ML060380674
| ML060380674 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/26/2004 |
| From: | Facility Risk Consultants |
| To: | Office of Nuclear Reactor Regulation, Tennessee Valley Authority |
| References | |
| TVA/BFN-01-R-002, Rev 0 | |
| Download: ML060380674 (103) | |
Text
ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION INDIVIDUAL PLANT EXAMINATION FOR EXTERNAL EVENTS SEISMIC-INDUCED II/I SPRAY EVALUATIONS AT BROWNS FERRY NUCLEAR PLANT UNIT 1 REV. 0, MARCH 2004 (SEE ATTACHED)
FAcIl.ITY RISK CONSULTANTS, INC.
SEISMIC-INDUCED 11/1 SPRAY EVALUATIONS AT BROWNS FERRY NUCLEAR PLANT UNIT 1
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TVANBFN-01-R-002 Revision 0 March 26, 2004 SEISMIC-INDUCED 11/1 SPRAY EVALUATIONS AT BROWNS FERRY NUCLEAR PLANT UNIT 1 March 2004 Prepared for:
BROWNS FERRY UNIT 1 RESTART PROJECT Prepared by:
FACILITY RISK CONSULTANTS, INC.
Page i FACILITY RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 APPROVAL COVER SHEET
Title:
Seismic-Induced Il/I Spray Evaluations at Browns Ferry Nuclear Plant Unit 1 Report Number:
TVA/BFN-01-R-002 Client:
Browns Ferry Unit 1 Restart Project Project Number:
TVA/BFN-01 0-3/26/04 ut 7.
John 0. Dizon Steph J. Eder John 0. Dizon Page ii FACILY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE OF REVISIONS ORIGINAL ISSUE3/60 0This report contains 102 pages total 3/60 Page iii FAcILTY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 EXECUTIVE
SUMMARY
This report summarizes the seismic-induced 11/I spray evaluation program for Browns Ferry Nuclear Plant Unit 1. Key engineering attributes of the seismic 11/I evaluation
-program consisted of the following:
- In-plant screening walkdown -evaluations and identification of potential outliers; Further evaluations and resolution of potential outliers; Engineering design of plant modifications to resolve outliers; Work order requests to address general maintenance and housekeeping items.
In-plant screening walkdown evaluations of seismic 11/I spray hazards were performed on an area-by-area basis in accordance with Walkdown Instruction Wi-BFN-0-CEB-06, "Engineering Walkdown Instruction for Evaluation of Seismic-Induced Spray Hazards." A total of 27 designated plant areas were included. Screening evaluations focused on certain key attributes of the non-seismic Class I (Class II) piping and fluid pressure boundary systems that may potentially pose as spray hazards to surrounding seismic Class I systems and components in the event of an earthquake. Screening tools such as seismic deflection estimates and charts for various plant features, pipe flexibility and seismic anchor movement evaluation charts, support and anchorage capacity screening charts, and others, were developed for use in the in-plant screening walkdown evaluations.
Certain configurations identified during the in-plant screening walkdowns as not meeting the screening criteria were documented in the Potential Outlier Sheet (POS) as potential outliers and for further evaluation and disposition. Walkdown results, including a total of 179 potential outliers identified, are documented in the Walkdown Data Packages (WDP's) for the respective plant areas.
Potential outliers identified during the in-plant screening walkdowns were further evaluated to the acceptance criteria of TVA Design Criteria BFN-50-C-7306, "Qualification Criteria for Seismic Class !! Piping, Pipe Supports, and Components." Further evaluations and bounding analyses of these potential outliers consisted of hand calculations using basic engineering mechanics techniques for simple configurations, and rigorous piping analyses (TPIPE computer program) for more complex piping configurations. A total of 19 outliers were found to have not met the acceptance criteria. Plant modifications were designed Page iv FAcaur ' RtSK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26,2004 and Design Change Notice (DCN) issued to implement the changes so that all of these concerns were resolved. Furthermore, 13 maintenance and/or housekeeping items were also identified for corrective actions. IM/aintenance work order requests were issued to address these items.
Overall program results for the seismic 11/I spray hazard evaluations at Browns Ferry Unit 1 are summarized in the following table:
RB El. 519' &
541 '-6" NWQUAD, NEQUAD, SWQUAD, SEQUAD, HPCI, TORUS 6
28 4
1 RB El. 565' 565A, 565B, 565C:, 565D, 5
52 4
7 STNL RB El. 593' 593A, 593B, 593C, 593D 4
32 1
2 RB El. 621 '-3" 621 A, 621 B, 621 C:, 621 D 4
23 2
1 RB El. 639' 639A, 639B, 639C, 639D 4
30 4
2 RB El. 664' 664A, 664B, 664C, 664D 4
14 4
0 Total No. of IVI Spray Walkdown Plant Areas 2
Total No. of I/I Spray Potential Outliers Identified Total No. of Plant Design Modifications (DCN 51669)
Total No. of Misc. Maintenance and Housekeeping Items Page v FACILITY RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABLE OF CONTENTS Page Approval Cover Sheet.......................
ii Table of Revisions...........................................................
iii Executive Summary..........
iv
- 1. INTRODUCTION.................................................................................
1-1 1.1 Report Organization............................................................
1-1
- 2.
PROGRAM SCOPE 2-1
- 3.
EVALUATION APPROACH AND BASES 3-1 3.1 In-Plant Screening Walkdown 3-2 3.1.1 Piping, Pipe Support and Equipment Design Attributes.3-2
--3.1-.2-Seismic Anchor Movement Issues
........................ 3-4 3.1.3 Proximity Interaction Issues............
3-4 3.1.4 In-Plant Screening Tools...........
3-5 3.2 Further Analysis and Evaluation...................
3-5 3.2.1 --EquiprmeniAnchorage Acceptance Critera :..x 3-6 3.2.2 Pipe Support Acceptance Criteria.3-6 3.2.3 Pipe Stress Acceptance Criteria..
3-7
- 4.
IN-PLANT SCREENING EVALUATION..
4-1 4.1 Screening Evaluation Results..
4-1 4.2 Summary of Potential Outliers..
4-2
- 5.
POTENTIAL OUTLIER RESOLUTION
.5-1
- 6.
SUMMARY
AND RECOMMENDATIONS
.6-1 6.1 Plant Modifications 6-1 6.2 Maintenance and Housekeeping Items.......................................
6-1
- 7.
REFERENCES...............................................................................
7-1 Page vi FACOWB RISK CONSULTANTS,
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE OF CONTENTS (CONT'D)
APPENDICES APPENDIX A: Seismic Il/I Spray Evaluation Walkdown Data Packages.
APPENDIX B: Seismic Il/I Spray Evaluation Outlier Resolution Calculation Data Packages.................................................
APPENDIX C: Seismic Il/I Spray Evaluation Plant Modification Design Calculation Data Packages.................................................
Page A-1 B-1 C-1 FIGURES 2-1 Reactor Building El. 519 Ft. & 541.5 Ft.
2-2 Reactor Building El. 565 Ft..............................................................
-- an----2-3--Reiactor Building EL593L3~
FLN.Xa 2-4 Reactor Building El. 621.25 Ft...........................................................
2-5 Reactor Building El. 639 Ft...............................................................
2-6 Reactor Building El. 664 Ft...............................................................
-Paqe-2-3 2-4 2-5 2-6 2-7 2-8 Page vii FACILTY RISK CONSULTANTS, INC.
TVAIBFN-01-R-002 Revision 0 March 26,2004 TABLE OF CONTENTS (CONT'D)
TABLES 2-1 Designated Plant Areas..................................................................
4-1 Potential Outliers - RB Elev. 519' & 541 '-6".........................................
4-2 Potential Outliers - RB Elev. 565'..............................................
4-3 Potential Outliers - RB Elev. 593'......................................................
4-4 Potential Outliers - RB Elev. 621'-3"..................................................
4-5 Potential Outliers - RB Elev. 639'......................................................
4-6 Potential Outliers - RB Elev. 664'......................................................
4-7 Summary of Potential Outliers for BFN-1 Seismic Il/N Spray Evaluation Program--
4-8 Distribution of-Potential Outliers by Category for BFN-1 Seismic Il/I Spray Evaluation Program...............................................................
5-1 Potential Outlier Resolution Summary - RB Elev. 519' & 541'-6".............
-= 2 Pote-n-iaaVOu rier Resolutio-nSu rr rnmaR -E1ev-.565'................................
5-3 Potential Outlier Resolution Summary - RB Elev. 593'...........................
5-4 Potential Outlier Resolution Summary - RB Elev. 621'-3".......................
5-5 Potential Outlier Resolution Summary - RB Elev. 639'...........................
5-6 Potential Outlier Resolution Summary - RB Elev. 664'...........................
6-1 Summary of BFN-1 Seismic Il/I Spray Evaluation Program.....................
6-2 Summary of Plant Modifications for BFN-1 Seismic Il/I Spray Evaluation Program..........................................................................................
6-3 Summary of Misc. Maintenance & Housekeeping Items for BFN-1 Seismic Il/l Spray Evaluation Program.
Page 2-2 4-3 4-5 4-9 4-12 4-14 4-17 4-19 4-20 5-2 5-7 5-16 5-22 5-27 5-33 6-2 6-3 6-7 Page i FACtITY RISK CONSULTANTS, INC.
TVANBFN-01 -R-002 Revision 0 March 26, 2004
- 1. INTRODUCTION This report documents the seismic 11/I spray hazard evaluations for the Browns Ferry Nuclear Plant Unit 1 (BFN-1). The evaluation was performed to assess the structural integrity and seismic adequacy of non-seismic Class I, non-safety related systems and components (Class II) in the vicinity of or over and above safety-related, seismic Class I systems and components. Key elements and highlights of the BFN-1 seismic 11/I spray evaluation program are as follows:
The BFN Final Safety Evaluation Report (FSAR) Appendix C, Section 2.1, subparagraph b states in part "An item designated Class II shall not degrade the integrity of any item designated Class I".
Nuclear Regulatory Commission (NRC) Generic Letter (GL) 87-02 identifies that seismic spatial interaction (proximity and falling) are included within the scope for resolution of Unresolved Safety Issue (USI) A-46. USI A-46 program will be resolved under a separate task for BFN-1. However, seismic induced spray interactions are not included within the scope of USI A-46.
TVA is committed to complete the seismic 11/I spray hazards evaluation program as part of BFN-1 restart (TROI open item NCO910044001).
Potential spray interactions are addressed at BFN-1 by in-plant screening evaluation walkdowns performed in accordance with Walkdown Instruction WI-BFN-0-CEB-06 (Reference 7-1), and subsequent analytical evaluation performed using the criteria contained in TVA Design Criteria BFN-50-C-7306 (Reference 7-2).
1.1 Report Organization This report is organized as follows. Chapter 2 presents the scope of the program.
Technical bases and evaluation approach for in-plant screening evaluations and further analyses and-evaluations are-described in Chapter 3. Summary of in-plant screening evaluations is presented in Chapter 4, while that of potential outlier resolution is in Chapter 5. Overall summary and recommendations, including plant modifications and Page 1-1 FActLuT RuSE CONSULTANTS, INC.
TVANBFN-01 -R-002 Revision 0 March 26, 2004 maintenance work orders, are provided in Chapter 6. References are listed in Chapter 7 of the report.
There are 3 appendices to this report. Appendix A contains a listing of walkdown data packages (WDP) which document the in-plant screening evaluations performed by the Walkdown Teams. Appendix B contains a list of engineering calculations which document the resolution of potential outliers by further analyses. A list of calculations containing the engineering design of plant modifications for the resolution of BFN-1 seismic 11/l spray outliers are provided in Appendix C.
Page 1-2 FAcLw T RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004
- 2. PROGRAM SCOPE The Seismic Il/I spray programs were completed for BFN Units 2 and 3 prior to their respective restarts (References 7-3 and 7-4, respectively), and included all common
--structures (intake pump house, standby gas treatment building, off gas treatment building, and diesel generator buildings) as well as the control bay common areas.
The scope of BFN-1 seismic 11/l spray evaluation program includes a total of twenty-seven (27) general plant areas in Unit 1 Reactor Building as listed in Table 2-1.
The seismic-induced 11/l spray hazards program scope encompasses non-safety-related, non-seismic Class I components (Class II) that may degrade the integrity of safety-related, seismic Class I components by fluid spray initiated in the event of a design basis earthquake. Non-safety-related, non-seismic Class I components with fluid pressure boundary are evaluated as potential sources of fluid spray, while safety-related, seismic Class I components are considered as potential spray targets. Seismic Class I boundaries for BFN-1 systems (as defined in Reference 7-5) are used by this 11/l spray program to identify plant components as either safety-related, seismic Class I (spray targets) or non-safety related, Class II (spray sources).
Page 2-1 FACtuTy RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE 2-1 Designated Plant Areas El. 519' &
541 '-6" NWQUAD, NEOUAD, SWQUAD, SEQUAD, HPCI, TORUS (2) 6 El. 565' 565A, 565B, 565C, 565D, STNL (3) 5 El. 593' 593A, 593B, 593C, 593D 4
El. 621'-3" 621A, 621B, 621C, 621D 4
El. 639' 639A, 639B, 639C, 639D 4
El. 664' 664A, 664B, 664C, 664D 4
Total Plant Areas Notes:
(1) See Figures 2-1 to 2-6 for specific location of the above plant areas (2) Areas include both elevations of the four RB corner (quad) rooms, HPCI room, and areas above and below the Torus (3) STNL - Steam Tunnel, includes the IVISIV vault and areas south of the blow-out panel Page 2-2 FACItuT RHsK CONSULTANTS, INC.
TVANBFN-01 -R-002 Revision 0 March 26, 2004 Figure 2-1: Reactor Building El. 519 Ft. & 541.5 Ft.
Page 2-3 FAclLtn RFISK CoNSuTANs, INc.
- TVA/BFN-01-R-002 Revision 0 March 26, 2004 Figure 2-2:: Reactor Building El. 565 Ft.
Page 2-4 FALITY RISK CONS ULTANS, INC.
TVANBFN-01 -R-002 Revision 0 March 26, 2004 I' I Figure 2-3: Reactor Building El. 593 Ft.
Page 2-5 FAcILITY RISK CONSULTANTS3, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 IF III
[I I
.I.:
Figure 2-4: Reactor Building El. 621.25 Ft.
Page 2-6 FACILUT RiSK CoNSuLTANTs, INC.
TVANBFN-01-R-002 Revision 0 March 26, 2004 IFf:
ZI Figure 2-5: Reactor Building El. 639 Ft.
Page 2-7 FACIULTY RISK CoNSuLaNs INC.
I
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 Figure 2-6: Reactor Building El. 664 Ft.
Page 2-8 FAcma RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004
- 3. EVALUATION APPROACH AND BASES Very few components of nuclear plant systems are unique to the nuclear facilities.
Nuclear plant systems include equipment, piping, tubing, cable tray and conduit raceway systems, and many other plan't features that are common components of conventionaLpvwepi-ants and industria~lfacilities. Seismic experence data based methods have been developed to address seismic issues associated with the adequate performance of these equipment and cormmodities not designed, procured and installed to current nuclear seismic criteria. By reviewing the performance of the database facilities that contain equipment similar to that found in nuclear plants, conclusions can be drawn about the performance of nuclear plant equipment during and after earthquake events.
Extensive work has been performed documenting the performance of power plant equipment performance and the common sources of seismic damage to equipment and pinglrn-eneral-equiprnent*, piping-ad-tubingsysemsiwnthseismic-expedience
---database have performed very well in earthquakes, even though they were typically X
designed for deadweight and operating loads only, with little or no consideration for seismic loads. Performance of piping and equipment in past strong-motion
- earthquakes-are summarized in References 77-6ancdL7,respectively. Earthquake e
ence-based mhsbacked by analytical-based evaluation acceptance criteria, provide the bases for the seismic-induced I/IA spray hazards program at BFN-1.
The evaluation criteria for seismic-induced I/IJ spray hazards at BFN-1 consist of in-plant screening criteria and outlier evaluation criteria. The in-plant screening criteria focus on identification of piping and fluid pressure boundary system attributes that are known to be potential seismic hazards, as evidenced by past strong-motion earthquakes. Factors of safety for the in-plant screening assessments are set to ensure that components accepted by the screening criteria are seismically rugged.
The in-plant screening criteria are discussed in detail in Section 3.1 below.
The outlier evaluation criteria are for further, more detailed analysis of configurations that do not pass the in-plant screening criteria, identified as potential outliers during the screening walkdowns. Evaluation acceptance criteria are discussed in Section 3.2.
Page 3-1 FActILTY RISK CONSULTANTS, INC.
TVANBFN-01-R-002 Revision 0 March 26, 2004 3.1 In-Plant Screening Walkdown Various design attributes of the as-installed scope of piping and tubing, and associated supports were reviewed and evaluated by trained Walkdown Teams to ensure that BFN-1 installations are representative of acceptable experience database design practices and that components are free of known seismic vulnerabilities. Earthquake
-experience basidentified certain conditions that have resulted in failure of piping and tubing systems and components. The conditions evaluated in the screening walkdown reviews included the following:
Piping, Pipe Support and Equipment Design Attributes Seismic Anchor Movement Issues Proximity and Falling Interaction Issues The above design attributes and conditions are briefly discussed below.
3.1.1 Piping. Pipe Support and Equipment Design Attributes The Walkdown Teams reviewed the piping and tubing systems, and associated supports to ensure that the design attributes and conditions are consistent with good design and industry standard practices. The systems were also screened to ensure that they are free from known seismic vulnerabilities identified from earthquake
- -00 _ __- experience data.-Thesede~jgr-attributes inc ude:
=-
Piping with dead weight support spacing significantly in excess of the B31.1 suggested spans, or tubing with excessive sagging.
Pipe supports that exhibit marginal capacities, prone to fatigue failures and/or non-ductile behavior.
Heavy, unsupported, in-line components.
Piping constructed of non-ductile materials such as cast iron or PVC.
Non-standard fittings or unusual attachments that could cause excessive localized stresses.
Presence of severe corrosion in piping and associated supports.
Page 3-2 FActITY RtSK CONSULTANTS, N1C.
TVANBFN-01-R-002 Revision 0 March 26, 2004 Screening criteria requirements for support adequacy include evaluation for a minimum dead load factor of safety of 2.0 using design allowable loads. Generic evaluations of pipe hanger hardware are used to establish screening charts which include the 2.0 load factor, based on dead load from maximum B31.1 piping spans. Factored capacities based on manufacturers' suggested values are used for the development of the screening charts for typical standard pipe hanger components such as rod and clevis pin, beam attachments, pipe clamps and U-bolts. Similar factor is used to develop
-reduced screening capacities-for other support components such as welds, expansion anchor bolts and cast-in-place anchors.
Rod-hung piping systems have in general performed well in past earthquakes. The best performers are rod hangers utilizing clevis and pin connections; those impose no excessive prying loads to anchors, or high ductility demands on the rods. Certain configurations of short, fixed-end rod hangers may be subject to failure due to low-cycle fatigue effects. This is due to high rotation strains at the rod ends. Rod hanger fatigue evaluations considered cycliciresponse to the design basis time history as seismic demand, and rod hanger seismic capacity based on rod hanger fatigue test ultimate mean values less one standard deviation on the number of cycles to failure.
Brittle materials such as cast iron or P\\VC have performed poorly in past earthquakes when subjected to significant-deforrmations.- Cast iron-pipe component failures included fracture of threaded fittings such as such at tees and elbows. Similarly, certain types of mechanical fittings such as victaulic coupling, compression flange or bell and spigot joint may lose pressure boundary integrity when subject to seismic-imposed deformations, especially when the as-installed piping configuration is flexible.
Mechanical pipe fitting failures can also occur at the discontinuities in piping system global stiffness.
Cases of corroded piping failures have been noted in past earthquakes. The predominant failure mode observed consists of cracking and leaking at location where a significant decrease in wall thickness had occurred due to excessive corrosion.
Failures have also occurred where corrosion-cracked piping had been previously weld repaired. Corrosion in piping can be detected by discoloration, paint chipping, or leakage in affected areas.
Page 3-3 FACILITY RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 3.1.2 Seismic Anchor Movement Issues Seismic anchor movement induced failures have been the most common cause of loss of piping system pressure boundary integrity in past major earthquakes. The seismic experience database includes instances of seismic damage to piping, tubing and supports that were directly attributed to excessive movement of terminal end equipment, differential movement between supports in adjacent buildings, and excessive seismic movements imposed on branch lines by flexible headers.
Anchorage of terminal equipment such as pumps, tanks, heat exchangers and others are reviewed for adequacy to preclude damages to attached piping and tubing.
For piping spanning between two building structures, adequate flexibility must be provided to accommodate the postulated building differential movement. The imposed seismic displacement may be estimated as the absolute sum of the deflection of each
- separate structure. Building-deflection estimates may be obtained from the building floor response analysis.
Small-bore piping that spans from flexibly-supported, large-bore piping headers to a rigid support point may be subject to severe differential displacement of anchor points.
Small branch lines, pipe vents, taps and drains of flexible, rod-hung large-bore headers
are especially vulnerable to-thistype of-hazard-and rmaypoterntiallyjresult in breach of pressure boundary integrity. These configurations may be conservatively evaluated by uncoupled response approximations. An approximate conservative deflection estimate for large-bore piping can be obtained by considering first mode response of an equivalent simple beam span and applicable floor response spectra. This deflection can then be imposed to the small-bore branch line as seismic anchor movement to verify adequate piping flexibility based on a stress limit not to exceed 2.4 Sh, where Sh is the basic material allowable stress at maximum temperature (Reference 7-8).
Thermal effects on piping systems under consideration are included in the evaluations when deemed necessary.
3.1.3 Proximity Interaction Issues Proximity-related pipe-to-pipe interactions (impact) have not been a significant contributor leading to fluid spray sources for straight sections (welded or unjointed) of steel piping in past major earthquakes. However, piping constructed of non-ductile Page 3-4 FACILITY RISK CONSULTANTS, INC.
TVANBFN-01 -R-002 Revision 0 March 26, 2004 materials such as cast iron or PVC may be more vulnerable to damage when subject to impact. Proximity-related seismic interaction to small pressure boundary components and appurtenances could potentially result in a fluid spray hazard source. Thermal effects on piping systems under consideration are included in the evaluations when deemed necessary.
3.1.4 In-Plant Screening Tools A consolidated set of in-plant screening tools developed for use in the walkdown evaluations of potential seismic 11/I spray hazards at BFN-1 is contained in Reference 7-9. This calculation includes clarification and summary of screening tools previously developed for similar 11/l spray evaluations at BFN Units 2 and 3 (References 7-3 and 7-4). This also includes development of additional screening tools based on lessons learned and past experience. Some key screening data include:
Standard support hardware component capacities Anchor bolt and weld capacities Fixed-end rod fatigue screening Piping deflection estimates for seismic anchor movement and proximity impact considerations Pipe flexibility screening for differential displacement considerations
__.~
Deflection estimates for various plant features (cable trays, conduit, HVAC ducts) for proximity impact considerations Thermal deflection estimates Seismic demands at various elevations Upper bound displacement response spectrum Lower bound pipe frequency estimates The in-plant screening tools are intended to help streamline the in-plant walkdown evaluation process, and to ensure consistency among the various Walkdown Teams performing the walkdown evaluations.
3.2 Further Analysis and Evaluation Conditions which do not meet the above in-plant screening guidelines or which were judged by the Walkdown Team members to require further reviews are documented as "Potential Outliers". Acceptance criteria for further analysis and evaluation of potential Page 3-5 FACILCTY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 outliers are contained in TVA Design Criteria BFN-50-C-7306 (Reference 7-2), and are summarized in the following sections. Seismic demand is based on 5% damped building floor response spectra derived from the Design Basis Earthquake (DBE) response analysis for both horizontal cand vertical earthquake components. Realistic effects of non-linear behavior due to design features and phenomena such as proximity
- impact with other plant features, interferences and small clearances to stiff structures, geometric restoring forces, wall penetration sealants, and support ductile behavior are considered in the analysis as appropriate.
3.2.1 Equipment Anchorage Accentance Criteria Unanchored, unrestrained, marginally or inadequately anchored equipment components identified as potential outliers are subject to further evaluations.
Anchorage capacities are based on those provided in Appendix C of the Generic
__ Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment (Reference 7-10) with appropriate reduction factors as applicable. Piping and tubing attached to equipment components with flexible support systems, such as vibration isolators, --are evaluated for seismic-anchor-movement. - -
3.2.2 Pine Support Acceptance Criteria
_-Pip*?esupportanchorage loads are verified against capacities as provided in Appendix C
-=-----of-the-GIP (Reference-74-0). Support components thadtmay-exhibit non-ductile behavior are accepted based the following stress allowables:
Flexural and tensile stresses:
lesser of 0.7 S, and 1.2 Sy Shear stresses:
lesser of 0.42 S, and 0.72 Sy Bolt stresses:
greater of 0.7 S, and minimum specified Sy
- Where, S, is the material's ultimate strength Sy is the material's yield strength When test data are available, acceptable loads based on test data consider mean less one standard deviation capacity.
Pipe supports not meeting the above criteria may be accepted if adjacent supports and the resulting pipe span can resist dead loads with a factor of safety of 2.0. In-plant Page 3-6 FACIciTY Mu CONSULTANTS, INC.
TVANBFN-01-R-002 Revision 0 March 26, 2004 considerations regarding other consequences of support failure such as falling and excessive deflection are made when using this provision.
3.2.3 Pipe Stress Acceptance Criteria Pipe stresses induced by the combination of normal operating loads (dead load and
-pressure) and seismic loads (DBE inertial loads and DBE seismic anchor movements) are limited to 2.0 Sy.
In most cases the pressure term is not significant. The thermal stress term is not included in the criteria because majority of the Class 11 piping systems and components under consideration have insignificant thermal gradients, or are typically supported by rod hangers. Thermal stresses in flexibly supported piping are insignificant. The thermal stress is included in the above load combination if significant, as in the case of rigid support systems or large temperature ranges.
Page 3-7 FACILTY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004
- 4. IN-PLANT SCREENING EVALUATION In-plant screening walkdown evaluations for seismic 11/I spray hazards were performed on an area-by-area basis in accordance with Walkdown Instruction WI-BFN-0-CEB-06 (Reference 7-1) for the 27 designated plant areas listed in Table 2-1. Safety-related systems and components (seismic Class I) were considered as spray targets; and non-safety-related systems and components (non-seismic, Class II) were the spray sources.
Other systems that have non-safety-related primary functions but have some safety-related components were conservatively regarded as being either sources or targets.
Seismic boundaries for Unit 1 systems are defined in Reference 7-5.
Screening evaluations focused on certain key attributes of the non-seismic, Class II piping and fluid pressure boundary systems that may potentially pose as spray hazards to surrounding seismic Class I systems and components in the event of an earthquake.
Screening tools such as seismic deflection estimates and charts for various plant features, pipe flexibility and seismic anchor movement evaluation charts, support and anchorage capacity screening charts, and others, were developed based on the qualification acceptance criteria contained in TVA Design Criteria BFN-50-C-7306 (Reference 7-2). Guidelines for in-plant screening evaluation are discussed in Section 3.1 of this-report.--tntfant-screening tools -for-seismic Il/I spray-evaluation walkdowns are documented in Reference 7-9.
Results of in-plant screening walkdowrn evaluations for seismic 11/l spray hazards in each of the 27 designated plant areas in Unit 1 Reactor Building are documented in the respective walkdown data package (WDP). A listing of the walkdown data packages with unique identifier number can be found in Appendix A of this report.
4.1 Screening Evaluation Results Certain configurations identified during the in-plant screening walkdowns as not meeting the screening criteria were documented in the Potential Outlier Sheet (POS) as potential outliers. In general, typical outlier conditions identified by the Walkdown Teams for the seismic-induced 11/I spray hazards program at BFN-1 included one or more of the following general category of seismic concerns:
Page 4-1 FAcuLTY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 Piping overspans Seismic anchor movements Branch line flexibility Inadequate support capacity or load path Piping deficiencies (bent pipes, leaking flange, etc.)
Support hardware deficiencies (missing or detached components, etc.)
Equipment anchorage issues or unanchored equipment Anchor bolt capacity issues (bolt spacing and edge distance violations, etc.)
Heavy in-line components Large eccentric mass (valves) on small diameter lines Unusual or non-standard fittings Excessive corrosion Non-ductile materials Rod hanger fatigue concerns Complete lisng and description of all identified potential outliers, by plant areas and elevations, are presented in Tables 4-l to 4-6.
4.2 Summary of Potential Outliers Atotal-of-Gneliuikr Ewevyntyin-e (1 797pIoitiaEoutfiers were-identified uhre-rBFN-1 seismic lI/I spray evaluation program and are summarized by building elevation in Table 4-7. Distribution of potential outliers by categories is presented in Table 4-8.
Detailed description of the potential outlier conditions, including as-built data, sketches and/or photos are documented in the corresponding walkdown data packages (WDP's) for the respective plant areas. A listing of all walkdown data packages generated under BFN-1 seismic 11/I spray evaluation program is provided in Appendix A.
Page 4-2 F7ACILW~y RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004
'TABLE 4-1 Potential Outliers - RB Elev. 519' & El. 541'-6" (Plant Areas NWQUAD, NEQUAD, SWQUAD, SEQUAD, HPCI & TORUS)
NWQUAD-001 2"0 Aux. Boiler (to PSC) line has 15' span NWQUAD-002 Two angle supports are hanging from the 1"o Aux. Boiler line (i.e. Pipe is supporting the support).
NWQUAD-003 Line configuration results in excessive eccentricity for air-operated valve on 1 "0 RCIC Line NWQUAD-004 2"o PSC/PSC Overflow lines have overspan conditions (14' spans),,
NEQUAD-001 3/4"o RCW lines to CRD Pumps 1A & 1 B are copper tubing with sweated fittings, prone to failure.
NEQUAD-002 314"o line to CRD Pumps 1 A & 1 B is completely unsupported and line is sagging.
NEQUAD-003 3"o Rad Waste Drain line has 15' span NEQUAD-004 1"o Condensate S&S line has several overspan conditions.
NEQUAD-005 2Y2"0 CRD return line with 12'-6" span has support with questionable capacity. (Long cantilever angle section)
NEQUAD-006 1"0 Condensate S&S line has 12'-10" span with concentrated load from 4'-4" of 3/4"0 line.
NEQUAD-007 1 "o Equipment Drain line from RHR system has 23' span NEQUAD-008 4"o DW line ends at elbow after valve 1-2-1140. Existing configuration is either work-in-progress or is out-of-service. Line (as-is) is a cantilever with large mass (valve) at end.
NEQUAD-009 MOV operator on the 21/2"0 CRD line exceeds weight &
height limits of SQUG GIP screening guidelines.
Page 4-3 FACILTY RsK CONSULTANTS, iC.
TVANBFN-01-R-002 Revision 0 March 26,2004 TABLE 4-1 (cont'd)
Potential Outliers - RB Elev. 519' & El. 541'-6" (Plant Areas NWQUAD, NEQUAD, SWQUAD, SEQUAD, HPCI & TORUS)
HPCI-01 1"0 Aux. Bciler line has 12' span TORUS-001 Bolt missing on flange connection of 2"o Aux. Boiler line, near connection to RHR line.
TORUS-002 Rod hanger strap missing on 1"o Aux. Boiler line. This results in about 14' span.
TORUS-003 2"0 Aux. Boiler line has 3 consecutive spans (1 @ 13.5' &
2@ 13').
TORUS-004 2"o SS RacI Waste Line has 12'-1 " span TDrIPIi-nnr%
I 'Aux Boiler linehas 9'-8" span TORUS-006 4"0 CS Rad Waste line has 26' span TORUS-007 2"o SS Racd Waste line has 17'-2" span TORUS-008 4"0 CS Rad Waste line has 15'-3" span Wi-fO~z
-4wCS-R alstbneihas-15'-2! spans TORUS-010 4"o CS Rad Waste line has 16' span TORUS-011 2"o SS Rad Waste line has 11 '-5" and 13'-1 " spans.
TORUS-012 3"o CS Rad Waste has 13'-4" and 13'-8" spans TORUS-013 2"o CS RCIS line has 12' and 15'-3" spans.
TORUS-014 Two 1"o socket-welded Equipment Drain lines have 10' spans.
Note: No outliers were identified in plant areas SWQUAD and SEQUAD.
Page 4-4 rFACILTy RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE 4-2 Potential Outliers - RB Elev. 565' (Plant Areas 565A, 565B, 565C, 565D & STNL) 565A-001 1 "0 branch line off 18"o RCW header has inadequate flexibility concern.
565A-002 1 "0 Aux. Boiler line has consecutive overspans of 13'-9" and 11 '-6". Overspan also noted at the bypass valve loop.
565A-003 Edge distance violations noted on the building heater support anchor bolts.
565A-004 1 "0 DW line has an overspan of 11'.
565A-005 4"0 Floor Drain lines have several overspan conditions involving T-branch configurations.
565A-006 2"o RCW line has an overspan of 18'-6".
565A-007 Two 1 "0 Building Heat lines both have overspan conditions (11 '). These 2 lines are continuation of those identified in POS 565A-009 and POS 565B-014.
565A-008 2-1/2"0 insulated Potable Water line has 18' span.
565A-009 Two 1"0 Building Heat lines both have overspan conditions (9'). These are the same building heat lines identified in POS 565A-007 and POS 565B-014.
565A-010 2-1/2"o and 4"o Potable Water lines with visible rust at the threaded joints. Lines appear to be galvanized iron pipes.
565A-01 1 Disengaged rod on a 2-1/2"o Potable Water line.
565B-001 2"o Floor Drain line has multiple overspan conditions (1 5'-6" and 11 '-6" spans). Also, a rod hanger is detached.
565B-002 Edge distance violations noted on the building heater support anchor bolts. Also, attached 1 "o and 3/4"o lines have SAM-related concerns due to rod-hung heater.
Page 4-5 FAcIITY RAsd CONsULTmNs, INc.
TVANBFN-01 -R-002 Revision 0 March 26, 2004 TABLE 4-2 (cont'd)
Potential Outliers - RB Elev. 565' (Plant Areas 565A, 565B, 565C, 565D & STNL) 565B-003 Base plate anchor bolts for various RCW lines have bolt spacing violations with adjacent supports (total of 4 base plates).
565B-004 2"o insulated Potable Water line has an overspan of 22'.
565B-005 6"o Floor Drain line has an overspan of 20'-4".
565B-006 2"o DW line has an overspan of 13'-9".
565B-007 1"o Building Heat line has overspan condition involving a T-configuration.
565B-008 1 "0 Building Heat line has overspan condition involving a T-configuration.
565B-009 4"o Floor Drain line has overspan condition involving a T-configuration.
565B-01 0 2"o Floor Drain line has overspan condition involving a T-configuration. -
565B-011 1"o and 1-1/2"o Building heat lines have overspan conditions in 2 places involving T-configuration.
565B-012 2"o Floor Drain line has overspan condition (15' span).
565B-013 2"o Potable Water line has 3 consecutive overspans (14'-9", 10'-6" and 13'-6").
565B-014 Two 1"o Building Heat lines have multiple overspan conditions (ranging from 8' to 1 0'-6"). A span of 17'-10" exists due to a detached rod hanger support. Some lines run in series (top and bottom) and are supported by common rod hanger.
565B-01 5 6"o Floor Drain line has 20'-4" span.
565B-016 4"o Floor Drain line has 19' span.
565B-017 1"o & 1-1/2"o Building Heat lines have two overspan conditions involving a T-branch configuration.
Page 4-6 FACILTY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE 4-2 (cont'd)
Potential Outliers - RB Elev. 565' (Plant Areas 565A, 565B, 565C, 565D & STNL) 565B-01 8 Vertical capacity of the ceiling-mounted bracket support on top of the 2-1/2"0 Fire&Protection riser~branch line is questionablie.
--565B-019 Overspan on the 8"0 Fire Protection header (22' span).
565B-020 Significant rust condition noted at the tee connection between the 8"0 Fire Protection header and the 2-1/2"0 branch line.
565C-001 2"0 Condensate line has 12' span.
565C-002 8"0 Condensate line has 20'-4" span.
565C-003 4"o Floor Drain line has 24' span.
565C-004 4"0 DW line and two other lines are supported by a cantilevered Unistrut support.
565C-005 4"0 DW line has 20'-9" span.
565C-006 1--1I27 -DO/ line has 12'-6" span.
565C-007 1V" unidentified line has 9' span.
565C-008 2"0 Floor Drain line has 19' span.
565C-009 Pipe clamp is missing on a wall-mounted Unistrut pipe support for 3/4"o Rad Waste line.
565C-010 Edge distance violations noted on the building heater support anchor bolts. Also, attached piping to heater have flexibility concerns.
565C-011 2"o Raw Water Cooling line has 14' span.
565C-012 2"o Raw Water Cooling line has 14'-6" span (gang-supported to a 2"o N2 Makeup line above it). In addition, a 1 "0 line (about 8' tributary span) is hanging off the RCW line via spacer supports.
Page 4-7 FACILTY RtISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABLE 4-2 (cont'd)
Potential Outliers - RB Elev. 565' (Plant Areas 565A, 565B, 565C, 565D & STNL) 565C-013 1-112"0 Fire Protection branch line has 15' span.
565C-014 Missing hardware on a trapeze rod hanger support for 8"0 Fire Protection header, resulting into piping
--overspan.
565D-001 4"0 DW line has 17'-6" span.
565D-002 4"0 Floor Drain line has 17'-5" and 18'-4" spans.
565D-003 4"0 Floor Drain line rod hanger is detached.
565D-004 Vertical capacity of the wall-mounted bracket support on top--of the 2-1/2"0 Fire Protection riser branch line is questionable.
565D-005 4"0 Fire Protection line has 17'-6" and 16' spans.
STNL-001 1 "o RCIC/ Rad Waste line has 1 0'-2" and 1 0'-0" spans.
STNL-002 1
'b Reactor Feedwater line has 12'-3" span.
Page 4-8 FAhCtLTy RISK CONSULTANTS, INC.
TVANBFN-01-R-002 Revision 0 March 26, 2004 TABLE 4-3 Potential C)utliers - RB Elev. 593' (Plant Areas 593A, 593B, 593C & 593D)
Two 6"0 Fuel Pool Cooling lines have about 22' spans.
593A-001 593A-002 1"o uninsulated Air Conditioning line has multiple overspan conditions (max. of 16'-9" span).
593A-003 Two 1 "o insulated Air Conditioning lines have several overspan conditions.
593A-004 3"o Floor Drain has 2 overspan conditions (15' & 20'-6" spans).
593A-005 4"o Floor Drain line has 15'-9" span.
=
-593-A-006
-Two 1/2 "0 RBCCW socket-welded pipes have 11 '-5" and 10'-10" spans.
593A-007 Line is leaking at threaded bronze hand valve near T-connection of 1/2 "o tubing to 12"o Raw Cooling Water header. Also, the 1/2"0 line has 13'-4" span.
-593A-008
-Two 3"* insulated Building -Heat lines have 2 consecutive overspans (18' and 20'-3").
593A-009 1"o insulated Demin. Water line has 2 consecutive overspans (12' and 11'-4").
593A-01 0 Two 2"o P'SC/PSC Overflow lines have overspans (max.
of 14'-4").
593B-001 11/2 "0, 2"o and 3"o Building Heat lines have multiple overspan conditions.
593B-002 1"o Equiprment Drain line has a detached rod hanger resulting in overspan condition of 17'-6". Also, even with the detached rod hanger in place, span is 11 -1 0".
593B-003 3/4"o Building Heat lines have 2 consecutive overspan conditions (max. of 9'-8" span).
Page 4-9 FACILITY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE 4-3 (cont'd)
Potential Outliers - RB Elev. 593' (Plant Areas 593A, 593B, 593C & 593D)
I -- - -- 59313-004 1/2"0 RBCC'N pipe has multiple overspans (spans of 6'-
6", 8'-2", 10' & 10'-8") and is sagging in some areas (appear to have been stepped on causing permanent deformations).
593B-005 3"o Floor Drain line has 16' span.
593B-006 Branch line flexibility concern on 3/4"o and 1/2"o Building Heat lines near the rod-hung building heater.
593B-007 2"0 RBCCW line has a detached rod hanger resulting in overspan condition of 14'-10".
593B-008 4"o Floor Drain line has multiple overspan conditions involving T-configurations.
593B-009 2 - 2"0 PSC/PSC Overflow lines have overspans (max.
of 11'-10").
= -i593B-010
_ _/2 "e Primary Containment Isolation-line-has 11 -9" span.
593C-001 4"o Floor Drain line has 20'-1" span.
593C-002 2"o RWCU line has 14' span.
593C-003 Edge distance violations noted on the building heater support anchor bolts.
593C-004 4"o Floor Drain line has an overspan condition involving T-configurations.
593C-005 1/2 "0 RBCCW line has typical span of 10'. Another 1/2 "0 RBCCW line is gang-supported from the above line at 5' span, typical.
593C-006 Branch line flexibility concern on 3/4"o and 1/2"o Building Heat lines near the rod-hung building heater.
593D-001 2"o Condensate S&S line has 20'-5" span.
593D-002 3"o Floor Drain line has 17'-4" span.
593D-003 2"o RBCCW line has 13'-10" span.
Page 4-1 0 FACILY RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABLE 4-3 (cont'd)
Potential Outliers - RB Elev. 593' (Plant Areas 593A, 593B, 593C & 593D) 593D-004 3"0 Raw Cooling Water line has 17'-5" span.
593D-005 6"0 Fuel Pool Cooling lines have 20' spans.
593D-006 Potential rod fatigue concerns on multiple short fixed end rods supporting 4"0 Floor Drain line.
Page 4-11 FActLu-RISK cONSULTANTS, INc.
TVANBFN-01-R-002 Revision 0 March 26, 2004 TABLE 4-4 Potential Oulliers - RB Elev. 621'-3" (Plant Areas 6:21A, 621B, 621C & 621D) 621 A-001 3/4"o Gland Seal line has-multiple overspan conditions.
621 A-002 4"0 Equipment Drain has 17' span.
621A-003 3"o, 2"o & 1"0 Standby Liquid Control (SLC) flush lines empty into unrestrained 55 gal. plastic drum. Drum may overtum and spill contents.
621A-004 Bracket support for eyewash station is mounted to block wall with 1"4"o toggle bolts. Verify support adequacy.
621 A-005 1 "o SLC line has a detached rod hanger resulting in overspan-ccindition of 28'-10". Detached rod hanger is near midspan.
621A-006 Two 1"o Air Conditioning lines have several overspan conditions (max. of 1 0'-6" span).
621 B-001 Flexibility (SAM-related) concern on 1 "0 Building Heat
=
ifneeairodhe-niurcu-dingheaters 621 B-002 Excessive corrosion/rust on 1 "0 & 3/4"o Building Heat lines near the building heater.
621B-003 17/2"0 Building Heat line has overspan condition, with additional load from 1"o branch line at T-intersection.
621 B-004 11/2"0 Building Heat line has several overspan conditions involving T-configurations.
621 B-005 Two 1 "o Building Heat lines have several overspan conditions (max. of 10' span).
621 B-006 4"o Floor Drain line has multiple overspan conditions involving T-configurations.
621 B-007 6"O Condensate S&S line has 20' span.
Page 4-12 FRAcmurv RISK CONSULTANTS, INC.
TVANBFN-01-R-002 Revision 0 March 26, 2004 TABLE 4-4 (cont'd)
Potential Outliers - RB Elev. 621'-3" (Plant Areas 621A, 621B, 621C & 621D) 621 C-001 4"o-Condernsate S&S-line has 15'--6span.-- -
621C-002 3"0 Demin. Water line has 17'-6" span.
621C-003 RWCU pumps 1A& 1B appeared to be inadequately supported. Pumps are in-line supported on 11/2 "0 line with large eccentricities. Also, there are potential SAM-related flexibility concerns on the 3/4"o lines.
621 C-004 Flexibility (S'AM-related) concern on 1"0 & 3/4"o Building Heat lines near rod-hung building heater.
621C-005 11/2 "o Building Heat line has multiple overspan conditions (max. of 13' span) 621C-006 1"0 Building Heat line has multiple overspan conditions (max. of 13' span) 621 C-007 2/2 "o air-operated valve 1 -FCV-69-78 has large
-eccentricemass-.
621 D-001 Flexibility (SAM-related) concern on 1/4 "o Fire Protection branch off the 3"o riser.
621 D-002 Two 1"o Air Conditioning lines have several overspan conditions (typ. span of 11 ').
621 D-003 2"o Fuel Pool Overflow line has 3 consecutive overspans (max. span of 13'-6").
Page 4-13 FACtLTY RISK CONSULTANTS, INC.
I TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE 4-5 Potential Outliers - RB Elev. 639' (Plant Areas 639A, 639B, 639C & 639D) 639A-001 1"0 GS line has 18'-4" span and wall brackets lack U-bolts (line can slide off of supports).
639A-002 1"o GS line has 12' span.
639A-003 3"o GS / Condensate S&S line has 2 consecutive overspans /19' and 15'). Also, 2"o DW line has an overspan oi 19'.
639A-004 Anchorage appears marginal for GS storage tank.
639A-005 1"o DW line has 9'-6" span. Line is cut and capped, sagging noled.
639A-006 2"o FP Overflow line has 14'-7" span.
639A-007 3"o Floor Drain line has 20' span.
639A-008 1"o Building Heat line at interface with the unit area heater (including union) is rusted.
639A-009 Two 1"0 Building Heat lines have 12' span.
639A-01 0 Area heater of Building Heat system is rod hung and may cause SAM problems for the connecting 1 "0 & 3/4"o lines.
639A-01 1 3/4"o FP Overflow drain line has SAM-related concern due to the E-W movement of 6"o Rx Head Exhaust line.
Note that the pipe stanchion support for the 6"o line is free to slide in the E-W direction.
639B-001 4"o Floor Drain line has 18'-6" span.
639B-002 Lube oil cooler has marginal tack weld attachment to its support saddle.
639B-003 Building heat lines are rod hung and have several overspan conditions. Lines terminate at rod hung area heaters.
639B-004 Seismic movement of a 3"o FP riser imposes SAM to 1-1/2"o branch line (to hose station).
Page 4-14 FACtLuy RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABLE 4-5 (cont'd)
Potential Outliers - RB Elev. 639' (Plant Areas 639A, 639B, 639C & 639D)
I
-63913-005
-1"0 to 3"0 Condensate S&S line has multiple overspan conditions and non-standard reducer fittings are used.
639B-006 3"0 Floor Drain line has 23' span.
639C-001 Pipe flange is leaking on short riser of 3"o Condensate S&S line.
639C-002 1"o to 3"o Condensate S&S line has multiple overspan conditions and non-standard reducer fittings are used.
639C-003 4"0 RCW line has 2 overspan conditions - 1 @24' and 1 @ 16' that is piggy back from the 8"o RCW line.
639C-004 6"o Rx Head Exhaust line has stanchion support that is not positively anchored.------
639C-005 2"0 DW line has 3 consecutive overspans of 16'-6", 13',
and 14'.
639O-006--
- -Building heat lines-are rod hung-and have several overspan conditions. Lines terminate at rod hung area heaters (SAM-related issue).
639C-007 3"0 Floor Drain has 1-5'-6" span.
639C-008 3/4"o FP Overflow line has SAM-related concern due to movement of the 6"0 Rx Head Exhaust line with the stanchion support that is not positively anchored (see 639C-004).
639D-001 Lube oil cooler has marginal tack weld attachment to its support saddle.
639D-002 1"0 Condensate S&S line has multiple overspan conditions.
639D-003 2"0 DW line has multiple overspan conditions, and 1"0 branch has SAM concerns at 2"o riser.
Page 4-15 FSCHEWcT RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABLE 4-5 (cont'd)
Potential Outliers - RB Elev. 639' (Plant Areas 639A, 639B, 639C & 639D) 639D-004 2"o Potable Water line has 21'-6" span.
639D-005 Terminal equipment (Lube Oil Cooler) for RCW and lube oil piping has marginal anchorage.
Page 4-16 FAcaLy RISK CONSULTANTS, INC.
TVNBFN-01-R-002 Revision 0 March 26, 2004 TABLE 4-6 Potential Outliers - RB Elev. 664' (Plant Areas 6154A, 664B, 664C & 664D) 664A-001 Three (3) 1"oa Building Heat lines have 13' spans 664A-002 3"0 unidentified line has 13' span 664A-003 Verify seismic adequacy of the support member and weld attachment of typical building unit heater in the area. Building heater is located in col. lines Ri-S and R2-Px.
664B-001 8"0 Condensate S & S line has 26' span 664B-002 Overspan on both 1"0 insulated Building Heat supply and return lines off the area heater located in col. lines R4-Ux. Also, verify seismic adequacy of the support member and weld attachment of typical building unit heater in the area. Building heaters are located in col.
lines R2-Ux and R4-Ux.
664C-001 8"0 Condensate S & S line has 26' span
--664C--002 Building Heat line has-I 1' span 664C-003 2"0 Drain line has 15'-6" span 664C-004 Verify seismic adequacy of the support member and weld attachment of typical building unit heater in the area. Building heater is located in col. lines R6-Ux.
664C-005 Hot water heater is not anchored. Tank may slide and cause attached piping to break (3/4"0 water heater supply lines, System 029) 664D-001 Three (3) 1"o Building Heat lines have 13' spans 664D-002 3"0 Unidentified line has 13' span 664D-003 Three (3) 1 " Building Heat lines have 17'-6", 16'-2", and 14'-2" spans Page 4-17 FACILiTY RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABILE 4-6 (cont'd)
Potential Outliers - RB Elev. 664' (Plant Areas 664A, 664B, 664C & 664D)
--664D-004-Verify seismic-adequacy of the support member and weld attachment of typical building unit heater in the area. Building heaters are located in col. lines R4-Px and R6-Px.
Page 4-18 FACtULT RISK CONSULTANTS, INC.
TVANBFN-01 -R-002 Revision 0 March 26,2004 TABLE 4-7 Summary of Potential Outliers for BFN-1 Seismic IN1 Spray Evaluation Program El. 519' &
541 '-6" NWQUAD, NEQUAD, SWQUAD, SEQUAD, HPCI, TORUS (TABLE 4-1) 28 El. 565' 565A, 565B, 565C, 565D, STNL 52 (TABLE 4-2)
El. 593' 593A, 593B, 593C, 593D (TABLE 4-3) 32 El. 621'-3" 621 A, 621 B, 621 C, 621 D (TABLE 4-4) 23 El. 639' 639A, 639B, 639C, 639D (TABLE 4-5) 30 El. 664' 664A, 664B, 664C, 664D (TABLE 4-6) 14 Page 4-19 FACILTY RISK CONSULTANTS, INC.
I TVANBFN-01 -R-002 Revision 0 March 26, 2004 TABLE 4-8 Distribution of Potential Outliers by Category for BFN-1 Seismic Il/I Spray Evaluation Program Piping overspans 125 63.5 Seismic anchor movements / Branch line flexibility 16 8.1 Inadequate support-capacity or load path 14 7.1 Piping / Pipe support hardware deficiencies 13 6.6 Equipment anchorage / Unanchored equipment 8
4.1 Anchor bolt capacity 6
3.0 Heavy in-line components/Large eccentric masses 5
2.6 Unusual or non-standard fittings 4
2.0 Excessive corrosion 4
2.0 Non-ductile materials 1
0.5 Rod hanger fatigue 1
0.5 Page 4-20 FActu.iTr RtSK CONSULTANTS, INC.
TVANBFN-01-R-002 Revision 0 March 26, 2004
- 5. POTENTIAL OUTLIER RESOLUTION Potential outliers identified during the in-plant screening walkdowns, as documented in the respective Potential Outlier Sheet (POS) and tabulated in Tables 4-1 to 4-6, were further evaluated to the acceptance criteria of TVA Design Criteria BFN-50-C-7306 (Reference 7-2rfor appropriate resolution. Further evaluations and bounding analyses of these potential outliers consisted of hand calculations using basic engineering _
mnechauncs techniques for simpte configurations, and rigorous piping analyses using TPIPE computer program (Reference 7-11) for more complex piping configurations.
Results of further evaluations and analyses to resolve the identified potential outliers are presented in Tables 5-1 -to 5-6 for the designated plant areas by building elevations. A listing of the calculation packages associated with further evaluations and bounding analyses of potential outliers identified under BFN-1 seismic 11/l spray evaluation program is provided in Appendix B of this report.
For those outliers not meeting the acceptance criteria of TVA Design Criteria BFN C-7306 (Reference 7-2), plant modifications are designed and implemented to resolve the outlier conditions. Discussions of the plant modifications including general maintenance and/or housekeeping items are presented in Chapter 6 of this report.
Page 5-1 FACan-RISK CONSULTANTS, INC.
T\\R/NBFN-01 -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 519' & 541 '-6" Plant Areas: NW-. NE-. SW- & SE-QUAD. HPCI. TORUS For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others
~.
A..................
0~~~Be - e --V-rip;00trn of
-j 00:!
P05 No.:
ConBdito 0
Not Cluaio Nmer/
MD0 umayoRcmm dtin NWQUAD 2"0 Aux. Boiler (to PSC) line al See CDQ1 -999-2003-1 41 2.
N/A
-001 has 15' span Existing configuration is
____:acceptable.
NWQUAD Two angle supports are 4l Upon further review, the current N/A
-002 hanging from the 1" Aux.
observed conditions were due to Boiler line. (i.e. Pipe is the removal of a 3"o check valve supporting the support) next to 1 -SHV-71 -565 which is located just above these supports and are within the same piping loop (pre-startup steam supply).
Note that the 2 supports in
____________________question are DL only supports.
NWQUAD Line configuration results in 4l See CDQ1 -071 -2003-1136.
N/A
-003 excessive eccentricity for air-Existing configuration is operated valve on 1I"0 RIC acceptable.
Line NWQUAD 2" PSC/PSC Overflow lines 4See CDQ1 -999-2003-1412.
N/A
-004 have overspan conditions (14' Existing configuration is
______spans).
acceptable.
NEQUAD-3/4"0 RCW lines to CRD 4See CQ -024-2003-1135.
N/A 001 Pumps lA & lB are copper Existing configuration is tubing with sweated fittings, acceptable.
NW Toageprone to failure.
Page 5-2 PFACTY RISK CONSULTANTS, IMNC
TVVBFN-01 -R-002 i
a Revision 0 I
March 26,2004 ITLIER RESOLUTION
SUMMARY
- RB EL. 519' & 541'-6" NW-, NE-. SW- & SE-bUAD. HPCI TORUS TABLE 5 POTENTIAL O0 Plant Areas:
For Potential Outliers not acceptable per calculation, identify as: M 7 Support modifications; D - Hardware deficiencies; O - Others
- 0....
Oute E. luat.on by..C.lculaion P
P.No.onditi.
0.Not Calcu.atio N
b M..
0 um ar.of.ecmmed
- V"
" ' 'tT ' 't 'V "t L
''"t'V '"". ''I.
'; "'-a'a'.
NEQUAD-3/4"0 line to RD Pumps 1A Te existing cnfiguration is 4
See CDQ1 -085-2003-1693.
002
& 1 B is completely shown to be unacceptable with Add new support to 3/4"o line.
unsupported and line is no support for the 3/4"0 line (refer:
sagging.
to CDQ1 -085-2003-1 405).
NEQUAD-3"0 Rad Waste Drain line has 4l -
See CDQ1 -999-2003-1412.
N/A 003 15' span Existing configuration is acceptable.
_a _:I I
_i
- I~...........
ia '.,ui "0~ Conenate S&S line has N
Per CDQ1 -999-2003~-1412~, the v
CDQ1~u
-002UU.-20031617.
004 several overspan conditions.
.existing configrations of 8'3" Add support near the T-intersection llland the 9'-6" spans are to reduce the dead load span to l
l l
l
~acceptable. However, for the 79 l
l l
span involving a T-configu ration,.l l lit is not acceptable.
NEQUAD-l21/2"0 CRD return line with 4
Per CDQ1 -085-2003-1197, the 4_-- See CDQ1-085-2003-1616.l l 005 1
12'-6" span has support with lL2 1/2 x 21/2 x 3/16 section is Install new 1/2"o expansion bolt l
questionable capacity. (Long ovrtrse with 27" long near the end of cantilever anglel llcantilever angle section) lcantilever.
The existing welds section, or provide new support forl llare adequate to resist the the 21/2"0 CRD retumn line.l l____________
l_l__
imposed cantilever moment.
_l NEQUAD-1 1"0 Condensate S&S line 4
l See CDQ1 -999-2003-1412.
N/Al 006 lhas 1 2'-1 0" span with lExisting configuration isl llconcentrated load from 4'-4" acetal.
I l ~~of 3/4"o line.l
___l lNEQUAD-1 1"0 Equipment Drain line l
n See CDQ1 -999-2003-1412.
N/Al 007 lfrom RHR system has 23' Existing configuration isl
______span l
acceptable.___l IjPage
&3 1
-FACITY RtSK CONSULaTS, INC.
TVNBFN-0i -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 519' & 541'-6" Plant Areas: NW-. NE-. SW- & SE-QUAD, HPCI. TORUS For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O-Others POS;;-
No Bre Oectti.on of h -
ht h NEQUAD-4" DW line ends at elbow 4
See CDQ1 -002-2003-1413.
.N/A 008 after valve 1 1140 line is Existing configuiration is work-in-progress or is out-of-acceptable.
service. Line (as-is) is al cantilever with large mass (valve) at end.__
NEQUAD-MOV operator on the 2U/2"0 4
See CDQ1 -085-2003-1415.
N/A 009 ORD line exceeds weight &
Existing configuration is height limits of SQUG GIP acceptable.
screening guidelines._
HPCi-001 1."0 Aux. Boiler line has 12' 4
See CDQ1 -999-2003-1412.
N/A span Existing configuration is
_________acceptable.
TORUS-Bolt missing on flange 4
The existing configuration is not 4atIsu maintenance request or work 001 connection of 2"o Aux. Boiler acceptable with spray hazard, order to replace the missing bolt on line, near connection to RHR Missing bolt should be replaced.
flthe flange connection.
line.
TORUS-Rod hanger strap missing on 4l The existing configuration is not 4l See CDQ1 -012-2003-1618.
002 1 "o Aux. Boiler line. This acceptable with 14' span.
Replace missing strap.
results in about 14' span.
l TORUS-2"o Aux. Boiler line has 3 4
Se CDQ1 -999-2003-1412.
N/A 003 consecutive spans (1 @13.5' Existing configuration is and 2@ 13').
acceptable._
TORUS-2"0 SS Rad Waste Line has 4
Se CDQ1 -999-2003-1412.
N/A 004 12'-1 n span Existing config. is acceptble.
Page 5-4 FACLTYM RSK CONSULTANTS, INC.
,v1BFN-0 1-R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUITION
SUMMARY
- RB EL. 519' & 541'-6" Plant Areas: NW-. NE-. SW- & SE-QUAD, HPCI, TORUS For Potential Outliers not acceptable per calculation,' identify as-M - Support modifications; D - Hardware deficiencies; 0 - Others Oufer Evaflu
-htlo yC1cwt i
Bri Wf eipt of i....
0 e.i.................
S....,0..0
.iE E ;.,;g.
e r:"....................
- t-0...K OK Comments m ~n f !
.E L.E.i j E 0-i i n
-i:m 0 i i TORUS-1 "0 Aux Boiler line has 9'-8" 4
See CDQ1 -999-2003-1412.
N/A 005 span Existing configuration is acceptable.
TORUS-4"o CS Rad Waste line has 4
See CDQ1 -999-2003-1412.
N/A 006 26' span Existing configuration is acceptable.
TORUS-2"o SS Rad Waste line has 4
See CDQ1 -999-2003-1412.
N/A 00-7 1 7'-2 span Exstn
,uato
- -Is acceptable.I TORUS-4"o CS Rad Waste line has 4
See CDQ1 -999-2003-1412.
N/A 008 15'-3" span Existing configuration is
_ ___ acceptable.
TORUS-4"o CS Rad Waste line has 4
See CDQ1 -999-2003-1412.
N/A 009 15'-2" span Existing configuration is acceptable.
i TORUS-4"o CS Rad Waste line has 4
See CDQ1-999-2003-1412.
N/A 010 16' span Existing configuration is acceptable.
TORUS-2"o SS Rad Waste line has 4
See CDQ1-999-2003-1412.
N/A 011 11 '-5" and 13'-1" spans.
Existing configuration is acceptable.
TORUS-3"o CS Rad Waste has 13'-4" 4
See CDQ1-999-2003-1412.
N/A 012 and 13'-8" spans Existing configuration is acceptable.
Page 5-5 P
FACLITY RtSK CONSULTANTS, INC.
TVABiFN-0i -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 519' & 541'-6" Plant Areas: NW-. NE-. SW- & SE-QUAD. HPCI. TORUS For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others f l ; `r;~' '~ k u I
. :. :.. :.:E.::!.:
1: 0 Ii,:
........... i:-,E
-.. E....
i-.
TORUS-2"0 CS RCIS line has 12' and
- 4.
See CDQ1-999-2003-1412.
N/A 013 15'-3" spans.
Existing configuration is acceptable.
TORUS-Two 1"0 socket-welded 4
See CDQ1 -999-2003-1412.
N/A 014 Equip. Drain lines have 10' Existing configuration is spans.
acceptable.
i i
Page -6 PCmIY RtSK CONSULTANTSo INC.
TVAIBFN-01 -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 565' Plant Areas: 565A. 565B. 565C. 565D & STEAM TUNNEL For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others 565A-001 1 "0 branch line off 18"o RCW header has inadequate flexibility concern.
4 See Calc. CDQ1 -024-2003-1408.
Existing configuration is acceptable.
N/A 565A-1 "0 Aux. Boiler line has 4 1 See Calc. CDQ1 -999-2003-1409. 1.1 N/A 002 consecutive overspan of 13'-9" Existina configuration is and 11 '-6". Overspan also noted acceptable.
at the bypass valve loop.
565A-Edge distance violations noted on 4
Per Calc. CDQ1 -044-2003-1410, N/A 003 the building heater support anchor the existing anchorage bolts.
configuration was evaluated and shown to be acceptable.
565A-1 "o DW line has an overspan of 4
See Calc. CDQ1 -999-2003-1409.
N/A 004 11'.
Existing configuration is acceptable.
565A-4"o Floor Drain lines have several 4
See Calc. CDQ1 -999-2003-1409.
N/A 005 overspan conditions involving T-Existing configuration is branch configurations.
acceptable.
565A-2"0 RCW line has an overspan of 4
See Calc. CDQ1 -999-2003-1409.
N/A 006 18'-6".
Existing configuration is acceptable.
Page 5-7 FActuTy RISK CONSULTANTS, INC.
I
- i TABLE 5 POTENTIAL OUTLIER RES LUTION
SUMMARY
- RB EL. 565' Plant Areas: 565A. 565B. 565. a565D & STEAM TUNNEL TI VA/BFN-01 -R-002 Revision 0 March 26, 2004 F
For Potential Outliers not acceptable per calculation,; identify as;: M -' Support modifications; D - Hardware deficiencies; 0 - Others l~
I
.'.X
............7.'
- ....... i.....
- ,...........t.l l00 00.,,..,,,...,
.Ue s._.................
Z.
i_
........ -...........I........-......i.
..................... : ::...................... : ::: ::: ::: ::::.::::.::.........::.:.A :
'01
~~~~~~~~~~~~............., ;.:
............ I...-..-..,...
- ..;..;...;.-..i......
i:
a-S.X.-.......80 $*; CiR#b
..... :i --
.-ii.....Ei-d o m ons:
a,. ifiodnthift".i
.l-t;T.
- t.
- ..........
565A-Two 1"0 Building Heat lines both 4
See Cac. CDQ1 -999-2003-1.409...
N/A 007 have overspan conditions (11').
Existing configuration is These 2 lines are continuation of acceptable.
those identified in POS 565A-009 and POS 565B-01 4._
565A-2-1/2"0 insulated Potable Water 4
See Cac. CDQ1 -999-2003-1409.
I.
N/A 008 line has 18' span.
Existing configuration is acceptable. Also note that the line is pinned on top and bottom against 3"0 conduit near mid-span, thus, overspan may not be a concern.
565A-Two 1"0 Building Heat lines both 4
See CaIc. CDQ1 -999-2003-1409.
N/A 009 have overspan conditions (9').
Existing configuration is These are the same building heat acceptable.
lines identified in P05 565A-007 &
POS 565B-014.
565A-2-1/2"0 and 4"0 Potable Water 4
The rusted threaded joints have 4 Issue maintenance request or work 010 lines with visible rust at the to be addressed due to potential order to address the rusted threaded joints. Lines appear to brittle nature of the pipe material, threaded joints.
be galvanized iron pipes.s tm n
565A-Disengaged rod on a 2-1/2"0 4
Reinstall missing rod.
4 Issue maintenance request or work 011 Potable Water line.
order to reinstall the missing rod.
Pipe elev. is 588'-1"; support is located at 14' N of col. line P and 5'
_E of R2.
Page 5-8 FACILITY RISK CONSULTANTS, INC.
W N ~q lo IM W
W w
w w-
- I I
j TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 565' Plant Areas: 56A. 565B. 565C, 565D & STEAM TUNNEL TVNBFN-01-R-002 Revision 0 March 26,2004 For Potential Outliers not acceptable per calculation, identify as:,M - Support modifications; D - Hardware deficiencies; O-Others
,ure evutin by scftlo EiEEEi 565B-2"0 Floor Drain line has multiple Per Calc. CDQI -999-2003-1409, Issue maintenance request or work 001 overspan conditions (1 5'-6" and 4
th overspan condition is 41 order to reinstall the disengaged rod 11 '-6" spans). Also, a rod hanger acceptable. Hqwever, the hanger. The rod hanger in question is detached.
balculation is based on the is located at about 13' N of Line T detached rod hanger being and 7'-6" W of R4. Pipe elevation is reinstalled,*
about 588'-2".
565BR-Fdne distance. vinIatinns noted on
+1Per C21c. CDQi -044-2003-1410.
N/A 002 the building heater support anchor the existing anchorage bolts. Also, attached 1 "0 and configuration isl found to be 3/4"0 lines have SAM-related
'acceptable. Also, the SAM-concerns due to rod-hung heater.
.related issue is addressed in the bounding calculation for area unit heaters (refer to CDQ1 -044-2003-2319).
565B-B ase plate anchor bolts for ilSee Calc. CDQ1 -024-2003-1411.
I m
t e
soN/A 003 various RoW lines have bolt aExisting configuration is spacing violations with adjacent r acceptable.
supports (total of 4 base plates).
a i
565B-2"0 insulated Potable Water line 4
'See Calc. CDQ1-999-2003-1 409.
N/A 004 has an overspan of 22'.
Existing configuration is acceptable.
a 565B-6" Floor Drai inhline has an Pe Calc. CDQ1 -999-2003-1409.
N/A 005 overspan of 20'-4".
' Existing configuration is
___leha acceptable. Alo__theSAM_
coce.
duordhn etr eae su sadesdi h
Page 5-9 FACtuLTYRiSK CONSULTANTS, INC.
TVANBFN-01 -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 565' Plant Areas: 565A, 565B, 565C, 565D & STEAM TUNNEL For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others
."t""
POS Brief ecrpio ption o odition g jK0INot C
alt ber I
M D 0 ummeryof ecmendations[
565B-2"0 DW line has an overspan of 4l See Calc. CDQ1 -999-2003-1409.
N/A 006 1 3'-9".
Existing configuration is
___acceptable.
565B-1"0 Building Heat line has 4
See Calc. CDQ1 -999-2003-1 409.
-N/A 007 overspan condition involving a Existing configuration is T-configu ration.
acceptable.
.5&5B-1 " Bijlildinri Heat line has 41 Se C1/2Ice flflQ -999-2003-i 409 N/A 008 overspan condition involving a Existing configuration is
____T-conf igu ration.
acceptable.
565B-4"0 Floor Drain line has overspan 4
See Caic. CDQ1 -999-2003-1409.
N/A 009 condition involving a T-Existing configuration is configuration.
acceptable.
565B-2"0 Floor Drain line has overspana 4 See Calc. CDQ1 -999-2003-1409.
N/A 010 condition involving a T-Existing configuration is conf igu ration.
_acceptable.
565B-1"0 and 1-1/2"0 Building heat lines 4l See Calc. CDQ1-999-2003-1409.
N/A 011 have overspan conditions in 2 Existing configuration is places involving T-conf igu ration.
acceptable.-
565B-2"i0 Floor Drain line has overspan 4
See Calc. CDQ1 -999-2003-1409.
N/A 012 condition (15' span).
Existing configuration is acceptable.
565B-2"0 Potable Water line has 3 4l See Caic. CDQ1 -999-2003-1 409.
N/Al 013 consecutive overspans (14'-9",
Existing configuration is 1 0'-6" and 1 3'-6").
acceptable.
Page 5-1 0 PFACILIY RSK CONSULTANTS, INCH
I I i
iI I I I
TABLE 5-I OETA ULE EOLTO UMR BE.S Plant~~
Ara:I5 655z D&SEMTNE TVA/BFN-01 -R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculation, identify as: MI Support modifications; D - Hardware deficiencies; 0 - Others
- E.:.:.... :.:-E-565B-014
- ~~~~~~~ ~
!...'............ S.........N:0"4;XWL""";':'"C:;"'
"::l Two 1 "0 Building Heat lines have multiple overspan conditions (ranging from 8' to 10'-6"). A span of 17'-1 0" exists due to a detached rod hanger support. Some lines run in series (top and bottom) and are supported by common rod hnnn~r 4
Per Calc. CDQ1 -999-2003-1409, the identified overspan conditions on the 1"o Building Heat lines are generally acceptabie, except for one instance Where a new support is required.
4 See CDQ1 -044-2003-1691.
Provide a new rod hanger support to 1 "0 line at about 11 '-6" E of R2 and 8' N of the first rod hanger just N of Line T. Pipe elevation is about 585'-6".
565B-015 I
6"0 Floor Drain line has 20'-4" span.
See Caic. CDQ1 -999-2003-1409.
N/A Existing configuration is acceptable.
[
565B-016 4"o Floor Drain line has 19' span.
See Calc. CD61 -999-2003-1409.
Existing configuration is acceptable.
i N/A 565B-1 "o & 1-1 /2"o Building Heat lines 4
Per Calc. CDQ1 -999-2003-1409, 4
See CDQ1 -044-2003-1692.
017 have two overspan conditions the overspan condition is not Provide a new support to the involving a T-branch configuration.
acceptable.
1 -1/2"o line at about 4' south of the T-intersection with 1"o line.
565B-018 Vertical capacity of the ceiling-mounted bracket support on top of the 2-1/2"o Fire Protection riser branch line is questionable.
4 Per Calc. CDQ1 -026-2003-1606, the support in question is not acceptable.
4 See CDQ1 -026-2003-2542.
Provide a new support to the 2-1/2"o line at R2/U column, and about 5' above floor El. 565'.
Page 5-11 FACtLuTY RtSK CONSULTANTS, IrNC.
l i
TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 565' Plant Areas: 565A. 565B. 565C. 565D & STEAM TUNNEL TVANBFN-01-R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; 0 - Others 565B-019 Overspan on the 8"0 Fire Protection header (22' span).
See Calc. CDQ1 -026-2003-2151.
Existing configuration is acceptable.
N/A 565B-Significant rust condition noted at The rusted tee connection has to Issue maintenance request or work 020 the tee connection between the be addressed.
order to address the rusted tee 8"o Fire Protection header and the connection. The tee is located at 2-1/2"o hranch line f
5' N of I and 1' W of R2:
El. 588'-1".
565C-2"0 Condensate line has 12' span.
4 See Calc. CDQ1-999-2003-1409.
N/A 001 Existing configuration is acceptable.
565C-8"0 Condensate line has 20'-4" 4
See Caic. CDQ1-999-2003-1409.
N/A 002 span.
Existing configuration is acceptable.
565C-4"0 Floor Drain line has 24' span.
4 See Calc. CDdl -999-2003-1409.
N/A 003 Existing configuration is acceptable.
565C-4"0 DW line and two other lines Upon further review, the support N/A 004 are supported by a cantilevered 4
in question is for a conduit Unistrut support.
supported off DW and other lines in the area. 4"0 DW line span is
< B31.1 recommended span.
Existing configuration is acceptable.
Page 5-12 2FACIY RISK CoNSuaNs, INcH
lI!
I I I
I.
i I
i' TABLE 5 POTENTIAL6lUTLIER RESlLUTION
SUMMARY
- RB EL. 565' Plant Areas: 565A, 565B. 5656, 565D & STEAM TUNNEL TVA/BFN-01 -R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculationridentify as: M.l Support modifications; D - Hardware deficiencies; 0 - Others i
I
... I......:: :::
I.
i
i ] i i i . ] i
s
i.. :1 :: 1 :: X,
:
I.................. 1. ...
I.
I I
...... I... I..., I...........
I.........I I. I..
.................. I.,................ I
=
..,.ril _:
- I~
.1.......... I. ..
.... I.
I.....
-.1 I
I I
An.
A+
i-
-Pi 7
- n.
.H....
II:
~:):
- 0:::
- %A l
- EEEi, IL i
~.
-E:::
E
~
- ER: -.
PoSl X rief ecito.of..onii Nt
&~u~i Nube
,~
PAA SmeyofHcmen N..
5650-4"0 DW line has 20'-9" span.
v See Caic. CDQ1 -999-2003-1 409 005 Existing configuration is acceptable.
5650-1-1/2"0 DW line has 12'-6" span.
v See Calc. CDQ1 -999-2003-1 409.
N/A 006 Existing configuration is acceptable.
5650-1 0 unidentified line has 9 span.
v See Cac. CDQ1 -999-2003-1 409.
N/A 007
.Existing configuration is acceptable.
565C-2"0 Floor Drain line has 19' span.
See Calc. CDQ1 -999-2003-1409.
N/A 008 Existing configuration is acceptable.
I 565C-Pipe clamp is missing on a wall-e3/4"0 Rad Wate line results in Issue maintenance request or work 009 mounted Unistrut pipe support for excessive overspan due to i
order to reinstall the missing pipe 3/4"0 Rad Waste line, missing pipe clamp. Reinstall the clamp. Support is located just N of missing clamp.
U-Line (5" from wall) and W of R5 (nearest pipe elbow is at 5'-4" W of R5). Pipe elevation is at about 568'-6".
5650-Edge distance violations noted on Per Calc. CDQ1 -044-2003-1 41 0, N/A 010 the building heater support anchor 41 the existing anchorage bolts.
configuration is acceptable.
565C-2"0 Raw Water Cooling line has 4p See CaIc. CDQ1 -999-2003-1409.
N/A 011 14' span.
Existing configuration is acceptable.
56.C Piecapiisn nawl-34o dWselierslsi su aneac eus rwr Page 5-13 PCILTY RtSK CoNSumTS, Imc.
I I
TABLE 5 POTENTIAL
-UTLIER RESOLUTION
SUMMARY
- RB EL. 565' Plant Areas: 565A. 565B. 565 ~. 565D & STEAM TUNNEL TVNABFN-01 -R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculatiorl, identify as: M - Support modifications; D - Hardware deficiencies; 0 - Others
- I 565C-012 2"0 Raw Water Cooling line has 14'-6" span (gang-supported to a 2"0 N2 Makeup line above it). In addition, a 1 "o line (about 8' tributary span) is hanging off the RCW line via spacer supports.
4 Per Calc. CDQi -999-2003-1409, the existing configuration is found to be not acceptable.
4 I Provide a new support for the 2"0 N2 Makeup line, which in turn is supporting the overspan 2"0 RCW line below it.
4-.---4 565r-013 1-1.2"0 Fire Prnte ction branch line has 15' span.
4 See CaIc. CDQ1 -026-2003-2151.
'Existing configuration is
! acceptable.
N/A 565C-Missing hardware on a trapeze Per CaIc. CDQ1 -026-2003-2558, Reinstall all missing hardware in the 014 rod hanger support for 8"0 Fire 4
the existing configuration (with 4
support in order for the support to Protection header, resulting into the support assumed to be be effective.
piping overspan.
ineffective) is acceptable.
The support is located 8' N of S line However, it is recommended that and 8' W of wall penetration at R7 the support be, restored to its wall. Pipe elev. is at about 576'.
_ original design condition.
565D-4"0 DW line has 17'-6" span.
4 See CaIc. CDQ1 -999-2003-1409.
N/A 001 Existing configuration is
_ _ i __
acceptable.
565D-4"0 Floor Drain line has 17'-5" and 4
See Caic. CDQ1-999-2003-1409.
N/A 002 1 8'-4" spans.
Existing configuration is acceptable.
Page 5-1 4 FACItTY RISK CONSULTANTS, INC.
l l
TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 565' Plant Areas: 565A. 565B. 565C, 565D & STEAM TUNNEL TVA/BFN-01 -R-002 Revision 0 March 26,2004 For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others
- ,C
.:T.....'-.....
i,....
t: f f..
- 'i:':.":'S '"L' 't"t: 4 l " '
n :
'"0 :0 '..;".0 t.f'S" t. .' '"'~ "'"L E"St fe.n KmmKC..e.t 565D-4"0 Floor Drain line rod hanger is 4"0 Floor Drain line results in
_Issue maintenance request or work 003 detached.
al excessive overspan due to the 4l order to reinstall the detached rod disengaged rod hanger. Reinstall hanger. Support is located at about the detached rod hanger.
10' N of Q and 3' E of R6. Pipe
_ elevation is at about 588'-4".
565D-Vertical capacity of the wall-Per Calc. 0001 -026-2003-1952, See CDQ1 -026-2003-2543.
004 mounted bracket support on top of 4
the support in question is not 4
.P..
a, new
.suo to the 2-1/2.0 Fire Protection nser a2-12" line at R7/P column.
branch line is questionable.
Pipe elev. is at about 582'.
565D-4"o Fire Protection line has 147'-6" 4
See Caic. CDQ1 -026-2003-2151.
.ss N/A 005 and 16' spans.
Existing configuration is h
acceptable.
hange._____of__and___of
__Pip STNL 1 "0 RCIC/ Rad Waste line has 4
See CaIc. CDQ1 -999-2003-1409.
N/A
-001 10'-2" and 1b0'-0" spans.
Existing configuration is the____
2_1__ Fire Protection iseracceptable.
2_______line
_at ______column.
STNL 1 "0 Reactor Feedwater line has 4l See Caic. CD0 1-999-2003-1409.
N/A
-002 12'-3" span.
Existing configuration is acceptable.
Page 5-15 P 55CItwY RISK CONSULTANTS,* INC.
I TVA/BFN-01 -R-002 Revision 0 March 26, 2004 I
i I i
TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 593' Plant Areas: 593A, 593B. 593C & 593D For Potential Outliers not acceptable per calculaticrn, identify as: M, Support modifications; D - Hardware deficiencies; O - Others i P i03 lBrief Daescriptio of Cnitn 0
Not atclat dube M D 0 Sumryo Recommend:tion Nt.0Z CU a OMi; W
593A-Two 6"0 Fuel Pool Cooling lines 4
See Calc. CDQ1 -999-2003-1601.
_.. N/A 001 have about 22' spans.
Existing configurations are acceptable.!
593A-1 "0 uninsulated Air Conditioning 1
See Ca. c. CDQ1 -999-2003-1601.
N/A 002 line has multiple overspanExisting configurations are conditions (max. of 1 6'-9" span).
acceptable.
593A-Two 1 "0 insulated Air Conditioning 4
Se Caic. CDQ1 -999-2003-1 601.
N/A 003 lines have several overspan Existing configurations are conditions.
acceptable.
m 593A-3"0 Floor Drain has 2 overspan 4
See Ca.c.
.CDQ1
-999-2003-1601.
N/A 004 conditions (15' & 20'-6" spans).
Existing configu rations are acceptable.l 593A-4"0 Floor Drain line has 1 5'-9" See Ca.c. CDQ1 -999-2003-1 601.
... N/A 005 span.
Existing configuration is acceptable.
I 593A-Two 1/2 "0 RBCCW socket-welded 4
See Calc. CDQ1 -999-2003-1601.
N/A 006 pipes have 11 '-5" and 10'-1 0" Existing configurations are spans.
acceptable.
Page 5-16 FCLTy RtSK CONSULTANTS, IAmc
Tv'AIBFkN- 01-R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 593' Plant Areas: 593A. 593B. 593C & 593D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others On t 593A-Line is leaking at threaded bronze Per Calc. CDQ1 -999-2003-1601, Issue maintenance request or work 007 hand valve near T-connection of 4l the overspan condition of 1 3'-4" 41 order to repair the leaking x/2 "0 tubing to 1.2" Raw Cooling span is acceptable. However, connection. The
./2".
line with Water header. Also, the 1/2"0 line leaking connection on the 1/2"0 line leaking connection is located about has 13'-4" span.
is not acceptable.
4' west of R3, between P & Q (off POthe 12" RCW header). The l
1/2"0 line is at Elev. 608'-1".
593A-Two 3"0 insulated Building Heat 1
See Calc. CDQ1 -999-2003-1601.
N/A 008 lines have 2 consecutive Existing configurations are
____overspans (18' and 20'-3").
___acceptable.
593A-1 "L insulated Demin. Water line P See CaIc. CDQ1 -999-2003-1601.
I m
t e
soN/A 009 has 2 consecutive overspans (12' Existing configurations are
& 11'-4").
acceptable.
593A-Two 2"0 PSO/PSt Overflow lines 4
See Cahc. CDQ1 -999-2003-1601.
rTN/A 010 have overspans (max. of 1i4'-4").
Existing configurations are acceptable.__
593B-1Tw/2 o 2"o and 3"0 Building Heat 4
See CaIc. CDQ1 -044-2003-1607.
N/A 001 lines have multiple overspan Existing configurations are conditions.
acceptable.
Page 5-17 FACLITY RtSK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAl OUTLIER RESOLUTION
SUMMARY
- RB EL. 593' Plant Areas: 593A. 593B. 593C & 593D For Potential Outliers not acceptable per calculation! identify as: M I
i
- Support modifications; D - Hardware deficiencies; 0 - Others ri
- e..
fo of C on M
u
.0
'i"t X....
C.;.........S.,--
0.S..
X..... It D,0 f-.
fl MAI iA i;Ti.
i 't'.
I
'.. C...................
t 593B-1 "0 Equipment Drain line has a Per Caic. CD.1 -999-2003-1.601, See Caic. CQ1 -000-2003-1605.
002 detached rod hanger resulting in v
normal operatin~g stresses for the 4Risall the disengaged rod l overspan condition of 17'-6".
'1 "o line due to !the disengaged rod hanger.
Also, even with the detached rod (1 7'-6" span) i; marginal.
l hanger in place, span is 11,i
'0,.
However, the span of 11'-1 0" is
>acceptable provided that the disengaged rod hanger is
~~reinstalled.
593B-
"o Building Heat lines have 2 4
See Calc. CDQ1 -999-2003-1601.
N/A 003 consecutive overspan conditions I Existing configurations are (max. of 9'-8" span).
acceptable.
593B-1/2"P RBCCW pipe has multiple Existing configurations are See Calc. CDQ1 -070-2003-1604.
004 overspans (spans of 6'-6", 8'-2",
1 bo unded by similar overspan Replace the deformed segments of 1 0' & 1 0'-8") and is sagging in conditions iden~tified in P05 593A-the pipe routing, or reroute the some areas (appear to have been 006 (see Calc) CDQ1 -999-2003-piping, as necessary.
stepped on causing permanent 1601) which were shown to be deformations).
acceptable. However, the deformed conditions are not acceptable.
593B-3"o Floor Drain line has 16' span.
See Calc. CDQ1 -999-2003-1601.
N/A 005 Existing configuration is (max.__of_9
__8
__span)._acceptable.
593B-~~
./"
BC iehsmlil xsigcnigrtosaeSeCl.CQ 0020-64 593B-006 Branch line flexibility concern on 3/4"o and 1/2"o Building Heat lines near the rod-hung building heater.
Branch line flexibility (SAM-related) issues are addressed in the bounding calculation for typical area unit heaters (refer to CDQ1 -
044-2003-2319).
- I N/A Page 5-18 FACILITY RSK CQONSULTANTS, iNC.
TABLE 5 POTENTIAL dUTLIER RESOLUTION
SUMMARY
- RB EL. 593' pDlni Avrana cO'aA IrqaR rani z nQofn TVAIBFN-01-R-002 Revision 0 March 26, 2004
.w sz vc.
<o e
rp s1.
_.a v
For Potential Outliers not acceptable per calculations identify as: M - Support modifications; D - Hardware deficiencies; O-Others St,;ft'St'St:~~~~~~~~~~~.i::.
- ...... :f-A S-
-Sf
..... Sg
- g
.:i..itE.: ~ ~
~
~
~
~
~
~
~
~
~
~
- .,-...,:....i
.:. EE Rii
.~-
i n-lE:.E~..
.....: i.....~t i
ni :---:ii: Sii
..-:.....i. i:
No,:
Brief t
ot
......0..
No.
Galculatlonr Number I C`o1MmenS:;
593B-2"0 RBCCW line has a detached See CaIc. CDQ1 -999-2003-1601.
Issue maintenance request or work 007 rod hanger resulting in overspan Existing configuration is found to be 4
order to re-install the missing rod.
condition of 14'-1 0".
acceptable. However, it is The location of the missing rod is at recommended that the missing rod 7'-2" east of R2 and 2'-9" north of be re-installed,to preclude any column line T. The 2"o line is at falling interaction of the support Elev. 617'-3". Note that pipe clamp hardware that are still in place.
is still attached to the pipe.
593B-4"o Floor Drain line has multiple 4
See CaIc. CDQ1 -999-2003-1601.
N/A 008 overspan conditions involving Existing configuration is T-configurations.
acceptable.
593B-2 - 2"o PSC/PSC Overflow lines 4
See Calc. CDQ1 -999-2003-1601.
N/A 009 have overspans (max. of 11 '-1 0').
Existing configuration is acceptable.
5938-Y/2 "0 Primary Containment 4
See CaIc. CDQl -999-2003-1601.
N/A 010 Isolation line has 11 '-9" span.
Existing configuration is acceptable.
593C-4"0 Floor Drain line has 20'-1" 4
See Calc. CDQ1 -999-2003-1601.
N/A 001 span.
Existing configuration is acceptable.
593C-2"0 RWCU line has 14' span.
4 See CaIc. CDQ1 -999-2003-1601.
N/A 002 Existing configuration is acceptable.
I Page 5-1 9 i I I
FACatY RtSK CONSULTANTS, Ihca
TVN'BFN-01 -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 593' Plant Areas: 593A, 593B, 593C & 593D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others
-POSit Brieft Dciptio of Cndi tio
. W.
...., X..;X
.....X 593C-Edge distance violations noted on 003 the building heater support anchor bolts.
Qutiii
- i.
P0 No"t:
OKi C..............
Edge distance violations on th existing anchorage configurati are similar to and bounded by those identified in El. 565' (refi Calc. CDQ1 -044-2003-1410).
Although the seismic demand are larger for El. 593', it is judc aceptsablex bazsed onl te large margins shown in the above calculation.
100:iby :60"'0u at1o
.......... r I
O M i.E i..,
..,..-,.... EE L~~~ -M DSf Summary of Recommendatic
......I................
e N/A on er to loads
]ed irS 593C-4"o Floor Drain line has an 4
See Calc. CDQ1 -999-2003-1601.
N/A 004 overspan condition involving Existing configuration is T-configurations.
acceptable.
593C-1/2 "0 RBCCW line has typical See Calc. CDQ1 -999-2003-1601.
N/A 005 span of 10'. Another 1/2 "0 o
Existing configurations are RBCCW line is gang-supported acceptable.
from the above line at 5' span, typical.
593C-Branch line flexibility concern on Branch line flexibility (SAM-related)
N/A 006 3/4"0 and 1/2"o Building Heat 4
issues are addressed in the lines near the rod-hung building bounding calculation for typical heater.
area unit heaters (refer to CDQ1 -
044-2003-2319).
593D-2"o Condensate S&S line has 4
See Calc. CDQ1 -999-2003-1601.
N/A 001 20'-5" span.
Existing configurations are acceptable.
Page 5-20 FACtLTy RtSK CONSULTANTS, IMtC
TABLE 5 POTENTIAL OUTLIER RES6LUTION
SUMMARY
- RB EL. 593' Plant Areas: 593A, 693B. 593C & 593D TVA'BFN-01 -R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others P
B e..
f pt..
of C'io 0
m..y
'f
-mmI
"tio'Ins
.:F q I.P..-.X.
.. L..........
EfiiiT;.E
.iiiiE........-.-
593D-3"0 Floor Drain line has 1 7'-4" 4l See Calc. CDQ1 -999-2003-1601.
N/A 002 span.
Existing configuration is
_________________________________________a c c e p ta b le._
593D-2"0 RBCCW line has 1 3'-1 0" 4
See Caic. jCD6 1 -999-2003-1601.
N/A 003 span.
Existing configuration is
~acceptable.
593D=
3"o Raw Cooling Water line has 4!
See Ga~c.G(1-9920-1601.
N/A 004 1 7'-5" span.
Existing configuration is acceptable.
593D-6"0 Fuel Pool Cooling lines have 4l See Calc. CDQ1 -999-2003-1601.
N/A 005 20' spans.
Existing configuration is
_acceptable.
593D-Potential rod fatigue concerns on 4
See Caic. CDQ1 -000-2003-1603.
N/A 006 multiple short fixed end rods Existing configuration is supporting 4"0 Floor Drain line, acceptable.
.......... X.............
Page 5-21 FACLWTY RtSK CONSULTANTS, INC.
TVAABFN-01-R-002 Revision 0 March 26,2004 I
TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 621 '-3" Plant Areas: 621 A. 621 BI 621 C & 621 D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; 0 - Others iPOS tBrie lDscriptkn vil~ndi'ion00' M4 D 0l umm*ary of1 ReOmm ti~tons
- L:--.E':-,...
,.L:
i;
.d.::i........-........-
No 0
~~~~Not tievoulainNubr(Cm et 621 A-3/4" Gland Seal line has multiple See Cac. CQ -999-2003-1602.
N/A 001 overspan conditions.
Existing configurations are acceptable.
621 A-4" Equipment Drain has 17' 4.e Ca.c. CdQi -999-2003-1602.
N/A 002 span.
Existing configuration is acceptable.___
621 A-3", 2"o & 1 "0 Standby Liquid 4l Unrestrained drum may overtun See Ca-c. CDQ1 -063-2003-1614.
003 Control (SLO) flush lines empty and spill contents, thereby poses Provide restraint to the free-into unrestrained 55 gal. plastic as a 1i/I spray hazard during a sadn lsi rm drum. Drum may overturn and seismic event. The plastic drum spill contents.
has to be restrained or removed
~from the area.__
621 A-Bracket support for eyewash 4
See Calc. CDQ1 -000-2003-1613.
N/A 004 station is mounted to block wall Existing anchorage configuration with 1/4/"o toggle bolts. Verify for the eyewash station is shown to support adequacy.
be adequate. [
621 A-1 "0 SLC line has a detached rod Per Caic. CDQ1 -999-2003-1602, See Calc. CDQ1 -063-2003-1615.
005 hanger resultin in esn 4me overspillan condition is not 4v Reinstall the disengaged rod condition of 28'-1 0". Detached rod acceptable. Haowever, per Cac.
hanger, or provide a new support h
anger is near midspan.
CQT-063-2003-1615, the above near the location of the detached overspan condition was found to be rod hanger.
acceptable prqvided that the detached rod hanger is reinstalled at or near mid0pan.
aboenarheocaionofhe
_etahe Page 5-22 i
, i Pg52FAc RiSK CoNSuLTAmS, Ic.
,1, TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 621 '-3" Plant Areas: 621 A. 621 B. 621 C & 621 D TVANBFN-01-R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others N..
..'0..
.Nt.,
.al..atio Num r I Coms.
I.....
. HEEt
.li............
.' '"'a
..'.;" ' i;"'
621 A-Two 1 "0 Air Conditioning lines 41 See Caic. CD 1 -999-2003-1 602.
N/A 006 have several overspan conditions Existing configuration is (max. of 10'-6" span).
acceptable.a 621 B-Flexibility (SAM-related) concern 4
z See Calc. CDQ1 -044-2003-1608.
N/A 001 on 1 "o Building Heat lines near Existing configuration is the rod-hung building heater, acceptable. In addition, the SAM-related issue is also addressed in the bounding caicuiation for area unit heaters (refer to CDQ1 -044-
___2003-2319).
d 621 B-Excessive corrosion/rust on 1"o &
4 The rusted threaded joints have to 4 Issue maintenance request or 002 3/4"o Building Heat lines near the be addressed to preclude any work order to address the rusted building heater.
potential Il/I spray hazard.
threaded joints.
621 B-1 1/2"0 Building Heat line has v See Ca.c. CDQ1 -044-2003-1608.
N/A 003 overspan condition, with additional Existing configuration is load from 1 "o branch line at acceptable.
T-intersection.
621 B-1 Y2"0 Building Heat line has 4
See Calc. CDQ1 -044-2003-1 608.
N/A 004 several overspan conditions Existing configuration isi involving T-configu rations.
acceptable.
621 B-Two 1 "0 Build ing Heat lines have 4'See Calc. CDQ1 -044-2003-1608.
N/A 005 several overspan conditions (max.
Existing configurations are of 1(0' span).
acceptable.
I Page 5-.23 FACLITY RtsK CoNSuLA S, iacl
Tv'A'NFN-O1 -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 621 '-3" Plant Areas: 621 A, 621 B. 621 C & 621 D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others
"it""'t
..le e.tIo nul.....
PC Br f Cp r ipto ofCodtin 0 Snmro e:mnai
- No i..
Cacuato Nube Comments:4;000;t0;:
- 0t'l"'~ :;.
621 B-4"o Floor Drain line has multiple 4
See Ca.c. CDQ1 -999-2003-1602.
N/A 006 overspan conditions involving Existing configuration is T-configurations.
acceptable.
621 B-6"0 Condensate S&S line has 20' 4
See Calc. CDQ1 -999-2003-1602.
N/A 007 span.
Existing configuration is T__ o____________
acceptable.
621 C-4"o Condensate S&S line has 15'-
4 See Calc. CDQ1 -999-2003= 602.
N/A 001 6" span.
Existing configuration is acceptable.
621 C-3"o Demin. Water line has 1 7'-6" 4
See Calc. CDQ1 -999-2003-1602.
N/A 002 span.
Existing configuration is acceptable.
621OC I
I C-
)3
_RWCU pumps 1 A & 1 B appeared to be inadequately supported.
Pumps are in-line supported on 1 t/2 "0 line with large eccentricities.
Also, there are potential SAM-related flexibility concerns on the 3/4"0 lines.
4 See Calc. CDQ1 -069-2003 Existing pump support configuration and the poter SAM-related flexibility conc the 3/4"0 lines are shown to acceptable.
-1612.
N/A itial oems on be Page 5-24 P 4FACLTy RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 I
TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 621 '-3" Plant Areas: 621 A. 621 B. 621 C & 621 D For Potential Outliers not acceptable per calculation. identify as: M &- Support modifications; D - Hardware deficiencies; O-Others na r E.
hb, th SA related issue in also addressed in the bounding calculation for typical area unit heaters (refer to CDQ1 -
044-2003-2319).
6210C-1.2 "0 Building Heat line has See Caic. CD.1 -044-2003-1608.
N/A 005 multiple overspan conditions Existing configu~rations are (max. of 13' span) acceptable. j 6210C-1 "0 Building Heat line has multiple 4
See Calc. CDQ1 -044-2003-1 608.
N/A 006 overspan conditions (max. of 1 3'-
Existing conf igu~rations are span) acceptable.
6210C-2 "0 air-operated valve 1 -FCV-See Ca.c. CDQ1 -069-2003-1610.
N/A 007 69-78 has large eccentric mass.
'Existing valve configuration is acceptable.
621 D-Flexibility (SAM-related) concern 4
See Calc. CDQ1 -026-2003-1609.
N/A 001 on 11 / "3 Fire Protection branch Existing configuration is off the 3"o riser.
acceptable.
621 D-Two 1 "o Air Conditioning lines v
See Calc. CDQ1 -999-2003-1 602.
N/A 002 have several overspan conditions Existing configuration is (typical span of 11').
acceptable.
621 D-2"0 Fuel Pool Overflow line has 3 4
See Calc. CDQ1 -999-2003-1602.
N/A 003 consecutive overspans (max.
Existing configuration is span of 13'-6)).
acceptable.
Page 5-25 FACtLITY RISK CONSULTANTS, INCH
-Ww T, A'BFN-01 -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 639' Plant Areas: 639A. 639B. 639C & 639D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; 0 - Others CE t
- ......- t.-;
- '"""i;'"f0'"dS'f"f't'"d;S"':'"'t
.'6""
O.t.i.r. E Aluel by..fcu o
NO..............
a k u tn A Pum e -i tnmm nt c m e d t tE d-f--S--,-
-h -q f-
... i. -.
...-.-. L.-..
- i.
ii........-
- h.
639A-1 "0 GS line has 18'-4" span and Per Caic. CDQ1 -037-2003-1177, Refer to Caic. CDQ1 -037-2003-001 wall brackets lack U-bolts (line can 4
stress on the overspan segment is 4
1177 for recommended plant slide off of supports).
marginal. Also, seismic modification - i.e., add new wall displacement of the existing bracket to the overspan pipe.
configuration may cause line to slide ott its supports.
639A-1"o GS line has 12' span.
4 Per Calc. CDQ1 -999-2003-1072, N/A 002 the existing configuration is acceptable.
639A-3"o GS / Condensate S&S line Per Calc. CDQ1 -999-2003-1072, N/A 003 has 2 consecutive overspans (19' a
the existing configurations are and 15'). Also, 2"o DW line has acceptable.
an overspan of 19'.
639A-Anchorage appears marginal for A
Per Calc. CDQ1 -037-2003-1178, N/A 004 GS storage tank.
the existing configuration is acceptable, 639A-1"o DW line has 9'-6" span. Line 4
Per Calc. CDQ1 -999-2003-1072, N/A 005 is cut and capped, sagging noted.
the existing configuration is
_ _ _ acceptable.
639A-2"o FP Overflow line has 14'-7" 4
Per Calc. CDQ1 -999-2003-1072, N/A 006 span.
the existing configuration is acceptable.
Page 5-26 6FACLTy RtSK CONSlTANTS, INC.
W
,-W 1W1 Wr1Wlw1 TVANBFN-01 -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 639' Plant Areas: 639A. 639B. 639C & 639D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O-Others 3"o Floor Drain line has 2(
Per Calc. COQ1 -999-2003-1072, the existing!configuration is acceptable.
N/A 639A-008 1 "0 Building Heat line at interface with the unit area heater (including union) is rusted.
I I
NV The rusted pipe segments and threaded joints have to be addressed to preclude any potential iN spray hazard.
Issue maintenance request or work order to replace rusted pipe segments and union joints at the heater interface.
639A-Two 1"o Building Heat lines have 009 12' span.
Existing configurations are bounded by similar conditions addressed in CaIc. CDQ1-044-2003-1087 for POS 639B-003, and therefore are acceptable.
N/A 639A-010 Area heater of Building Heat system is rod hung and may cause SAM problems for the connecting 1"o & 3/4"o lines.
Existing configuration is bounded by similar conditions addressed in CaIc. CDQ1 -044-2003-1087, and therefore is acceptable. In addition, the SAM-related issue is also addressed in the bounding calculation for typical area unit heaters (refer to CDQ1 -044-2003-231 9).
N/A
_~
Page 5-27 FACILITY RISK CONSULTANTS, INC.
W VW lw qW W VW 1W 1W 1W wq NW w
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RE Plant Areas: 639A For Potential Outliers not acceptable per calculation, identify as:
i..i.......
oi l.
v8Iu-tt S
Brief D"e~scriptitn of Cnditi V
Galcufatlor
.i SOLUTION
SUMMARY
- RB EL. 639' 639B. 639C & 639D M - Support modifications; D - Hardware deficiencies; 0 - Others 1...
....... m e n i 639A-3/4"0 FP Overflow drain line has Existing configuration is bounded Refer to Calc. CDQ1 -078-2003-011 SAM-related concern due to the 4
by similar conditions identified in 4
1226 for recommended plant E-W movement of 6"0 Rx Head POS 639C-004 and POS 639C-008 modification - i.e., provide a new Exhaust line. Note that the pipe (refer to Calc. CDQ1 -078-2003-support to the 6"0 line near the stanchion support for the 6"o line 1226), and is therefore stanchion support.
is free to slide in the E-W unacceptable.
direction.
639B-4"0 Floor Drain line has 18'-6" 4
Per Calc. CDQ1 -999-2003-1072, N/A 001 span.
the existing configuration is acceptable.l 639B-Lube oil cooler has marginal tack 4
Per DCN # t51219, the MG sets will N/A 002 weld attachment to its support be replaced by VFD and the lube saddle.
oil coolers will be removed.
639B-Building heat lines are rod hung 4
Per Calc. CDQ1 -044-2003-1087, N/A 003 and have several overspan the existing configuration is conditions. Lines terminate at rod acceptable!
hung area heaters.
639B-Seismic movement of a 3"0 FP 4
Per Calc. CDQ1 -026-2003-1088, N/A 004 riser imposes SAM to 1-1/2"0 the existing configuration is branch line (to hose station).
acceptable_
639B-1 "o to 3"0 Condensate S&S line 4
Per Calc. CDQ1 -002-2003-1086, N/A 005 has multiple overspan conditions the existing configuration is and non-standard reducerfittings acceptable are used.
I Page 5-8 PFAACIL TY RISK CONSULTANTs, INC,
w wF -
w w
w w
w w
l-TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 639' Plant Areas: 639A, 639B. 639C & 639D TVANBFN-01-R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; 0 - Others POS
-Brif X
D rt:
in u
b
"....of
- 'Xf'SEES"X'~~~~A
.:.---.f--
T.f 1:1 A--: '"f
"t0'~V'"t.
.4.
N.
K~
.acuato.Nm.r...met Riomndt 639B-3"0 Floor Drain line has 23' span.
4 Per Calc. CbQl -999-2003-1072,
_ N/A 006 lthe existing configuration isl acceptable.
6390-Pipe flange is leaking on short 41 This problem is not directly related 4 Work Order # 03-005020-000 is 001 riser of 3"o Condensate S&S line, to seismic adequacy and should be issued to address the leaking resolved by.maintenance action,.
flange connection.
6390-1 "0 to 3"o Condensate S&S line Per Calc. COQi -002-2003-1086, N/A 002 has multiple overspan conditions 4
the existing configuration is; and non-standard reducer fittings acceptable (included in the analysis are used.
to address P05 639B-005).
6390-4"e ROW line has 2 overspan Per Calc. CDQ1 -999-2003-1072, N/A 003 conditions - 1 @?24' and 1 @16' 41 the existing' configuration is that is piggy back from the 8"e acceptable.
i ROW line.
6390-6"o Rx Head Exhaust line has Per Calc. CDQ1 -078-2003-1226, Refer to CaNc. GDQ1 -078-2003-004 stanchion support that is not 4
the existing stanchion support does 4
1226 for recommended plant positively anchored.
not provide adequate restraint to modification - i.e., provide a new the 6"o line, thus could result in support to the 6"s line near the SAM-related concer on the l"0 stanchion support.
Fuel Pool Overflow drain line.
639C-2"o DW line has 3 consecutive v
Per Calc. CDQ1 -002-2003-1085, N/A 005 overspans of 1 6'-6",13', and 14'.
the existing configuration is tbc t acceptable.
Page 5-29i FACtuTY RtsK CONSULTANTS, INC.
W v
-R-----
TVANBFN-01-R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 639' Plant Areas: 639A. 639B. 639C & 639D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; 0 - Others I
I I
Page 5-30 FACLItY RISK CONSULTANTS, INC.
.N W
-w w
w ni MDFN-01 -R-002 Revision 0 March 26, 2004 TABLE 5 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 639' Plant Areas: 639A. 639B. 639C & 639D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; 0 - Others F
X I
I I
I Page 5-31 FACILITY RISK CoNSuLTANTS, INC.
pw 4
-Wlw MW -
w TVANBFN-O1-R-002 Revision 0 March 26, 2004 TABLE 6 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 664' Plant Areas: 664A. 6640. 664C & 664D For Potential Outliers not acceptable per calculation, identify as: M - Support modifications; D - Hardware deficiencies; O - Others l
- 1........
E 664A-001
,,..X.-.
- I...
.....I....
E i...-.
'd i-t :t-.. ' 't,'.tE :.1 l :
i,g 0 Three (3) 1"0 Building Heat lines have 13' spans See CDQ1 -999-2003-1414.
Existing configurations are acceptable.
664A-3"0 unidentified line has 13' span J q
See CDQ1-999-2003-1414.
- l N/A n02 EFxistinn rnnfiniirntinn is acceptable.
664A-Verify seismic adequacy of the Per Calc. CDQ1 -044-2003-1406, N/A 003 support member and weld the existing support attachment of typical building unit configurations of unit heaters in heater in the area. Building heater this area are acceptable.
is located in col. lines R1-S and R2-Px.
664B-8"0 Condensate S & S line has 26' 4
See CDQ1 -999-2003-1414.
N/A 001 span Existing configuration is acceptable.
i i
I Page 5-32 I PFACITY RSK CoNSuAmS, imc.
W e-X TABLE 6 POTENTIAL 1UTLIER RESOLUTION
SUMMARY
- RB EL. 664' Plant Areas: 664A. 664B. 664C & 664D TVANBFN-01 -R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculation, identify as: M + Support modifications; D - Hardware deficiencies; 0 - Others PoS rIef DeritAotioNo I
oti 664B-Overspan on both 1 "0 insulated Per Calc. ODQl -044-2003-1198 Install new aircraft cable support, 002 Building Heat supply and return 4
the existing piping configuration 4
bracing the 11/4"o pipe member to lines off the area heater located in is acceptable, thius overspan the main building steel column.
col. lines R4-Ux. Also, verify conditions are resolved.
Refer to Calc. CDQ1 -044-2003-seismic adequacy of the support However, per qalc. CDQ1 -044-1600 for design loads and details.
member and weld attachment of 2003-1406, existing support tvpical bHilding unit heater in the config.uration of one of 2 unit area. Building heaters are located heaters in this area (R4-Ux) is not in col. lines R2-Ux and R4-Ux.
acceptable. Unit heater in col.
lines R2-Ux is ad equate as-is.
6640-8"0 Condensate S & S line has 26' 4
See CDQ1 -999-2003-1 41 4.
N/A 001 span Existing configuration is acceptable.__
6640- 1 "0 Building Heat line has 11' 4
See CDQ1 -999-2003-1414.
N/A 002 span Existing configurations are acceptable.
6640-2"o Drain line has 1 5'-6" span 4
See CDQ1 -999-2003-1414.
N/A 003 Existing configurations are Macceptable.
6640-Verify seismic adequacy of the Per Calc. CDQ1 -044-2003-1406,
.c b
N/A 004 support member and weld 4nthe existing support configuration attachment of typical building unit of unit heater in this area is heater in the area. Building heater acceptable.
is located in col. lines R6-Ux.
a Page 5-33 FACILTY RISK CoNSuLa s, IMt:c
p 4RW w"I 1_
11 114
-W_10 W
~
i4 I
I
.II I
I TABLE 6 POTENTIAL OUTLIER RESOLUTION
SUMMARY
- RB EL. 664' Plant Areas: 664A. 664B. 664C & 664D TVA/BFN-01 -R-002 Revision 0 March 26, 2004 For Potential Outliers not acceptable per calculation, identify as: M ; Support modifications; D - Hardware deficiencies; 0 - Others Tank may slide and cause attached piping to break (3/4"0 water heater supply lines, System 029)
Per Calc. CDQ1 -029-2003-1407, the seismic motion would cause the attached piping to rupture at the union connection, and result in a spray hazard.
steel clip angles and expansion anchor bolts.
Refer to Calc. CDQ1 -029-2003-1407 for design loads and details.
664D-Three (3) 1"0 Building Heat lines 1 VSee CDQ1-999-2003-1414.
l. l l
N/A 001 have 13' spans Existing configuration is acceptable.
664D-3"0 Unidentified line has 13' span 4
See CDQ1 -999-2003-1414.
N/A 002 Existing configuration is acceptable.
664D-Three (3) 1"0 Building Heat lines 4
Per CDQ1 -999-2003-1414, the 4
Add a new gang-support at column 003 have 17'-6", 16'-2", and 14'-2" existing configuration is not R7-Px to reduce the existing spans acceptable.
overspan of the 3-1"0 lines.
Refer to Calc. CDQ1 -044-2003-1611 for design loads and details.
664D-Verify seismic adequacy of the Per Calc. CDQ1 -044-2003-1406, Install new aircraft cable support, 004 support member and weld 4
existing support configuration of 4
bracing the 1 14"0 pipe member to attachment of typical building unit one of 2 unit heaters in this area the main building steel column.
heater in the area. Building (R4-Px) is not acceptable. Unit Refer to Calc. CDQ1 -044-2003-heaters are located in col. lines heater in col. lines R6-Px is 1600 for design loads and details.
R4-Px and R6-Px.
acceptable as-is.
Page 5-34 FACITY RtSK CoNsua NTs, inc.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004
- 6.
SUMMARY
AND RECOMMENDATIONS Of the twenty-seven (27) plant areas in the Reactor Building considered for BFN-1 seismic-induced 11/I spray hazard program, a total of one hundred seventy-nine (179) potential outliers were identified during the in-plant screening walkdowns. Majority of these potential outliers were resolved by performing further analyses and evaluations to the acceptance criteria of TVA Design Criteria BFN-50-C-7306 (Reference 7-2). For the remaining outliers that did not meet the above evaluation criteria, plant design modifications are developed for appropriate resolution. In addition, work requests are initiated for those outliers that fall into the general category of maintenance and housekeeping items, such as missing support hardware, severe rust conditions and others. Table 6-1 presents a summary of the BFN-1 seismic 11/I spray evaluation program.
6.1 Plant Modifications Plant design modifications are developed for outliers not meeting the acceptance requirements of TVA Design Criteria EIFN-50-C-7306 (Reference 7-2). Design modifications ranged from simple support hardware modifications to addition of new pipe supports, rerouting of piping and others. A total of nineteen (19) plant design modifications were implemented for the resolution of these seismic 11/I spray outliers. A -
brief description of each of the plant modifications is provided in Table 6-2.
Engineering design of the plant modifications are documented in various calculation packages listed in Appendix C of this report. These plant modifications will be implemented under Design Change Notice DCN 51669.
6.2 Maintenance and Housekeeping Items In addition to the plant modifications discussed in Section 6.1 above, a total of thirteen (13) miscellaneous maintenance and housekeeping items were identified for appropriate actions and resolution. These maintenance items, along with their locations and brief description, are tabulated in Table 6-3. These items will be disposed through maintenance work requests.
Page 6-1 FACILaTy RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE 6-1 Summary of BFN-1 Seismic I1/I Spray Evaluation Program RB El. 519' &
541'-6" NWQUAD, NEQUA[),
SWQUAD, SEQUAD, HPCI, TORUS 6
28 4
1 RB El. 565' 565A, 565B, 565C, 565D, 5
52 4(1) 7 STNL RB El. 593' 593A, 593B, 593C, !593D 4
32 1(2) 2 RB El. 621 '-3" 621 A, 621 B, 621C, (321 D 4
23 2
1 RB El. 639' 639A, 639B, 639C, 639D 4
30 4
2 RB El. 664' 664A, 664B, 664C, 664D 4
14 4
0 Total No. of IVI Spray Walkdown Plant Areas 2:
Total No. of IVl Spray Potential Outliers Identified Total N-of-PraiitfDes-inModifications (DCN-51669)-=
Total No. of Misc. Maintenance and Housekeeping Items (1) POS 565C-012 was resolved per DC:N 51178.
(2) POS 593B-004 was resolved per DCN 51182.
Page 6-2 FACIUTY RiSK CONSULTANTS, INC.
TVAIBFN-01 -R-002 Revision 0 March 26,2004 TABLE 6-2 Summary of Plant Modifications BFN-1 Seismic IVI Spray Evaluation Program 1
RB El. 541'-6" POS NEQUAD-002 Add one new support to the 3/4"6 Control Rod Drive line (085) at El.
548'-7". Use standard typical pipe support per Dwg. 0-47B436-52.
See Calc. no. CDQ1-085-2003-1693 1 -47B600-5412 2
RB POS Add one new support to the 1 "b 1-47B553-96 El. 541'-6" NEQUAD-Condensate S&S line (002) at El.
004 551 '-0".
See Calc. no. CDQ1-002-2003-1617 3
RB POS Add one new support to the 2-1/2"6 1-47B600-5411 El. 541'-6" NEQUAD-Control Rod Drive line (085) at El.
005 558'-0". Use standard typical pipe support per Dwg. 0-47B436-52.
See Ca/k. no. CDQ1-085-2003-1616 4
RB POS Repair and reconnect existing hanger 1-47B404-2 El. 541'-6" TORUS-support for 1"6 Aux. Boiler line (012) 002 at El. 555'-9".
See Cal,. no. CDQ1-012-2003-1618 5
RB POS Add one new support to the 1 "O 1-47B920-1310 El. 565' 565B-014 Building Heat line (044) at El. 585'-6".
See Ca/c. no. CDQ1-044-2003-1691 6
RB POS Add one new support to the 1-1/2"6 1 -47B920-1311 El. 565' 565B-01 7 Building Heat line (044) at El. 587'-6".
Use standard typical pipe support per Dwg. 0-47B436-52.
See Caic. no. CD01-044-2003-1692 Page 6-3 FACPtTY RISK CONSULTANTSt IWC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABLE 6-2 (cont'd)
Summary of Plant Modifications BFN-1 Seismic Il/I Spray Evaluation Program 7
RB El. 565' POS 565B-01 8 Add one new support to the 2-1/2"%
Fire Protection line (026) at El. 569'-9".
See Calc. no. CDQ1-026-2003-2542 and Cakc. no. CD01-026-2003-2566 1 -47B491 -3323 see note (3)
RB POS Add one new support to the 2"O Raw see note (4)
El. 565' 565C-012 Cooling Water line (024) at El. 578'-5".
Use standard typical pipe support per Dwg. 0-47B436-52.
See Cac. no. CDQ1-024-2003-1619 8
RB POS Add one new support to the 2-1I2"6 1-47B491-3324 El. 565' 565D-004 Fire Protection line (026) at El. 582'.
see note (3)
See Calk. no. CDQ1-026-2003-2543 and Caic. no. CDQ1-026-2003-2566 z9-u
- RSz zP
--- eplace-existing pipe support for the---- --
1 7B481-5 El. 593' 593B-002 1"0 Floor Drain line (040) at El. 616'-5" with standard typical pipe support per Dwg. 0-47B436-52.
See Cakc. no. CDQ1-040-2003-1605 RB P0s Replace and resupport damaged 1/2"O see note (5)
El. 593' 593B-004 RBCCW (070) pipe located along col.
line R2, between S and U at El.
608'-5".
See Caic. no. CDQ1-070-2003-1604 10 RB POS Install seismic restraints to the 1-47B462-2014 El. 621 '-3" 621 A-003 collection drum for Standby Liquid Control flush lines (063) located on the floor at El. 621 '-3".
See Caic. no. CDQ1-063-2003-1614 Page 6-4 FACEuTr? RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABLE 6-2 (cont'd)
Summary of Plant Modifications BFN-1 Seismic IlI Spray Evaluation Program 11 RB El. 621'-3" POS 621 A-005 Repair and reconnect existing hanger support for 1"6 Standby Liquid Control line (063) at El. 635'-1". Use standard typical pipe support per Dwg.
0-47B436-52 See Caic. no. CDQ1-063-2003-1615 1-47B462-2015 12 RB POS Add one new support to the 1 "O Gland 1-47B446-311 El. 639' 639A-001 Seal line (037) at El. 653'-6".
See Caic. no. CDQ1-037-2003-1177 13 RB POS Add new support for the 6"6 1 47B920-1 354
-El. 639' 639C-004 Secondary Containment line (064) -
1-47B920-1355 14 639C-008 two locations at El. 643', col. lines 639A-01 1 R4/S and R4/Q.
See Calc. no. CDQ1-064-2003-1226 15 X
_RB POS
-Add-one new support to the 2"-
1-478494-3322 El. 639' 639D-004 Potable Water line (029) at El. 653'-6".
See Calc. no. CDQ1-029-2003-1217 16 RB POS Modify existing support for Building 1-47B920-1307 El. 664' 664B-002 Heater (044) - two locations at El.
1-47B920-1308 17 664D-004 674', cot. lines R4/Px and R4/Ux.
See Calc. no. CDQ1-044-2003-1600 18 RB POS Install seismic restraints to the Hot 1-47B491-3321 El. 664' 664C-005 Water Heater (Potable Water Tank, 029) located at El. 672'-8".
See Caic. no. CDQ1-029-2003-1407 Page 6-5 FACILrnY RISK CONSULTANTS, INC.
TVANBFN-01-R-002 Revision 0 March 26, 2004 TABLE 6-2 (cont'd)
Summary of Plant Modifications BFN-1 Seismic INI Spray Evaluation Program 19 RB POS -
Add one new support to (3) 1 "i 1 -47B920-1 309 El. 664' 664D-003 Building Heat lines (044) at El. 675'.
See Calc. no. CDQ1-044-2003-1611 (1) Detailed description and as-built information of these items, including photos and/or sketches, can be found in the Potential Outlier Sheet (POS) contained in the respective seismic 11/l spray Walkdown Data Packages (WDPs).
(2) Refer to DCN 51669, unless noted otherwise.
(3) Refer to DCN 51669, PIC 60370.
(4) Subject pipe was removed per DCN 51178. Hence, no additional work is required.
POS 565C-012 is resolved.
(5) Subject pipe was removed per DCN 51182, as shown on DCA Dwgs. 51182-038 and 51182-039. Hence, no additional work is required. POS 593B-004 is resolved.
Fage 6-6 FACILUTY RISK CONSULTANT, INC.
TVANBFN-01-R-002 Revision 0 March 26, 2004 TABLE 6-3 Summary of Misc. Maintenance & Housekeeping Items BFN-1 Seismic IUI Spray Evaluation Program 1
Above Torus El. 541'-3" POS TORUS
-001 One bolt missing on flange connection
-of 27o Aux. !Boiler line, near connection to RHR line.
Pipe flange is located at 8" N of AZ 900, 6' E of Rl and about 70" below the ceiling (El. 565').
Work Order WO #
03-018259-000 was issued to replace the missing bolt on the flange connection.
2 RB POS 2-1/2"0 and 4"o Potable Water lines Work Order WO #
El. 565' 565A-with visible rust at the threaded joints.
03-018269-000 was 010 Lines appear to be galvanized iron issued to address the pipes.--
rusted threaded Rusted joints in the lines are located joints.
at 14' N of 1P and 7'-6" E of R2. Pipe elevation is at about 576'-6".
3 RB POS Disengaged rod on the 2-1/2"0 Work Order WO #
El. 565' 565A-Potable Water line.
03-022090-000 was 011 Pipe elevation is at El. 588'-1 issued to reinstall the support is located at 14' N of col. line missing rod hanger.
Pand5'EofR2.
4 RB POS 2"0 Floor Drain line has a detached Work Order WO #
El. 565' 565B-rod hanger.
03-018270-000 was 001 The rod hanger in question is located issued to reinstall the at about 1'1' N of T and 7'-6" W of R4.
disengaged rod Pipe elevation is at about 588'-2".
hanger.
5 RB POS Significant rust condition noted at the Work Order WO #
El. 565' 565B-tee connection between the 8"o F.P.
03-022093-000 was 020 header and 2-1/2"0 branch line.
issued to address the Pipe elevation is at El. 588'-1"; tee rusted tee connection is located at 6.5' N of U connection.
and 1'W of R2.
Page 6-7 FACILEy RiSK CONSULTANTS, INC.
I TVA/BFN-01-R-002 Revision 0 March 26, 2004 TABLE: 6-3 (cont'd)
Summary of Misc. Maintenance & Housekeeping Items BFN-1 Seismic Il/I Spray Evaluation Program 6
RB El. 565' POS 565C-009 Pipe clamp is missing on a wall-mounted Unistrut pipe support for 3/4"o Rad Waste line.
Support is located just N of U-Line (5" from wall) and W of R5 (nearest pipe elbow is at 5'-4" W of R5). Pipe elevation is at about 568'-6".
Work Order WO #
03-018272-000 was issued to reinstall the missing pipe clamp.
7 RB POS Missing hardware on a trapeze rod Work Order WO #
El. 565' 565C-hanger support for 8"o Fire Protection 03-013733-000 was 014 header-missing rod on the south end issued to reinstall the and missing nut on the north end-of the -missing rod-and nut.
support.
The support is located about 8' N of S line and 8' W of wall penetration at R7 wall. Pipe elev. is at about 576'.
8 RB POS 4"o Floor Drain line rod hanger is Work Order WO #
El. 565' 565D-detached.
03-018273-000 was 003 Support is located at about 10' N of a issued to reinstall the and 3' E of R6. Pipe elevation is at about 588'-4".
9 RB POS Line is leaking at the threaded bronze Work Order WO #
El. 593' 593A-hand valve near T-connection of Y2 "0 03-018274-000 was 007 tubing to 12"o Raw Cooling Water issued to repair the header.
leaking connection.
The Y/2 "o line with leaking connection is located about 4' W of R3, between P
& Q (off the 12"o RCW header). The Y12"0 line is at Elev. 608'-1".
Pacle 6-8 FACIALTY RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 TABLIE 6-3 (cont'd)
Summary of Misc. Maintenance & Housekeeping Items BFN-1 Seismic Il/I Spray Evaluation Program 10 RB El. 593' POS 593B-007 2"o RBCCW line has a detached rod hanger.
The location of the missing rod is at 7'-2" E of R2 and 2'-9" N of T. The 2"o line is at Elev. 617'-3". Note that pipe clamp is still attached to the pipe.
[Work Order WO #
03-018275-000 was issued to re-install the missing rod.
---I 11 RB POS Excessive corrosion & rust observed Work Order WO #
El. 621 '-3" 621 B-on the 1 "0 & 3/4"o Building Heat lines 03-018277-000 was 002 and threaded joints near the interface issued to replace to area heater.
rusted pipe segments Area heater is located on the south and threaded Joints.
face of RC column R2/T.
12 RB POS Rusted conditions observed on the Work Order WO #
El. 639' 639A-1"o Building Heat lines at interface 03-018281 -000 was 008 with the unit area heater (including issued to replace
_ X_
union).
rusted pipe segments Area
-and threaded joints at Area heater is located on the north the heater interface.
face of Q-line between R2 & R3.
13 RB POS Pipe flange is leaking on short riser of Work Order WO #
El. 639' 639C-3"o Condensate S&S line.
03-005020-000 has 001 Pipe flange is located about 4'-6" S of been issued to column line S and 3'-6" E of R3. Pipe address the leaking elevation is at about 659'.
flange connection.
- Detailed description and as-built information of these items, including photos and/or sketches, can be found in the Potential Outlier Sheet (POS) contained in the respective seismic 11/l spray Walkdown Data Packages (WDPs).
Page 6-9 FAcIurr RISK CONSULTANTs, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004
- 7. REFERENCES 7-1 WI-BFN-0-CEB-06, "Engineering Walkdown Instruction for Evaluation of Seismic-Induced Spray Hazards." Rev. C).
7-2 BFN-50-C-7306, "Qualification Criteria for Seismic Class II Piping, Pipe Supports, and Components." Rev. 1.
7-3 CD-Q0999-910005, "Evaluation of Seismic-induced Spray Hazards, BFN, Unit 2 and Common."
7-4 CD-Q3999-931257, "BFN Unit 3 lI/I Spray Evaluation."
7-5 NDQ0 999 920011, "Seismic Class I Piping System Boundaries."
7-6 EPRI Report RP-2635-1, "Piping Seismic Adequacy Criteria Recommendation Based on Performance During and After Earthquakes." February 1987.
7-7 EPRI Report NP-7149, "Summary of the Seismic Adequacy of Twenty Classes of Equipment Required for Safe Shutdown of Nuclear Plants." March 1991.
7-8 USAS B31.1.0, "Power Piping." 1967 Edition.
7-9 CDQ1 999 2003 0831, "In-Plant Screening Tools for Seismic Il/I Spray Walkdown Evaluations." Rev. 1.
7-10 "Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment." Rev. 2A, March 1993.
7-11 "TPIPE Program User Manual." Version 16, July 1994.
Page 7-1 FACtuTY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 APPENDIX A:
BFN-1 SEISMIC IIf SPRAY EVALUATION in WAL-KDOWN-DTATPACKAGES X
I Page A-1 FACIUTY RISK CONSULTANTS, INC.
TVANBFN-01-R-002 Revision 0 March 26,2004 BFN-1 Seismic Il/I Spray Evaluation Walkdown Data Packages (1 of 2)
BFN1 -CEB-SPRY-NWQD Seismic lil/I Spray Walkdown Screening Evaluation Documentation - Plant Area NWQUAD 1
BFN1-CEB-SPRY-NEWD Seismic Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area NEQUAD BFN1-CEB-SPRY-SWQD Seismic (VI Spray Walkdown Screening Evaluation 0
Documentation - Plant Area SWQUAD BFN1-CEB-SPRY-SEQD Seismic Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area SEQUAD BFN1-CEB-SPRY-HPCI Seismic IlI Spray Walkdown Screening Evaluation 0
Documentation - Plant Area HPCI BFN1-CEB-SPRY-TORS Seismic Il/I Spray Walkdown Screening Evaluation 0
-Documentation - Plant Area TORUS BFN1-CEB-SPRY-565A Seismic Il/I Spray Walkdown Screening Evaluation 2
Documentation - Plant Area 565A BFN1-CEB-SPRY-565B Seismic Il/I Spray Walkdown Screening Evaluation 1
Documentation - Plant Area 565B BFN1-CEB-SPRY-565C Seismic Il/I Spray Walkdown Screening Evaluation 1
Documentation - Plant Area 565C BFN1-CEB-SPRY-565D Seismic 1l/I Spray Walkdown Screening Evaluation 1
Documentation - Plant Area 565D BFN1-CEB-SPRY-STNL Seismic Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area Steam Tunnel BFN1-CEB-SPRY-593A Seismic Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 593A BFN1-CEB-SPRY-593B Seismic Il/1 Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 593B BFN1-CEB-SPRY-593C Seismic Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 593C BFN1 -CEB-SPRY-593D Seismic Il/l Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 593D Page A-2 FAcILTy Rsu CoNsuANs, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 BFN-1 Seismic Il/I Spray Evaluation Walkdown Data Packages (2 of 2)
BFN1 -CEB-SPRY-621 A Seismic Il/1 Spray Walkdown Screening Evaluation Documentation - Plant Area 621 A 0
-I I
I I
I BFN1 -CEB-SPRY-621 B Seismic Il1/ Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 621 B BFN1-CEB-SPRY-621C Seismic Il/1 Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 621 C BFN1-CEB-SPRY-621 D Seismic 1Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 621 D BFN1-CEB-SPRY-639A Seismic 1Il/1 Spray Walkdown Screening Evaluation 1
Documentation - Plant Area 639A BBFN1-CEB-SPRY-639B Seismic Il/I Spray Walkdown Screening Evaluation 0
_ __fcumnei tatbn-PantArea-639B BFN1-CEB-SPRY-639C Seismic Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 639C BFN1 -CEB-SPRY-639D Seismic Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 639D BFN1 -CEB-SPRY-664A Seismic lI/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 664A BFN1 -CEB-SPRY-664B Seismic Il/I Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 664B BFN1-CEB-SPRY-664C Seismic Il/l Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 664C BFN1 -CEB-SPRY-664D Seismic Il/l Spray Walkdown Screening Evaluation 0
Documentation - Plant Area 664D Page A-3 FAcUty RIsK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 APPENDIX B:
BFN-1 SEISMIC 11/ SPRAY EVALUATION OUTLIER RESOLUTION CALCULATION PACKAGES Page B-1 FA CIny RISK CONSULTANTS, INC.
I TVA/BFN-01 -R-002 Revision 0 March 26, 2004 BFN-1 Seismic Il/I Spray Evaluation Outlier Resolution Calculation Packages (1 of 4)
CDQ1 -999-2003-0831 In-Plant Screening Tools for Seismic li/I Spray Walkdown iEvaluations 1
CDQ1 -999-2003-1072 Evaluation of Seismic Il/1 Spray Potential Outliers 1
for Overspan Piping, Reactor Bldg., El. 639' CDQ1 -002-2003-1085 Demineralized Water Il/I Spray Seismic Analysis -
0 Resolution of POS 639C-005 CDQ1 -002-2003-1086 Condensate S&S Il/I Spray Seismic Analysis -
0 Resolution of POS 639B-005 CDQ1-044-2003-1087
-- -Building Heat Il/l Spray Seismic Analysis -
1 Resolution of POS 639B-003 CDQ1 -026-2003-1088 Fire Protection Il/I Spray Seismic Analysis -
0 Resolution of POS 639B-004 CDQ1 -024-2003-1135 Raw Cooling Water Cu Tubing Il/I Spray Seismic 0
Analysis - Resolution of POS NEQUAD-001 CDQ1 -071-2003-1136 RCIC Il/I Spray Seismic Analysis - Resolution of 0
POS NWQOLAD-003 CDQ1 -037-2003-1178 Evaluation of Seismic Il/l Spray POS 639A-004, 0
Gland Seal Storage Tank Anchorage, Reactor Building, El. 639 Ft.
CDQ1 -085-2003-1197 CRD Piping Il/I Spray Seismic Analysis -
0 Resolution of POS NEQUAD-005 Page B-2 FACILITY RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 BFN-1 Seismic lIU Spray Evaluation Outlier Resolution Calculation Packages (2 of 4)
CDQ1 -044-2003-1198 Building Heat Supply & Return Lines at RB El. 664 ft. - Il/I Spray Seismic Analysis and Resolution of POS 664B-0)02 0
CDQ1 -085-2003-1405 Control Rod Drive Line Il/I Spray Seismic Analysis 0
- Resolution of POS NEQUAD-002 CDQ1 -044-2003-1406 Building Heater Support Anchorage Il/I Spray 0
Seismic Analysis for Reactor Building, El. 664 ft.
CDQ1 -024-2003-1408 Raw Cooling Water Line lI/1 Spray Seismic 0
nalysis-esolution of POS 565A-001 CDQ1 -999-2003-1409 Evaluation of Seismic Il/I Spray Potential Outliers 0
for Overspa.n Piping, Reactor Bldg., El. 565 ft.
CDQ1 -044-2003-1410 Building Heater Support Anchorage Il/1 Spray 0
Seismic Analysis - Resolution of POS 565A-003, POS 565B-002 and POS 565C-01 0 CDQ1-024-2003-1411 Raw Cooling Water Support Anchorage Il/1 Spray 0
Seismic Analysis - Resolution of POS 565B-003 CDQ1 -999-2003-1412 Evaluation of Seismic 1l/I Spray Potential Outliers 0
for Overspan Piping, Reactor Bldg., El. 519 ft. and 541.5 ft.
CDQ1-002-2003-1413 Demineralized Water 11/l Spray Seismic Analysis -
0 Resolution of POS NEQUAD-008 CDQ1-999-2003-1414 Evaluation of Seismic Il/l Spray Potential Outliers 0
for Overspan Piping, Reactor Bldg., El. 664 ft.
Page B-3 FACITy RISK CONsuLTANTs, iNc.
TVA/BFN-01 -R-002 Revision 0 March 26,2004 BFN-1 Seismic: lVI Spray Evaluation Outlier Resolution Calculation Packages (3 of 4)
-CDO1 -085-2003-1415 Control Rod Drive Line Il/I Spray Seismic Analysis
- Resolution of POS NEQUAD-009 0
CDQ1 -999-2003-1601 Evaluation of Seismic Il/I Spray Potential Outliers 0
for Overspan Piping, Reactor Building, El. 593 ft.
CDQ1 -999-2003-1602 Evaluation of Seismic Il/1 Spray Potential Outliers 0
for Overspan Piping, Reactor Building, El. 621 '-3" CDQ1 -000-2003-1603 Floor Drain Line Il/I Spray Seismic Analysis -
0 Resolution of POS 593D-006 CDQ1 -044-2003-1607 Building Heat Piping Il/I Spray Seismic Analysis -
0 Bounding Evaluation for El. 593' CDQ1 -044-2003-1608 Building Heat Piping Il/1 Spray Seismic Analysis -
0 Bounding E:valuation for El. 621'-3" CDQ1 -026-2003-1609 Fire Protection Branch Line Il/I Spray Seismic 0
Analysis - Resolution of POS 621 D-001 CDQ1-069-2003-1610 RWCU AOV 1-FCV-069-0078 Il/I Spray Seismic 0
Analysis - Resolution of POS 621C-007 CDQ1 -069-2003-1612 RWCU Pump Support Anchorage Il/l Spray 0
Seismic Analysis - Resolution of POS 621 C-003 CDQ1 -000-2003-1613 Eye Wash Station Support Anchorage Il/l Spray 0
Seismic Analysis - Resolution of POS 621A-004 Page B-4 FACtLry RISK CONSULTANTS, INC.
I TVA/BFN-01 -R-002 Revision 0 March 26,2004 BFN-1 Seismic Il/I Spray Evaluation Outlier Resolution Calculation Packages (4 of 4)
CDQ1 -044-2003-2319 Building Heat Line & Area Unit Heater Seismic Il/I Spray Screening Tool 0
CDQ1 -026-2003-1606 Fire Protection Hose Station Piping Il/I Spray 0
Seismic Analysis - Resolution of POS 565B-01 8 CDQ1 -026-2003-1952 Fire Protection Hose Station Piping Il/I Spray 0
Seismic Analysis - Resolution of POS 565D-004 CDQ1 -026-2003-2151 Fire Protection Hose Station Piping Il/I Spray 0
Seismic Analysis - Resolution of Overspan Conditions for POS 565B-01 9, POS 565C-01 3 and POS 565D-005 CDQ1 -026-2003-2558 Fire Protection Hose Station Piping Il/I Spray 0
Seismic Analysis - Resolution of POS 565C-01 4 CDQ1 -999-2003-1404 Summary of Seismic Il/I Spray Evaluation Program 0
at Browns Ferry Nuclear Plant, Unit 1 Page B-5 FACILIy RISK CONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26, 2004 APIPENDIX C:
BFN-1 SEISMIC 11/1 SPRAY EVALUATION PLANT MODIFICATION DESIGN CALCULATION PACKAGES
--I-Page C-1 FActuir RISK 0ONSULTANTS, INC.
TVA/BFN-01-R-002 Revision 0 March 26,2004 BFN-1 Seismic IVI Spray Evaluation Plant Modification Design Calculation Packages (1 of 2)
CDQ1 -037-2003-1177 Gland Seal Line Il/I Spray Seismic Analysis -
Resolution of POS 639A-001 0
CDQ1-029-2003-1217 Potable Water Il/i Spray Seismic Analysis -
0 Resolution of POS 639D-004 CDQ1-078-2003-1226 Fuel Pool Cooling Line li/I Spray Seismic Analysis 1
- Resolution of POS 639C-004 & -008 and POS 639A-01 1 CDQ1 -029-2003-1407 Hot Water Heater (Potable Water Tank) Anchorage 0
Il/1 Spray Seismic Analysis - Resolution of POS 664C-005 CDQ1 -044-2003-1600 Resolution of POS 664B-002 and POS 664D-004, 0
Building Heater Support Strengthening, Il/I Spray Seismic Analysis for Unit 1 Reactor Building, El.
664' CDQ1 -070-2003-1604 RBCCW Piping Il/1 Spray Seismic Analysis -
0 Resolution of POS 593B-004 CDQ1 -000-2003-1605 Floor Drain Line Il/I Spray Seismic Analysis -
0 Resolution of POS 593B-002 CDQl -044-2003-1611 Reactor Building El. 664', Building Heat Lines IVI 0
Spray Seismic Analysis - Resolution of POS 664D-003 CDQ1 -063-2003-1614
'Standby Liquid Control Flush Lines Il/1 Spray 0
Seismic Analysis - Resolution of POS 621A-003 CDQ1 -063-2003-1615 Standby Liquid Control Line Il/1 Spray Seismic 0
Analysis - Resolution of POS 621A-005 Page C-2 FACtLny RISK CONSULTANTS, INC.
TVA/BFN-01 -R-002 Revision 0 March 26, 2004 BFN-1 Seismic IVJ Spray Evaluation Plant Modification Design Calculation Packages (2 of 2)
CDQ1 -085-2003-1616 CRD Pipe Support Seismic Strengthening, JI/
Spray Seismic Analysis - Resolution of POS NEQUAD-005 0
CDQ1 -002-2003-1617 Condensate S&S Line li/I Spray Seismic Analysis -
0 Resolution of POS NEQUAD-004 CDQ1 -01 2-2003-1618 Auxiliary Boiler Line Il/1 Spray Seismic Analysis -
0 Resolution of POS TORUS-002 CDQ1 -024-2003-1619 Raw Coolin( Water Piping Il/I Spray Seismic 0
Analysis --Resolution of POS 565C-012 CDQ1 -044-2003-1691 Building Heat Piping Il/I Spray Seismic Analysis -
0 Resolution of POS 565B-014 CDO1 -044-2003-1692 Building Heat Piping Il/I Spray Seismic Analysis -
0 Resolution of POS 565B-01 7 CDQ1 -085-2003-1693 Control Rod Drive Line Seismic Strengthening -
0 Resolution of POS NEQUAD-002 CDQ1-026-2003-2542 Fire Protection Hose Station Piping Il/1 Spray 0
Seismic Strengthening - Resolution of POS 565B-018 CDQ1 -026-2003-2543 Fire Protection Hose Station Piping Il/I Spray 0
Seismic Strengthening - Resolution of POS 565D-004 Page C-3 FACIuTY RISK CONSULTANTS, INC.
FACILITY RISK CONSULTANTS, INC.
www.facilltyrlsk.com Alabama Office 6275 University Dr., Ste. 37 Huntsville, AL 35806 USA TEL: (256) 679-3234 FAx: (256) 325-5099 California Office 43575 Mission Blvd., #301 Fremont, CA 94539-6342 USA TEL: (510) 676-1554 FAx: (510) 490-2011