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.| ML18033A160 |
| Person / Time |
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| Site: |
Browns Ferry  |
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| Issue date: |
02/25/1988 |
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| From: |
TENNESSEE VALLEY AUTHORITY |
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| To: |
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| Shared Package |
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| ML18033A159 |
List: |
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| References |
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| CEB-CI-21.100, TAC-R00298, TAC-R00299, TAC-R00300, TAC-R298, TAC-R299, TAC-R300, NUDOCS 8803170016 |
| Download: ML18033A160 (12) |
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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
Enclosure 2 "3W~F TENNESSEE VALLEYAUTHORITY Divhkm of Nuclear Englneerhg 84I .'88 0225 001 CIVIL ENGINEERING BRANCH INSTRUCTION CEB-CI 21. 100 TITLF. BFN CLASS I HVAC DUCT AND DUCT SUPPORT SEISMIC OUALIFICATION INTERIM OPERABILITY ACCEPTANCE CRITERIA REVISION RO R2 ISSUE DATE RB 85 l988 PREPARED REVIEWED APPROVED 8803i700i6 880310 PDR ADOCK 05000260 P DCD
t UUHUINR I IVI'i LVV CEB-CI 21.100 BPN CLASS T NVAC OT AND DUCT SUPPORT SELSNTC CUA+TCATTON T' 'NTERIM OPERABILITY ACCEPTANCE CRITERIA enotes review A-Denotes approval Revision: p BRANCH (CEB) INSTRUCTIONS ENGINEERING AND TECHNICAL SERVICES (E&TS)
'ECB ntracts CEB EEB MEB NEB i n R A R A R A R A R R A PROJECT ENGINEERING (PR ENG)
BFEP BLEP SQEP WBEP WP PSB R . R A R A R A R A OPERATIONS ENGINEERING ENGINEERING ASSURANCE (EA) DNQA SERVICES (OES)
YS & EVA S.VS ADM PMS El&C MSB RAM R A R A R R A A R A R STAFFS OTHER ORGANIZATIONS BAGS ERIS PSS R A R A A A R A R A UJ z
O
REVISION LOC BFN CLASS I HVA UCT AND DUCT SUPPORT SEISi1IC Q IFICATIO Tj tie ~ 'NTERIt i OPERAB ILITY ACCEPTANCE CR ITERIA CEB-CI 21. 100 Revision Date No. DESCRIPTION OF REVISION Approved 0 Original Issue TYA tos34 {EC4 OES 4 78)
BFN CLASS I HVAC DUCT AND DUCT SUPPORT SEISMIC QUALIFICATION INTERIM OPERABILITY ACCEPTANCE CRITERIA CEB-CI 21.100 TABLE OF CONTENTS
~Pa e 1 0
~ PURPOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
2' SCOPE.
3.0 POLICY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~
4.0 INTERIM ACCEPTANCE CRITERIA......................
5.0 EXCEPTIONS 6.0 DOCUMENTATION.....................,.....,.
(
7.0 REFERENCES
TVA I0535 (EN OES-7-77)
BFN CLASS I HVAC DUCT AND DUCT SUPPORT SEISMIC QUALIFICATION INTERIM OPERABILITY ACCEPTANCE CRITERIA CEB-CI 21.100 1.0 PURPOSE The purpose of this criteria is to provide a basis for interim acceptance of existing Class I HVAC ducts and duct supports which do not meet long-term design basis requirements. Ductwork and supports meeting requirements of this criteria shall be considered suitable for interim plant operation until physical modifications can be .made.
2.0 SCOPE This criteria applies to all existing BFN Class I HVAC ducts and duct supports which will require physical modification to meet the long-term design basis requirements given by Design Criteria BFN-50-C-7104, Attachment B.
3.0 POLICY In general, Class I HVAC ductwork and duct supports shall be evaluated to requirements of Section 4.0 herein for interim acceptance. Specific exceptions may be approved on a case-by-ease basis if thoroughly justified and documented by issued supporting calculations in accordance with NEP-3.1. Approved exceptions shall be recorded in Section 5.0 of this document. Each exception shall be assigned a subsection number (e.g., 5 1, 5.2, etc.) along with a brief descriptive title for the specific case to which it applies. Following this shall be a brief
~
explanation of the rationale for allowing the exception, a statement of the specific requirements that vary from Section 4.0, and a reference to supporting calculations for the varied requirements. Issuance of exceptions shall be by revisions or CEB Interim Orders to this instruction in accordance with Civil Engineering, Branch Instruction 21-CI 21.02.
Class I ductwork and duct supports which meet the interim acceptance criteria (including approved exceptions) shall be acceptable for interim plant operation; however, mddifications to meet the long-term design basis requirements shall be scheduled and made as expeditiously as possible. Class I ductwork and duct supports failing to meet the interim acceptance requirements herein (including approved exceptions) shall not be allowed for plant operation until modifications are made to meet the long-term design basis requirements.
4.0 INTERIM ACCEPTANCE CRITERIA Requirements of this section and/or Section 5.0 shall be met as the basis for interim acceptance of existing Class I HVAC ducts and duct supports.
Figure 1 provides a logic diagram for applying this criteria.
4.1 DESIGN LOADS Design loads shall be determined in accordance with requirements of Design Criteria BFN-50-C-7104, Attachment B; however, allowable stresses shall be as given below in subsection 4.2.
DNE4 3581M TVA 10535 (EN OES-7-77)
pe ~ \
BFN CLASS I HYAC DUCT AND DUCT SUPPORT SEISMIC QUALIFICATION INTERIM OPERABILITY ACCEPTANCE CRITERIA CEB-CI 21.100 4.2 ALLOWABLE STRESSES 4.2.1 Ductwork The maximum allowable stress in a duct section for load combinations involving the DBE seismic event shall be as follows (Reference 7.1):
o Rectangular duct section stress < 12,000 psi.
o Circular duct section stress < 15,000 psi
'.2.2 Su ort Members and Connections
~
The support member stresses shall not exceed the lesser of 1.2 Fy or 0.7 Fu for tensile and flexural stresses and 90 percent of the critical buckling stress as defined in AISC Specifications (Reference 7.2) for axial compression and compression in a flange due to bending. Shear stresses shall not exceed 60 percent of the allowable stresses for tension and flexure.
The stress allowables for bolting shall be the greater of 70 percent of the ultimate strength or the minimum specified yield stress of the bplt material.
4.2.3 Concrete E ansion Anchors Anchorages to concrete shall be evaluated. in accordance with
..interim allowables of Civil Design Standard DS-C1.7.1 where the minimum factor of safety shall be 2.0 for shell and wedge bolt type anchors.
5.0 EXCEPTIONS No exceptions to the requirements of Section 4.0 have been taken as of the RO issue date.
6, 0 DOCUMENTATION Engineering evaluations performed to determine acceptability for interim operation shall be documented by calculations in accordance NEP-3 1. ~
Modifications which may be postponed to after restart shall be tracked by marking "Post-Restart Modification Required" on the calculation cover sheet and on the calculation log.
7.0 REFERENCES
7.1 SWEC calculation No. CD-Q0000-871818, backup calculation for BFN-50-C-7104, RIMS No. B22880204128 7.2 AISC, Manaual of Steel construction, 8th Edition DNE4 3581M TVA 10535(EN OES-7-77)
LOGIC HVAC PROGRAH Wa lkdown Evaluate No System OK and Sketch Walkdown Hods Configuration Information to Design Criteria System Not OK Evaluate Walkdown System OK Information to No for Operability Interim Hods Post Operation Operability Hods to Acceptance Design Criteria Criteria Sys tern Issue PORC Not OK Package Design Package Design Hods Issue PORC to Design Package Design Criteria Package nW I
A FIGURE 1 H