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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18039A8811999-09-28028 September 1999 Proposed Tech Specs Re Increased MSIV Leakage Rate Limits & Exemption from 10CFR50,App J ML18039A8241999-07-28028 July 1999 Proposed Tech Specs Providing TS for Operation of Oscillation PRM Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A8001999-06-0303 June 1999 Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions ML18039A6991999-02-22022 February 1999 Proposed Tech Specs & Bases Pages Incorporating NRC Approved TS Change 354,requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6601998-12-15015 December 1998 Proposed Tech Specs,Revising pressure-temp Curves to Extend Validity of Curves to 32 EFPY ML20206F8131998-12-0303 December 1998 Rev 12 to ODCM, for BFN ML18039A5041998-09-0808 September 1998 Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys ML18039A5001998-09-0404 September 1998 Proposed Tech Specs Re Use of Containment Overpressure for ECCS Pump Net Positive Suction Head Analyses ML18039A4791998-08-14014 August 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-33, DPR-52 & DPR-68 to Change Ts.Proposed Changes Decrease Frequency of once-per-cycle Instrument Calibrations by Substituting 24 Months for 18 Months ML18039A4611998-07-31031 July 1998 Proposed Tech Specs B 3.6-2,B 3.6-7 & B 3 3.7-2 for Power Uprate Operation Omitted Pages ML18039A4481998-07-17017 July 1998 Proposed Tech Specs,Adding LCO 3.4.10 & Accompanying TS Bases Provisions from Improved TS-362 Conversion Package as Adapted for Power Uprate Conditions ML18039A4091998-06-26026 June 1998 Proposed Tech Specs Section 3.4,allowing Units 2 & 3 to Operate at Uprated Power Level of 3458 Mwt ML18039A4021998-06-19019 June 1998 Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS ML18039A3921998-06-12012 June 1998 Proposed Tech Specs Change 390,decreasing Frequency of once-per-cycle SRs by Substituting 24 Months for 18 Months in Affected TS SRs ML20249A5661998-06-10010 June 1998 Proposed Tech Specs Section 5.0,revising Administrative Controls ML20248C5151998-05-27027 May 1998 Proposed Tech Specs Section 3.8.1,revising AC Sources- Operating ML18039A3181998-04-16016 April 1998 Proposed Rev 2 to Tech Specs Section 3.6, Containment Systems, Converting from Current TS to Improved TS ML18039A2711998-03-16016 March 1998 Proposed Tech Specs Re Power Uprate Operation ML18039A2671998-03-13013 March 1998 Proposed Tech Specs,Converting to Improved Std Ts,Per NUREG- 1433,rev 1, Std TS for GE BWRs (BWR/4). ML18039A2641998-03-12012 March 1998 Proposed Tech Specs ITS Section 3.8 Re Electrical Power Sys. ML18039A2611998-03-0303 March 1998 Proposed Tech Spec Changes TS 393 Re Reactor Vessel Pressure Temperature Curves ML20199E8051998-01-23023 January 1998 Proposed Tech Specs Section 5.0 Re Administrative Controls ML18039A2401998-01-15015 January 1998 Bfnp Unit 2 Cycle 10 Power Ascension Test Program Start-Up Rept, for Period 970929-1105 ML18039A2221997-12-30030 December 1997 Proposed Tech Specs Re RHR SW Pumps Required for multi-unit Operation & Cold Shutdown ML18039A2151997-12-23023 December 1997 Proposed Tech Specs Section 3.7 Re Plant Sys ML18039A2181997-12-22022 December 1997 Proposed Tech Specs Section 3.8 Re Electrical Power Sys ML20217P5051997-12-0808 December 1997 Rev 10 to ODCM, Containing Markups to Rev 9 & 10 ML18039A2101997-12-0404 December 1997 Proposed Tech Specs Pages Re TS Change 362,suppl 7 Re ITS Section 3.1, Reactivity Control Sys. ML18039A2071997-12-0404 December 1997 Proposed Tech Specs Pages Re Suppl 9 to TS Change 362, Including Rev Pages to Improved TS Section 3.5 ML18039A2011997-12-0303 December 1997 Proposed Tech Specs Section 3.9 Re Refueling Operations & Section 3.10, Special Operations. ML18039A1981997-12-0303 December 1997 Improved Tech Specs Pages Re Section 5, Administrative Controls. ML20199D5471997-11-14014 November 1997 Proposed Tech Specs Section 3.0, Limiting Condition for Operation (LCO) Operability & Section 4.0, Design Changes ML20199E1361997-11-14014 November 1997 Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys ML20198Q4521997-11-0505 November 1997 Proposed Tech Specs,Incorporating Improved TS (ITS) Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions ML18038B9611997-10-0101 October 1997 Proposed Tech Specs,Allowing Bfn,Units 2 & 3,to Operate at Uprated Power Level of 3458 Mwt ML18038B9361997-08-15015 August 1997 Proposed Tech Specs,Extending Existing 7-day EDG Allowed Outage Time to Fourteen Days ML20210V1171997-07-29029 July 1997 Qualification Plan & Rept MIL-STD-462D,CS114,Conducted Susceptibility,Bulk Cable Injection Numac Reactor Bldg Vents Radiation Monitor TVA Bfn,Units 1,2 & 3 ML18038B9061997-06-19019 June 1997 Proposed Tech Specs Supporting one-time 14-day Limiting Condition for Operation for Each EDG to Accommodate Pending Vendor Recommended Maint Activities ML20138J3781997-05-0101 May 1997 Proposed Tech Specs,Revising TS-362 Amend for Section 3.8, Electrical Power Sys Which Addresses NRC Review Comments ML18038B8651997-04-24024 April 1997 Proposed Tech Specs,Submitting Revised BFN TS Bases Section 3.5.N, References, Reflecting Updated LOCA Analyses for Units 2 & 3 ML20137U1691997-04-11011 April 1997 Proposed Tech Specs Re Pr Neutron Monitor Upgrade W/ Implementation of Average Pr Monitor & Rod Block Monitor TS (ARTS) Improvements & Max Extended Load Line Limit Analyses ML18038B8341997-03-12012 March 1997 Proposed Tech Specs Re Extended EDG Allowed Outage Time ML20136F7851997-03-0606 March 1997 Proposed TS Supporting Planned Replacement of Current Power Range Monitoring Portion of Existing Nms W/Ge Digital Nuclear Measurement Analysis & Control Power Range Neutron Monitor Retrofit Design ML20134G5401997-02-0505 February 1997 Proposed Tech Specs Revising Bases Section 3.7.A/4.7.A, Primary Containment, to Delete Wording Re Maintaining Drywell to Suppression Chamber Differential Pressure Constant for Duration of Drywell to Suppression Chamber ML18038B8281997-01-31031 January 1997 Rev 1 to GE-NE-B13-01805-22, Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3. ML18038B8111997-01-22022 January 1997 Rev 0 to Browns Ferry Nuclear Plant,Surveillance Instruction,Inservice Insp Program,Unit 3. ML20132B7401996-12-11011 December 1996 Proposed Tech Specs 2.2.A Re Safety/Relief Valve Setpoint Requirements for Reactor Coolant Sys Integrity ML20117P3341996-09-15015 September 1996 Proposed Tech Specs to Change Unit 3 TS LCO 3.6.F.1 in Order to Perform Repairs & Maint Necessary to Return RCS Recirculation Loop a to Operations ML18038B7541996-09-0606 September 1996 Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1 ML20117G7121996-08-30030 August 1996 Proposed Tech Specs Re License Condition on Compliance W/Thermal Water Quality Stds 1999-09-28
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206F8131998-12-0303 December 1998 Rev 12 to ODCM, for BFN ML20217P5051997-12-0808 December 1997 Rev 10 to ODCM, Containing Markups to Rev 9 & 10 ML18038B8281997-01-31031 January 1997 Rev 1 to GE-NE-B13-01805-22, Internal Core Spray Line Flaw Evaluation Handbook for Browns Ferry Units 2 & 3. ML18038B8111997-01-22022 January 1997 Rev 0 to Browns Ferry Nuclear Plant,Surveillance Instruction,Inservice Insp Program,Unit 3. ML20137H3251996-08-23023 August 1996 Rev 8 to ODCM for Bfn ML18038B8851996-08-14014 August 1996 Rev 8 to Surveillance Instruction 2-SI-4.6.G, ISI Program Unit 2. ML18038B7811996-04-26026 April 1996 Rev 7 to Surveillance Instruction 2-SI-4.6.G, ISI Program Unit 2. ML18038B6541995-08-12012 August 1995 Rev 7 to Odcm. ML18038B6531995-05-25025 May 1995 Rev 6 to Odcm. ML18037A8151993-11-19019 November 1993 Rev 3 to Odcm. ML18037A7681993-10-21021 October 1993 Rev 3 to Surveillance Instruction 1/3-SI-4.6.G, ISI Program Units 1 & 3. ML18037A7661993-10-21021 October 1993 Rev 2 to Surveillance Instruction 2-SI-4.6.G, ISI Program Unit 2. ML18037A8161993-10-0101 October 1993 Rev 14 to RETS Manual. ML20062L9321993-09-30030 September 1993 Test Plan GE102, Electromagnetic Interference & Susceptibility Test Plan for Rbvprm Part Number: 304A3718G001 ML18037A4471993-04-16016 April 1993 Emd Owners Group Procedure EMD9314, Recommended Maint Program. ML18036B1631993-02-16016 February 1993 Rev 1 to Surveillance Instruction 2-SI-4.6.G, ISI Program, Unit 2. ML18036B1521993-01-29029 January 1993 Rev 1 to Odcm. ML18036B1961993-01-27027 January 1993 Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training. ML20114D7161992-08-31031 August 1992 Inservice Testing Program for Pumps & Valves for Second 10-Yr Interval. Relief Requests Encl ML18036A8441992-06-30030 June 1992 Revised Odcm. ML18036A5911992-03-25025 March 1992 Rev 0 to Odcm. ML20086D5561991-11-14014 November 1991 Rev 6 to General Design Criteria BFN-50-C-7104, Design of Structural Supports ML20079C3431991-06-12012 June 1991 Design Criteria BFN-50-C-7100,Attachment F, Browns Ferry Nuclear Plant Detailed Design Criteria for Structrual & Miscellaneous Steel/Components for Class I & II Structures ML18033B6431991-02-28028 February 1991 Revised Browns Ferry Nuclear Plant Offsite Dose Calculation Manual,Jul-Dec 1990. ML18033B6121990-06-22022 June 1990 Rev 8 to Radiological Effluent Tech Spec Manual. ML18033A9191989-06-30030 June 1989 Changes to ODCM for Jan-June 1989. ML18033A6621989-03-0202 March 1989 Radioactive Effluent Release Rept Browns Ferry Nuclear Plant Rev of Process Control Program. ML20246P8801989-02-22022 February 1989 Rev 1 to Design Criteria BFN-50-C-7302, Operation Criteria for Evaluation of Lower Drywell Access Platforms ML20246H3521989-02-0101 February 1989 Maint Improvement Program, Books 1 & 2 ML18033A4391988-08-31031 August 1988 Rev 0 to Partially Deleted TVA-BCD-906N, Summary Rept for Browns Ferry Nuclear Plant,Unit 2,Cycle 6,Insp & Reconstitution Program. ML20151G7131988-07-20020 July 1988 Emergency Operating Instruction Procedures Generation Package ML18033A6611988-07-20020 July 1988 Semiannual Radioactive Effluent Release Rept Browns Ferry Nuclear Plant,Changes to Odcm. ML20153B3531988-07-0707 July 1988 Rev 1 to Ampacity Evaluation Program Plan ML18033A2701988-06-13013 June 1988 Rev 0 to Site Director Std Practice SDSP-12.7, Sys Preoperability Checklist (Spoc). ML20151B2871988-06-10010 June 1988 Safety Sys Functional Insp Plan ML18033A2801988-05-24024 May 1988 Operability Criteria for Miscellaneous Steel. ML18033A2771988-05-23023 May 1988 Operability Criteria for Evaluation of Lower Drywell Access Platforms - Browns Ferry. ML20151L4611988-05-13013 May 1988 Rev 0 to Special Test ST-88-16, Diesel Generator a Emergency Load Acceptance Test ML20151L4711988-04-27027 April 1988 Rev 0 to Special Test ST-88-17, Diesel Generator B Emergency Load Acceptance Test ML18033A2691988-04-18018 April 1988 Rev 2 to Site Director Std Practice SDSP-12.4, Return to Svc & Closure of Mods. ML20151L5051988-04-14014 April 1988 Rev 1 to Restart Test Program Test Instruction 2-BFN-RTP-082, Standby Diesel Generators ML18033A1961988-03-31031 March 1988 Rev 1 to Civil Engineering Branch Instruction CEB-CI 21.100, Brown Ferry Nuclear Class I HVAC Duct & Duct Support Seismic Qualification Interim Operability Acceptance Criteria. ML18033A1911988-03-31031 March 1988 Rev 1 to Civil Engineering Branch Instruction CEB-C1.102, Operability Criteria for Miscellaneous Steel. ML18033A1881988-03-31031 March 1988 Rev 1 to Civil Engineering Branch Instruction CEB-CI 21.97, Operability Criteria for Pipe & Pipe Supports on TVA Class I Seismic Piping - Browns Ferry. ML20148G6141988-03-25025 March 1988 ASME Section XI, Revised Pump & Valve Test Program ML18032A7391988-03-10010 March 1988 Procedure BFN 50 C 7100, Detailed Design Criteria for Structural Acceptance of Drywell Access Platforms. ML18033A1631988-03-0303 March 1988 Rev 0 to Civil Engineering Branch Instruction CEB-C1.102, Operability Criteria for Miscellaneous Steel. ML18033A1601988-02-25025 February 1988 Rev 0 to Civil Engineering Branch Instruction CEB-CI-21.100, Browns Ferry Nuclear Plant Class I HVAC Duct & Duct Support Seismic Qualification Interim Operability Acceptance Criteria. ML20150E3771988-02-22022 February 1988 Rev 4 to Design Baseline & Verification Program ML20151L4811988-01-28028 January 1988 Rev 1 to Restart Test Program Test Instruction 2-BFN-RTP-065, Secondary Containment 1998-12-03
[Table view] |
Text
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Browns Fcrry M'icle:r Plant Page 1 .
. ." Site'Dircetor standard Practica BF-SDSP-1 BF SDSP-2.11 FORM SDSP-1 REV 0001
' DP&CU Logging No. _ T'P 4 /,-O /
, PROCEDURE / INSTRUCTION CHANGE REQUEST THIS FORM SHOULD BE COMPLETED IN BLACX INX OR TYPE'.lRITT Iype of Change l l Permanent
.' 11l Temporary Change-To Becomo Permanent l 1 Temporary Change-Expiration Date (60 Days if not specified) l _l Advanced Revision
... Procedure No. l Unit l Iitle
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O [ To< <,c.do % cec >c,,a Procedo,c Reason for Revision: ~'
?"Correc.% Ic, yq poca e,.w < < d u c e. con Ce. en Eov WC P G lmeer CM id3 a.n a S'
Affected Pages b , 6 Cod 9
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SEi::titted By v Section Dato 3DJ Extension SDSP-15 has been completed and is attached (not a'pplicable for advan (od D D san ks, - f-f Pd' APPRO7ED n V Restt Sectioq Pfocedure e Date Responsible Section f A ///*ffn Responsib'le _
&gdrator u ~/~WR ionSup Date APPROVALS (STANDARD PRACTICES ONLY)
. APPROVALS (PLANT INSTRUCTIONS) y4 Progra=atic Contact * ~
g g JUL16 E
~~ . Date PORC Chairraan hh ~
Date -
JUL 1 c ;;3 QA Supervisor Dato p lant Manager Date
/J A Principal Manager
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PORC Chairman Dato Rotontion Period: Lifetico A. Rosponsibility: DP&CU Supervisor
~J' Plant Manager To be completod by DP&CU:
Revision l2lissuedatrevision
/
Sito Director
- Date l_~__ldid not rosult in change of revision level
' Required for. Site Director's Standard Practices ONLY 0181p e60e190402 860015 PDR ADOCK 0500 9 F N Page 20
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,cr.nossue sonicy Auft.orsty Peg 2 I Browns Fcery Nuclece Pigne BF-50SP-35
- Site Director Stintgre Practico ,
BF SCSP-2.ll
- FORM SD'iP-IS REV 0001 PROCEDURE REVIEW RECCR0 THIS FORM SHOULD BE CCMPLETED IN BLACK INK CR TYp? WRITTEN l
Procedure No. b ~2 b Unit O DeaCu Tracking No.
-M-Ol l ALL BLANKS MUST BE CC.uPLETED. NA SHOULD BE IN THOSE BLANKS NOT A PROCEDURE llNSTRUCTICNCHANGE.
Does this inciernent, delete, change a reference to a venoor manual? If YES, venoor Manual Coordinator signature is required. YES Y No NA Venoor Manuas Cooraanator Dato Does this inglement, delete, change an Si data cover sheet. I if YES, Planning and Scheduling supervisor signature is required. _ YES No N
P1anneng & Seneousing Daro is item added, deleted, or frequency changed on IE (or CSSC) PM Requirements. If YES, complete BF-lIi. YES NO Is this a change in procedural detail of FSAR or other licensing document? YES I No l CR is this a new instruction?
If YES to either of the above questions, a USCO is required. YES Y NO .
Is this change in response to an LER, IE bulletin, YES N NO NRC inspection report, mrprtlsupv inspection, QA audit, etc.
If YES, specify doeurnent under Reason for hvision.
Was this change made to meet an NRC connitment?
YES No if YES, refer to 6.l.l.4 for proper identification of chango.
Does this revision irrelarr.ont or delete a sourca document? YES Y NO If YES, attach form SDSP-4. Due date of SDSP--! is .
Is fire protection system involved?
YES NO If YES, Fire Protection Engineer signature required.
Fire Protection Eng Signature Dare is security system involved? YES NO IfYES,PublicSafetysupervTs[rsignaturerequired.,'-
o *
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hM -3u ruoiic sarory duperv>sor Dare c
Is personnel or Industrial safety affected?
if YES, Safety Supervisor signature required, YES _M NO .
in Satory Supervisor k
Da ta Was this revision prepared in advance of the euroletion of an activity? If YES, all subsequent approved revissorts have been YES N NO incorporated on this revision as a plicable. '.
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F.asponsiosu suctu;u rrocucure eYW- nator f' Datu ,
lsthisprocedureCSSCrelated) l If NO, NA all approval blanks on SDSP-l as ap repriato. YES _ _Y NO i I
h tention Period: Lifetime h tention bsponsibility: DP!.CU Supervisor Ol8tp
. . . . ~ peo. H .. -
~
NOTE: THIS PAGE IS A TYPED' COPY OF THE CORRESPONDING IP 26-01 ISSUED PAGE WHICH INCLUDES MARK-UPS. Page 6 BFN - IPD BFN-IP-26 OCT. 23, 1985 INITIATED CANCELLED ,
Initial / Time Initial / Time 2.3.4 Evacuate all personnel from refuel floor operations except personnel required to perform tie-down of reactor building crane, bridge, and trolley and remove hatch covers.
Tie-down crew to evacuate refuel floor when crane is secured.
2.3.5 Dispatch ADO to evacuate elevation 621 turbine building.
2.3.6 Notify water treatment plant i
personnel of tornado warning.
Instruct them to stay inside until further notice.
Notify Hypochlorite Building 4
2.3.7 personnel of tornado warning.
Instruct them to stay on the first floor of the building until further notice.
2.3.8 Notify personnol in plant by pith 11e address of Lornado warning. ~ Direct them to go to turbine building elevation S65.
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. NOTE: . THIS PAGE IS A TYPED COPY OF THE' CORRESPONDING -IP 26-01 ISSUED PAGE WHICH INCLUDES MARK-UPS. Page 8 BFN - IPD BEN-IP-26 OCT. 23, 1985 INITIATED CANCELLED Inillai/ Time Initial / Time
, 2.3.12 Notify all control room operating personnel of the tornado warning.
2.3.13 . Position personnel for emergency switching on electrical distribution system.
2.3.14 Notify Public Safety Service to immediate the following actions.
a) Notify the Administration' Building
Contact:
Site Directors Office (3675).
Site Services Manager (3S80), or Support Services Manager (3813) b) Notify the Engineering Building
Contact:
. Engineering Manager (2546)
DNE Project Engineer (2SSI), or PSS Officer on duty in lobby e) Holify Lite Tt* dining Services Conter '
contact: E&TT Supervisor (3601) or Operations Training Supervisor (3873) 0088y I
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NOTE: THIS PACE IS A TYPED COPY OF THE CORRESPONDING IP 26 ISSUED PACE WHICH. INCLUDES MARK-UPS, Page 9 BFN - LPD BFN-IP-26 OCT. 23, 1985 1NITIATED CANCELLED Initial / Time Initial / Time d) Holify Warehouse 12 (2793 or 2794) e) Notify motor patrol of tornado warning. They should direct all workers in the yard, cooling tower area, and outside the protected area back inside the protected area to turbine building elevation 565. If the workers do not have site badges direct them to the l
nearest tornado chelter area.
l l
f) tiotify PSS field personnel of' specific actions to be Laken per PSS SIL-17.33.
g) Ensure that all personnel have been evacuated from buildings outside'the fence to the sheller area specified in section 2.3.15 below.
h) Dispatch PSS Officer to assist AUO
. in directing employees to proper shelter areas within Lho plant.
- 1) Shift Engineer has been notifled that all nullfication have been completed by Public Safety Service.
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o o TENNESSEE VALLEY AUTHORITY CHATTANOOGA TENNESSEE 374ol SN 157B Lookout Place AUG 151996 i U.S. Nuclear Regulatory Commission Region II Attn: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Dr. Grace:
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 - RADIOLOGICAL EMERGENCY PLAN IMPLEMENTING PROCEDURES DOCUMENT REVISION In accordance with the requirements of 10 CFR Part 50.54(q), enclosed are copies of a revision to the Browns Ferry Nuclear Plant Radiological Emergency Plan Implementing Procedures Document, i
The revised procedure being provided is IP-26 dated July 16, 1986.
If you have any questions, please call J. D. Wolcott at (205) 729-3570.
Very truly yours, TEN 'S EE V AUTHORITY R. L. Gridley, irector Nuclear Safety and Licensing Enclosure cc: Office of Nuclear Reactor Regulation (
Enclosure:
2)
Attn: Document Control Desk
- U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i
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'11'/$ h i
p An Equal Opportunity Employer !
. s RECEIPT ACKNOWLEDGEMENT FORM Document: IP 26-01 TORNADO EMERGENCY PROCEDURE (TEMPORARY - To Become Permanent)
Sign below and return to: -
.: . Distribution Center Clerk Tennessee Valley Authority 43 164D Lookout Place Chattanooga, Tennessee 37402-2801 Signature Or5anization i
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