leplesentationdate.

Pertor.nel Gualifications G4/00 03/17/82 03/17/82 l A 16 l

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Page C. 2 BROWNS FERRY NUCLEAR PLANT (BFN) 08/29/88 AliACHMENT 2 SAFETYISSUESMANA6EMENTSYSTEM UNIT 2 iM!! TEM MPA 4  !$$UE IMPolli!0N IMPLEMENTATION REMARtl DATE DATE A l? InstrueentationtoFollosthe Refuel 66 CourseofanAccident-Al1.97 A-11 10CFR50.726.73 Reporting 05/30/84 05/30/84 Requireeents A 19 HydrogenControl 02/12/88 Refuel 96 lateriesodificationisin place.

A-20 10CFR50.62Atul Restart I 01 Diesel Generator Lockout 07/15/82 07/15/12 1 05 Stress Corrosion Cracking in SW Restart Technical Spullications mitt RCS (WUREl 03131 be subsitted before restart according to TVA letter dated 08/Cl/18.

I-06 lafety/ReliefValveSurveillance N/A NRR aborted MPA sithout leposingrequireeents.

116 Energency Plan Revies N/A hRR tereinated -

04/0!/81. MPA- opened to continuework.

317 Hydraulic Snubber: 05/24/82 05/24/82 120 ContaineentLeakageDuetoSeal 08/25/80 09/25/80 lepolitionandispleuntation Ceterioration dates based on internal NRC eteo dated 01/11/96 shore MPAt 1 20 was made part of MPA4 3 24.

121 Less of 125V DC lus and Annunciator 05/25/82 N/A hRR closed MPA.

Systes 1 22 PechanicalSnubbers 35/24/82 05/24/12 1 23 Cegradation of 6rld Voltage 09/03/11 09/03/11 Werkisfieldcoeplete.

124 Containunt Vent and Purge 07/d1/85 07/01/85 Thisitseincrrporatedisto Ites!!.E.4.2.6(MPA4Fif) 125 feedssterandCROheriteCracking 06/06/84 Restart 127 OfigasEsplestonPrevention(lll 01/22/79 01/22/79 78-03)

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C/29/00 AffACHRENT2 SWETYISSUESMANAGGINTSYSTEM UNIT 2 TMIliEM MPA 6 IllVE IMPOSIT10N IMPLEMENTAi!ON REMARKS DATE DATE I 41 Fire Protection - 10CFR50 App. R Restart 3 42 iM1 Follou-Up Nork (IEl 79 01) 12/27/79 12/27/79 According to discussion with

6. Gears, MPA 'overtakei' by NUREE0737.

1-44 Dedicated Hydrogen Penetrations & N/A N/A According to discussion eith Recoebiner (2.1.5.A,C) 6. Sears, MPA ' overtaken' by NUREG-0737.

3-44 Control Roos Access, TSC, OSC N/A N/A According to discussion eith (2.2.2) 6. Sears, MPA ' overtaken' by NURf6-0737.

3 44 High Range Radiation Monitors N/A N/A According to discussion eith (2.1.8.8) 6. Gears, MPA ' overtaken' by NURf6 0737.

1 44 Post Accident Saeoling (2.1.1.A) N/A N/A According to discussion eith

6. Gears, MPA 'overts an' by WE6-0737.

1 44 Shielding Revies (2.1.6.0) N/A N/A According to discussion eith 6.6 ears,MPA' overtaken'by ME6-0737.

l l 44 Core Cooling Instrueentation ll/A N/A According to discussion eith

(2.1.3.8) 6.6 ears,MPA' overtaken'by ME60737.

1 44 Relief & Safety Valve festing N/A N/A According to discussion eith (2.1.21 6.6 ears,MFA' overtaken'by ME6-0737.

144 DiverseContaineentIsolation N/A N/A According to discussten eith (2.1.41 ,

6.6 ears,MPA' overtaken'by WEG-0737 3 44 Shif t Supervisor Responsibilities, N/A N/A According to discussion eith STA, furnover Procedures (2.2.1. A, 6.6 ears,MPA' overtaken'by 1,Cl OEE0737.

1 44 leprovedlodineInstrueentation h/A N/A Accordingtodiscussioneith (2.1.1.C) 6. lears, MFA ' overtaken' by WEG0737.

3 44 Valve Position Indication (2.1.3. Al N/A N/A According to discussion eith 6.lears,MFA' overtakes'by GE60737.

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AffAr,HMENT2 SAFETY ISSUES MANAGEMENT SYSTEM talf 2 TMIITEM MPA 0 ISSUE IMPOSifl0N IMPLEMENTAi!ON REMARKS DATE DATE l44 Systee Integrity for Hig'i N/A N/A According to discussion eith Radioactivity (2.1.6.A) 6. Sears, MPA ' overtaken' by NUREG-0737.

145 Prieary Coolant Systu Pressure 01/01/60 08/01/00 IsolationValves 1 46 lE Turbine Disk Analysis 05/16/10 N/A hRR aborted MPA without leposingrequireeents.

341 Distribution Systu Adequacy 07/31/05 07/31/85 158 Scras Discharge Value Capability Restart 1 59 Masonry Hall Design (!El 80 11) 06/27/84 Rntart I60 EGofSafetyRelatedElectrical Restart Equipeent 3 61 LossofNon!EIncPoserEvaluation 10/10/85 LastECNclosedon 10/10/85.

(!El 19 27) 162 ESF Reset Controls (!El B H 4) Restart I63 Stationllackout 12/02/81 12/02/91 365 Pipe Breaks in Id Scras Systes 01/03/86 01/03/06 l 70 Monitoring RCS Fatiqu Transient 05/23/82 N/A NRA closed MPA.

Lleits I72 TMITechnicalSaecifications 05/23/18 loolenn.stiondateisthe datelastissueclosed.

I76 Post trip Revin Prograe (R 13 20 06/17/05 06/11/05 Ites1.1) i l77 EquipHnt Claslification b Vendor 01/13/07 InfleeHtation date band on Interf ace (R 83 21 Ites 2.1) last general revision of FMP 0601.01.

178 Post Paintenance Testing 03/23/88 Rutart Procedures / Vendor (6L 03 29 Ites 3.1.163.1.21 j I 79 PostMaintenancefestingofRPI 10/27/06 10/27/06 (R 83 21 Ites 3.l.3)

a  ;

Page D. 5 BROWNS FERRY NUCLEAR PLANT (BFN)

C/29/II AfiACHMENT2 SAFETYISSUESMANA6EMENTSYSTEM l*li 2 iMIITEM MPAI ISIVE IMPOSITION IMPLEMENTATION REMARKS  !

DATE DATE l93 NUREl-0737 Technical Specifications 08/19/16 ' Refuel 16 (R 83 34) 114 StainlessSteelPipeInspection 01/25/88 6eneric Letter 64 11 (R 84-11) superceded by 6eneric titter 88-01. This ites incorporated intoMPA43-05.

115 Post trip Revies capability 06/12/15 06/12/05 (R 83 21 Ites 1.2) 106 Equipeent Classification & Vendor 03/05/17 lopl uentation dated based on Interf ace (R 13 21 ltee 2.2) TVA letter dated 03/05/17.

AealtingRA!orSER.

117 Post Maintenance inting (R 13 20 03/23/00 03/23/00 Ites3.2.1&3.2.2) 1 10 TechnicalSpecificationsfor 10/27/06 10/27/06 Post Maintenance futing (R 13 28 Ites3.2.3) 3 92 ReactorTripfesting(6l,1320 03/23/11 03/23/68 Ites 4.5.11 113 Reactor Trip Functional Test (6L 09/02/06 lealesentation date for itse 1328Itees4.5.264.5.3) 4.5.2only. Awaiting RAI or SERforItes4.5.3.

C02 ATuS Recirculation Pues trip Restart C10 Control of Heavy Loads - Phan ! 06/06/14 Ref ul 16 (WV9El-0612) i.

l C il PPIPo.erSupply 06/27/05 06/27/05 Modificationtoeplete. Testing tobedoneafterrestartto supportTechnical Specificationsutaittal.

C 15 Control of Navy Leads Phan !! 06/21/95 06/21/15 (WVREl1612)

I l 01 Long Tere Contalennt Progros 05/06/05 Restart 011 Fission Product Release for With 10/13/71 N/A hRR alerted MPA. No istnus of LeR Foi requirenats issud.

014 posttervesselAtysicalsels 4/4 N/A hRC SIRI list stat n this was i Material 16W generic concern. RFA sdutantly cloud.

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Page C. 6 BROWNS FERRY NUCLEAR PLANT (BFN)

C/29/88 ATTACHMENT 2 SAFETY ISSUES MANA6EAENT SYSTEM UNIT 2 TM! ITEM MPA 8 Illut IMP 0lli!0N IMPLEMENTAi!ON REMARK 8 DATE DATE D 15 HEL8 and Consequential Systu 02/02/84 N/A NRR closed MPA.

Failure D16 Revlee of Corporate CapabilitlH N/A NRR aborted MPA. No changes imposedonlicensee.

D17 Clarification of 'Oprability' 02/06/81 02/06/81 019 Diesel Senator Reliability 08/19/08 Technical Specifications (6L 84-15)

D20 MarkiDrynliVacuustreakus 11/25/86 01/29/87 !apteentation date based on '

(6L83-08) TVA letter dated 01/2f/87.

E 01 laut Fuel Pool Espansion N/A NRC closed MPA in '82.

E-03 Reload Aeendeent N/A hRC closed MPA in '82.

E04 lingleLoopOperation N/A NRR abortet MPA.

l.A.l.l.4 F 01 Long Ters STA Requiresets 01/15/82 01/15/82

!.A.I.3.1 F 02 Shift Overtise Lisits 02/26/86 02/26/86 1.4.2.1.4 F 03 Upgrading R0 and SRO Training 10/12/83 10/12/83 1.C.I.2.A F 04 Inadegaste Core Cooling 02/09/83 06/07/84 Ongoingissuebeingaddressed byBWR06. lepositiondateper SER of 6pult Letter 83 05. ,

!.C.I.2.8 F 05 foergency Operating Procedure 02/09/83 Restart !scosition date per $ER of Revieu 6enericLetter4305.

l.C.$ F-06 Operating Esputece feedtsch 12/08/81 12/01/81 Progras l 1.C.6 F 07 Operational Fuf orence 12/08/81 04/13/82 l Verification 1.D.l.1 F08 Cetailed Control Roce Design Refuel 17 Pavita Progras Plan

!  !.D.I.2 F 71 Cetailed Control Roos design 12/30/16  !

Revies fuesary Report i

1.0.2 F 09 lifety Parentu Displar Irstee Refuel 16 ,

($P05)  ;

Page No. 7 BROWNS FERRY NUCLEAR PLANT (BFN) ,

CD/2f/tt ATTACHREhi2 SAFEif!$$UESMANAGEMENTSYSTEM (M!i 2 TMIITEM MPA 8 IllVE IMPOSITION IMPLEMENTAi!04 REMARKS DATE DAlt

!!.I.1 F 10 RCS High Point Vents 01/02/82 01/02/12

!!.B.2.2 F il Plant Shielding Modifications 03/09/83 03/09/13 11.l.3.2 F 12 Post Accident Saapling 05/27/11 Refuelle Modifications 11.1.4.1 F 13 Training for Mitigating Core 10/12/03 10/12/13 Dasage 11.0.1.2 F 14 ReliefValveandSafetyValve 09/01/13 09/01/13 Testing

!!.t.4.1.2 F il Dedicated Hydrot u Pecetratises 05/23/10 05/23/81 IVA undwstands this to be the dedicatedhydrogenpenetration singlefailureproofissue only.

!!.t.4.2.6 F it Contatnuntisolation 07/01/15 07/01/05 Cepudability ll.F.1.1 F 20 Noble 64sMonitor Rutart

!!.F.1.2 F-21 lodineandParticulateSaepling Restart

!!.F.1.3 F 22 Containent Hip Ruge Monitor Restart

!!.F.1.4 F 23 Containunt Pressure 06/16/93 Restart Instruentation ,

II.F.I.5 F 24 Containunt Wate Level 06/16/13 Restart Instrunntation

!!.F.1.6 F 25 Containant Hydrogen Monitor 05/16/13 Restart

!!.F.2.3 F 26 InadetwateCoreCooling 11/11/16 Restart Instrueentation e

!!.t.3.3 F31 Report en Relief and Safety Valve 03/31/12 05/30/14 Failures c i

!!t.3.13 F43 HPCI ed RCIC Initiation Level: 09/1t/13 Rutart ,

I  !!.t.3.15 F45 liolattu of HPCl ud RCl*, 06/30/12 03/11/13

!!.K.3.16 F 44 Relief Valves Chall e ges ud 11/13/84 03/16/l$ Last (C4 cculeted on t Failurn 01/16/15.

1 i

Pep C. I BROWNS FERRY NUCLEAR PLANT (BFN) 08/29/00 AffACHMENT2 SAFETyISSUESMANAGEMENTSiliEM UN!i2 iMIITEM MPAi ISSUE IMPOSITION IMPLEMENTAi!0N REMARtl DATE DATE II.K.3.17 F 47 h:/gency Core Coeling Systes 08/24/13 01/24/13 Outages

!!.t.3.il F 41 ADSActuationStudy Restart II.K.3.lt F 49 Recirculation Puep Interlock 04/22/83 IFNhasjetpumps.

Medification.

II.K.3.!! F 50 RestarteiCoreSprayandLPCI 10/26/12 07/21/13 !apteeentationdatebasedon Inspe< tion deport 13 23.

!!.t.3.22 F 51 RCIC Suction Modifications 07/27/14 07/27/14

!!.t.3.24 F 52 AdecuacyofSpaceCoolingfor 11/10/12 11/10/12 HPCl/RCIC i  !!.t.3.25 F 53 Power to Pues Seals 01/25/13 01/25/13

!!.t.3.27 F-54 Coeson Reference Level 12/30/12 12/30/82 lacorporated into itee !.I.1.

II.K.3.21 F35 Gualification of Accusolators 07/24/15 Refie!96 Intertesostfications I installed until permanent sodiilcationisinplace.

!!t.3.30 F 57 Seill lore LOCA Analysis 12/21/13 12/28/13

!!.K.3.31 F SI Coeofiance eith 10 CFR 50.44 12/21/13 12/21/13

!!.t.3.44 F 59 fransients with $1ngle Failures 12/21/11 12/29/11 ll.K.3.45 F60 M uual Depressuritation 05/11/13 07/29/13 lopleoentation date based on Inspection Report 13-23.

Ill. A.'.2 F 63 Techaical Support Center 06/11/14 Refuel 96 Confireatory Order dated <

l 06/12/14 is the basis for imposition date. This ites coeplete except for SPDS toplpentation.

!!!.A.l.2 F 64 Operational Support Center 06/12/14 06/12/14 Confireatory Order dated 06/12/14 is the basis for imposition anJ impleuntation l bles.  ;

!!:,A.I.! F65 Ea:rgecy Curations Facility C6/12/14 06/12/14 Confireatory Order dated i j 04/12/14 isthebasisfor inociition and lepi nentation dates.

f

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Page t'. 9 BF.0WNS FERRY NUCLEAR PLANT (BFN)

C/21/80 AllACHMENT2 SAFETYISSUESMANA6EMENTSYSTEM lMIT 2 TMI!!EM MPA i IB8UE IMP 091T!0N IMPLEMENTAi!ON REMARKS DATE DATE

!!!.A.2 FH helear Data Link 04/15/03 ThisdateisbasedonTVA letterdated 04/15/03.

Ill.A.2.1 F 67 Energency Plan upgrade 05/11/13 05/11/13 Ill.4.2.2 FH MeteorologicalDataUsgrade 05/04/17 lased on setting with NRC and TVA staHs as reported in NRC letterdated 05/04/17.

!!!.D.3.3 F 69 inplaat Radiation Monitoring 02/22/12 02/22/92

!!!.D.3.4 F-70 Control Rooe Habitsbility 08/30/12 01/30/12 5

e I

t

I BROWNS FERRY NUCLEAR PLANT (BFN)

Aff.iCHMENT3' SAFETY!$$UESMANA6EMINTSYSTEM UNIT 3 T51 ITEM MPA 6  !$$UE IMP 0lli!0N IMPLEMENTAi!0N REMARKS Daft DATE A 01 10CFR50.55All) Inservice hitart inservice inspection for first Inspection tenyearintervalmillbe coepleted before restart according to TVA letter dated 03/01/84. Thisisanongoing offort.

A-02 10CFR50 App. I - RETS and REMS 02/05/87 02/05/17 A-03 SecurityPlan 02/23/79 02/23/79 A04 ContaineentLeakTesting-10CFR50 Restart App.J A05 Mark i Short Ters Prograe 12/08/71 12/08/79 A-06 Respiratory Protection Progras 10/ll/7f 10/11/79 A08 LPCIModifications 05/11/79 04/11/07 ECN coepleted 04/11/87.

A-Of Reactor Vessel Beltline Material 02/06/81 02/06/01 NRR closed this MPA by Surveillance internalNRCletterdated 05/19/t)uithoutimposing s requirteents. According to discussionseith6. Gears, aeondeentshouldbelistedfor topleeentationdate.

A 10 Safeguards Contingency Plan Revies 06/19/11 06/19/81  ;

A-Il GuardTrainingPlanRevies 06/15/81 06/15/81 A 12 Vital Area Analysis N/A NRR closed MPA is 04/12.

A 14 laservicePuseandValvefesting 03/25/06 Thistopleoentationdateis Progras based on the TV4 subsittat to hRC dated 03/25/St. Asalting Technical Specification ,

aeondsent free hRC. This is an ongoing ef fort.

i A 15 Olesel 6cnerator Fuel Oil GA 12/04/87 Last general revision of procedure that assigned diesel fuel oil a GA status is used asleplesentationdate.

l l

A 16 Perssu el Gualifications - 04/GC 03/17/02 03/17/82 l

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Page C. 2 BROWNS FERRY NUCLEAR PLANT (BFN) 06/29/]

AliACHMENT3 SAFETY!$$UESMANAGEMENTSYSTEM (M!i 3 TMIITEM MPA I ISSUE IMP 051t!0N IMPLEMENTATION REMARKS DATE DATE A17 Instrueentation to follos the Restart Course of an Accident R6 1.97 A !B 10CFR$0.72 6.73 Reporting 05/30/84 05/30/84 Requirteents A 19 HydrogenControl 02/12/88 Refuel 66 A 20 10CFR$0.62ATuS Restart 8 01 Dinel Generator Lockout 07/15/82 07/15/82 3-05 Stress Corrosion Cracking in DuR Rutart Technical Specifications mill RCS(NURE60313) be subsitted before restart according to TVA letter dated 08/0\l88.

I 06 lafety/ Relief Val u Sur eillance N/A NRR aborted MPA mithout imposing repirtents.

M6 EnergencyPlanRevice N/A NRR tereinated MPA on 04/01/81. MPAt F 67 og n ed to continue work.

3-17 Hydraulic Snubbers 05/24/82 05/24/82 1 20 Containent Leakage Due to Seal 08/25/80 08/25/80 leposition and isolesentation Deterioration dates bated on internal NRC seen dated 08/18186 shore MPA4 3 20 was sade part of MPA8 l 24.

1 21 Loss rf 125V DC fut and Annunciator 05/25I82 N/A hRR cloud MPA.

j Iystee I 22 Mechanical Snubber 05/24/82 05/24/82 1 23 tegradation of 6 tid Voltage 03/29/82 03/29/82 Norkisfieldcoeplete.

1 24 Containunt Vent and Purge 07/01/85 07/01/85 This ites incorporated lato

!tes!!.E.4.2.6(MPA4 fit) 1 25 Fu dsater and CRD N:rtle tracking 06/06/84 10/15/84 ECNclosed 10/15/84.

3 27 Offgas Emplosion Pre nntion 08/22/79 08/22/79 I!El 7 M 31, 141 Fire Protection - 10CFR50 App. R Restart

Page b 3 BROWNS FERRY NUCLEAR PLANT (BFN)

QSI21Ita AfiACHMENT3 6 SAFETY!$$UESMANA6EMENTSYSTEM UNIT 3 TMlITEM MPA I ISSUE IMPOSITION IFLEMENTAi!0N REMARis DATE DAtt I 42 iMI Follee-Up Nork (IER 79-01) 12/27/79 12/27/79 According te discussion eith

6. 6 ears, MPA ' overtaken' by NUREG-0737.

I 44 Dedicated Hydrogen Penetrations 6 N/A N/A According to discussion eith Recoehiner 12.l.5. A.C) 6. Sears, MPA ' overtaken' by -

NURt6-0737.

3 44 Control Roos keets, TSC, OSC N/A N/A According to discussion eith  ;

(2.2.2) 6. 6 ears, MPA ' overtaken' by pti0737.

B-44 High Range Radiation Monitors N/A N/A According to discussion eith f (2.1.1.11 6. 6 ears, MPA ' overtaken' by NURt6-0737.

1-44 Post-Accident $4epling (2.1.I.Al I/A N/A According to discussion eith

6. lears, MPA ' overtaken' by UEG0737.

1-44 Shielding Revin (2.1.6.11 N/A N/A According to discussion eith

6. Sears, MPA ' overtaken' by NURil0737.

B-44 Core Cooling Instrueentation N/A N/A According ta discussion eith (2.1.3.5) 6. Sears, MPA ' overtaken' by NURE60737.

1-44 Relief 6 Safety Valve Testing N/A N/A According to discussion eith (2.1.2) 6. Sears, MPA ' overtaken' by NURE6-0737.

I 44 Diverse Containeent Isolation N/A N/A According to discussion eith l (2.1.4) 6. Gears, MPA ' overtaken' by NUREG-0731.

1 44 Shift Supervisor Responsibilities, N/A N/A According to discussion eith

STA, Turnever Procedures (2.2.1. A, 6. 6 ears, MPA 'overtaku' ty I,Cl NUREG-0737.

I 44 !acrevedlodinelastrueentation N/A N/A According to discussion eith (2.1.1.Cl 6. lears, MPA ' overtaken' by WURil0737.

1 44 Valve Posities Indication (2.1.3.N) N/A N/A According to discussion eith i 6. 6 ears, MPA 'ciertaken' by NURE6-0737.

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PageC". 4 BROWNS FERRY NUCLEAR PLANT (BFN) 08/21/00 ATTACHMENT 3 SAFETY!$5UESMANA6EMENTIVlfEM 1411 3 TRIITEM MPA i  !$$UE IMPOSITION IMPLEMENTAfl04 REMAAtl DATE DATE l 44 Systee Integrity for High N/A N/A According to discussion eith Radioactivity (2.1.6.41 6. Curs, MPA 'overtalen' by NUREl-0737.

145 Prisery Coolant Systes Pressure 01/01/10 01/01/60 IsolationValves I 46 EETurbineDiskAnalysis 05/16/10 N/A NRR aborted MPA sithout leposing requireeents.

1 41 listribution lystes Adequacy 07/31/95 07/31/05 l51 ScrasDischargeVolveeCapbility Asstart I 59 Masonry hall Design (IEI Ibtli 06/27/14 Restart 5 60 El of Safety Pelated Electrical Antart Etulpeent I 61 LossofNonIEIntPourEvaluation 07/26/02 Inspection report closed for IIES 71 271 UnitsIand3only.

362 ESFResetControls(IElIF06) Restart l 63 Itation llackout 12/02/11 12/02/11 1 65 Pipe Breats le leR Scras Systes 01/03/84 01/03/06 i I 70 MonitoringRCSFatigueTransient 05/25/12 N/A NRR closed MPA.

Lleits I -

I72 TMl technical Specifications 05/23/01 lopleuntationdateisthe datelastissueclosed.

I 76 Post trip Revies Prograe ( R 13 20 06/17/I5 06/17/15 ltee1.1) 3 17 Equip unt Classification & Vender 01/13/17 leclesentation date based on Interf ace (R 1121 Itn 2.11 last general revision et Pff 0601.01.

I71 Post Maintenance festing 03/23/11 Restart Proce bres/ Vender ( R 13 21 Itte 3.1.1 L 3.1.2) 1-79 Pcst Paintesance testing of RPS 10/27/96 10/27/96 (R 13 21 Ites 3.l.3)

P 3 BROWNS FERRY NUCLEAR PLANT (BFN)

AffACHMENT3 SAFETY!$$UESMANA6EMENTSySTEM UNIT 3 iM1 ITEM MPA 4 IllVE IMPOSITION IMPLEMERfAi!ON REMARKS DATE DATE I 13 NUREl 0737 Technical leecifications Rutut (R 13-36) ,

114 Itainten Steel Pipe Innection 01/23/18 6enwit Lettw 14 il (R I411) superceded by Geewie Letter 88 01. This ites incorporated latoMPA4l-05.

l 15 Post Trip Revies Capability 06/12/15 04/12/05 (R 83 28 Itu 1.21 1-16 EquipeentClassification& Vendor 03/05/17 lepinentationdatebasedon intef ace (R 83-28 Itu 2.2) TVA letter date 03/05/17.

AnaltingRAIorSER.

117 Post Maintenance Testing (R 13-28 03/23/08 03/23/80 Itee 3.2.1 6 3.3.2) l 3 84 Technical Specifications for 10/27/84 10/27/84 Post Maintenance inting (R 13 28 ,

Ites3.2.31 I 92 P nctor Trip Testing (R 13 21 03/23/19 03/23/88 ItM 4.5.11 ,

I 93 Rutter Trip Functional fest (R 09/02/06 lopleeentationdateforItes 1328Itees4.5.264.5.3) 4.5.2only. Asatting RAI or [

SER for It u 4.5.3. t C-02 Aful Retirculation Pue, Trip pestart C 10 Control of Heavy Leads Phase 1 06/06/04 Pestart (WUREl-0612)

C!! RPS Poew Supply 06/27/85 06t27/85 Modificationcoeclete. .

Testing to be doce after  !

restut to suppert Technical Specification sdelttal.

C15 ',cWol of Heavp Leafs Phan Il 06/21/15 06/21/15 [

(r#EE-0612) r 0-01 LongtersCentaissentProgras 05/06/05 futut l t/4 tat aborted MPA. no I 0-11 Fission Product Release for High 10/13/78 parnup of LtR Fuel requirteents issued.

1 14 Reactor Vessel Atypical belf I/A N/A hRC$1MIliststatesthissas Matutal lld generic concern. MFA sdsnuently closed.

Pagehe. 6 BROWNS FERRY NUCLEAR PLANT (BFN) 0210 t AliACHM(NT 3

$AFETY lllV(l MANA6EMENT SYlitM UNIT 3 TM! ITDI MPA 6 lilut IMPOSITION . IMPLEMENTATION REMARKS DATE DATE 0 15 HELI and Consequential Systu 02/02/04 N/A NRR closed 194. 3 Failure D-16 Revin of Corporate Capabilities N/A NRR aborted MPA. Nochanges imposedonlicenee.

l 0 17 Claritication of 'Opwattlity' 02/06/11 02/06/11 0 19 Dieul lenwater Reliability 08/11/11  ;

, Technical Specifications (SL I415)

D-20 Mart ! Drynll Vacuve trealers 11/25/84 01/29/17 !apleoentationdatebasedon (GL 13-01) TVA letter dated 01/29/17.

t-ti SpentFoolPoolEspansion N/A NRC closed MPA in 'I2.

E-03 Reload Asen hent N/A NRCclosedMPAin'92.

E04 lingle Loop Operation N/A NRR aborted MPA.

1

!.A.1.1.4 F 01 L xg Tere ITA Reestreeents 01/15/12 01/15/12

(

l.4.1.3.1 F 02 lhif t Overtise Lietts 02/26/84 02/26/06

!.A.2.1.4 F-03 Upg,ading R0 and IRO Training 10/12/13 10/12/83

!.C.I.2.A F 04 Inadequate Core Ccoling 02/09/13 06/07/14 Ongoinginnebeingaddressed ,

by But06. lopetitiondate  !

according to $(R of lenetic  !

Lettw 13-05. j

!. Col.2.8 F-05 Energency Operating Procedere 02/09/13 Restut leposition date according to Situ SERofGenericLetter1305, t 1.C.5 F-06 Oswating Esperience Feedback  !!/01/11 12/01/11 Progras

1.C.6 F 07 0;erational Pwicreence 12/08/I. 04/13/12  !

! Vrification j

I.0.1.1 F-Cl Detailed Control Roos tesign Refuel 47 l Revin Progree Plan j 1

I.I.l.2 F 71 Detailed Control Rose tesign  !!/30/14 l, Revin lunur Report l 1.8.2 F 09 !afety P u ante Disslay lystee Restut i (SP!$)

I

Page D. 7 BROWNS FERRY NUCLEAR PLANT (BFN) 04/29/] "

Aff4CHPENT3 SWETY 158Utl MANAGEMENT SYlitM UNIT 3 TMI litM MPAi 158UE IMP 0$! TION IMPLEMENTAi!04 REMAAtt Daft DAff 1i.1.1 F 10 RCSHighPointVents 01/02/12 08/02/12 11.1.2.2 F il PlantShieldingModifir;tions 03/01/13 03/04/13 II.I.3.2 F 12 Post Accidect leepling 05/27/17 Antart Modifications  ;

!!.I.4.1 F13 fraining for Mitigating Core 10/12/83 10/12/83 Casage 11.0.l.2 F 14 Relie!ValveandSafetyValve 09/01/03 09/01/13 inting II.E.4.1.2 Fil tedicatedHydrogenPenetrations 05/23/06 05/23/18 TVA understands this to be the dedicatedhydrogenpenetration singlefailureproofissue only.

!!.t.4.2.6 F It Containeent isolation 07/01/85 07/01/05 Dependability

!!.F.l.1 F20 ho61e las Monitor Restart

!!.F.I.2 F21 lodineandParticulatelaspling Restart II.F.l.3 F 22 Containant High Range Monitor Ruttet II.F.1.4 F23 Containeet Frenure 06/16/03 Rutart  ;

i lettrueentation ll.F.1.5 F 24 Contaireent Water Level 06/16/93 Rutart Instruentation

!!.F.I.6 F 25 Containeet Hydrogen Monitor 06/16/13 Rutart II.F.2.3 F 26 InadequateCoreCocling 11/11/96 Rutart lastrueentation II.K.3.3 F 31 Report on Relief and Safety Yahe 03/31/12 05/30/14 Failurn

,  !!.t.3.13 F 43 kPCIandRCICInitiationtevel: 09/19/03 Putart

!!.t.3.15 F 45 lulation of hPCI and RCIC 06/30/12 06/30/12 hRC isind Technical l Specificationanndunton 03/29/12.

f  !!.K.3.16 F 46 Relief Valvn Challenges and 11/13/84 03/16/05 LutECNcoe;1stedon

Failures 03/16/15.

i

P9O I EROWNS FERRY NUCLEAR PLANT (BFN) 06/29C ATTACHMENT 3 SAFETY ISSUES MANAGEMENT SYliER LMIT 3 TM! ITEM MPA i  !$$UE IMPOSITION IMPLEMENTAi!0N REM 4AKS DATE 04tt

!!.K.3.17 F 47 Energency Core Coeling Systu 01/24/13 08/24/13 Outages

!!.K.3.ll F 41 ADS Actuation Study Restart

!!.K.3.lt F 49 Recirculation Pues Interlock 04/22/13 DFNhasjetpueps.

Modification.

!! M 3.21 F 50 RutartofCoreSprayandLPCI 10/26/12 07/21/13 lealeontation date band on Inspection Report 13-23.

!!.K.3.22 F-51 ACIC Suction Modifications 07/27/14 07/27/I4

!!.K.3.24 F 52 Adequacy of Space Coc!!ng ior 11/10/12  !!/10/12 IfCl/RCIC ll.K.3.25 F 53 Po wr to Puse Seals 01/25/13 01/25/13

!!.K.3.27 F 54 Coeson Refernce Luel  !!/30/12 12/30/12 Incorporated into ItH I.I.l.

!!.K.3.21 F 55 lualificationofAccusalaters 07/24/85 Refuel 46

!!.K.3.30 F 57 lull lore LOCA Analysis 12/21/13 12/21/13 II.K.3.3! F-51 Coopliance with 10 CFR 50.46 12/21/13 12/21/13 II.K.3.44 F 59 fransients eith Single Failures 12/29/11 12/21/11 II.K.3.45 F 60 Manual Deprnsartistion 05/11/13 07/29/13 loplewntationdatebasedon Inspection Report 13-23.

Ill.A.l.2 F-63 Technical $ciport Center 06/12/14 Restart Confireatory Order dated 06/12/64 isthebasisfor leposition date. This ites is coeplete utest for SPDS ispInentation.

!!!.A.1.2 F 64 Operational Support Cuter 06/12II4 06/12/14 Confirmatory Order dated 06/12/14 is the basis for incosition and impleoestation dates.

!!!.A.l.! F 65 E ntgency Operattens Facility 06/12/14 06/12/14 ConfireateryOrderdated 06/12/14 is the tesis for taputtien and topleoentation dates.

!!!.A.2 F 66 haclear Cata Lint 04/15/13 This date is based on TVA letterdated 04/15/13.

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Pagelie. I BROWNS FERRY NUCLEAR PLANT (BFN)

N/29/]

. ATTACHMENT 3 SAFliY ISSUES MANAGEMENT SYlfEM Ull!T 3 iMIITEM MPA 4 IllVE IMPolli!0N IMPLEMENTAi!0N REMARKS DATE DATE

!!!.A.2.1 F 67 toergency Plan upgrade 05/11/03 05/11/03  :

!!!.A.2.2 F64 Meteorological Data Upgrade 05/04/17 lepleeentationdatecasedon seettag eith NRC and TVA stalls as reported la llRC letterdated 05/04/07.

111.9.3.3 F 69 inplant Radiation Monitoring 02/22/12 02/22/12

!!!.D.3.4 F-70 ControlRoosHabitability 08/30/12 08/30/12 4

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