ML19340C234

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Forwards Final Rept Re IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Rept by Gilbert Associates,Inc Encl.Tables in App III a & B Will Be Updated in Next Revision
ML19340C234
Person / Time
Site: Crane Constellation icon.png
Issue date: 10/13/1980
From: Hukill H
METROPOLITAN EDISON CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-79-14, TLL-518, NUDOCS 8011140289
Download: ML19340C234 (102)


Text

{{#Wiki_filter:T(C >rr e. Metropolit, Edison Company Iy - 'e-Middletown, Pennsylvania 17057 Post Office Box 480 l 717 9444041 Writer's Direct Dialpymber E$ l October 13, 1980 7-TLL 518 e ~ "6-(n Office of Inspection and Enforcement l':(( Attn: B. H. Grier, Director [i ?,,, Region I 'O i: U. S. Nuclear Regulatory Commission EE 631 Park Avenue Q o x King of Prussia, PA 19406 Three Mile Island Nuclear Station, Unit 1 (TMI-1) Operating License No. DPR-50 Docker No. 50-289 IE Bulletin 79-14 Series Enclosed please find the final report in response to Bulletin 79-14, concerning the adequacy of the Seismic Class I piping systems. The information provided in the tables in Appendices IIIA and IIIB will be updated in the next revision tentacively scheduled for the first auarter of 1981. Sincerely, Hu -ill Director, TMI-l HDH:DCM:lma Enclosures cc: J. T. Colline w/ Enclosures V. Stello D. Eisenhut R. W. Reid w/o Enclosures B. J. Snyder H. Silver D. DiIanni 8 02 Jl 4 0%% Metr a n: n Ed: son comcany is a Memoer of tne General Puccc utat es system

.e ( USNRC IE BUIJ.ETIN NO. 79-14 FINAL REPORT SEPTEMBER 30, 1980 Prepared for Metropolitan Edison Co. Three Mile Island Nuclear Station Unit 1 I Prepared by Gilbert Associates, Inc. (

' " " - -l' [r U1Servico 11 1X 1 17 TECHNICAL DATA REPORT PROJECT NO. PAGE OF w-( PROJECT: TMI Unit (/l Restart NM-35 DEPARTMENTISECTION RELEASE DATE 9-30-80 REVISION DATE DOCUMENT TITLE: Final Report to US 3C for IE Bulletin 79-14 Requirements at TMI Unit //l ORIGINATOR SIGNATURE DATE APPROVAL (S) SIGNATURE. DATE Gilbert Associates. Inc. 9-30-80 _M N - 12SV- - Ido# l $Yf ffkN-D-_ ' L v DATE APM0/AL FOR EXTERN AL DISTRIBUTION g/[lw_ 10-2-8 0 7 i7 o DISTRIBUTION ABSTRACT: / Statement This report is the response by Metropolitan Edison Co. to the Reporting Requirements of the USNRC IE Bulletin 79-14, including all revisions and supplements, for TMI Unit //l (Docket No. 50-289). .h Sum:t a ry The reputt explains the inspection procedure implemented to verify that installed safety related Seismic Category I Piping Systems and Pipe Supports meet the design intent. It details any nonconformances found and defines what actions are being taken to correct or accept these nonconformances (i.e., support redesign, piping reanalysis). Conclusion It is the conclusion of this report that upon completion of all reworks and incorporation of as-built drawings, safety related Seismic Category I Piping and Supports will accurately reflect the original or updated design intent. Recommendations The report also details methods for current and future maintenance of as-built documents. o a n m w-b _m cCOVER PAGE ONLY -- A000 0030

f TDR NO. Ir LJ IServ. ice 1,4 TITLE Final Report to USNRC for IE Bulletin 79-14 PAGE i OF Requirements at TMI Unit #1 1 REV

SUMMARY

OF CHANGE APPROVAL DATE Acoo 0017

TDR-TMI-194 I TABLE OF CONTENTS Item Title Page 1.0 Purpose and Summary 2 2.0 Methods 3 2.1 Scope of Inspection 3 2.2 Inspection Procedure 4 2.3 Site Inspection 6 3.0 Evaluation 7 3.1 Nonconformance Evaluation - Piping Analyses 8 3.2 Reasons for Reanalysis 8 ~ 3.3 Pipe Support Evaluation 11 4.0 Res lts 12 4.1 Pipe Support Redesign 12 5.0 Conclusions 15 6.0 Recommendations 15 6.1 Document Control 15 7.0 References 15 7.1 Computer Programs 15 7.2 References for Analysis Input 16 j Appendix I Systems Inspected and Applicable Drawings l Appendix II Inspection Procedure i Appendix IIIA Summary of Nonconformances and Results of Reanalysis. Appendix IIIB Results of Supports Evaluations Appendix IV System Inspection Boundaries Appendix V Inaccessible Inspection Elements - Visual Inspections - +

TDR-TMI-194 Page 2 s 1.0 PURPOSE AND

SUMMARY

This is the fi si report of Metropolitan Edison Company in response to USNRC IE Bulletin No. 79-14, dated July 2, 1979, ine' ,ag Revision 1 dated July 18, 1979, Supplemeat I dated August 15, isi9, and Supplement 2 dated September 7,1979 for Three Mile Island Nuclear Station, Unit 1, Docket No. 50-289. 4 The purpose of this report is to describe the results of piping system reanalysis and the resolution of nonconformances identified as a result of an inspection program to compare as-built conditions to design intent. As described in the interim report, issued May 2, 1980, an inspection program was implemented to verify that the type, location and orientation of piping, type and location of supports, pipe attachments, valve and valve operator orientation and weights, and pipe geometry were installed as input into the seismic analysis. In conjunction with the inspection program, engineering evaluations were performed on piping supports and systems with nonconformances to determine whether or not the as-built conditions meet design requirements. Supports which do not meet design requirements will be redesigned and construction modifications made as required. i

TDR-TMI-194 Page 3 2.0 METHODS ~2.1 SCOPE OF INSPECTION The following is a list of safety-related Seismic Category I piping consistent with the scope of inspections for IE Bulletin 79-14. The inspections of these systems or portions of systems are complete in accordance with the inspection procedure implemented for TMI Unit 1 (See Appendix II). Also listed for reference are system identifying codes. Code System Title MS Main Steam AS Auxiliary Steam FW Feed Water EF Emergency Feed Water NS, MC, RB Nuclear Services Closed Cycle Cooling Water (Reactor Building Emergency Air Cooling) DC Decay Heat Closed Cycle Cooling Water MU Make-up and Purification (Reactor Protection System) SF Spent Fuel Cooling WD Waste Disposal CO Condensate RC, PR Reactor Coolant LR Leak Rate CF Core Flooding (Reactor Protection System) DH Decay Heat Removal (Reactor Protection System) BS, SPS, SBW Building Spray (Reactor Building Emery.ncy Air Cooling) RW, IP, RR River Water (Decay HT & Nuclear Services River Cooling Water System) MPA Monitoring Post Accident Purge CH Chilled Water (Vital Ventilation System) IA Instrument Air IM Incore Monitoring IC Intermediate Cooling

TP" TMI-194 F..e 4 The flow diagrams included in Appendix IV identify by analysis identification -s number, (ME-No.), those portions of safety-related Seismic Category I systems which were inspected. Information from the original flow diagram has been eliminated to provide clarity. The subdivision of systems into specific ME-No. was done to facilitate the computer modeling of the piping for analysis purposes. The boundaries of the analyses were selected on the basis of anchor points, or other physical limitations. Appendix I provides a detailed list of piping isometries, piping layouts drawings, and flow diagrams used for analysis input. This appendix is seperated into those systems analyzed and further subdivided into the actual analysis number. The revision of drawings being used to perform inspections and verifications of the analyses corresponded with the latest revision current on the date of the inspection or verification. When the document used to verify that analysis had been revised from that used in the original analysis, such revisions were reviewed to insure that they had been included in an updated analysis or did not affect it. 2.2 INSPECTION PROCEDURE The following is a summary of the procedure used by inspectors at the plant site in checking the geometry of piping and configuration of pipe support assemblies. The inspection procedure is more fully described in Appendix II. 2.2.1 General A support assembly was defined as a rigid support, variable and constant support, or seismic restraint. The complete support, including support attachment or bracing steel was inspected. (

TDR-TMI-194 Page 5 2.2.2 Inspection Tolerances 2.2.2.1 Pipe support locations were inspected relati;e to tolerances related to pipe diameter. Refer to Appendix II. If tolarances were not met, actual locations were recorded. 2.2.2.2 Pipe geometry was inspected against a tolerance of one pipe diameter in any direction. If this tolerance was not met, the actual dimensions were recorded. 2.2.2.3 Valve and valve operatorr. were inspected against an axial and radial tolerance. Nonconformances were recorded. 2.2.2.4 Support / restraint structural attachment orientation in relation to the pipe attachment was ir<pected against a tolerance of plus or minus seven (7) degrees in any direction. Nonconformances were recorded. 2.2.2.5 Snubbers were inspected for size, orientation, and setting. Nonconformances were recorded. 2.2.3 Inspection Elements 2.2.3.1 Support assemblies were inspected for the following: Type (e.g., rigid rod, spring, U-bolt) Quantity and size of pipe attachments Size of spring cans Bore and stroke en hydraulic snubbers Weld size, length and type Hex nut engagement Assembly component size and quantity 2.2.3.2 Clearances were recorded at four 90* locations for wall pe netrations, and pipe box restraints. This information was used to evaluate any possible adverse effects on thermal or seismic displacements. g. --7

TDR-TMI-194 Page 6 2.2.3.3 Material size and shape substitutions were recorded for evaluation. 2.3 SITE INSPECTION The following is a description of the site inspection program for piping systems and supports including methods of inspection and reporting on nonconformances. I 2.3.1 Methods

v. Inspection The inspection procedure (see Appendix II) identifies the requirements for the inspection of Seismic Category I piping and pipe support assemblies.

Two principal documents used in the inspection were: l a. Piping Analysis Isometric Drawings i These drawings were part of the design input for the original dynamic analyses of Seismic Category I systems. They define the pipe geometry, support locations and function, valve locations and orientations, pipe sizes and other elements affecting the analyses. b. Pipe Support Design Drawings j These are drawings of pipe supports, hangers and seismic restraints which show the type, location and configuration necessary to satisfy analytical requirements. i Additional reference documents used are listed in Section 7.0 and include physical piping arrangement drawings, flow diagrams and i vendor drawings The inspectors worked in teams and divided the piping system <. into work packages including an analysis isometric ) \\ e s <.we., 7y ,m

S TDR-TMI-194 Page 7 . ~. and related support assembly drawings. Nonconformances determined by comparison of the physical installation with the inspection package information was recorded on inspection dat sheets. Samples of the data sheets are included with Appendix II. In those cases where thermal insulation prevented the inspection of critical support elements (such as pipe attachments) the insulation was removed for the inspection of 10% of the obstructed pipe supports for both normally accessible and inaccessible systems. Additionally, en the balance of the obstructed pipe supports, that pcrtion of the.apport not covered by insulation was inspected. 2.3.2 Inaccessible Elements - Visual Inspections In accordance with the inspection procedure (Appendix II, Section 1.8), and Bulletin requirements, any elements which were either inaccessible or were visually inspected in lieu of actual measurements are identified. Appendix V lists any elements in these categories along with reasons for their inspection status and any safety consequences this status may have on their respective systems. 2.3.3 Reporting Nonconformances A unique number was assigned te each ins?ection report by the inspectors. For supports, the support number was used and for piping systems, the ME number was used. Piping nonconformances were reported on a Piping Inspection Report (PIR) form and transmitted to engineering for evaluation. Support nonconformances were reported on a Support Inspection Report (SIR) form and submitted to engineertug for evaluation.

S TDR-TMI-194 I Page 8 3.0 EVALUATION 3.1 Nonconformance Evaluation - Piping Analyses Subsequent to field inspections, the PIR's were submitted to a piping analysis group for evaluation. PIR's were reviewed to evaluate whether the nonconformances recorded would necessitate reanalysis. Reanalysis was not required if a nonconformance would not adversely affect pipe stress levels. New load sheets, however, were generated for all supports on these non-reanalyzed lines for review by engineering. This review considered any effects of nonconformances on support capabilities. A summary of systems and nonconformances is listed in Appendix IIIA. Valve manufacturers' drawings were used te verify that the valve weights and center of gravity used in the analysis were representative of the installed valve. Where manufacturers' drawings were unavailable, vendor catalogs or conservative estimates were used to define valve data. The line specification and original design were reviewed to verify that the specified pipe wall thickness and material properties were input-into the analysis. Any nonconformances identified were incorporated into i. reanalysis. 3.2 Reasons for Reanalysis 3.2.1 Nonconformances The following is a list of 9 typical nonconformances which may have necessitated piping reanalysis: Code Nonconformances 1 Dimensional Chaages of Valve or Support Location talve or support as-built location different from design intent. Inspection tolerances not met. i i

~ l TDR-TMI-194 Pagn 9 Code Nonconformances -s i i Orientation of Valve or Support 2 '.alve operctor or support member was not oriented with respect to the piping as originally analyzed. 3 Support Type Support type was incorrect, e.g., spring hanger instead of rigid rod. 4 New Support (not shown on drawings) Support added during construction, start-up, or thereafter and not considered in original analysis. 5 Missing Support Support included in original analysis but not found during inspection. 6 Pipe Geometry Dimensional differences between originally analyzed pipe and as-built pipe. 7 Miss. ; Valve Field inspections indicated an as found valve which was not included in the original analysis. 8 Center of Gravity or Weight of Valve Center of gravity and/or weight of a valve used in the original analysis adjusted to conform with as-built condition.

TDR-TMI-194 Page 10 ) ~ 9 . Seismic Input 4 4 Original analyses used seismic floor response curves which fall into three categories: a. Incorrect response curve used, i b. Floor response curve used in original analysis was an average rather than an envelopc. Reanalysis has been [ performed using the response curve for the highest elevation of the as-built pipe. I c. Some reactor building piping was analyzed using ) response curves for internal floors in lieu of reactor building shell curve which was unavailable at the time of the original analysis.

3. 2..

Additional Considerations for Reanalysis The following is a list of additional factors which were considered in the reanalysis process: i l Code Factor i l 10 Seismic Spacing Criteria i Reanalysis to consider effects of piping, supported by seismic j spacing criteria, integrally attached to formally analyzed l portions of pipe. 11 Generic Anchors i Piping reanalyzed to obtain refined load combinations required to perform USNRC IE bulletin 79-02 evaluation l of anchors. g I 9 --wma,w+cco-- y-y---- y-y-. c- -.--.-y q 9. p-r e-q~.--- y 3 -w e -e + w -yi,-r

TDR-TMI-194 Paga 11 12 Support Loading Some analyses were rerun using a 1980 State of the Art Computer Program, PIPDYNII, in an effort to reduce the conservatism in pipe support reactions, thereby minimizing amount of support rework. The decision to use this program, in certain cases, was made based upon original pipe stress levels and the number and types of nonconformances found. 13 Seismic piping not previously analyzed to seismic I criteria. Appendix IIIA indicates by use of the nonconformance code number, the nonconformances which apply to a particular reanalysis. This Appendix also indicates the results of the reanalysis; supports added or supports deleted. Analysis results are summarized in Section 5.0. 3.3 Pipe Support Evaluation All supports were submitted for -engineering review. This review process was used to determine if an evaluation was required. A pipe i support evaluation was performed for the following reasons: a. Nonconformances discovered as a result of field inspections. b. Piping reanalysis indicated reaction forces higher than original analysis. i, 4 i

TDR-TMI-194 i Page 12 1 l Ihe objective of the evaluation is to determine whether or not a support meets design requirements. Seismic Category I pipe supports that were evainated by engineering, used the original design criteria. When a support is not acceptable as installed, it is designated for redesign. Appendix IIIB tabulates by HE-Nos., the results of pipe support evaluations. This Appendix includes supports from formally analyzed lines and seismic spacing criteria supported lines. 4.0 RESULTS 4.1 Pipe Support Redesign The redesign of existing supports or the design of new supports is intitiated by the definition of an RDR (Redesign Required). The RDR package contains all i information compiled on the supports including field inspection reports, load sheets, support drawings, and evaluation calculations. The RDR cover sheet indicates the components which failed to meet design requirements. a de, sign input document was prepared as a basis for redesign. This document contains the procedure for applying loads and also gives the allowable stress limits for all components used. The design of new supports is similar to the redesign of supports where additional members were added. Location and type of restraint is provided on a support drawing. The designer then checks other discipline drawings to find an acceptable location for attachment. Where additional information is needed on accessibility or location, field personnel 1 ~ are consuited through a formal field request procedure. Engineerong then finalizes the desi.gn using the most current loads. An Engineering Change Memo (ECM) is issued in order to initiate the rework resulting from the need of additional, deleted or redesigned supports. Examples of redesign as implemented by an ECM are as follows: a. Add additional structural bracing to an existing support i --.m. ,+- -w o-

TDR-TMZ-194 Page 13 i b. Change an existing tension rod support to a sway strut 4 c. Add shear lugs to pipe to resist axial pipe loading d. Replacement of existing spring cans or snubbers. An evaluated support may have been identified for redesign, although the fix could actually be categorized as a maintenance item. A Maintenance Inspection Report (MIR) would be implemented rather than an ECM. Examples of items placed on an MIR are as follows: a. Adjusting the tension rod hangers b. Reset spring cans c. Set snubber stroke length. I -l l l \\ 4 1 w w

TDR-TMI-194 Page 14 1

5.0 CONCLUSION

S i The verification of safety related piping system seismic analysis is accomplished in the following four parts, as previously discussed: a. Site Inspection b. Seismic Reanalysis c. Support Evaluation d. Support Redesign i The following provides a summary of the results of each of the four parts completed to date: a. Site Inspections Site inspection functions are complete with the exception of Seismic Spacing Criteria portions of Decay Heat Removal, Make-up and Purification and Building Spray Systems. Of the 21 systems, approximately 2400 supports and 185 piping analyses were inspected. b. Piping Reana'.ysic The PIR's received from the field were evaluated to determine whether formal reanalysis was required. This resulted in 140 computer reanalyses and 44 original analyses reviewed by engineering and accepted without formal reanalyses. Nonconformance effects on supports, however, are evaluated. The remaining ME(S) were accepted as found. c. Support Evaluation Load sheets were reviewed to determine if support evaluation was required. To date, supports reviewed and those also evaluated after review total 1170. The disposition of these indicate 839 supports acceptance and 331 supports needing redesign. The redesign total includes all new supports added as a result of reanalysis findings. j d. Support Redesign l A total of 141 supports have been redesigned to date. ?" =

TDR-TMI-194 Page 15 6.0 RECOMMENDATIONS 6.1 - Document Control This section describes office and field control procedures to assure that pipe support modifications taking place now and in the future will be reflected on "as-built" drawings. Interim drawings are prepared by a redesign group to depict the proposed support modification required. Once approved, they are issued to construction-for installation by way of an ECM procedure. Once construction is complete, the field personnel document the installation using the interim d swings. These drawings are then submitted to engineering in the form of an "as-built". Should engineering determine that the as-built condition is not acceptable, another interim drawing is prepared and issued to construction following the above outlined procedure. Where engineering agrees with the as-built condition in the field, the master is updated reflecting these conditions and distributed, all of which is performed in a timely manner. Where inspected supports do not require redesign, an interim drawing is not necessary. As-built data, however, will be incorporated onto the master and distributed in a timely manner.

7.0 REFERENCES

7.1 Computer Programs 7.1.1 Piping Analysis Piping analyses were performed using the following verified computer programs: M003 PIPDYN II t

TDR-TMI-194 Page 16 7.1.2 Support Evaluation and Redesign Computer programs used by a pipe support evaluation group are listed below with a brief description of their application to the work. These verified programs are used to solve problems that are impractical to solve by other means, or when an accurate analysis is required in order to minimize support redesigns. Program Names STRUDL A general purpose finite element analysis program with design facilities, used to analyze pipe support plane frames and space frames. SPSTRESS A general purpose finite element program used to analyze individual pipe support elements such as clamps and bars. t PRY This program is used for flexible base plate analyses for prying action on non-preloaded concrete expansion anchors. 7.2 References For Analysis Input DOCUMENT ANALYSIS INPUT a. Pipe Specification for Plant Piping materials, fittings, and Piping (SP-5544) wall thickness, design pressures and temperatures. b. Building Seismic Response Building seismic response spectra by Curves elevation and building seismic movements c. Insulation Specification Insulation types and thicknesses - used SP-5546 to determine weights of piping i

TDR-TMI-194 Page 17 s DOCUMENT ANALYSIS INPUI d. Manufaturer's Valve Drawings Valve weights, e.g.'s and lengths e. Piping Isometrics Pipe routings, fittings in a format for (Refer to Appendix I) use with computer analyses. (Derived from physical drawings) f. Physical Pipe Drawings Pipe routings, fittings, valve locations (Refer to Appendix I) g. Flow Diagrams Line specifications, operating (Refer to Appendix I) temperatures h. Pipe Support Drawings See Note 1 i. USAS B31.1, 1967 Design criteria j. TMI-I FSAR Scope of Seismic I Piping NOTE 1: The pi,pe supports were designed using le-d information that is part of the computer analysis output. The pipe support sheets were used as part of inspection document and as-built information was input into the ar.alysis. i l

4 8 9 o 5 TDR-TMI-194 APPENDIX I SYSTDis INSPECTED AND APPLICABLE DRAWINGS \\ \\

TDR-TMI-194 APPENDIX I Page 1 of 12 SYSTEMS INSPECTED AND APPLICABLE DRAWINGS ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV I Condensate 47 D-321-625 1 E-304-102 14 C-302-101 18 (Supply to E-304-124 10 Emergency Feedwater) MK-No's 49 D-312-697 1 E-304-102 14 CO-206 C-322-726 0 E-304-101 17 E-304-102 14 P Core Flooding 34 C-312-551 2 E-304-641 20 C-302-640 24 E-304-642 28 C-302-640 24 E-304-711 13 C-302-711 12 MK-No's 35 B-312-550 4 E-304-641 20 C-302-640 24 CF-E-304-711 13 C-302-711 12 Decay Heat IA SS-312-554 5 E-304-641 20 C-302-640 24 Removal E-304-642 28 MK-No's 3 SS-312-556 2 DH-4 B-312-568 2 5 B-312-599 0 10 C-312-711 0 34 C-312-551 2 35 B-312-550 4 51 SS-312-640 0 60 B-312-652 2 61 B-312-653 1 4 72 SS-312-588 2 73 SS-312-589 2 74 SS-312-564 2 7 e 96 C-312-654 2 E-304-641 20 C-302-640 24 I t E-304-642 28 120 C-317-684 1 E-304-631 21 121 B-317-685 1 123 SS-312-687 1 7 146 C-312-692 1 E-304-641 20 y

TDR-TMI-194 APPENDIX 1 Page 2 of 12 SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) 1 ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV 168 B-312-723 1 E-304-611 9 C-302-640 24 174 C-312-744 0 E-304-712 17 C-302-712 15 222 C-312-758 0 E-304-646 1 C-302-645 10 223 C-312-761 0 E-304-646 1 C-302-645 10 C-302-645 10 Spacing Criteria Decay Heat 56 C-312-648 1 E-304-644 15 C-302-645 13 Closed Cycle E-304-645 15 c.oling 57 C-312-649 .1 MK-No's DCH-58 SS-312-650 1 59 SS-312-651 1 86 C-312-647 1 87 C-312-646 1 165 B-312-712 0 166 B-312-713 0 l 189 B-312-755 0 E-304-646 1 190 B-312-748 0 222 C-312-758 0 3 223 C-312-761 0 l i 224 C-312-760 0 225 B-312-759 0 9 Spacing p Criteria l Feedwater 29 B-312-507 5 E-304-081 11 C-302-081 17 (Isolation 30 B-312-506 4 E-?04-081 11 Portion) E-304-085 11 MK-No's 138 B-312-672 2 E-304-081 14 FW-E-304-085 11 139 B-312-673 3 E-304-081 14 E-304-085 7 Y i I

TDR-TMI-194 APPENDIX I 4 Page 3 of 12 ) ( SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV i i E-304-271 11 C-302-271 18 Instrument Air Spacing MK-No's Criteria E-304-272 3 IA-E-304-274 6 E-304-275 8 E-304-276 6 E-304-277 8 E-304-771 4 E-304-772 8 L E-304 773 8 E-304-774 3 E-304-776 3 E-304-775 5 1 Monitoring Post Spacing D-304-716 3 C-302-721 3 2 Acc Purge Criteria (Sampling Portion) MK-No's MPA-l l E-304-244 0 C-302-72"- 5 Leak Rate Spacing MK-No's Criteria E-304-725 7 g LR-l Main Steam 24 B-312-503 5 E-304-012 14 C-302-011 22 (Supply to Emerg. Feed Water Pump Turbine, Contain-ment Isolation) ( l

TDR-TMI-194 APPENDIX I Page 4 of 12 ^ SYSTLMS INSPECTED AND' APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV MK-No's 25 B-312-503 5 E-304-012 14 C-302-0'1 22 MS-26 B-312-502 5 E-304-012 14 VE-27 B-312-502 5 E-304-012 14 E-304-011 11 38 C-312-771 1 E-304-012 14 E-304-013 15 39 C-312-772 1 40 C-312-773 1 41 C-312-774 1 9 42 B-312-581 4 E-304-012 14 E-304-013 15 43 B-302-582 4 44 S3-312-590 3 230 C-312-779 1 P 234 Spacing Criteria o Make-up and 6 C-312-775 1 E-304-661 15 C-302-661 19 Purification E-304-662 15 MK-No's 7 C-312-776 1 E-304-662 15 MUE-E-304-663 12 MUH-E-304-664 18 E-304-665 9 8 C-312-7.7 2 E-304-663 12 E-304-665 9 9 C-312-778 1 E-304-663 12 1 11 C-312-752 1 E-304-661 15 C-302-660 17 E-304-662 15 y 97 B-312-644 3 E-304-661 15 C-302-661 19 ~ E-304-664 18 o

~ TDR-TMI-194 APPENDIX I Page 5 of 12 SYSTEMS INSPECTED AND APPLICABLE DR. WINGS (Cant'd) i ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV 98A SS-312-643 1 E-304-663 8 C-302-661 19 103 D-312-641 3 E-304-661 15 E-304-663 12 118 C-312-642 1 E-304-663 12 146 C-312-692 1 E-304-661 15 E-304-664 18 7 163 C-312-714 0 E-304-661 15 C-302-660 17 164 C-312-715 1 E-304-661 15 C-302-660 17 167 C-312-718 0 E-304-661 15 C-302-661 19 E-304-662 15 168 B-312-723 2 E-304-641 17 169 B-312-724 2 170 B-312-716 0 E-304-661 15 E-304-662 15 209, B-312-719 0 E-304-661 15 E-304-662 15 210 C-312-720 1 E-304-661 15 211 3-312-721 0 E-304-663 12 E-304-664 18 212 B-312-722 0 E-304-663 12 E-304-664 18 220 B-312-717 0 E-304-661 15 E-304-662 15 225 B-312-759 0 E-304-646 0 Spacing p Criteria i Nuclear Services 52 D-312-638 1 E-304-212 5 C-302-610 25 Closed Cycle 53 D-312-639 1 E-304-212 5 Cooling 94 D-312-632 1 E-304-611 9 E-304-612 14 4

TDR-TMI-194 APPENDIX I l Page 6 of 12 ( SYSTEMS INSPECTED AND APPLICABLE DRAk7.NGS (Cont'd) j ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV l MK-No's 95 D-312-634 1 E-304-611 10 C-302-610 25 l E-304-612 14 I NSE-99 B-312-666 1 E-304-213 5 i E-304-214 9 NSH-100 B-312-670 0 E-304-213 6 MC-E-304-214 9 4 RB-106 B-312-667 2 E-304-213 6 C-302-610 25 E-304-214 9 107 B-312-668 1 108 B-312-669 2 109 B-312-671 0 l 110 C-312-662 1 111 C-312-663 1 112 C-312-664 1 ] 113 C-312-665 1 114 C-312-660 1 4 n In Core Monitoring 101 B-312-676 ._-521-021 6 N/A MK No's 102 B-312-676 1 E-521-021 6 N/A 115 C-312-661 1 E-304-611 9 C-302-610 25 116 D-312-655 2 E-304-611 9 E-304-f!2 14 Nuclear Services 117 D-312-655 2 E-304-613 9 Closed Cycle 131 C-312-635 2 E-304-611 9 Cooling E-304-612 14 MK-No's E-304-613 9 NSE-133 C-312-633 1 E-304-612 14 NSH-140 B-312-690 1 E-304-611 9 MC-141 B-312-691 1 E-304-611 9 i RB-142 B-312-690 1 E-304-611 9 u i r

---.= = -. - TDR-TMI-194 APPENDIX I Pabe 7 of 12 SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV 143 B-312-691 1 E-304-611 9 C-302-610 25 144 B-312-693 2 E-304-612 14 i 145 B-312-634 1 E-304-612 14 3 155 C-312-704 1 E-304-613 9 156 C-312-705 1 E-304-613 9 l 179 D-312-762 1 E-304-614 10 E-304-615 2 183 B-312-737 0 E-304-611 9 185 B-312-734 0 E-304-611 9 186 B-312-735 0 E-304-611 9 187 B-312-733 0 E-304-611 9 188 B-312-738 0 E-304-611 9 4 189 B-312-755 0 E-304-646 1 C-302-610 25 190 B-312-748 0 E-304-646 1 C-302-610 25 C-302-645 10 191 B-312-740 0 E-304-612 12 C-302-610 195 B-312-742 0 196 B-312-727 0 1 4 198 B-312-750 0 E-304-612 14 C-302-610 25 l 199 B-317-741 0 E-304-613 9 200 B-312-756 0 E-304-613 9 201 B-312-728 0 E-304-102 13 4 203 B-312-757 0 E-304-213 4 204-2 C-312-780 2 E-304-614 10 4 1 E-304-615 2 204-3 C-312-781 2 E-304-614 10 ? E-304-615 2 j 204-1 C-312-782 2 E-304-614 10 y 205 D-312-731 2 E-304-614 10 C-302-610 2' E-304-615 2 i 4 i ~

TDR-TMZ-194 APPENDIX 1 Page 8 of 12 SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) i ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV I 213 C-312-765 0 E-304-614 25 C-302-610 25 214 C-312-766 2 i 215 C-312-767 2 l 218 D-312-763 2 219 D-312-764 4 y 222 C-312-758 0 E-304-646 1 g 225 B-312-759 0 E-304-646 1 C-302-610 25 C-302-645 10 Spacing Criteria ) Reactor Bldg. 20 SS-312-596 1 E-304-712 17 C-302-712 15 i Spray 32 B-312-629 0 E-304-712 17 MK-No's 45 SS-312-574 2 E-304-712 17 BS-46 B-312-628 1 E-304-712 17 SPS-75 C-312-618 1 E-304-713 2 SBW E-304-714 6 76 C-312-620 1 77 C-312-621 1 78 C-312-622 1 79 C-312-623 1 1 80 C-312-624 2 f y 81 C-312-626 2 E-304-713 2 C-302-712 15 E-304-714 6 82 C-312-627 2 83 C-312-696 1 J 84 B-312-612 2 85 B-312-613 2 g 9 i 171 C-312-743 1 E-304-712 17 C-302-712 15 172 C-312-746 0 E-304-712 17 C-302-712 15 E-304-641 20 C-302-640 24 E-304-641 28 i i ._~

TDR-TMI-194 j APPENDIX X 1 Page 9 of 12 i l SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) i l ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV l 173 C-312-745 0 E-304-712 17 C-302-712 15 E-304-641 20 C-302-640 24 E-304-642 28 l 174 C-312-744 0 E-304-712 17 C-302-712 15 175 C-312-747 0 E-304-712 17 1 i 176 C-312-751 0 E-304-712 17 226 C-312-768 1 E-304-712 17 } E-304-625 9 227 C-312-769 0 E-304-625 9 f Spacing p Criteria t River Water 14 C-302-202 20 MK-No's 28 C-312-600 1 E-303-135 7 RW-33 C-312-616 1 E-303-135 7 IP-36 D-312-617 2 E-303-135 7 RR-37 D-312-619 3 E-303-135 7 52 157 SS-312-707 1 E-303-131 15 E-303-132 13 158 SS-312-708 1 159 C-312-706 1 161 SS-312-709 1 U 216 B-312-729 1 E-303-135 5 217 B-312-729 1 l Spacing J Criteria 1 i l e. + +4%. p.= -._-4 ryi .-m-.. p -i-ey y r,. w.y yh = - - g --ww-m,

~. ~. _.. _. _- - - i TDR-TMT-194 APPENDIX I Page 10 of 12 SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Emergency 47 D-312-625 1 E-304-124 14 C-302-081 17 Feedwater 49 D-312-697 1 E-304-102 13 MK-No's 69 SS-312-504 2 E-304-086 14 71 SS-312-593 2 o 21 B-312-567 4 E-304-086 14 22 C-312-566 4 E-304-086 14 ] l EF-62 SS-302-584 3 E-304-086 14 i 63 SS-302-583 3 E-304-086 14 2 64 SS-312-585 3 E-304-086 14 65 SS-312-586 3 E-304-086 14 66 SS-312-587 3 E-304-086 14 67 SS-302-591 2 E-304-086 14 68 SS-302-592 2 E-304-086 14 70 SS-312-595 2 E-304-086 14 201 B-312-728 0 E-304-102 13 4 1 Spent Fuel 119 C-312-683 1 E-304-631 21 C-302-630 11 MK-No's E-304-632 17 SFE-120 C-312-684 1 SFH-122 SS-312-678 1 124 C-312-677 1 125 ' 312-681 1 126 B-312-682 2 127 B-312-682 2 128 C-312-674 1 129 B-312-680 1 130 B-312-680 1 132 C-312-679 1 l 134 B-312-675 1 I 135 C-312-686 1 136 B-312-688 1 137 C-312-689. 1 ] l Spacing l Criteria i m e a r-w+, -p -,,e-+ y..a q ,e n----e m--. g* a ---,,..r-r.,

TDR-TMI-194 APPENDIX I Page 11 of 12 SYSTEMS INSPECTED l 3 APPLICABLE DRAWINGS (Cont'd) 1 '1 ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV I Waste Disposal Spacing E-304-699 18 C-302-690 17 MK-No's Criteria C-302-691 16 } WDE-C-302-692 19 WDH-C-302-693 20 Reactor 51 SS-312-640 1 E-304-641 16 C-302-650 18 Coolant 88 B-312-579 3 E-304-653 10 C-302-650 18 MK-No's 89 SS-312-577 2 E-304-653 10 RC-91 SS-312-576 2 E-304-653 10 PR-92 SS-312-580 3 E-304-653 10 93 B-312-578 2 E-304-653 10 147 SS-312-695 2 E-304-653 10 148 B-312-700 2 E-304-653 10 160 C-312-710 4 E-304-653 10 E-304-709 4 162 B-312-565 4 E-304-653 8 163 C-312-714 0 E-304-661 13 9 Inte rmediate Cooling 54 D-312-630 1 E-304-621 10 C-302-620 149 D-312-701 3 E-304-622 20 C-302-620 150 C-312-703 1 151 C-312-702 2 154 D-312-701 3 7 181 C-312-753 E-304-621 12 182 C-312-754 2 q p Chilled Water 144 B-312-693 2 E-304-612 12 D-302-655 1 145 B-312-694 1 E-304-612 12 D-302-655 1 250 C-312-783 E-311-841 u z i l l 4

~. _ _. i \\ TDR-TMI-194 l ) APPEhTIX I 1 l Page 12 of 12 i i ) SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) l i d t j ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV l Chilled i Water 251 C-312-784 D-302-655 1 E-311-841 i 25 2 i Spacing p Criteria 1FSAR Class III System. Inspected Portion Class I. 2FSAR Class II System. Inspected Portion Class I. 1 i 4 L .1 i 4 e 6 I i t P l

TDR-TMI-194 APPENDIX II INSPECTION PROCEDURE

TDR-TMI-194 APPENDIX II Page 1 of 10 INSPECTION PROCEDURE 1.0 GENERAL PROCEDURE 1.1 Inspection of aupports and piping geometry of Seismic Category 1 systems sht se as specified herein. 1.2 Piping supports to be inspected are fixed hangers and supports, variable and constant-support hangers and supports, seismic restraints and hydraulic snubbers. They shall be termed supports for this prc:edure. 1.3 Piping ;;ometry shall be inspected for arrangement and location of supports and valves in comparison to the mechanical isometrics and piping arrangement drawings. 1.4 Nonconformances and significant deviations shall be evaluated within the requirements of th= plant tech-specs to determine their effect, if any, on the ability of the system to function. 1.5 Deviations which decrease the function of load capacity of a support chall be indicated on an action item or support inspection report. An engineering evaluation shall be made to determine the support's capability and the systems ability to function. If the support's capability is determined to be insufficient and/or the system function is disabled, then the Manager TMI-1 Engineering or the 4 TMI-1 Lead Mechanical Engineer shall be promptly notified in accordance with the requirements of IEB 79-14 including Supplement 2. 1.6 Damaged supports shall be indicated on an action item or support inspection report and submitted for Engineering Evaluation. 1.7 Where a support deviates from the drawing, sufficient and detailed information sh4il be provided (on a separate sheet if necessary) to allow an Engineering Evaluation and to allow drawing changes to be made. f ~ ~ w m. -m-ww-mm 7

TDR-TMI-194 APPENDIX II 4 Page 2 of 10 1.8 Data which has been obtained by way of visual estiaation in lieu of measurement will be identified in ;he final report prepared by GAI I for GPU/ Met-Ed. 1.9 Thermal insulation may be removed, if required by IE Bulletin 79-14, Supplement 2. Mirror insulation removal and reinstallation shall be per Maintenance Procedure 1410-47. 1.10 Inspections requiring access which are impractical even with the reactor shutdown (and consequently are not performed) will be evaluated in GAI's final report on a case basis. 1.11 Observe Radiation Work Permit (RWP) requirements for all radiation / contamination areas. 2.0 PIPING INSPECTION 2.1 PIPING INSPECTION REPORT a PIPING INSPECTION REPORT shall be completed for each piping i isometric. If a portion of a system appears on more than one isometric, the isometric on which that system paction was inspected shall be referenced on the other isometric's system evaluation data sheet. 2.2 PIPE SUPPORT ATTACHMENT 2.2.1 Location of pipe support attachment to pipe shall be inspected and compared to the piping isometric.

TDR-TMI-194 APPENDIX ZI Page 3 ef 10 2.2.2 The following axial tolerances are allowable: PIPE SIZE TOLERANCE To 6" 4" 8" to 18" 18" 20" to 36" tl2" 2.2.3 Support attachment locations not within tolerance shall be recorded on the piping isometrics for actual dimensions. The support shall be identified on the PIPING INSPECTION REPORT. Supports not shown on the piping isometrics shall be located on the 2.2.4 drawings. A sketch showing function and attachment shall be attached to and referenced on the PIPING INSPECTION REPORT. 2.2.5 The piping shall be checked for unspecified interferences which limit the thermal movement of the pipe. These shall be located on the piping isometric and referenced on the PIPING INSPECTION REPORT. 2.3 VALVES 2.3. Valves shall be located within tolerances specified in Item 2.2.2 of dimension shown on piping isometric. 2.3.2 Valve operator rotation from piping axis shall be within 15 of that shown on drawing or to next bolt valve bonnet if flanged bonnet valve. 2.3.3 Valves or valve operators not within tolerance shall have actual diment lonsf angular rotation recorded on the piping isometric and referenced on the PIPING INSPECTION REPORT. y --e m

-= l TDR-TMI-194 APPENDIX II Page 4 of to ([ 2.4 SUPPORT ORIENTATION 2.4.1 Support structural attachment orientatica with the pipe attachment shall be within t7 of specified orientation. 4 2.4.2 Beam brackets or the equivalent may be rotated 90 for rigid rod hanger S2pports. i 2.4.3 Beam brackets used with sway braces shall be oriented so as not to j hinder axial movement, unless otherwise specified on the drawing. 1 i 2.4.4 Restraints designed to.act in pairs shall provide the same function as the designed supports. t ' 2. 5 PIPE GE0 METRY i i Pipe geometry shall be as shown on the isometric drawings. Where geometry deviates by more than one pipe diameter it shall be recorded on the isometric and referenced on the PIPING INSPECTION REPORT. 3.0 SUPPORT INSPECTION 3.1 SUPPORT INSPECTION REPORT i 3.1.1 A SUPPORT INSPECTION REPORT shall be completed for each support inspected. 3.1.2 The support including attachment to plant structure shall be as i shown on the support drawing. Deviations not allowed within this procedure shall be recorded on the SUPPORT INSPECTION REPORT and evaluated by Engineering. l l I { l

TDR-TMI-194 APPENDIX II Page 5 of 10 3.2 SUPPORT STRUCTURAL ATTACHMENT 3.2.1 Support attachment to concrete shall be as shown on the drawing. Where concrete expansion anchors are shown, the number and size only shall be recorded. Loose anchors shall be identified. 3.2.2 Supports attached by Unistrut shall have the number and size of bolts in Unistrut recorded. i 3.2.3 Embedments shall have dimensions and location of support attachment as shown on the drawings. Deviations greater than 1" shall be recorded. 3.2.4 Base plates shall be checked for the following (record deviations greater than 10 percent of measure quantity): 1. Plate thickness, dimensions, orientation 2. Anchor location, size, and quantity 3. Edge distance from center of anchor to plate edge (if less than 2 X diameter of bolt, record) 4. Location of support attachment. 3.2.5 Anchors for other supports within 8 in. center-to-center shall be shown on support drawing. f 3.2.6 Edge distance of anchor center-line to edge of concrete shall be shown if less than 6". 3.2.7 Floor and wall penetrations shall have clearance as specified on drawing. Check at four locations 90 apart. If no clearances specified, measure and record. e d

TDR-TMI-194 APPENDIX II Page 6 of 10 3.3 SUPPORT TYPE 3.3.1 Support shall be that shown on drawing except as acted herein. 3.3.2 Rigid Rod Hangers 1. Single rigid rod hangers may be interchanged with double-rod trapeze hangers provided new support is adequate to carry load. 2. Double-rod trapeze hangers may be interchanged with single rigid rod hangers provided single rod diameter is 1-1/2 times r or greater than double-rod diameter. 3.3.3 Spring Hangers 1. Types "A", "B" AND "C" spring hangers may be interchanged. 2. The elevation of Type "A", "B" OR "C" spring may be different. 3.3.4 Hydraulic Snubbers 1. A large bore snubber may be substituted for a smaller bore snubber. 2. The fluid reservoir may be reversed from the drawing provided the vent hole is on the 'high' side of the snubber. i 3. Threaded end of the snubber shall be on the support structural attachment (building) side. 4. Snubber shall be < 1/4" from full extension or full compression.

TDR-TMI-194 APPENDIX II Page 7 of 10 1 3.4 WELDF.D ATTACHMENT.7 3.4.1 Welded attachments to pipe shall be as shown on drawing. 3.4.2 Record any cracked welds, or missing attachments. 3.5 SUPPORT COMPONENTS 3.5.1 Support components shall be equal to or heavier than that specified on drawing or bill of material. 3.5.2 All components shall be installed. Missing components shall be identified. 3.5.3 Two steel plates may be substituted for a beam bracket. Record dimensions of plates. 1 3.5.4 Attachment plates with forged clevises may be interchanged with beam brackets with welded eyerods if equal to or heavier size than shown on drawing. 3.5.5 Weldless eyenuts with threaded rod may be interchanged with welded eyerods if equal to or heavier than shown on drawing. 3.5.6 Field fabricated pipe insulation saddles may be substituted for manufactured pipe insulation saddles. Record dimensions. 3.6 SUPPORT LOAD ATTACHMENT 3.6.1 If location not specified, record location from point of structural attachment to building. Record distance between structural attachment points. (e.g., rigid rod hanger on angle held by two anchor bolts.) t

-~ 1 IDR-TMI-194 i APPENDIY IX Page 8 of 10 3.6.2 Lengths of structural shapes used to form a support bracket (e.g., i knee brace) shall be as shown on drawing. 3.7 WELDING 3.7.1 WELDING - Symbol Shown Welding shall be in accordance with symbol shown or develop the strength of the weaker member. 3.7.2 WELDING - Symbol Not Shown Welding shall be 1/4" fillet all-around or develop the strength of 4 the weaker member. 3.7.3 Cracked or damaged welds shall be recorded. 3.8 THREADED MEMBERS 3.8.1 LOCKNUTS 1. Lockn2ts shall be tight and in accordance with the drawings except as specified herein. 2. Only one locknut is required at turnbuckles on rigid rod hangers that have eyerods at the structural and pipe attachment points. The locknut may be either on the top or bottom of the turnbuckle. 3. Two locknuts are required on any hanger that has a rod threaded at both ends and is between a clevis or eyenut and turnbuckle. 4 One locknut may be at the clevis /eyenut end, or at the turnbuckle end of the rod threaded at both ends. The other locknut shall be on the other rod at the turnbuckle.

TDR-TMI-194 - + APPENDIX II l Page 9 of 10 3.8.2 U-BOLTS U-bolts shall be installed to the tight or loose condition as specified on the drawing. All nuts shall be installed as shown. 3.8.3 THREAD ENGAGEMENT 1. Nuts shall have full thread engagement (one full thread exposed through the nut). 1 2. Clevis / turnbuckles shall have full thread engagement (one full thread exposed). 3. Less than full thread engagement shall be recorded. Indicate diameter and depth not engaged in nut / clevis / turnbuckle. 3.9 MAINTENANCE ITEM REPORT 3.9.1 Items found during inspection which do not affect the function or load capacity of a support shall be identified on a MAINTENANCE ITEM REPORT for action by the Plant Staff as necessary. 3.9.2 Examples are: 1. Loose nuts with full thread engagement (except on tight U-t bolts). 2. Loose pipe clamps. 3. Loose bolts when used in shear only. 3.10 ACCEPTANCE 3.10.1 Supports which are in accordance with the drawing or have deviations which do not affect the load capacity in accordance with this procedure are acceptable. 1 --r-y _y.,,

..m TDR-TMI-194 APPENDIX II 1 i Page 10 of 10 i l 3.10.2 Supports which do not meet the drawing requirements and have i i deviations which reduce the load capacity shall be identified on an i i SUPPORT INSPECTION REPORT and sumbitted for Engineering Evaluation. i i 3.10.3 Data package is complete including all INSPECTION REPORT data sheets and marked up isometric drawings. i j i i P D E 4 i i l

TDR-TMI-194 ATTACHMENT NO. I to APPENDIX II PIPING INSPECTION REPORT PIR-System Recommended Disposition ME Yes/No - Comp. Dwg. Rev. Acceptable Reference Dwg. Analysis Required Drawing Revision Reg'd 4'ithin INSPECTION Tolerance 1. Support Location 2. Support Orientation 3. Valve Location 4. Valve Operator Orientation 5. Pipe Geometry Date Engineer / Inspector j j DEVI?.TIONS ANALYSIS i Date Engineer / Analyst i ) i i

4 TDR-TMI-194 ATTACHMENT NO. 2 to APPENDIX II SUPPORT INSPECTION REPORT SIR-I Support No. Recommended Disposition Drawing No. Rev. Acceptable Drawing Rev. Reg'd l Repair /Reqork Reg'd INSPECTION Yes/No 1. Structural Attachment Per Dwg. 2. Concrete Expansion Anchor Bolts Used No./ Size / 3. Undstrut Attachment Bolts Used No./ Size / 4. Support Type Per Dwg. i 5. Spring / Snubber Correct Size j 6. Structural Components per Dwg. t 7. Welding per Dwg. l 8. Locknuts Installed per Dwg. AIR 9. Full Thread Engagement MIR l Date Inspector DEVIATIONS DISPOSITION i f Date Engineer / Designer r ,m..

] TDR-TMI-194 l ATTACHMENT No. 3 to APPENDIX II 1 MAINTENANCE ITEM REPORT MIR-i 1 Support No. ] Drawing No. Rev. 1 l DESCRIPTION OF PROBLEM 4 i .1 I i d 1 i 4 Date Inspector MAINTENANCE ACTION i f I t i

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Date DISPOSITION 1 I Date i l i i 1 -%e -m-..- >-r+ r w -r at-$- s, wa= _y -n-e- -'b ~""9

TDR-TMI-194 ATTAClefENT NO. 4 to APPENI)IX II ACTION ITEM REPORT No. 14-Support No. d No. Drawing No. Rev. DESCRIPTION OF FINDING

RESPONSE

4 DISPOSITION

TDR-TMI-194 APPENDIX IIIA SLTIARY OF NON-C0hTOD!ANCES AND RESULTS OF REANALYSES

SUMf!ARY OF NONCONFOR11ANCES AND RESULTS OF REANALYSIS Results of F.eanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title Supports Supports Supports Review HE-1A 2, 11, 12 Pump 'A' Suction 23 0 0 23 HE-3 1 4 0 0 4 HE-0411 6 12" D.ll.1% mp Suction 6 8 0 14 2 HE-6 12 Cold Leg of Pump C to Reanalysis Not Complete Cold Leg of Pump B HE-7 1, 4 HU-V-89A to Filters Heanalysis Not Complete MU-F4A and HU-F4B HE-8 1, 4, 12 From Filters HU-F4A and Reanalysis Not Complete HU-F4B to Reactoc Wall Pen. #337 HE-010 1, 2, 12 D.11. Removal 6" Crossover 16 1 1 16 HE-Il 6 From Pen. #309 to Anchor Reanalysis Not Complete HE-14 6 R.B. Energency Cooling Water Reanalysis Not Complete Pump-Discharge from Pump RR-PIB HE-020 12 R.B. Spray Pump Suction 21 6 0 27 (Pump B) HE-21 1, 4, 5 Aux. Feedwater to Steam 26 0 2 24 HE-22 1, 2, 4, 5 Auxiliary Feedwater to 26 0 0 M Steam Gen. 7%d $"7 hd NE-24 1, 2, 3 Main Steam from Stm. Gen. 14 0 0 14 A to Anchor at Reactor oy7 Bldg. Wall ,G -s-M

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title Suppoets Supports Supports Review HE-25 1, 2, 3 Hain Stm. from Stm. Gen. 12 0 0 12 A to Anchor at Heactor Illdg. Wall HE-25 1, 2, 3 Hain Steam from Steam 13 1 0 14 Gen. B to Anchor at Reactor Bldg. Wa:1 HE-27 1, 2, 3 Hain Stm. From Stm. 14 0 0 14 Gen. B to Anchor HE-28 1, 2 Decay lleat Service 12 0 0 12 Cooling Water HE-29 1, 2, 3 Feedwater f rom Anchor at 10 0 0 10 Reactor Bldg. Wall to Stm. Gen. B HE-30 2, 3 Feedwater from Anchor Reactor 18 0 0 18 Bldg. Wall to Stm. Gen. B HE-32 1, 2, 4, 6, 8, 12 R.B. Spray Pump Disch. 26 4 0 30 (Pump A) HE-33 1, 2 Decay lleat Rt ?;ervice 6 0 0 6 Cooling Water (Rivur Wtr.) HE-34 1, 2 Core Flooding and Decay lleat. 19 0 0 19 Hemoval Piping to Reactor (South) E % El HE-35 9 Core Flooding and Decay 14 0 0 14 ggy lleat Removal Piping to ggg Reactor opy n. H@ HE-36 1, 2, 12 D.ll. Service Cooling, 42 3 0 45 gH^ 5 River Water

Resulta of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title Supports Supports Supports Review HE-37 1, 4, 8, 12 D.ll. Service Cooling, 38 0 0 38 River Water HE-38 2 Main Steam Piping from 26 0 0 26 Reactor lildg. to Turbine Gen. ME-39 2 Main Steam Piping from 25 0 0 25 Reactor lildg. La Turbine Gen. HE-40 2, 4 Main Steam Piping from 21 0 0 22 Reactor Bldg. to Turbine Gen. HE-41 1, 2, 5, 7 H.S. Piping from R.B. to 21 0 0 21 Turbine Generators ME-42 1, 2, 4, 8, 10, M.S. Piping from Stm. Gen. A 23 0 0 23 12 To Emerg. Feedwater Pump Turbine HE-43 2,3,4,8, 12 M.S. from Stm. Gen. 11 25 0 0 25 to lleader ME-44 1,2,6 M.S. from Steam Gen. 10 0 0 10 B to lleader at 297'-0" ME-45 1 R.B. Spray Pump Suction SEE ME-20 (for both pumps) ME-46 1, 2, 4, 6, 12 R.B. Spray Pump Disch. SEE ME-32 (Pump D) @%y 5 '" 7 mhj HE-47 9 Condensate from Storage Tank 7 0 0 7 'A' to "mergency Feedwater o p *;* Pumps

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a CT( 1 St RC RC DW Dt DWC DC DV DW Et ) 2 ec 3 na n m o 2 rei 8 1 odt 2 f oc nC e 5 4 3 1 6 8 o S 2 c 1 n e 4 2 2 2 4 3 3 o e 2 1 2 N S ( 1 1 1 1 1 1 1 1 3 1 2 s i r se 9 1 2 3 6 7 8 9 0 1 2 yb 4 5 5 5 5 5 5 5 6 6 6 l m ~. au E E E E E E E E E E E nN H H H H M H M M M M H A

g7$yg# ggdg. { yg u om C g sn ti w rre oii 6 1 5 6 4 1 8 3 2 puv 1 1 1 pqe ueR SR s i s s dt y er l t o 0 0 0 0 0 0 0 0 0 a ep n l p a eu e DS R fo 2 9 0 0 s 6 4 1 1 s t t d r E E E E 0 M 3 0 0 M M 0 0 l eo 0 0 M 1 u d p s d p E E E E e Au E E E E R S S S S S l s at l nr 5 6 1 1 8 3 2 aio 6 1 t gp 1 1 1 oip TruOS l l aW r n e t t e d e e e o B. a l l w y e t t t a t R l n u u e r l o g B O O B p h g o o o i r n () S c r. t 1 t t t eo n p A B e s eh l c mi o m r B. g I I l i mc ra r u Et ir u C C o n t D E s eW e h S c t o P l tR i i i d d c nu ch g l l c p l T "1 eD a. a s n D D a& i "A eS uc v eg e i v S n ri e P 1 i p hd D ip A t p r r Rl l l l r m r wi e e rm y l p D u mB m p p D u eo dP l l ma a m P o o m m P t t F o o oW r u e r r r u u e a n o. o r pl Wr P r n. f o f P P n. o C B. C B. fd S// e ir t i r o gi l bt .h rt .R 1.R 1.e g .d bt c F. W W r w F. c a r w F. F. e l I ec i n a ud n mu

l. o 1

o 1 h I. ud e i El TF ER E E E TF EA ES Dt Dt DS RR l ) 2 ec 3 2 2 n 1 1 a n m o 2 rei 1 8 8 odt 2 f oc 6 3 nC e 6 8 1 o S 2 c n e 2 3 3 8 1 4 2 2 2 2 2 o e N S ( 1 1 2 6 6 2 1 1 1 1 1 1 2 s i r A se 3 4 5 6 7 8 9 0 1 2 3 4 5 yb 6 6 6 6 6 6 6 7 7 7 7 7 7 l m au E E E E E E E E E E E E E l l nN M t M M M f t M M M t M t A

Fesults of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Numlier (See Section 3.2) Title Supports Supports Supports Review ME-76 2 R.B. Spray Piping Spray 15 0 0 15 Ring #2 ME-77 2 R.B. Spray Piping Spray 18 0 0 18 Ring #3 ME-78 2 R.B. Spray Piping Spray 22 0 0 22 Ring #4 tlE-79 2 R.B. Spray Piping Spray 23 0 0 23 Ring #5 HE-80 2 R.B. Spray Piping Spray 23 0 0 23 Ring #6 ME-81 2 R.B. Spray Piping Spray 30 0 0 30 Ring H7 HE-82 2 R. ll. Spray Piping pray 33 0 0 33 Ring #8 ) HE-83 2 R.B. Spray Piping Spray 33 0 0 33 Ring #9 flE-84 1,2,3,4,5,9 R.B. Spray Wtr. Piping from 19 0 0 19 Pen. #308 to lleader D at El. 417'-6" ME-85 1, 2, 9 R.B. Spray Wt r. Piping from 13 0 0 13 Pen. #301 to lleader at El. 417'-6" ygg % ;3 7 e M E! >< Y O HC m e. C

7!YGc. E NMkNa z U2 s O g sn ti w rre oii 3 4 0 0 puv 1 1 4 1 pqe ueR SR e s t i s e s dt l y er p l t o 2 0 m 0 0 a ep o n l p C a eu e DS t R o N fo s 9 9 s i 8 8 s t s t d r y E E l eo 0 3 l 0 M 0 H u d p a s d p n E E e Au e E E R S R S S l s at l nr aio 5 1 0 0 t gp 1 1 4 1 oip Tr3OS gno e i t d cr l o o l i e oB t mt m e e vl o2 o o i n roA CC e rl r i i l eoI v fl f S L SCP eC l a o cD a f W fk o f t e d mC i V e en t e l eoD vr id ia il T f l l t sr re f l l l i of p el e ee e e ea m S o i Ri R n i RW T lc .u o l l ea e ed i i l rP dCA el eS Rl r k r r R rl k tL e I aWo s mP a uyn uD uen e t oo-eW sra s e sia rC r sat so r shT l g l l nA CFD ud ed et u eS yi2 sl r nn r s r n p se P oi Pl sl P mi al C co-l rm ei ca l el oa eoC

l. t u rl

" er " a ra " rr i DCD DWP PS 6SD 6W PW 4fD ) 2 ec 3 na n m o 2 2 2 r ei 1 1 1 odt f oc nC e 3 3 3 3 9 o S c n e 2 2 2 2 4 o e 2 N S ( 1 4 1 1 1 1 1 s ir se 6 7 8 9 1 2 3 yb 8 8 8 8 9 9 9 l m au E E E E E E E nN H H H H H H H A

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring haber (See Section 3.2) Title Supports S_upp'o r ts Supports Review HE-94 1,2,4,5,6 N.S. Cooling f rom lit. 24 0 0 24 Exchangers to Pumps HE-95 1, 2, 4, 6 N.S. Cooling Water 18" 46 0 0 46 Supply to lleat Exchangers t!E-96 1, 2, 3, 7, 11, Dil Hemoval Borated Water Tank See HE-1A 12 Discharge HE-97 1,4,6 2-1/2" liigh Pressure injection 14 0 1 13 Piping from Pcu. #r.1 to !!&W Conn. #17 HE-101 9 Incore Monitoring System 8 0 0 8 Piping HE-102* 1, 2, 4, 9 Incore Monitoring System 5 0 0 5 Piping HE-103* 1, 2, 4, 9 2-1/2" liigh Pressure Injection 26 0 0 26 Piping from Pen. #322 to B&W Conn. #15 HE-Il0 1, 2 Heact.. Bldg. Emerg. Cooling 18 0 0 18 Wt.r. Return from Air llandling Urd t All-E-1I A to Pen. #407 HE-Ill 1, 4, 9 R.B. Cooling Water from Pen. 16 0 0 16

  1. 410 to All-E-I A ME-Il2*

1, 3 Heact. Bldg. Emerg. Cooling 16 0 0 16 ygd Wtr. Heturn from Air llandling gmy Unit All-E-lC to Pen. #409 ,hg MY O HE qmn W

l8E7 j {(TdN gu 1 [a eo t g sn ti w rre e oii 3 6 6 0 8 4 0 t 8 puv 1 1 1 7 1 3 2 e pqe l ueR p SR m o C s t i s o s dt N y er l t o 0 0 0 1 6 0 0 0 s 0 a ep l i n l p I s a eu y e DS E l R H an f e a o e e s S R s t t d r eo 0 1 0 0 0 1 0 0 lu d p s d p e Au R S l s at l nr aio 3 5 6 1 8 3 0 8 t gp 1 1 1 7 1 3 2 oip TruOS g m n n o o o e W g s i t r i n gl g f t& n a o cB e nd8 n1 i B tk n "I P i n0 i 1 B I e p n ng r j o ri m ra on l a4 l4! u "& m ol # o# - p nt oP on oT m l i .E m o o o I h ri h o p t "A r C r. C e 8 c. f a c e rni u f in nll P R" e3 n l. l t ng f nP Ae eA r3 A ge A a o r g P gP r rs u# D nR r gCl e e r m r t es er s m mo n a i l t eoo emi t r t es s. oo po ot iWv t aC mrt mon ao al t en rt it rS l & o Wl Ef E rU Wh Won re f P f oB m i T B f c oi PP 7 7 r o e gE n1 g gn gC o g1 gl l ge C" R n-gr - gyn nA n P h m n1 nI l nt 8 l d uE dl i i il go i i - a i a l t i l l t - l pl l o l er i r9 l & l 1 l W eoa FW l A o Bel B pd ot ouo f1 o o1 o ut c i l un o oFh o6 o5 n od F oo .Rl I I Ct A .S a C C c " g Cl C i C e 1 t r t .H .h t n 2 n t3 y l .t c .nA /i n .pg a n l a 2 cet c F. F F. u i F. B. 4 1 ati arr S. i S. s e 1 pn l pn r eic i po io ean et i o pF e R# RWU RWA ND NSt 2PC SS SSR SB SSD ) 2 e 2 c 3 2 1 n 1 a n m o 1 rei 4 1 odt f oc 2 nC e 6 3 3 4 8 1 o S 2 c n e 3 2 1 2 2 6 8 o e N S ( 1 1 1 1 1 1 1 1 9 1 s ir 3 4 5 6 7 8 9 0 1 2 se l l l l 1 l l 2 2 2 yb I I l I 1 l I 1 1 1 l m au E E E E E E E E E E nN H H H H H H H H H H A

= Results of Reanalysis Nonconformance Total Supports Analysis Code Origiual Added Deleted Requiring Number (See Section 3.2) Title Supports Support.s Supports Review HE-123 12 Decay lleat Removal Piping from See HE-32 Seal Plate in Wall to Conn. on 8" Fuel Piping HE-124 1, 6, 8, 12 S. Cooling WLr. Piping to 26 0 0 26 ted Wtr. Recirc. Pump & S . Piunps SF-P-1 A & SF-P-111 ME-125 1, 8, 12 S.F. Cooling Water Piping from 34 0 0 34 Coolers SF-C-1A & SF-C-1B HE-126* 1 Spent Fuel Cooling Water 2 0 0 2 Piping to Spent Fuel Water Pool SF-T-2A HE-127* 1 Spent Fuel Cooling Water 2 0 0 2 Piping to Spent Fuel Water Pool SF-T-2B HE-128 1, 5 S.F. Cooling Piping from 9 0 2 7 Pen. #304 Fuel Canal HE-129* 1, 2 Spent Fuel Cooling Piping from 5 0 0 5 Spent Fuel Pumps SF-P-IA to-coolers SF-C-1A HE-130* 1, 2 Spent Fuel Cooling from Spent 2 0 0 2 Fuel Pumps SF-P-1B to Cooling SF-C-1B HE-131* 1, 2, 3 Nuclear Services Cooling Water 21 0 0 21 ygg from Spent Fuel Coolers "A" ggy "B" Anchors yg M't O e-* OP

Results of Heanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Numlier (See Section 3.2) Title Supports Supports Supports Review ME-132 8, 12 S.F. Cooling from S.F. Pools 19 0 0 19 SFT-2A & 211 NE-133* 1, 2 Nuclear Services Cooling Water 13 0 0 13 from Storage Tank to Pump Suction HE-134* 1, 2 Spent Fuel Cooling from Pen. 9 0 0 9

  1. 340 to SFil-37 ME-135 1, 4, 8, 11, 12 S.F. Cooling from SF-T-2A 13 1

0 14 ME-136 1, 2, 5, 6 S.F. Cooling from SF-T-2B 5 0 0 5 HE-137 1, 4, 6, 10, 11, -S.F. Cooling from Borated 20 0 0 20 12 Water Recire. Pump 11E-138 1, 2, 4, 8 Edwtr. f rom 30" lidr. to 4 1 0 5 Hecire. Pump HE-139 3, 5 F.W. from 30" lleader to 4 0 0 4 Fen. #227 HE-140 3 Nuclear Services Cooling 9 0 0 9 Water from Heact. Coolant Waste Gas Equip. HE-141 1, 8 N.S. Cooling Water from 9 0 0 9 NSil-100 to R.C. Waste Gas Evap. "B" E' D d ME-142 3 Nuclear Services cooling See NE-140 m me m

  • h h.

Water from Heact. Coolant C Waste Gas Evap. "A" g7 S,-. G ,O* s

$ 'j p T %NhM Ua E%" g sn ti w m' r re oii 3 9 2 8 9 2 4 8 puv 1 3 2 2 p <g e SRA ue te lp m s o i s C s dt y er t l t o 1 o 0 0 0 0 0 0 0 a ep N n l p s a eu 1 s t e DS 4 i r R 1 s o y p f E l p o H a u s n S s t e a t d r e e o l eo S 0 R 0 0 N 1 0 0 2 0 u d p s d p e A u R S l s at l nr aio 4 9 2 7 9 2 2 8 t gp 1 3 2 2 oip TruOS r p o m h o u c f f t P n e e r A r i i n y e r i l l r l t e g m A m U e e u p aB t n o "A o HC R H t o p WI a i r" o r I et u P WA l f t f o h h R t S r-I o t & t t B n eR gP o rp r r u r r4i r vD n-C 1 e ea e e n1 o o e2 o e i i R s l t v t t o1 S N t P t R p l R ss t aE a a i a& a m o eu i W W W t o o W r W8 t u om co T e aA t t Ao 4 aP C o i l i gt g gB c1 g4h g2 e r v ns n n4 i - r r n2 c n l m .f rp l ia i s i f P e e i - n i & o g em W l r l & i - z z l EA l yr re S u lo oe o rU i i o-l oA af eg P os oA uH r r ol d o4 c mr r o C C. C n C4 P u u CA e C2 e. E a ae e s s e s e m Dh .h ed .R .d .C &p sv sv mu .E c c l i m el el S. os S. l B. i S. S. n S. ll uu r a r a " s s cs l o o rs 0i un Nt NC NA HP PV PV NfA NA 21 RD NI ) ) 2 ec 3 2 n 1 a n m o rei 8 6 odt f oc 2 nC e 1 6 3' 4 o S c n e 8 6 3 2 6 3 3 o e N S ( 1 1 1 1 2 6 2 1 3 2 1 s i r 3 4 5 6 7 8 5 6 7 8 9 se 4 4 4 4 4 4 5 5 5 5 5 yb 1 1 1 1 1 1 1 1 1 1 1 m lau E E E E E E E E E E E nN H H H H H H H H H H H A

-.~.- Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Sect. ion 3.2) Title Supports Supports Supports Review ME-160 1, 2, 3, 5 Pressurizer Auxiliary Spray 41 0 0 41 NE-161* 1, 2 20" Decay lleat River Water 2 0 0 2 Discli, from Pum, DR-PIA i l NE-162 1, 3 Electromatic Relief to 6 0 0 6 Secondary Shield Wall HE-163 3, 8 Hll f rom 2-1/2" B&W Conn. to 18 0 0 18 1.etdown Coolers ME-164 1, 3, 4, 5, 6 From Letdown Coolers to R.B. 21 0 0 21 Wall Pen. #309 ME-165 12 12" Bypass for D.ll. Cooler See ME-56 Dil-CIA l NE-166 1, 8, 12 12" llypass for Decay lleat See ME-57 Cooler Ell-Cll! HE-167 1, 3, 4, 5, 6 Discharge from HU Pumps Reanalysis Not Complete MU-PIA, PIB & Plc HE-168* 2, 3 4" Hake-up Piunp Suction from 3 0 0 3 Decay lleat Removal Cooler Dil-CI A HE-169 1, 3, 12 4" HU Pump Suction from D.ll. See ME-146 Removal Cooler Dil-CIA ME-170 1, 2 Make-up Tank MU-Tl to Make-up See HE-146 EDd Suction lleader $"7 ~ HE-171 1, 12 6" R.B. Spray Text Line to See HE-32 " 5 'E Borated Water Recire. Pump Oisj 09

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Req': Iring Numlier (See Section 3.2) Title Supports Supports Supports heview l NE-172 11 Pen. #354 to R.li. Spray Pu qi Reanalysis Not Complete Suction HE-173 2, 12 Pen. #352 to R.B. Spray Pump Reanalysis Not Complete HE-174 1, 12 Sodium Hydroxide to Anchors See HE-Il9 HE-175* 1, 2 4" Sodium Thiosulphate Tank 14 0 0 14 IIS-Tl Disch. to React. Bldg. HE-176 12 10" Connection Piping Bldg. See HE-20 Spray Pumps PIA-PIB HE-179 1, 2, 3, 4, 12 N.S. Cooling Water from 48 0 5 43 RC-P-lC & HE-218 to HE-204 HE-183 12 Outlet to React. Coolant 1 0 0 1 Pump Seal Return Cooler HE-185 1, 4 NE-141 to Distillate See HE-141 Cooler B HE-186 3 Dist illa te Cooler "B". to See HE-140 HE-140 HE-187 12 NE-143 to Distillate See HE-Il6 Cooler A HE-188 1, 2, 6 Distillate Cooler "A" to See HE-95 ghg HE-142 g on. gfh HE-189 12 Disch. from Hake-up Purif. 46 7 0 53 Pump to HE-131 ,Mi ~U$

p

Results of Reanalysis Nonconformance Total Supports Analysis Code original Added Deleted Requiring Number (See Section 3.2) Title Supports Supports f oports Review HE-190 1, 5, 6 ME-16 to MU Purif. Pump 36 1 0 37 Suction Hb-UIS 1, 2, 6 N.S. Closed Cycle Cooling 11 0 1 10 Water Outlet of A.II. Units All-E-15A & ISP to HE-95 ME-196 3, 6, 12 ME-144 to Inlets of Sample See HE-144 Coolers HE-198 6, 12 Outlet of Sample Coolers See ME-145 to HE-197 ME-199 1, 4, 6 Fan Motor Coolers to HE-155 See ME-155 & 131 ME-200 4,5,6 NE-166 to Fan Motor Cooler See HE-156 Inlets HE-201 4, 8 ME-53 to ME-70 See HE-49 HE-204 1, 2, 3, 6, 12 8" Line from Pen. #347 to 53 2 2 53 to RCP-IA, IB, IC & ID HE-205 1, 3, 4, 9, 12 RC-P-ID to Pen. #346 24 1 0 25 ME-206 1, 3, 8, 10 From Condensate Tank "B". Reanalysis Not Complete HE-209 12 Hake-up Water & Purif. Pump See ME-167 Disch. Pipe to Disch. Ileadet E$$ ME-210 1, 2, 4, 5 HE-167 to Pen. #321 & #322 Reanalysis Not Complete %@7 dd HE-211 1,3,4,6,8 Make-up Pump Discharge Reanalysis Not Complete

  • y7 lleader to Pen. #338

,sG mn N

Results of Reanalysis Nonconformance Total , Supports Analysis Code Original Added Deleted Reclui ring Number (See Section 3.2) Title Supports Supports Supports Review HE-212 1, 3, 4, 6 Hake-up Pump Discharge lleader See HE-211 to Pen. #339 HE-213 1, 4, 9, 12 Cooling Water faom !!E-205 to 20 0 0 20 RC-P-lC & HE-214 NE-214 1,2,3,4,5, N.S. Cooling Water from 20 5 0 25 6, 9, 12 HE-213 to RC-P-1A & HE-215 HE-215 1, 3, 5, 12 N.S. Cooling Water from 26 0 1 25 tlE-214 to RC-P-ID HE-216 1, 2, 4, 8, 12 Decay lit. Serv. WL. See HE-36 and 37 River Water HE-217 1, 2, 4, 8, 12 Decay lit. Serv. WL. See HE-36 and 37 Hiver Water HE-218 1, 2, 4, 5, 12 Cooling Water from RC-P-IA 48 1 0 49 & HE-214 to ME-179 HE-219 1, 2, 3, 12 Cooling Water from RC-P-lli 39 1 1 39 to HE-218 HE-220 12 Hake-up Water Fill Lir.e to See HE-167 Make-up Pumps Disch. lleader HE-222 12 Decay lleat Cooling Water See HE-189 from HE-189 to HE-223 & HE-131 NE-223 1, 4 Cooling Water from HE-222 to See HE-189 $gg ,o HE-56 and HE-57 ,o m to en a gh HE-224 1, 3 Cooling Water HE-Il6 to See HE-190 ME-159 & HE-59 M,L o~U$ 09 i

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title Supports Supports Supports Review flE-225 3, 4, 6, 12 NSCCC-HC-224 to flE-190 See HE-190 HE-226 1, 3 R.B. Spray Pump Suction Tank Reanalysis Not Complete HE-227* 2, 3 DilCCC-3" L'ne React. Bldg. 10 0 0 10 Spray Pump to 16" Line from DilR Cooler (Dil-CIB) PIE-230 2, 8, 12 Main Steam Pump Line to See HE-42 & 43 Intermediate Bldg. Wall HE-234 13 From Emergency Feedwater Pump 7 0 0 7 Turbine to Exlianst Stack ?!E-250 1, 3, 4, 6 Cliilled Wat er Reanalysis Not Complete ?!E-251 1, 3, 4, 6 Cliilled Water Pump (All-P-3A Reanalysis Not Complete & All-P-38) Suction ?!R-252 1, 3, 4, 6 Cliilled Water Reanalysis Not Complete

  • No formal computer analysis performed 5%Y

%N7 M !2 "p7 ew M U N

0 4 8 9 9 9 I TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS

TDR-TMI-194 APPENDIX IIIB i RESULTS OF SUPPORT EVALUATIONS Page 1 of 15 i 7 Results of Evaluation 1 Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-1A Pump "A" Section 22 0 0 0 ME-3 Pump "A" Discharge 4 2 1 1 ME-04A 12" D.H. Pump Suction 14 12 4 8 ME-6 Cold Leg of Pump C Evaluation Not Started to Cold Leg of Pump B KE-7 MU-V-89A to Filters Evaluation Not Started MU-FVA and MU-F4B ME-8 From Filters MU-F4A Evaluatiou 'ot Started and MU-F4B to reactor wall pen. #337 ME-010 D.H. Removal 6" 16 15 9 6 Crossover ME-11 From Pen. #309 0 0 0 0 to Anchor ME-14 R.B. Emergency Cooling Evaluation Not Started Water Pump Discharge from Pump RR-PIB ME-020 R.B. Spray Pump Suction 27 19 13 6 (Pump B) ME-21 Aux. Feedvater To Steam 24 13 11 2 Gen. ME-22 Auxiliary Feedwater to 26 26 20 6 Steam Gen. ME-24 Main Steam from Stm. 14 13 13 0 Gen. A to Anchor at Reactor Bldg. Wall ME-25 Main Stm. from Stm. 12 7 6 1 Gen. A to Anchor at Reactor Bldg. Wall ME-26 Main Steam from Steam 14 10 8 2 Gen. B to Anchor at Reactor Bldg. Wall a h_ M A A

TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 2 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign j i ME-27 Main Stm. from Stm. 14 5 4 1 Gen. B to Anchor ME-28 Decay Heat Service 12 12 11 1 Cooling Water -ME-29 Feedwater from Anchor 10 8 7 1

  1. /

at Reactor Bldg. Wall to Stm. Gen. B f ,/ ME-30 Feedwater from Anchor 18 19 16 3 Reactor Bldg. Wall to Stm. Gen. B ME-32 R.B. Spray Pump Disch. 30 28 17 11 (Pump A) ME-33 Decay Heat Removal ( 6 6 0 Service Cooling Water (River Wtr.) ME-34 Core Flooding and Decay 19 18 16 2 Heat Removal Piping to Reactor (South) ME-35 Core Flooding and 14 4 1 3 Decay Heat Removal Piping to Reactor ME-36 D.H. Service Cooling, 45 26 21 5 River Water ME-37 D.H. Service Cooling, 38 20 20 0 River Water ME-38 Main Steam Piping from 26 19 16 3 Reactor Bldg. to Turbine Gen. ME-39 Main Steam Piping from 25 20 14 6 Reactor Bldg. to Turbine Gen. ME-40 Main Steam Piping from 22 15 13 2 Reactor Bldg. to Turbine Gen. ME-41 M.S. Piping from R.B. 21 12 9 3 i to Turbine Generators

TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 3 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign PE-42 M.S. Piping from 23 1 0 1 Stm. Gen. A to Emerg. Feedwater ME-43 M.S. from Stm. I 1 1 0 Gan. A to Header ME-44 M.S. from Steam Gen. 10 10 5 5 B to Header at 297'-0" ME-45 R.B. Spray Pump See ME-20 Suction (for both Pumps) ME-46 R.B. Spray Pump Disch. See ME-32 (Pump B) ME-47 Condensate from 7 0 0 0 Storage Tank "A" to Emergency Feedwater Pumps ME-49 Condensate '. 31 26 21 5 Storage TK.. to EFW Pumps (Inside Struc.) ME-51 12" D.C. Piping from 7 5 1 4 Secondary Shield Wall to 36" R.C. Pipe ME-52 River Water from 19 11 10 1 Emerg. Cooling Coils ME-53 River Water from 24 19 15 4 Emerg. Cooling Coils ME-56 D.H. Clo ed Cycle 23 14 9 5 Cooling Water from Cooler DHE-1A ME-57 D.H. from Cooler 22 0 0 0 DCH-1B to Cooler DCH-2B

TDR-TMI-194 APPENDIX IIIB i RESULTS OF SUPPORT EVALUATIONS Page 4 of 15 l Results of Evaluation Supports Supports Reviewed Supports Analysis ' Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Rj esign ME D.H. Closed Cycle See 11E-56 Cooling Wtr. frem Pump DH-RIA to Cooler DH-CIA ME-59 D.H. from Pump DH-1B See ME-57 to Cooler DH-CIB ME-60 D.H. Removal 24" 8 5 1 4 Borated Water Tank Discharge ME-61 D.H. Removal 8" 10 6 3 3 Borated Water Line Inlet Line ME-62 E.F. Ptunp "A" Disch. 13 7 7 0 to Hesder ME-63 E.F. Pump "B" Disch. 6 4 3 1 to Header ME-64 Turbine Drive Emerg. 11 10 8 2 Fdwtr. hmip Disch. ME-65 E.F. from Header to See ME-62 Reactor Bldg. Wall ME-66 E.F. from Header to-5 1 0 1 R.B. Wall ME-67 E.W. Pump Disch. to 6 2 2 0 Header ME-68 E.W. Pump "A" Suction See ME-49 ME-69 Turbine Driven Emerg. 4 1 1 0 Fdwtr. Pump Suction ME-70 E.F. Water Suction 11 6 5 1 Anchor to Anchor ME-71 Emerg. Fdwtr. Pump B 8 7 7 0 Suction Piping e ME-72A D.H. Cooler DH-CIA See ME-10 3 j Outlet to R.B. j ME-73 D A Coo er DE CIB See ME-10 w

  • e m

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TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 5 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-74 D.H. from Reactor 3 3 1 2 (Between Shield Wall & R.B.) ME-75 R.B. Spray Piping 12 0 0 0 Spray Ring #1 ME-76 R.B. Spray Piping 15 0 0 0 Spray Ring #2 PE-77 R.B. Spray Piping 18 0 0 0 Spray Ring #3 ME-78 R.B. Spray Piping ' 22 0 0 0 Spray Ring #4 ME-79 R.B. Spray Piping 23 0 0 0 Spray Ring #5 NE-80 R.B. Spray Piping 23 0 0 0 Spray Ring #6 NE-81 R.B. Spray Piping 30 0 0 0 Spray Ring #7 MI-82 R.B. Spray Piping 33 0 0 0 Spray Ring #8 PE-83 R.B. Spray Piping 33 0 0 0 Spray Ring #9 ME-84 R.B. Spray Water Piping 19 8 6 2 from Pen. #308 to Header D at El. 417'-6" NE-85 R.B. Spray Wtr. Piping 13 3 3 0 from Pen. #301 to Header at El. 417'-6" ME-86 Decay Heat Closed 13 9 2 7 Service Cooling Wtr. from Cooler DC-C2A to Pump DC-P1A 4 ME-87 D.H. Closed Service 14 12 4 8 Cooling Wtr. T ,m Cooler DC-C2B to Pump DC-P1A

TDR-TMI-194 APPENDIX IIIB RESJLTS OF SUPPORT EVALUATIONS Page 6 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Titla Review Evaluated to Date Supports Redesign ME-88 Pressure Relief Valve Evaluation Not Started to Shield Wall ME-89 6" Pressure Relief 40 20 17 3 from Secondary Shield Wall to Drain Tank ME-91 6" Pressure Relief See ME-89 from Wall to Drain Tank ME-92 Pressure Relief to 10 0 0 0 Shield Wall ME-93 4" Pressure Relief See ME-89 Line from Shield Wall to Drain Tank ME-94 N.S. Cooling from HT 24 0 0 0 Exchangers to Pump l ME-95 N.S. Cooling Water 18" 46 27 20 7 Supply to Heat l Exchangers ME-96 D.H. Removal Borated See ME-1A Tank Discharge l ME-97 2-1/2" High Pressure 13 9 6 3 Injection Piping f:om Pen. #321 to B&W Conn.

  1. 17 ME-101 Incore Monitoring 8

3 2 1 System Piping ME-102 Incore Monitoring 5 4 4 0 System Piping ME-103 2-1/2" High Pressure 26 23 19 4 Injection Piping from Pen. #322 to B&W Conn. #15 ME-110 React. Bldg. Emerg. 18 9 8 1 Cooling Wtr. Return from Air Handling Unit AH-E-11A to Pen. #407

TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 7 of 15 Results of Evaluation Supports Supports Reviewed Supports j Analysis Requiring or Reviewed and Acceptable' Requiring Number Title Review Evaluated to Date Supports Redesign ME-111 R.B. Cooling Water 16 7 6 1 from Pen. #410 to AH-E-1A ME-112 React. Bldg. Emerg 16 11 8 3 Cooling Wtr. Return from Air Handling Unit AH-E-1C to Pen. #409 ME-113 R.B. Cooling Water 13 3 3 0 from Pen #412 to AH-E-1C ME-114 React. Bldg. Emerg. 16 11 9 2 Cooling Water Return from Air Handling Unit A11-E-1B to Pen. #408 ME-115 React. Bldg. Emerg. 16 11 10 1 Cooling Wtr. Supply from Pen. #411 to Air Handling Unit AH-3-1B ME-116 N.S. Cooling Water Pump 70 46 28 18 Disch. to Anchors ME-117 N.S. Cooling Water See ME-116 heturn from Spent Fuel Coolers "A" & "B" to Anchor Points ME-118 2-1/2" High Pressure 18 16 16 0 Injection Piping from Pen. #338 to B&W Conn.

  1. 19 ME-119 S.F. Cooling from 34 10 9

1 Anchor SFH-116 to l D.H. Piping ME-120 S.F. Cooling Piping 20 1 1 0 from Base Supp. 5HF-117 to Retain Ring in Wall

TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 8 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-121 S.F. Cooling from Evaluation Not Started Anchor to Borated Water Storage Tank ME-122 Spent Fuel Cooling 8 3 1 2 from SFH-31 to 8" B&W Conn. on Decay Heat Removal Piping ME-123 Decay Heat Removal See ME-32 Piping from Seal Plate in Wall to Conn. on 8" Fuel Piping ME-124 S.F. Cooling Wtr. 26 17 13 4 Piping to Borated Wtr. Recire. Pump & S.F. Pumps SF-P-1A & SF-P-1B ME-125 S.F. Cooling Water 34 10 10 0 Piping from Coolers SF-C-1A & SF-C-1B ME-126 Spent Fuel Cooling 2 1 0 1 Water Piping to Spent Fuel Water Pool SF-T-2A ME-127 Spent Fuel Cooling 2 1 0 1 Water Piping to Spent Fuel Water Pool SF-T-2B ME-128 S.F. Cooling Piping 7 4 0 4 from Pen. #304 Fuel Canal ME-129 Spent Fuel Cooling 5 3 2 1 Piping from Spent Fuel Pumps SF-P-1A to coolers SF-C-1A l i

TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 9 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-130 Spent Fuel Cooling 2 0 0 0 from Spent Fuel Pumps SF-P-1B to Cooling SF-C-1B ME-131 Nuclear Services 21 15 12 3 Cooling Water from Spent Fuel Coolers "A" l & "B" Anchors ME-132 S.F. Cooling from S.F. 19 14 9 5 Pools SFT-2A & 2B 1 ME-133 Nuclear Services 13 13 11 2 Cooling Water from Storage Tank to Pump Suction ME-134 Spent Fuel Cooling 9 5 4 1 i from Pen. #340 to ] SFH-37 ME-135 S.F. Cooling from 14 4 2 2 SF-T-2A ME-136 S.F. Cooling from 5 3 1 2 SF-T-23 ME-137 S.F. Cooling from 20 7 4 3 Borated Water Recire. Pump ME-138 Fdwtr. from 30" 5 4 0 4 Header to Recire. Pump ME-139 F.W. from 30" Header 4 0 0 0 to Pen. #227 ME-140 Nuclear Services 9 5 5 0 Cooling Water from React. Coolant Waste Gas Equip. PE-141 N.S. Cooling Water from 9 7 7 0 NSH-100 to R.C. Waste Gas Evap. "B"

TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 10 of 15 i Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign 1 ME-142 Nuclear Services See ME-140 Cooling Water from React. Coolant Waste Gas Evap. "A" ME-143 N.S. Cooling Water See ME-141 from Anchor to R.C. Waste Evap. "A" ME-144 N.S. Cooling Water to 13 5 5 0 Air Condensers ME-145 N.S. Cooling Water Evaluation Not Star'.ad from AH-C-4A & 4B ME-146 MU & Purification to 39 29 25 4 MU Pumps MU-P-1A, IB & IC ME-147 Pressurizer to South 2 0 0 0 Relief Valve ME-148 Pressurizer to North No Supports Relief Valve NE-155 N.S. Cooling Water 28 1 0 1 Return from AH-E-24A to Assumed Anchor Point NE-156 N.S. Cooling Water 29 1 1 0 Supply to AH-E-24A & 24B ME-157 20" Decay Heat River 2 2 2 0 Water Disch. from Pump DR-PIB ME-158 R.B. Emerg. Cooling 4 3 0 3 Water Pump Disch. from RR-PIA ME-159 Nuclear Services 8 8 8 0 Cooling Inside Pump House ME-160 Pressurizer Auxiliary 41 11 0 11 Spray s -+ m<

l TDR-TMI-194 l APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 11 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-161 20" Decay Heat River 2 2 2 0 Water Disch. from Pump DR-PIA ME-162 Electromatic Relief to 6 2 2 0 l Secondary Shield Wall ME-163 MU from 2-1/2" B&W 18 0 0 0 Conn. to Letdown Coolers ME-164 From Letdown Coolers. 21 19 15 4 to R.B. Wall Pen. #309 l ME-165 12" Bypass fro D.H. See ME-56 Cooler DH-CIA ME-166 12" Bypass for D / SEE ME-57 Heat Cooler DH-CIB ME-167 Disch. from MU Pumps Evaluation Not Started MU-PIA, PIB & PIC ME-168 4" Make-up Pump Suction 3 1 0 1 from Decay Heat Removal Cooler DH-CIA i ME-169 4" MU Pump Suction See ME-146 from D.H. Removal Cooler DH-CIA l ME-170 Make-up Tank MU-T1 to See ME-146 j Maie-up Suction Header ME-171 6" R.B. Spray Text Line See ME-32 to Borated Water l Recire. Pump ME-172 Pen #354 to R.B. Spray Evaluation Not Started Pump Suction ME-173 Pen. #352 to R.B. Spray Evaluation Not Started Pump ME-174 Sodium Hydroxide to See ME-119 Anchors

TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 12 of.15 t Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-175 4" Sodium Thiosulphate 14 13 11 2 Tank BS-T1 Disch. to React. Bldg. ME-176 10" Connection Piping See ME-20 Bldg. Spray Pumps PIA-PIB ME-179 N.S. Cooling Water from 43 24 16 8 RC-P-1C & ME-218 to ME-204 ME-183 Outlet to React. I 1 0 1 Coolant Pump Seal Return Cooler ME-185 ME-141 to Distillate See ME-141 Cooler B ME-186 Distillate Cooler "B" See ME-140 to ME-140 ME-187 ME-143 to Distillate See ME-116 Cooler A ME-188 Distillate Cooler "A" See ME-95 to ME-142 ME-189 Disch. from Makeup & 53 0 0 0 Purif. Pump to ME-131 ME-190 ME-16 to MU Purif. 37 21 19 2 Pump Suction ME-195 N.S. Closed Cycle 10 10 6 4 Cooling Water Outlet of A.H. Units AH-E-15A & 15B to ME-95 ME-196 ME-144 to Inlets of See ME-144 Sample Coolers ME-198 Outlet of Sample See ME-145 Coolers to ME-197 ME-199 Fan Motor Coolers to See ME-155 ME-155 & 131

m-TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 13 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-200 ME-166 to Fan Motor See ME-156 Cooler Inlets ME-201 ME-53 to ME-70 See HE-049 ME-204 8" Line from Pen. #347 53 40 19 21 to RCP-1A, IB, 1C & 1D ME-205 RC-P-1D to Pen #346 25 12 4 8 ME-206 From Condensate Tank F. valuation Not Started "B" ME-209 Make-up Water & Purif. See ME-167 Disch. Pipe to Disch. Header ME-210 ME-167 to Pen. #321 & Evaluation Not Statted

  1. 322 ME-211 Make-up Pump Disch.

Evaluation Not Started Header to Pen. #338 ME-212 Make-up Pump Disch. See ME-211 Header to Pen. #339 ME-213 Cooling Water from 20 9 8 1 ME-205 to RC-P-1C & ME-214 I ME-214 N.S. Cooling Water 25 22 11 11 ME-213 to RC-P-1A & ME-215 ME-215 N.S. Cooling Water 25 21 13 8 ME-214 to RC-P-1B ME-216 Decay Heat See ME-36 & 37 ME-217 Decay Heat See ME-36 & 37 ME-218 Cooling Water from 49 39 26 13 RC-P-1A & ME-214 to ME-179 ME-219 Cooling Water from 39 26 16 10 RC-P-1B to ME-218 \\ 4

TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS Page 14 of 15 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number -Title Review Evaluated to Date Supports Redesign ME-220 Make-up Water Fill See ME-167 j Line to Make-up Pumps Disch. Header ME-222 Decay Heat Cooling See ME-189 Water from ME-189 to ME-223, ME-131 ME-223 Cooling Water from See ME-189 ME-222 to ME-56 & ME-57 ME-224 Cooling Water ME-116 See ME-190 to ME-59 & ME-59 ME-225 NSCCC-MC-224 to ME-190 See ME-190 ME-226 R.B. Spray Pump Suction Evaluation Not Started Tank to Anchor ME-227 DIICCC-3" Line React. 10 7 7 0 Bldg. Spray Purap to 16" Line from DER Cooler (DH-CIB) ME-230 Main Steam Pump Line See ME-42 to Intermediate Bldg. Wall ME-234 E.F. from Emerg. 7 0 0 1 0 Feedwater Pump Turbine to Exhaust Stack ME-250 Chilled Water Evaluation Not Started ME-251 Chilled Water Pump Evaluation Not Started (AH-P-3A & AH-P-3B) Suction ME-252 Chilled Water Evaluation Not Started i t e e -n -s,,. .--,,n m .y

TDR-TMI-194 APPENDIX IIIB Restults of Evaluation Pags 15 of 15 (Cont'd.) For Seismic Spacing Criteria Results of Evaluation Supports Reviewed or Supports Reviewed and Supports Requiring Evaluated Acceptable Requiring Supports System Review To Date Supports Redesign Added Liquid Waste Disposal 61 26 9 17 5 Monitoring Post Accident Purge 4 Leak Race 12 Instrument Air 41 Decay Heat Removal 8 Main Steam 2 Make-up and Purification 'ncluding ME 9, 98A) 101 5 5 2 Nuclear Services Closed Cycle Cooling (including ME-191, 99, 203,100,106,107,108,109) 106 5 3 1 5 Reactor Bldg. Spray 8 River Water 32 Spent Fuel 13 5 1 4 5 Chilled Water 12 Decay Heat Closed Cycle Cooling 42 1 Condensate 7 Intemediate Cooling (comprised soley of ME-54, 149,150,151,154,181,182) 13 (_-

l ~( ', TDR-TMI-194 s APPENDIX IV l SYSTEM INSPECTION BOUNDARIES TABLE OF CONTENTS Sheet System 1 Main Steam (Auxiliary Steam) 2 Feedwater (Emergency seedwater) 3 Nuclear Services Closed Cycle Cooling Water 4 Decay Heat Closed Cycle Cooling Water 5 Make-up and Purification 6 Make-up and Purification 7 Spent Fuel Cooling System 8 Liquid Waste Disposal 9 Condensate 10 Reactor Coolant ( 11 Containment Vessel Leak Rate Test 12 Core Flooding 13 Decay Heat Removal 14 Building Spray 15 River Water 16 Hydrogen Purge Disch and Containment Monitoring 17 Chilled Water 18 Instrument Air 19 Intermediate Cooling Legend $tRRRRRRRRRRRRF Seismic spacing Criteria 31515151E Computer analyzed C .-e-

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( 1 TDR-TMI-194 APPENDIX V INACCESSIBLE INSPECTION ELEMENTS VISUAL INSPECTIONS \\ ~ \\

TDR-TMI-194 APPENDIX V Page 1 of 2 INACCESSIBLE ELEMENTS OF INSPECTION (, VISUAL INSPECTIONS INACCESSIBLE - The following elements were inaccessible to inspection. SYSTEM AND INSPECTION ELEMENT ME NO. BURDEN OF INSPECTION SYSTEM CONSEQUENCES SPENT FUEL COOLING SFH-166 137 Und.scwater-Spent Based upon support Fuel Pit location and type, and upon the function of the associated piping, no adverse safety consequences are indicated SFH-167 135 Underwater-Spent Based upon support Fuel Pit location and type, and upon the function of the associated piping, no adverse safety consequences are indicated q SFH-168 135 Underwater-Spent Based upon support Fuel Pit location and type, and upon the function of the associated piping, no adverse safety consequences are indicated MAKEUP AND PURIFICATION MUH-175 SSC High Radiation Area

1. Piping is in low MUH-176 SSC High Radiation Area pressure (< 150 MUH-177 SSC High Radiacion Area psig) and low MUH-178 SSC High Radiation Area temperature MUH-179 SSC High Radiation Area

(< 200 F) portion MUH-180 SSC High Radiation Area of the make-up and purification system. ft e g y

o TDR-TMI-194 APPENDIX V Page 2 of 2 ( SYSTEM AND INSPECTION ELEMENT ME NO. BURDEN OF INSPECTION SYSTEM CONSEQUENCES

2. The piping in each cubicle has a re-dundant flow path in the piping througb the other demineralizer and the bypass around the both deminer-alizers with iso-lation capabilities for both demineralizers.
3. The plant can safely be shut down without the use of the letdown portion of the make-up and purification system.

VISUAL INSPECTION - :Se following elements were visually inspected due to reasons lis ed. The visual inspection did indicate existance, integcity, configuration and location of the elements. ( SYSTEM AND INSPECTION ELEMENT ME NO. BURDEN OF INSPECTION REACTOR COOLANT RC-3 160 Obstructed by shielding RC-6 160 Obstructed by shielding CHILLED WATER CHE-12 250 Space limitations CHE-16 250 Space limitations eqr CHE-58 251 Space limitations MAKEUP PURIFICATION MUH-79 6 Space limitations SPENT FUEL COOLING SFH-149 121 Space limitations us .}}