ML20147E438
ML20147E438 | |
Person / Time | |
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Site: | Browns Ferry |
Issue date: | 10/16/1986 |
From: | Russell Adams TENNESSEE VALLEY AUTHORITY |
To: | |
Shared Package | |
ML18032A736 | List: |
References | |
PROC-861016, NUDOCS 8803070063 | |
Download: ML20147E438 (53) | |
Text
{{#Wiki_filter:. Of Reiord B22 '86 1016 005 TENNESSEE VALLEY AUTHORITY DIVISI'ON OF NUCLEAR ENGINEERING PROGRAM DOCUMEh7 BROWS FERRY NUCLEAR PLAhi 4 TITLE: INSPECTION AND SEISMTC OUALIFICATION OF EXISTING ELECTRICAL. CONDUIT AND CCNDUIT SUPPORTS REVISION RO R1 R2 R3 l R4 R5 IS F,U E D A T E OCT 161986 l PREPARED l l l CHECKED j. (/,l. 4. l REVIEWED gg[d , APPROVED ,pMM.?.c. W ! ,
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CONTENTS I. Introduction . Page A. Purpose................................................. 1 B. Scope..... ............................................. 1 C. Executive Summary and Historical Ba'ckground............. 1 4 D.. Correspondence History.............................. 7.. II. Technical Requirements A. General Inspection Procedure............................ le , B. Design Criteria......................................... 19 C. Pr oj e c t I n s tr u c t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 D. General Design Instruction.............................. 20 E. Training and Employen Qualifications.................... 20 F. Analysis................................................ 20 III. Testing Programs .
; A. , Specific Component Test................................. . .
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B. C r i t i c al ~ D am p i n g T e s t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 C. Seismic Model Testing................................... 23 l > IV. Seismic Experience Data Base Evaluation..................... 24
! V. Schedule and Budget......................................... 25 i
i Appendix A (BFEP PI 85-02) l
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! Appendix B (Design Instructions) ! Appendix C (Volume Boundary Sketches) i i l
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i l 1 INTRODUCyION ' s A. PURPOSE The purpose of the "Inspection and Seismig Qualification of Existing Electrical Conduit and Conduit Supports" ' program at Browns Ferry Nuclear Plant is to assure that the plant has a conduit system ; seismically supported which allows safe operation and the ability to , maintain the units in a safe shutdown mode following a design basis earthquake. Additionally, this program will provide a documented design baseline from which engineering decisions may be made for i future modifications with a high degree of confidence as to the seismic qualification of the existing features, j l B. SCOPE l The scope of the program includes the following sequence of work:
- l. Perform an inspection and seismic qualification of all exposed electrical conduit and conduit supports in the Unit 2 Reactor {
building installed prior to May 1984 '
- 2. Perform an inspection and seismic qualification of the exposed :
electrical conduit and conduit supports insts11*d prior to May l 1984 in Units 1 and 3 Reactor buildings and common areas which l are required to safely shutdown and maintain Unit 2 in a safe ' shutdown mode.
- 3. Perform an inspection and seismic qualification of the remaining exposed electrical conduit installed prior to May 1984 in all Class I structures.
- The seismic qualification includes any necessary analysis, testing, l and construction modifications required to adequately demonstrate a seismically qualified system.
C. EXECUTIVE
SUMMARY
AND HISTORICAL BACKGROUhT During a routine safety inspection conducted in February and March of 1983, the Browns Ferry Nuclear Plant (BFN) NRC resident inspector questioned the installation and inspection documentation for conduit systems. When TVA personnel were unable to produce inspection - documentation or documentation of compliance with acceptance criteria which would assure a seismically qualified conduit system, a Browns Ferry Cor'rective Action Report (BF CAR 83-174) was issued on 11/22/83. The corrective action indicated was for TVA i Engineering Design (now the Division of Nuclear Engineering) to l "provide standard drawings or other documentation clearly identifying the engineering requirements" for a seismically j qualified conduit system. 1 4221A
C. EXECUTIVE SUMKART AND HISTORICAL BACKGROUND (Continued) Following several months of document search and staff meetings, site director J. A. Coffey, on' August 7, 1984, established a committee consisting of Quality Engineering, Design Services, Modifications, and the Plant Manager to review the specifications, guidelines, and criteria related to conduit supports at BFN. This connittee concluded that whereas design criteria (D.0) BFN-50-714 had existed since 1971, except for Unit 1. no documentation existed that conduit supports were designed or installed in accordance with the design criteria. It was also acknowledged that some past modification work which involved installation or rework of conduit supports could have been performed without knosledge of the criteria. The committee recommended closing BF CAR 83-174, which guestioned "acceptance criteria", and addressing the question of "lack of documentation" in a new CAR. BF CAR 84-088 was issued on December 26, 1984. Upon recommendation of the committee, a conduit sampling program was initiated to determine the extent of the problems of documentation and lack of' conformance to the design criteria. It was hoped that the sampling program would demonstrate seismic gualification, at least for an interim period, of the installed Class 1E conduit system. However, it was determined that not all Class IE conduit ..$ could be seismically qualified without modification. Consequently, a decision was made to bring all Class 1E conduit and supports into compliance with DC BFN-50-714 through a program of inspection and modification. A qualification program was developed and is defined in Browns Ferry Engineering Project, Project Instruction 85-02 R1 (BFEP PI 85-02). This revision details the program documentation required for all Class IE conduit in Units 1, 2, and 3 installed prior to May 1984 Conduit and supports installed after May 1984 are properly documented by the use of typical drawings issued as action to prevent recurrence for BF CAR 83-174. , In April of 1986, a decision was made to include all conduit l installed prior to May 1984-(as opposed to only Class 1E) in the ' inspection and seismic qualification program. BFEP 85-02 was l reissued to include this change in scope. The inspection is currently in progress.
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4 C. EXECUTIVE
SUMMARY
AND HISTORICAL BACKGROUND (Continued) i The first phase of inspection encompasses the. conduit in the Unit 2
-Reactor building along with the conduit in the connon areas necessary to safely shut down Unit 2 in the event of a design basis earthquake (DBE). The areas considered common,to Unit 2 are as follows: .e
- 1. Diesel generator buildings
- 2. Intake pumping station and tunnels
- 3. Control Bay 4 Specific locations in Unit 1 or 3 Reactor Buildings which are identified by BTEP Electrical Engineering Branch
- 5. Off gas treatment building
- 6. Standby gas treat ent building The inspect' ions were initially performed with the acceptance criteria being Design Criteria BFN-50-174 and General Construction Specification G-3. A conduit system not seismically supported in '
accordance with these criteria was identified with a unique discrepancy number. As a result of testing DC FBN-50-714 was superseded and replaced by DC BFN-50-723 which became the sole acceptance criteria after its issue. Consequently, the resolution of all discrepancies will be based upon the requirements contained ' in DC BFN-50-723. Discrepancies are categorized into the following areas for dispositioning:
- 1. Seismically qualified as installed, as determined by analytical methods, by testing, or comparison to similar conditions previously qualified.
- 2. Acceptable for interim operation but modification is required at the end of the next operating cycle.
- 3. Acceptable for interim operation based upon comparison with similar features contained in the Seismic Experience Data Base, l 4 Unaccepteble for interim use and must be fixed prior to ,
operation. To reduce the overall cost and schedule impact on TVA, every effort is made to seismically qualify the identified discrepant conditions without resorting to field modification. Evaluations are made to determine if a discrepant condition may be qualified for Unit 2 interim operation of one cycle and modified during the next scheduled unit outage. Additionally, evaluations are made be EQE Inc. to determine the compatibility of the discrepant condition with l 3 4221A
s C. EXECUTIVE SURMARY AND HISTORICAL BACKGROUND -(Continued) the Seismic Experience Data Base to justify interim acceptance without modification as described in Section IV. Various testing programs were performed as described in Section III to eealuate or qualify certain situations such as component load capacities, percent critical damping, over span conditions, and - configurations that were not addressed in the original acceptance criteria, BFN-50-714. The cost and schedule for engineering ecapletion of Unit.2.and common conduit for long tera qualification is presented in Section Y. Upon engineering completion of.the Unit 2 and common conduit design activities, the remaining conduits in Units 1 and 3 installed prior to May 1984 will be inspected and qualified. The schedule for completion of this activity is also shown in Section Y. D. CORRESPONDENCE HISTORT The following- correspondence is a chronological representation of the ~ events that led up to the decision to perform the seismic qualification program and of the decisions which affected the implementation of the program.
- 1. Memo from Kelleshan to Parrish dated August 6, 1970 (B22 860611 020)
"Seismic Criteria for Electrical Conduit Supports"
- 2. Memo from Sprouse to Dunham dated September 2, 1970 "Conduit Supports" (B22 860611 015)
- 3. Femo from Dunham'to Sprouse dated January 22, 1971 (attached)
- Seismic Analysis of Conduit Supports"
- 4. Memo from Parrish to Kelleghan dated June 9, 1972 (attached)
"Identification and Reclassification of Additional Safety-Related Cables"
- 5. Memo from Dunham to Etthcote dated April 30, 1973 "Seismic Qualification of Field Run Piping, Ducts, and Electrical Conduit" (B22 860611 017) ,
- 6. Memo from Lane to Chandler dated July 27, 1986 .
"Testing of One-Hole Conduit Straps" (804 860519 200) '
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f D. CORRESPONDENCE HI3 TORY (Cantinusd) -
- 7. Memo from Hall to Jones dated April 11. 1984 (BWP 840411 005) :
"BFN 50-714 Conduit Support Seismic Design f or Browns Ferry Nuclear Plant"
- 8. Memo from Rinne to Coffey dated July 20, 1984 (attached)
"Conduit Support Installation impact on Un.it 3 Cycle 5 schedule" -
- 9. Memo from Hall to Those listed dated August 14, 1984 (125 840814 810) "Conduit Supports and Hangers - Meeting Notes"
- 10. Memo from Hall to Those listed dated November 28, 1984 (R25 841213 868) "Conduit Supports and Hangers - Meeting Notes"
- 11. Memo from Hall to Beasley dated January 22, 1985 (BFP 85 03.23 001) "Conduit Spacing"
- 12. Reply no.no from Sinens to Kagay dated January 29, 1985 (attached)
"Conduit Spacing"
- 13. Memo from Hall to.Those listed dated January 31, 1985 (R25 850131939) "Conduit Supports and Hangers - Consmittee Meeting Notes" ;
- 14. Memo from Hall to Those listed dated March 11, 1985 (B22 850312 013) "Conduit Supports - Sample Inspection"
- 15. Informal meno from English to Marshall dated March 12, 1985 ,
(attached) "Conduit Supports" j
- 16. Memo from Beasley to Hall dated April 25, 1985 (B22 850425 024)
"Conduit Spacing" *
- 17. Memo from Beasley to Hall dated June 14, 1985 (B22 850614 012)
"Conduit Supports - Sample Inspection" ,
- 18. Memo from Beasley to Hall dated July 8, 1985,(B22 850708 009) J "Test Results for the Unistrut P1100 Series and Similar Conduit Clamps" .
- 19. Memo fron. Raulston to Barnett dated July 26, 1985 (B46 850725 001) )
"Test of Fingertype Clamps and U-Bolt Beam Clamps" j
- 20. Memo from Beasley to Hall dated July 26, 1985 (B22 850726 002)
"Qualification of Conduit Clamps for Seismic Use"
- 21. Memo from Beasley to Hall dated August 28, 1985 (522 850828 004)
"Requirements for Interim Qualification of Existing Class 1E' Conduit" i
- 22. Memo from Beasley to Hall dated October 7, 1985 (B22 851007 010)
"Seismic Qualification of Existing Class IE Condult" 5
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D. CORRESPONDENCE HISTORY (C:ntinu:d) ,
- 23. Letter from Robert H. Bryans to Hall dated October 7. 1985 (R23 851015 127)
- 24. Memo from Beasley to Hall dated October 18. 1985 (B22 851018 014)
"Revision to Cost Estimate - Seismic Qual.ification of E:isting Class IE Conduit Supports" -
- 25. Memo from Barnett to Beasley dated October 28, 1985 (B41 851028 014)
"Qualification of Seismic Conduit Support's"
- 26. Memo fros Beasley to Hall dated November 1. 1985 (B22 851101 001)
"Transmittal of Information Package on Existing Class 1E Conduit Qualification Program"
- 27. Memo from Beckner to Civil Ensinaering Branch Flies dated November 5. 1985 (B41 851105 030) "Conduit Qualification Program -
Review against OEP"
- 28. Memo from Beasley to Hall dated November 18, 1985 (B22 851118 013)
"Concrete Anchor Sample Inspection for Conduit Qualification Program" '2 9 . MemofromBeasleftoHalldated' November 20, 1985 (B22 851120 013) "Requirements for Qualification of Existing Class IE Conduits"
- 30. Letter from Bryans'to Hall dated November 22, 1985 (R25 851126 017)
"Conduit / Supports Qualification Program Evaluation Report"
- 31. Memo from Barnett to Chandler dated November 26, 1985 (B41 851126 001)
"SCRBFNCEB8522 R0 - Electrical Cable Weights"
- 32. Memo from Beasley to Schlinger dated March 1, 1986 (B22 860301 004)
"Discontinuing Use of Typical Conduit Support Drawings"
- 33. Memo from Chitwood to Barnett dated March 5, 1986 (B43 860306 903) ,
"SCRBFMCEB8522 - Electrical Cable Weights" '
34 Memo from Childers to Cutsinger dated March 11, 1986 (B43 860306 903)
"Stress-strain Curves of 6063 T1 Aluminum Tubing" '
- 35. Memo from Schlinger to Beasley dated March 20, 1986 (R23 860320 907)
"Autaorization to Process Design Change Request (DCR) B-3264"
- 36. Memo from Roberts to Cutsinger dated April 2, 1986 (B42 860402 004)
"Development of the Conduit Discrepancy Reporting System"
- 37. Memo from Beasley to Schlinger dated April 5, 1986 (B22 860405 001) -
"Proposed Redirection of Existing Program" Memo from Turner to Schlinger dated April 17, 1986 (R32 860417) 38. "Seismic Conduit Support Walkdown"
- 39. Memo from Beasley to Schlinger dated April 18, 1986 (B22 860418 005)
"Requirements for seismic Qualification of Conduit"
- 40. Meme free Schlinger to Stapleton dated May 6. 1986 (R25 860506 E31) l "Approval to Scope Design Change Request (DCR) B-3264 R1" 6
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i PAGES 7 THROUGH 17 INTENTIONALLY OMITTED. THESE PAGES CONSIST OF COPIES OF INTERNAL TVA MEMORANDA ONLY. a J 4 I i i d l i 1 l
II yECHNICAL REQUIREMENTS A. GENERAL INSPECTION PROCEDURE Since neither drawings nor calculations exist Tor conduit supports installed prior to May 1984, field inspection is necessary to-establish seismic qualification as required by TVA's Design criteria. Also, since the gus11ty of the initial installation is not in accordance with manufacturers recommendations nor good industry practice some construction work is performed in parallel with inspection to bring all installed conduit up to a common baseline standard. The detailed implementing document for the inspection and seismic qualification of conduit supports (BFEP PI 85-02) is shown in Appendix A. The implementing document for upgrading existing installations to the baseline standard is Special Electrical Maintenance Instruction -51 (SEMI-51). A synopsis of the inspec, tion procedure,BTEP PI 85-02 follows. In order to understand the developaent of the inspection program, one must first consider the problem size, complexity, and i I constraints imposed. There are thousands of conduit of which only approximately 20% are Class 1E. Conduits are identified only at terminal points regardless of conduit length. Class IE conduits are ; i distinguished from non-Class 1E by conduit number inscribed on color coded tags. Non-Class 1E conduit tags are white color coded, which with age, closely resemble the yellow color of Class 1E conduit tags. . Conduit is located in congested areas, crosses contamination zones, and in many instances requires ladders and/or s'caffolding to inspect. With these constraints, a systematic approach to inspection was necessary to ensure that all conduit was inspected. , The approach initially taken in BFEP PI 85-02, through Revision 1, was to inspect only yellow tagged Class 1E conduit. However, due to many of the problems previously listed, the decision to inspect and seismically qualify all conduit was made in April of 1986. As detailed in BTEP PI 85-02, the entire plant is divided into discrete inspection volumes covering an area with specific boundaries. Copies of sketches distinguishing the boundary lines are included in Appendiz C. Each volume is inspected by inspection teams to evaluate all conduit installed prior to May 1984 and to provide detailed information on conduit and supports which in the judgement ~ of the inspectors might fail to meet the acceptance criteria. 18 4221A
A. GENERAL INSPECTION PROCEDURE (Continued)
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Conduit installed after May 1984 is readily discernable from Pre-May ! 1984 conduit due to identifiable support configurations and heat treat numbers stenciled into support members. Conduit and supports which are questionable in accordance with the acceptance criteria are identified with unique discrepancy numbers for further evaluation. Typical information provided with the discrepancy includes:
- 1. Conduit routing
- 2. Location of discontinuities such as elbows, tees, and threaded connections.
- 3. Location and configuration of supports with contributory spans for analysis.
- 4. Material and size of conduit.
- 5. Conduit number when available.
IdentifieddiscrepanciesUillbetrackedthroughresolutionbythe diset spancy number.. . Upon completion of an inspection area, team composed of two lead inspectors independent of the original inspection team, will reinspect a portion of the conduit within the area to verify the conclusions of the original team. If the conclusions of the original inspection team cannot be verified as accurate or conservative, further analysis inspection, or other actions deemed appropriate by the DNE coordinator will be initiated to resolve the differences. . B. DESIGN CRITERIA The seismic design criteria for electrical conduit was first issued . in January 1971 [sse Section I, part D(3)). In February 1984, the criteria was revised and given Design Criteria number BFN-50-714 ' This criteria forms the historical design basis for the installation ' of conduit and conduit supports and the lack of its implementation resulted in the filing of SF CAR 83-174 and the subsequent J initiation of the inspection and qualification program. In order to minimize the number of support modifications required to j bring the as-built conduit configuration into compliance with DC BFN-50-174 the design criteria was reviewed for conservatisms. It was concluded that full scale, representative model testing of -
- enveloping conduit configurations might result in significant relaxation to the, requirements in DC BFN-50-714 Consequently, testing war performed at Wyle Laboratories in Huntsville, Alabama and at TV2's Norr'is Laboratory. The results of these tests confirmed that BFN-50-714 was an extremely conservative design criteria and a new criteria, BFN-50-723, was issued in March of 1986. The new criteria superseded BFN-50-714 and was based largely on the results of testing as shown in its references.
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C. PROJECT INSTRUCTION BFEP PI 85-02 The document implementing the' inspection requirements, documentation requirements, and providing direction to the conduit inspection and qualification program is BFEP PI 85-02. Due to the significance of this document it is included herein as Appendix A. D. GENERAL DESIGN INSTRUCTIONS i General instructions were prepared to sunnarize design input information and to unify support modifications. The instructions are shown in Appendix B. E. TRAINING AND EMPLOYEE OUALIFICATIONS Seismic qualification of conduit based on inspection of as-built systems for which no drawings exists relies heavily upon the experience, qualification, and judgment of the inspector. In order to achieve the highest inspection quality level reasonably attainable, BFEP employed only degreed cirli or mechanical engineers with structural experi,ence in the design of structural supports to serve as lead inspectors on two-man inspection teams. In all but two instances, the second inspector on the two man inspection team is also a degreed civil or mechanical engineer. In no case does an inspector have less than a four year engineering technology degree. New employees sre integrated into the inspection and qualification program in a time frame which assures f amiliarity with requirements before assuming a responsible role. All potential inspectors must serve an internship with an established inspection team and are not : upgraded to inspector status until the lead inspector and principal engineer (section supervisor) are satisfied the internee meets the standards required in the qualification program. A similar process is followed in urgrading an inspector to a lead inspector. All
- inspectors have been given uncontrolled copies and have received i training in the use of BFEP PI 85-02 and DC BFN-50-714 or DC j BFN-50-723 as applicable and portions of TVA General Construction !
! Specification G-32 (Bolt Anchors Set In Hardened Concrete). I F. ANALYSIS Installed conduit identified during the fleid walkdown as potentially deficient may be rigorously analyzed. The rigorous analysis consists of dead load and a Design Basis Earthquake (DBE) response spectral analysis to cover treguency modes from zero to 20
- hertz and a rigid response analyses to cover frequency modes greater -
than 20 hertz. j j i The response spect'alr analyses in all cases are two dimensional i j analyses, running' onch horizontal direction (I and Z) in conjunction with the vertical direction (Y). Separate response analyses are run l l for the IT plane and Y2 plane, and these load cases are screenec with the results from the rigid response analysis. 20 l 4221a l
F. ANALYSIS (Cantinu:d) Conduit supports are modeled as rigid supports except where field inspection indicates stiffness requirements of DC BFN-50-723 are not met. Supports not meeting the stiffness requirements require support flexibility to be included in the design. Anchor points are used in analysis for conduit's embedded in concrete, and three way supports are used for attachments to anchored junction boxes (The junction bor,is reviewed to determine if it is capable of carrying the loads of the magnitude I calculated.) Unsupported junction boxes are consicered as lumped masses with the conduit joint designed as a pin. Unistrut clamps are assumed to provide a three way restraint. Finger type clamps are assumed to provide lateral, but not axial restraint. l l 1 I
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TESTING PROGRAMS A. SPECIFIC COMPONENT TESTS Due to the diverse manuf acturers of conduit elamps used at Browns Ferry Nuclear Plant, a testing program was initiated with TVA's Singleton Materials Engineering Laboratory to determine the load carrying capacity of each brand. p Conduit clamps tested consisted of Unistrut P1100 Series. L-Line clamps 2007 thru 2019. Kendorf clamps, malleable finger type clamps with and without backs, and right angle K clamps using U-bolts. The Unistrut, B-Line, and Kendorf clamps were tested with several types of bolts (ie. round head with slot. hez bead with and without slots, carbon steel bolts, and brass bolts) to envelope the as installed conditions at BFN. - Except for the malleable clamps which were tested for axial capacity only (lateral capacity was tested by Singleton Materials Engineering Laboratory in 1976), the tests were conducted with the load applied separately in each direction (lateral, vertical, and axial) with respect to the conduit longitudinal axis. Load defection curves ' were plotted for all clamp tests. Full scale model, shaker table tests were also conducted at Wyle Laboratories on conduits to Unistrut with P1100 series clamps. The results of those tests confirmed that a properly torqued P1100 clamp would restrain conduit laterally, vertically, and axially during the design basis earthquate for Browns Ferry. Load capacities and test results are shown in TVA documents with the following RIMS numbers: (B46 850709 001), (B46 850715 002), (B46 850725 001) , B. CRITICAL DAMPING TEST Test specimens consisting of 3/4,1,1 1/2, 2, 3, 4, and 5 inch f aluminum conduit were fabricated in 11 foot sections and shipped to TVA's Engineering Laboratory at Norris for a determination of critical damping. To ensure the measured damping values enveloped all situations at Browns Ferry two specimens of each size were tested. The critical damping was determined for one specimen of
, each size with the maximum cable fill of 40 percent and one specimen of each size with no cable.
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- 8. CRITICAL DAMPING TitT (Cantinutd)
The results from the Norris test demonstrated significantly higher damping values than were allowed in DC BFN-50-714. Consequently, the higher damping values wer incorporated into the new Design Criteria (BFN-50-723) issued to replace BFN-50-714. The test results can be found in the following reports:
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- 1. "A Preliminary Study of Vibration Damping in Electrical Conduit". TVA Engineering Laboratory Report No. WR28 900-140 (B41 860327002). ,
- 2. "An Experimental Investigation of Vibration Damping in Aluminum Electrical Conduit", TVA Engineering Laboratory Report No. WR28-4-900-176 (B41 860327 003).
C. SEISMIC MODEL TESTING The response of aluminum conduit during a design basis earthquake at Browns Ferry was tested on a tri-axial shaker table at Wyle Laboratory in Huntsville, Alabama. Enveloping configurations of conduit size, bend geometry, fitting location, conduit spacing, and junction box locations' were included'in the test samples. Clamp qualification, results of interaction between closely spaced conduit, qualification of line mounted junction boxes, cantilever span qualification, and limited prediction of failure modes all resulted from the tests. The qualification of these parameters resulted in an immediate decrease in the number of discrepancies being written on the as-built conduit system within the plant. The document providing the scope of work for the Wyle tests is: Test Plan Number CEB-BN-1002, "Seismic Testing of Selected Configuration Groups of Aluminum Electrical Conduits for the Browns Ferry Nuclear Plant", dated February 18, 1986. A commercial quality, video cassette recording was made of all tests and provides visual documentation. The final written Wyle test report will be ' included in the summary report written at the completion of the conduit qualification program. 4 l l 23 j 4221A )
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IV SEISMIC EXPERIENCE DATA BASE EVALUATION EQE Incorporated (EQE) has complied a detailed. seismic experience l data base of the performance of various power and industrial facilities during past earthquakes. EQE complied the majority of this data as the primary consultant for the seismic Qualification Utilities Group (SQUG), as part of eventual generic resolution of Unresolved Safety Issue (USI) A-46, which includes conduit systems. The SQUG have concluded that conduit systeus do not present a significant safety concern, based upon the consistent lack of - significant earthquake damage to these systems in the data base facilities. The SQUG guidelines for review of conduit systems are currently being developed (EQE is the consultant) and in general , will be very simplified. ! EQE reviewed the walkdown procedures and review criteria of the TVA Browns Ferry conduit seismie qualification program, and concluded ' that the program has high conservatism that is not warranted in certain cases, based on the observed performance of similar systems , in past earthquakes. The review also concluded that the walkdowns performed under the TVA program enveloped the guidelines that would ' be eventually finalized by the SQUG A-a6 program. EQE developed a walkdown procedure and review criteria for evaluation of conduit discrepancies identified by the TVA profram. This review program is a conservative estimation of what is expected i to be the final SQUG guidelines. The EQE evaluation determines the ' compatibility of the discrepancy condition with the seismic . experience data base conduit installations that were undamaged by ! earthquakes more severe than the postulated Browns Ferry Design Basis event. The EQE evaluation also checks for caveats and 'l restrictions established by any evidenced damage to conduit and ; similar systems (i.e. small bore piping) that occurred in past ' earthquakes. Conduit system discrepancies determined to be sufficiently similar I to or more rugged than these data base systems have justification l for interim acceptance without modification. Conduit discrepancy l conditions that are not similar to data base systems, or include any I of the established caveats or do not meet all restrictions, are identified as outliers and require modification. Modifications are designed per BFN-50-723 under the TVA program. 24 4221
A V SCHEDULE AND BUDGET The original schedule and cost estimate is documented in the memorandum from N. R. Beasley to G. R. Hall dated October 7, 1985 (B22 851007 010). The original ecst was estimated at 81.82 million dollars with the following completion dates: Unit 2 Complettorf Dec' ember 5,1985 Unit 3 Completion December 31, 1986 Unit 1 ' Completion June 1, 1987 The cost estimate at the preparation of this document for the engineering effort is 85.3 million dollars with the following completion dates: Unit 2 Completion November, 1986 (Interim Qualification) Unit 2 Final Completion to be determined l . Unit 1'and 3 Completion to be determined Final Report To be determined i e l l l p l k 25 4221A 4 4
s F t a i APPENDIX A a I BTEP PI 85-02 i THIS DOCLHENT HAS BEEN PROVIDED SEPARATELY i h I l 4 5 7 i j 1 l l .i 1 I M l
APPENDIX B GENERAL DESIGN INSTRUCTIONS 1.0 PURPOSE Design criteria BFN-50-723 contains the design requirements for seismic qualification of existing electrical , conduit and conduit supports and shall not be deviated from. Exception items deemed comparable to the seismic experience data base by EQE, Inc. will be allowed as deviations from BFN50-723. The purpose of these instructions are to provide the guidelin.es to'be used to ensure uniformity in the design and inspection. 2.0 REFERENCE KATERIAL
- 1. AISC 7th and 8th Edition
- 2. "Specification For The Design of Cold Formed Steel Structures".
AISI, 1983 Ed.
- 3. "Design of Welded Structures", O. Blodgett ,
4 "Formulas For Stress and Strain". 4th Ed., R Roark
- 5. "Formulas For Stress and Strain", 5th Ed., Roark and Young
- 6. Earthquake Analysis, Reactor Building, Blume (ceb 800619 006)
- 7. "Torsion Analysis For Rolled Steel Sections", Bethlehem Steel
- 8. Unistrut General Engineering Catalog No. 9 and 10
- 9. BFNP - Qualification of Conduit clamps - CEB840124007, ,
B46 850709.001, B46 850725 001
- 10. Design Criteria BFN-50-723
- 11. Seismic Qualification of Existing Electrical Conduit'and Supports, PI 85-02 R2
- 12. Addendum to the Report on the Earthquake Analysis of the Reactor Building-Floor Response Spectra (B41 851112 048)
- 13. General Construction Specification G-29C R9 l
- 14. General Construction Specification G-32 Ell *
- 15. GT STRUDL, Georgia Institute of Technology
- 16. Baseplate II, Cybernet Services
- 17. T-Pipe Program
- 18. Standard Unistrut channel and parts material list, Unistrut
\l Bulletin UN1-A-5 February 2, 1984 ..
- 19. AVS Dl.1, 1985
- 20. Civil Design Standard DS C1.7.1 R3 "l
l 3.0 MATERILLS 3.1 All structural shapes and plates shall conform to ASTM A36 unless noted otherwise. Bolt material shall ASTM A307 unless noted otherwise. All structural tubing shall be ASTM A501 or A500 Grade B unless noted otherwise. ~ 3.2 All welding shall be done utilizing E70 electrodes unless noted l otherwise. Existi'ng welds are to be considered as being done with E70 electrones. ' 3.3 Unistrut type components shall conform to ASTM A570, Grade 33 and to the material specifications as shown in ref (18). 3.4 Steel conduit shall conform to ASTM A72 (Fy = 25000 psi) or better. 1 4221A I
GENERAL DESIGN INSTRUCTIONS 3.5 Aluminum conduit shall conform to 6063-71 alloy (Fy = 13000 psi) or better. i 3.6 The concrete compressive strength shall be assumed tobe t'c=3000 psi with an allowable increase to f'ca4500 psi. 4.0 DESIGN PARAMETERS p 4.1 DESIGN BASIS Conduit supports are to be evaluated for deadweight and DBE accelerations. 4.2 CLAMPS The ability of Unistrut P1100 series clamps to resist DBE loadings was verified by full scale testing at Wyle Laboratories. Similar type clamps may also be assumed to resist DBE loadings without failure. The load capacity of Thomas and Betts finger type clamps
'and right angle K clamps was determined at TVA's Singleton Laboratory and,is given in TVA documents B46 850725 001 and B04 860519 200. U-bolt pipe clamps were also tested and the capacities are given in TVA document B41 850510 001.
4.3 TOLERANCES Existing supports shall be evaluated for the as-built configuration. Design of new supports shall envelope the tolerances allowed in the drawing notes assuming tolerances are taken in the maximum amount and in the worst locations. 4.4 DAMPING RATIOS . Conduit supports will be analyzed or designed using Si damping f or DBE loadings. I l 4.5 ALLOWABLE STRESSES 4.5.1 Interim Qualification 4.5.1.1 Allowable stresses for structural shapes and plates may be increased to the allowables shown in the exception to DC BFN-50-723.
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4.5.1.2 Clamps or components attaching conduits to the structural i member shall have a minimum f actor of safety of 1.2.- ! 4.5.2 Lont Tern Qualification i 4.5.2.1 Allowable stresses for structural shapes and plates shall I conform to the requirements given in DC BFN-50-723. 2 i 4221A
4 GENERAL DESIGN INSTRUCTIONS 4.4.2.2 U21 strut type channel members shall conform to AISI Cold Formed requirements (Ref. 2) as shown in DC BFN ,50-723. 4.5.2.3 Concrete anchorages shall conform to tho requirements of DS-C1.7.1.
- 4.6 SUPPORT QUALIFICATION / DESIGN CRITERIA 4.6.1 Support stiffness shall conform to the requirements of DC BFN-50-723 section 4.0.
4.6.2 Support frequency shall be determined utilizing the GT STRUDL RAYLIECH frequency option (Ref.15) or by hand calculation utilizing the formulas from "Formulas For Stress and Strain" (Ref. 4 and 5). Support frequency shall be determined utilizing the contributory dead load of the conduit on the support, the dead load of accessories attaching the conduit to the support, and.,the deadweight,of the support structure. 4.6.3 If an existing support cannot meet the stiffness requirements of BFN-50-723 a conduit stress analysis considering support l flexibility any be performed. 4.6.4 For torsion analysis of Unistrut type framing members refer to "Formulas for Stress and Strain, 5th Ed., Chapter 9 (Ref. 5). ! 4.6.5 Junction boxes are assumed to provide 3-way support for condult. To verify this assumption, junction boxes shall be reviewed for the loads applied. If, in the designers analysis, l the box cannot resist the applied loads, a support shall be installed within 12" of the box. , 1 l I l i 3 4221A
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I i J LISTING OF VOLUMES'FOR WHICH MAPS WERE'NOT GENERATED PLANT. AREA VOL. #
========== ======
INTAKE PUMPING STATION & TUNNEL 58 RHR SERVICE WATER TUNNELS 2 A-D- - 60 INSIDE TORUS - UNIT 2 61 INSIDE TORUS - UNIT 1 120 RHR SERVICE WATER TUNNELS 1 A-D 121 STANDBY GAS TREATMENT BUILDING 174 OFFGAS TREATMENT BUILDING 175 . INSIDE TORUS - UNIT 3 176 RHR SERVICE WATER. TUNNELS 3 A-D 177 d b f i r t l 't
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