Text

Rev 3 to Final Rept to NRC for IE Bulletin 79-14 Requirements at TMI-1
	ML20064F508
Person / Time
Site:	Crane
Issue date:	11/17/1982
From:	; GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT
To:	;
Shared Package
ML20064F501	List: ML20064F497; ML20064F503; ML20064F508;
References
	REF-SSINS-6820 IEB-79-14, TDR-TMI-194, TDR-TMI-194-R03, TDR-TMI-194-R3, NUDOCS 8301060393
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{{#Wiki_filter:e USNRC IE BULIITIN NO. 79-14 FINAL REPORT REVISION 3 NOVEMBER 17, 1982 Prepared for GPU Nuclear Three Mile Island Nuclear Station Unit 1 l t Prepared by Gilbert Associates, Inc. 1 roo1060393821:;ilo PDR ADOCK 0500(3289 G v2DR A

T"" REVISION NO. 3 hWke 110lX I 17 TECHNICAL DATA REPORT PROJECT NO. PAGE OF _ PROJECT: TMI Unit #1 Restart NM-35 DEPARTMENT /SECTION RELEASE DATE 9-30-80 REVISION DATE 11-17-32 DOCUMENT TITLE: Final Report to USNRC for IE Bulletin 79-14 Requirements at TMI Unit #1 ORIGINATOR SIGNATURE DATE APPROVAL (S) SIGNATURE, DATE Gilbert _ Associates, Inc. 9-30-80 A d-Ms 4 50 #0 dyin;;; (a>EW~*g J 1 U Vn APPROVkL FOR)EXTkPNAL DISTRIBUTION DATE h, M, \\\\( m h w g DISTRIBUTION ABSTRACT: Statement C_ !. _..,,-1 d D.K. Croneberger This report is the response by GPU Nuclear to the J.K. Culati Reporting Requirements of the USNRC IE Bulletin 79-14, N.C. Kazanas including all revisions and supplements, for TMI Unit #1 A.P. Rochino (Docket No. 50-289). 9.G. Slear E.G. Wallace Summary 3. Saxon 3. Nelson The report explains the inspection procedure implemented to J.J. Colitz verify that installed safety related Seismic Category I Piping R. Barley Systems and Pipe Supports meet the design intent. It details I R. Toole any nonconformances found and defines what actions were l

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Smyth taken to correct or accept these nonconformances (i.e., 1.F. Wilson support redesign, piping reanalysis). I. Delockery \\. Makitka 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 i The report also details methods for current and future maintenance of as-built documents,

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WICO 194 TITLE Final Report to USNRC for IE Bulletin 79-14 PAGE 1 OF Requirements at THI Unit #1 REV

SUMMARY

OF CHANGE APPROVAL DATE 1 General revision to Report Body as indicated d d, 346-81 (pgs. 3, 10, 11, 12, 14, 15) General revision to Appendix I 2 d updated Appendix IIIA updated Appendix IIIB updated Appendix IV g updated Appendix V 2 General revision to Report Body as indicated /b, 8-31-81 (pg. 14) update Appendix TTTA ,f 9/ update Appendix IIIB, added page 19 N'y w 3 General update to report body as indicated (pg.2,3and 14) Update Appendix IIIA '[- Update Appendix IIIB g /4 Update Appendix V / i Quh /J ' M

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TDR-TMI-194 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 8 3.1 Nonconformance Evaluation - Piping Analyses 8 3.2 Reasons for Reanalysis 8 3.3 Pipe Support Evaluation 11 4.0 Results 12 4.1 Pipe Support Redesign 12 5.0 Conclusions 14 6.0 Recommendations 15 6.1 Document Control 15 7.0 References 16 7.1 Computer Programs 16 7.2 References for Analysis Input 17 Appendix I Systems Inspected and Applicable Drawings Appendix II Inspection Procedure 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 i l l l l

TDR-TMI-194 Page 2 1.0 PURPOSE AND

SUMMARY

This is the final report of GPU Nuclear in response to USNRC IE Bulletin 3 No. 79-14, dated July 2, 1979, including Revision 1 dated July 18, 1979, Supplement I dated August 15, 1979, and Supplement 2 dated September 7, 1979 for Three Mile Island Nuclear Station, Unit 1, Docket No. 50-289. The purpose of this report is to describe the results of piping system reanalysis and the esolution 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 de not meet design requirements were redesigned and construction modifications 3 made as required. 4 i -,-n

TDR-TMI-194 Page 3 2.0 NETHODS 2.1 SCOPE OF INSPECTION The following is a list of safety-related Seismic Category I piping systems 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 the corresponding system prefixes. FLOW DIAGRAM SHEET NO. (SEE APPENDIX IV) SYSTEM PREFIX SYSTEM TITLE I MS Main Steam 1 AS Auxiliary Steam i 2 FW Feed Water 2 EF Emergency Feed Water 3 NS Nuclear Services Closed Cycle Cooling 4 DC Decay Heat Closed Cycle Cooling 5&6 MU Make-up and Purification 7 SF Spent Fuel Cooling 3 8 WD Waste Disposal - Liquid 9 CO Condensate 10 RC Reactor Coolant 11 LR Leak Rate Test 12 CF Core Flooding 13 DH Decay Heat Removal 14 BS Reactor Building Spray 17 CH Control Building, Chilled Water 18 IA Instrument Air None None Incore Monitoring 19 IC Intermediate Cooling 15 DR Decay Hest Removal - River Water 15 NR Nuclear Services Cooling - River Water 15 RR Reactor Building Emergene Cooling - River Water 15 SW Screen Wash & Sluice 16 CM Containment Monitoring j

TDR-TMI-194 Page 4 The flow diagrams included in Appendix IV identify by analysis identification number, (NF.-No.), those portions of safety-related Seismic Category I systems which were inspected. Information from the original flow diagram has been eliminated to provide ciarity. 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 isometrics, piping layout 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 checkiag 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 luspecLion Tolerances 2.2.2.1 Pipe support locations were inspected relative to tolerances related to pipe diameter. Refer to Appendix II. If tolerances 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 operators 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 inspected 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: i Type (e.g., rigid rod, spring, U-bolt) Quantity and size of pipe attachments Size of spring cans Bore and stroke on hydraulic snubbers Weld size, length and type Hex nut engagement Assembly component size and quantity t 2.2.3.2 Clearances were recorded at four 90' locations for wall penetrations, and pipe box restraints. This information was used to evaluate any possible adverse effects on thermal or seismic displacements. i l l

.S~ TDR-7NI-194 Page 6 2.2.3.3 Material size and shape subsLiLutions 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. 2.3.1 Methods of 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: Piping Analysis Isometric Drawings a. 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 i These are drawings of pipe supports, hangers and seismic l l restraints which show the type, location and configuration l necessary to satisfy analytical requirements. l l l Additional reference documents used are listed in Section 7.0 and include physical piping arrangement drawings, flow diagrams and vendor i drawings. The inspectors worked in teams and divided the piping systems into work packages including an analysis isometric and related support assembly drawings. Nonconformances determined by comparison of I l .c.. r 7.

TDR-TMI-194 Peg 2 7 the physical installation with the inspection package information was recorded on inspection data sheets. Samples of the data sheets are included with Appendix II. In those cases where thermal insulation prevented the inspecLion 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, on the balance of the obstructed pipe supports, that portion of the support 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 w-re 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 to each inspection report by the inspectors. For supports, the support number was used and for piping systems, the ME number was used. Piping nonconformances were reported l 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 engineering for evaluation. l l l

TDR-TMI-194 Pcgs 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 to 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 a 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 Changes of Valve or Support Location Valve or support as-built location different from design intent. Inspection tolerances not met.

TDR-TMI-194 Pega 9 Code Nonconfo rmances 2 Orientation of Valve or Support Valve operator or support mcaber 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 Missing 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 Pcgs 10 9 Seismic input 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. 3.2.2 Additional Considerations for Reanalysis The following is a list of additional factors which were considered in the reanalysis process: Code Factor 10 Seismic Spacing Criteria Reanalysis to consider effects of piping, supported by seismic spacing criteria, integrally attached to formally analyzed portions of pipe. 11 Generic Anchors Piping reanalyzed to obtain refined load combinations required to perform USNRC IE bulletin 79-02 evaluation of anchors. 12 Support Loading Some analyses were rerun using a 1980 State of the Art Computer Program, PIPDYN II, 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.

TDR-TMI-194 Pega 11 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 analysis; 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 support evaluation was performed for the following reasons: Nonconformances discovered as a result of field inspections and/or a. engineering review. b. Piping reanalysis indicated reaction forces higher than original analysis. The objective of the evaluation was to determine whether or not a support met design requirements. Seismic Category I pipe supports were evaluated by 1 engineering using the original design criteria. When a support was not acceptable as installed, it was designated for redesign. Appendix IIIB tabulates by ME-Nos., the results of pipe support evaluations. This Appendix includes supports from formally analyzed lines and seismic spacing criteria supported lines. i . ~ _ _

TDR-TMI-194 Page 12 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 information compiled on the supports including field inspection reports, load sheets, support drawings, and evaluation calculations. The Support Package cover sheet indicates the components which failed to meet design requirements. A design 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 are consulted through a formal field request procedure. Engineering then finalizes the design 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: Add additional structural bracing to an existing support a. b. Change an existing tension rod support to a sway strut 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 Item Report (MIR) would be implemented rather than an ECM. Examples of items placed on an MIR are as follows: i

TDR-TM1-194 Pcga 13 a. Adjusting the tension rod hangers b. Reset spring cans c. Set snubber stroke length. 1 1 l i t f l-

e TDR-TMI-194 Pega 14

5.0 CONCLUSION

S The verification of safety related piping system seismic analysis is 4.ccomplished in the following four parts, as previously discussed: a. Site Inspection b. Seismic Reanalysis c. Support Evaluation d. Support Redesign The following provides a summary of the results of each of the four parts: 3 a. Site Inspections Site inspection functions are complete. Of the 24 systems, approximately 2752 Seismic Category I supports and 54 Seismic 3 Category III supports were inspected. b. Piping Reanalysis The PIR's received from the field were evaluated to determine whether formal reanalysis was required. This resulted in 150 computer 3 reanalyses and 53 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 Supports were reviewed to determine if support evaluation was required as described in Section 3.3. The number supports reviewed and those also evaluated after review total 2762. The disposition of these indicate 2044 supports acceptable and 718 supports needing redesign. 3 An additional 145 new supports are required as a result of reanalysis findings. d. Support Redesign A total of 659 supports have been redesigned and modified prior to 3 plant restart. 3

TDR-TMI-194 Page 15 6.0 RECOMMENDATIONS 6.1 Document Control i 1 This section describes the control procedures that have been implemented to reflect the "as-built" condition. Interim drawings are prepared to depict a proposed support modification or addition as required. Once approved, these drawings are issued to construction for installation by an Engineering Change Memorandum (ECM). The ECM provides specific details referenced in specifications and construction procedures. The construction is initiated by release of a Work Authorization Notice (WAN). Construction problems are submitted to Engineering by a Field Questionnaire (FQ). After resolution of FQ's and completion of the repair, the pipe support modification / addition is inspected by QC for conformance with the drawings. Any discrepancies between the installation and the drawing requirements are documented on an Incomplete Work List (IWL) and distributed to the responsible parties for resolution. The IWL items are reviewed for resolution and returned for correction in accordance with the drawing. Corrective action is initiated by the WAN. After the IWL items are resolved, a copy of the ECM Interim Drawing is marked and stamped "as installed", then submitted to engineering by a Design Change Notice (DCN). The "as installed" drawings are filed with the "as-built" records. i I l ~

TDR-TMI-194 Page 16

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 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. PRY This program is used for flexible base plate analyses for prying action on non-preloaded concrete expansion anchors. t

TUH-TMi-194 Pag 2 17 7,2 References For Analysis Input DOCUMENT ANALYSIS INPUT a. Pipe Specification for Plant Piping acterials, fittings, and Piping (SP-5544) wall thickness, design pressures and temperatures. b. Building Seismic Response Building seismic response spectra Cu rves by elevation and building seismic movements c. Insulation Specification Insulation types and thicknesses - SP-5546 used to determine weights of piping d. Manufaturer's Valve Drawings Valve weights, e.g.'s and lengths e. Piping Isometrics Pipe routings, fittings in a format (Refer to Appendix I) for use with computer analyses. Derived from physical drawings) f. Physical Pipe Drawings Pipe routings, fittings, valve (Refer to Appendix I) locations g. Flow Diagrams Line specifications, operating (Refer to Appendix I) temperatures h. Pipe Support Drawings See Note 1 1. USAS B31.1, 1967 Design criteria j. TMI-I FSAR Scope of Seismic I Piping NOTE 1: The pipe supports were designed using load 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 analysis.

9 e 4 e TDR-TMI-194 APPENDIX I SYSTDIS INSPECTED AND APPLICABLE DRAWINGS t l i f

TDR-TMI-194 APPENDIX I Page 1 of 13 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS ME ISONETRIC REV PIPING REV FLOW DIACRAM REV l Condensate 47 D-312-625 1 E-304-102 14 C-302-101 18 (Supply to E-304-104 10 Emergency Feedwater) MK-No's 49 D-312-697 1 E-304-102 14 C-302-101 18 CO-206 C-312-726 0 E-304-101 17 C-302-101 18 E-304-102 14 Core Flooding 34 C-312-551 2 E-304-641 20 C-302-640 24 E-304-642 28 E-304-711 13 C-302-711 12 MK-No'n 35 B-312-550 4 E-304-641 20 C-302-640 24 CF-E-304-711 13 C-302-711 12 Decay Heat 1A 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 E-304-641 20 C-302-640 24 DH-E-304-642 28 4A B-312-568 2 E-304-641 20 C-302-640 24 E-304-642 28 5 B-312-599 0 E-304-641 20 C-302-640 24 E-304-642 28 10 C-312-711 2 E-304-641 20 C-302-640 24 E-304-642 28 34 C-312-551 2 E-304-641 20 C-302-640 24 E-304-642 28 C-302-711 12 E-304-711 13 35 B-312-550 4 E-304-641 20 C-302-640 24 E-304-711 13 C-302-711 12 51 SS-312-640 1 E-304-641 20 C-302-640 24 E-304-642 28 60 B-312-652 2 E-304-641 20 C-302-640 24 E-304-642 28

1 s s. sX. T '/ \\ \\ ~, N \\ TDR 'IMI-194* APPENDIX I Page 2 of 15 a' REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) y ME ISOMETRIC

REV PIPING REV FLOW DIAGRAM REV Decay Heat 61 B-312-653 1

E-304-641 20 C-302-640 24 Removal \\ E-304-642 2d (Cont'd) 72A SS-312-588 2 E-304-641 20

C-302-640 E-304-642 28 73 SS-312-589 2

E-304-641 20 C-302-640 24 Ea304-642 28 ,, n 74 SS-312-564 2 E-304-641 20 C-302-640 _ 2d > E-304-642 28 96 C-312-654 2 E-304-641 20 C-302-640 24 's E-304-642 -28 x s s 120 C-312-684 1 E-304-b31 s2), ' c-302-630 11 cw E-304-C32. 17 121 B-312-6 5 '1xE-3046k1 21 C-30i630, 11 E-304-632 -J7 N 3 E ' 04-641 ,20 C-302-b40 24 5 123 SS-312-687 1 s

E-304-642'

. 28 s' \\ 146 C-3I2-692 - 1. - 'E-304-641 20 E-304-642 28 G302-640 24 E-304-661 15 C-302-645

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]17 E-304-662, 15 C-302-660 t E-304-664 18 C 302-C62 19 s 168 B-312-723 2['E-304'641 ,20 'C-302-RJ.f[s~ 24 1 3 174 C-312-744 0 E-304-625 ' 9 N C-302-610 - 25 + s s\\,3 m s l E-304-642 28 ~C-302e712 _ 15 g s s E-30'-646, l' C-302-645 13 l 222 C-312-758 0 4 l s 223 C-312-761 0. E-304-646s, 11 C-301-645 13 s N Spacing C-302-645 13 ( Criteria 1 ) x, 's 3 ~ 6 es s e b ,A f

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\\ ',: TDR-TMI-194 APPENDIX 1 Page 3 of 15 REVISION 1 SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV -i Decay Reat 56 C-312-648 1 E-304-644 15 C-302-645 13 3 Close)d' Cycle E-$C4-645 15 Cooling 57 C-312-649 1 E-304-644 15 C-302-645 13 HK-No's E-304-645 15 DC-58 SS-312-650 1 E-304-644 15 C-302-645 13 E-304-645 15 59 SS-312-651 1 E-304-644 15 C-302-645 13 E-304-645 15 86 C-312-647 1 E-304-644 15 - C-302-645 13 E-304-645 15 87 C-312-646 1 E-304-644 15 C-302-645 13 E-304-645 15 165 B-312-712 0 E-304-644 15 C-302-645 13 E-304-645 15 v 166 B-312-713 0 E-304-644 15 C-302-645 13 E-304-645 15 189 B-312-755 0 E-304-646 1 C-302-610 25 ( t s i C-302-645 13 J 190 B-312-748 0 E-304-646 1 C-302-645 13 'A 222 C-312-758 0 E-304-646 1 C-302-645 13 223 C-312-761 0 E-304-646 1 C-302-645 13 224 B-312-759 0 E-304-646 1 C-302-645 13 7 r 225 B-312-759 0 E-304-645 15 C-302-645 13 E-304-646 1 Spacing E-304-646 1 C-302-645 13 Criteria i-1 r s. k 4 i a s -,-.,___,.[_[., . =

TUR-TM1-194 APPENDIX I Page 4 of 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Feedwater 29 B-312-507 5 E-304-081 11 C-302-081 17 (Isolation 30 B-312-506 4 E-304-081 11 C-302-081 17 Portion) E-304-085 7 MK-No's 138 B-312-672 2 E-304-081 11 C-302-081 17 FW-E-304-085 7 139A B-312-673 3 E-304-081 11 C-302-081 17 E-304-085 7 Instrument Air Spacing E-304-271 11 C-302-271 18 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 E-304-773 8 E-304-774 3 E-504-776 3 E-304-7/5 5 Monitoring Post Spacing D-304-716 3 C-302-721 3 i Acc Purge Criteria (Sampling Portion) MK-No's MPA-l Leak Rate , Spacing E-304-244 0 C-302-725 5 MK-No's Criteria E-304-725 7 LR-

TDR-TM1-194 APPENDIX I l Page 5 cf 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIACRAM REV l Main Steam 24 B-312-503 5 E-304-012 14 C-302-011 22 (Supply to Emerg. 25 B-312-503 5 E-304-012 14 C-302-011 22 Feed Water Pump 26 B-312-502 5 E-304-012 14 C-302-011 22 Turbine, Contain-27 B-312-502 5 E-304-012 14 C-302-011 22 ment Isolation) E-304-011 11 MK-No's 38 C-312-771 1 E-304-012 14 C-302-011 22 MS-E-304-013 15 VE-39 C-312-772 1 E-304-012 14 C-302-011 22 E-304-013 15 40 C-312-773 1 E-304-012 14 C-302-011 22 E-304-013 15 41 C-312-774 1 E-304-012 14 C-302-011 22 E-304-013 15 42 B-312-581 4 E-304-012 14 C-302-011 22 E-304-013 15 43 B-312-582 4 E-304-012 14 C-302-0:1 22 E-304-013 15 44 SS-312-590 3 E-304-012 14 C-302-011 22 E-304-013 15 230 C-312-779 1 E-304-012 14 C-302-011 22 E-304-013 15 234 C-302-011 22 l Spacing C-302-011 22 i Criteria l Make-up and 6 C-312-775 1 E-304-661 15 C-302-660 17 { Purification E-304-662 15 C-302-661 19 5-304-663 12 MK-No's 7 C-312-776 1 E-304-662 15 C-302-660 17 MUE-E-304-663 12 C-302-661 19 MUH-E-304-665 9 l

TDR-TMI-194 APPENDIX I Page 6 of 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Make-up and 8 C-312-777 2 E-304-663 12 C-302-660 17 Purification E-304-665 9 C-302-661 19 (Cont'd) 11 C-312-752 1 E-304-661 15 C-302-660 17 E-304-662 15 C-302-661 19 97A B-312-644 3 E-304-661 15 C-302-661 19 E-304-663 12 E-304-664 18 103 D-312-641 3 E-304-661 15 C-302-660 17 E-304-663 12 C-302-661 19 118 C-312-642 1 E-304-663 12 C-302-660 17 C-302-661 19 146 C-312-692 1 E-304-661 15 C-302-660 17 E-304-662 15 C-302-661 19 E-304-664 18 163 C-312-714 0 E-304-661 15 C-302-660 17 C-302-661 19 164 C-312-715 1 E-304-661 15 C-302-660 17 C-302-661 19 167 C-312-718 0 E-304-661 15 C-302-660 17 E-304-662 15 C-302-661 19 168 B-312-723 2 E-304-641 20 C-302-640 24 E-304-642 28 l 169 B-312-724 2 E-304-641 20 C-302-640 24 E-304-642 28 170 B-312-716 0 E-304-661 15 C-302-660 17 E-304-662 15 C-302-661 19 209 B-312-719 0 E-304-661 15 C-302-660 17 E-304-662 15 C-302-661 19 210 C-312-720 1 E-304-661 15 C-302-660 17 E-304-662 15 C-302-661 19 l

TDR-TMI-194 APPENDIX I Page 7 of 15 REVISION I SYSTEMS INSPECTED AND APPLICACLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Make-up and 211 B-312-721 0 E-304-663 12 C-302-660 17 Purification E-304-664 18 C-302-661 19 (Cont'd) 212 B-312-722 0 E-304-663 12 C-302-660 17 E-304-664 18 C-302-661 19 220 B-312-717 0 E-304-661 15 C-302-660 17 E-304-662 15 C-302-661 19 E-304-645 15 C-302-610 25 225 B-312-759 0 E-304-646 1 C-302-645 13 C-302-661 19 Spacing C-302-660 17 Criteria C-302-661 19 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 C-302-610 25 Cooling 94 D-312-632 1 E-304-611 9 C-302-610 25 MK-No's E-304-612 14 NSE-95 D-312-634 1 E-304-611 9 C-302-610 25 NSH-E-304-612 14 MO-99 B-312-666 1 E-304-213 6 C-302-610 25 RB-E-304-214 9 100 B-312-670 0 E-304-213 6 C-302-610 25 i E-304-214 9 106 B-312-667 2 E-304-213 6 C-302-610 25 E-304-214 9 107 B-312-668 1 E-304-213 6 C-302-610 25 l E-304-214 9 l 108A B-312-669 2 E-304-213 6 C-302-610 25 E-304-214 9 109 B-312-671 0 E-304-213 6 C-302-610 25 E-304-214 9 110 C-312-662 1 E-304-213 6 C-302-610 25 E-304-214 9

i TDR-THI-194 APPENDIX I Page 8 of 15 i REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Nuclear Services 111 C-312-663 1 E-304-213 6 C-302-610 25 Closed Cycle E-304-214 9 Cooling (Cont'd) 112 C-312-664 1 E-304-213 6 C-302-610 25 E-304-214 9 113 C-312-665 1 E-304-213 6 C-302-610 25 E-304-214 9 114 C-312-660 1 E-304-611 9 C-302-610 25 E-304-612 14 115 E-312-661 1 E-304-611 9 C-302-610 25 116/117 D-312-655 2 E-304-613 9 C-302-610 25 131 C-312-635 2 E-304-611 9 C-302-610 25 E-304-612 14 E-304-613 9 133 C-312-633 1 E-304-612 14 C-302-610 25 140 B-312-690 1 E-304-611 9 C-302-610 25 141 B-312-691 1 E-304-611 9 C-302-610 25 142 B-312-690 1 E-304-611 9 C-302-610 25 143 D-312-691 1 E-304-611 9 C-302-610 25 144 B-312-693 2 E-304-612 14 C-302-610 25 145 B-312-694 1 E-304-612 14 C-302-610 25 155 C-312-704 1 E-304-613 9 C-302-610 25 156 C-312-705 1 E-304-613 9 C-302-610 25 E-304-611 9 179 D-312-762 1 E-304-614 10 C-302-610 25 i E-304-615 2 183 B-312-737 0 E-304-611 9 C-302-610 25 185 B-312-734 0 E-304-611 9 C-302-610 25 186 B-312-735 0 E-304-611 9 C-302-610 25 l 187 B-312-733 0 E-304-611 9 C-302-610 25 s 188 B-312-738 0 E-304-611 9 C-302-610 25 189 B-312-755 0 E-304-646 1 C-302-610 25 C-302-645 13

TDR-TMI-194 ' APPENDIX I = Page 9 of 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Nuclear Services 190 B-312-748 0 E-304-646 1 C-302-610 25 Closed Cycle C-302-645 13 I Cooling (Cont'd) 195 B-312-742 0 E-304-612 14 C-302-610 25 196 B-312-727 0 E-304-612 14 C-302-610 25 198 B-312-750 0 E-304-612 14 C-302-610 25 199 D-312-741 0 E-304-613 9 C-302-610 25 201 B-312-728 0 E-304-102 13 C-302-081 17 C-302-610 25 204-2 C-312-780 2 E-304-614 10 C-302-610 25 E-304-615 2 204-3 C-312-781 2 E-304-614 10 C-302-610 25 E-304-615 2 204-1 C-312-782 2 E-304-614 10 C-302-610 25 E-304-615 2 205 D-312-731 2 E-304-614 10 C-302-610 25 E-304-615 2 213 C-312-765 0 E-304-614 10 C-302-670 25 E-304-615 2 214 C-312-766 2 E-304-614 10 C-302-610 25 E-304-615 2 215 C-312-767 2 E-304-614 10 C-302-610 25 i E-304-615 2 218 D-312-763 2 E-304-611 9 C-302-610 25 E-304-614 10 E-304-615 2 219 C-312-764 4 E-304-611 9 C-302-610 25 E-304-612 10 E-304-613 2 222 C-312-758 0 E-304-645 15 C-302-610 25 E-304-646 1 C-302-645 13 225 B-312-759 0 E-304-646 1 C-302-610 25 ,a ,,-w +, m

TDR-TMI-194 APPENDIX I Page 10 of 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Nuclear Services 235 E-311-859 C-302-845 14 Closed Cycle 236 E-311-859 C-302-845 14 Cooling (Cont'd) Spacing C-302-645 13 Criteria Reactor Bldg. 20 SS-312-596 1 E-304-712 17 C-302-712 15 Spray 32 B-312-629 0 E-304-712 17 C-302-712 15 MK-No's 45 SS-312-574 2 E-304-712 17 C-302-712 15 l BS-46 B-312-628 1 E-304-712 17 C-302-712 15 SPS-75 C-312-618 1 E-304-713 1 C-302-712 15 SBW-E-304-714 6 76 C-312-620 1 E-304-713 1 C-302-712 15 E-304-714 6 77 C-312-621 1 E-304-713 1 C-302-712 15 E-304-714 6 78 C-312-622 1 2-304-713 1 C-302-712 15 E-304-714 6 79 C-312-623 1 E-304-715 1 C-302-712 15 E-304-714 6 80 C-312-624 2 E-304-713 1 C-302-712 15 E-304-714 6 81 C-312-626 2 E-304-713 1 C-302-712 15 E-304-714 6 82 C-312-627 2 E-304-713 1 C-302-712 15 E-304-714 6 83 C-312-696 1 E-304-713 1 C-302-712 15 E-304-714 6 84 B-312-612 2 E-304-713 2 C-302-712 15 4 E-304-714 6 85 B-312-613 2 E-304-713 2 C-302-712 15 1 E-304-714 6 i

TDH-TMI-194 APPENDIX I Page 11 of 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIACRAM REV Reactor Bldg. 171 C-312-743 1 E-304-712 17 C-302-712 15 Spray (Cont'd) 172 C-312-746 0 E-304-712 17 C-302-712 15 E-304-641 20 C-302-640 24 E-304-642 28 173 C-312-745 0 E-304-712 17 C-302-712 15 E-304-641 20 C-302-640 24 E-304-642 28 174 C-312-744 0 E-304-625 9 C-302-620 19 175 C-312-747 0 E-304-712 17 C-302-712 15 176 C-312-751 0 E-304-712 17 C-302-712 15 226 C-312-768 1 E-304-712 17 C-302-712 15 E-304-625 9 C-302-620 19 227 C-312-769 0 E-304-625 9 C-302-620 19 Spacing C-302-620 19 Criteria C-302-640 24 C-302-712 15 River Water 14 C-302-202 20 MK-No's 28 C-312-600 1 E-303-135 7 C-302-202 20 RW-33 C-312-616 1 E-303-135 7 C-302-202 20 IP-36 D-312-617 2 E-303-135 7 C-302-202 20 RR-37 D-312-619 3 E-303-135 7 C-302-202 20 52 D-312-638 1 E-304-212 5 C-302-202 20 157 SS-312-707 1 E-303-131 15 C-302-202 20 l E-303-132 13 158 SS-312-708 1 E-303-131 15 C-302-202 20 E-303-132 13 159 C-312-706 1 E-303-131 15 C-302-202 20 E-303-132 13 161 SS-312-709 1 E-303-131 15 C-302-202 20 1 E-303-132 13 Spacing C-302-202 20 Criteria 1 l l 1

TDR-TMI-104 APPENDIX I Page 12 of 15 HEVISION 1 SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) NE ISONETRIC REV PIPING REV FLOW DIAGRAM REV Emergency 21 B-312-567 4 E-304-086 14 C-302-081 17 Feedwater 22 C-312-566 4 E-304-086 14 C-302-081 17 MK-No's 47-D-312-625 1 E-303-124 15 C-302-081 17 EF-E-304-102 13 E-304-104 10 49 D-312-697 1 E-304-102 13 C-302-081 17 62 SS-312-584 3 E-304-086 14 C-302-081 17 63 SS-312-583 3 E-304-086 14 C-302-081 17 64 SS-312-585 3 E-304-086 14 C-302-081 17 65 SS-312-586 3 E-304-086 14 C-302-081 17 66 SS-312-587 3 E-304-086 14 C-302-081 17 67 SS-312-531 2 E-304-086 14 C-302-081 17 68 SS-312-592 2 E-304-086 14 C-302-081 17 69 SS-312-594 2 E-304-086 14 C-302-081 17 70 SS-312-595 2 E-304-086 14 C-302-081 17 71 SS-312-593 2 E-304-086 14 C-302-081 17 201 B-312-728 0 E-304-102 13 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 E-304-631 21 C-302-630 11 E-304-632 17 SFH-122 SS-312-678 1 E-304-631 21 C-302-630 11 E-304-632 17 124 C-312-677 1 E-304-631 21 C-302-630 11 i E-304-632 17 125 C-312-631 1 E-304-631 21 C-302-630 11 E-304-032 17 126A B-312-682 2 E-304-631 21 C-302-630 11 E-304-632 17 l 127A B-312-682 2 E-304-631 21 C-302-630 11 E-304-632 17

TDR-TMI-194 APPENDIX I Page 13 of 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Spent Fuel 128 B-312-674 1 E-304-631 21 C-302-630 11 (Cont'd) E-304-632 17 129 B-312-680 1 E-304-631 21 C-302-630 11 E-304-632 17 130 B-312-630 1 E-304-631 21 C-302-630 11 E-304-632 17 152 C-312-679 1 E-304-631 21 C-302-630 11 E-SC4-632 17 134 B-312-675 i E-304-631 21 C-302-630 11 E-304-632 17 135 C-312-686 1 E-304-631 21 C-302-630 11 E-304-632 17 136 B-312-688 1 E-304-631 21 C-302-620 11 E-304-632 17 137 C-312-689 1 E-304-631 21 C-302-630 11 E-304-632 17 Spacing C-302-630 11 Criteria 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 l Reactor 51 SS-312-640 1 E-304-641 20 C-302-650 18 Coolant E-304-642 28 MK-No's 88 B-312-579 3 E-304-653 10 C-302-650 18 RQ-89 SS-312-577 2 E-304-653 10 C-302-650 la 91 SS-312-516 2 E-304-653 10 C-302-650 18 92 SS-312-580 3 E-304-653 10 C-302-650 18 93 B-312-578 2 E-304-653 10 C-302-650 18 l - -~-

TDR-TMI-194 APPENDIX I Page 14 of 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV Reactor 147 SS-312-695 2 E-304-653 10 C-302-650 18 Coolant (Cont'd) 148 B-312-700 2 E-304-653 10 C-302-650 18 160 C-312-710 4 E-304-653 10 C-302-650 18 E-304-709 4 162 B-312-565 4 E-304-653 10 C-302-650 18 163 C-312-714 0 E-304-661 15 C-302-660 17 Intermediate 54 D-312-630 1 E-304-621 13 C-302-620 19 I Cooling 149 D-312-701 3 E-304-622 25 C-302-620 19 MK-No's 150 C-312-703 1 E-304-622 25 C-302-620 19 ICE-151 C-312-702 2 E-304-622 25 C-302-620 19 ICH-154 D-312-701 3 E-304-622 25 C-302-620 19 181 C-312-753 E-304-621 13 C-302-620 19 182 C-312-754 2 E-304-621 13 C-302-620 19 3 Chilled Water 144 B-312-693 2 E-304-612 13 D-302-610 25 MK-No's 145 B-312-694 1 E-304-612 13 D-302-610 25 CHH-250 C-312-783 E-311-841 14 D-302-655 1 CHE-E-311-842 11 E-311-843 17 E-311-844 9 251 C-312-784 E-311-841 14 D-302-655 1 E-311-842 11 E-311-843 17 l E-311-844 9 D-302-655 1 252 C-312-783 D-302-655 1 Spacing Criteria f

TDR-TMI-194 APPENDIX I Page 15 of 15 REVISION I SYSTEMS INSPECTED AND APPLICABLE DRAWINGS (Cont'd) ME ISOMETRIC REV PIPING REV FLOW DIAGRAM REV In Core 101 B-312-676 1 E-521-021 6 Monitorlag 102 B-312-676 1 E-521-026 6 FSAR Seismic Category III System. Inspected Portion - Seismic Category I. FSAR Seisuic Category II System. Inspected Portion - Seismic Category I. 3FSAR Listing - Vital Ventilation System, Control Bzilding ) 1 0

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TDR-TMI-194 APPENDIX II Page 1 of 10 INSPECTION PROCEDURE 1.0 GENERAL PROCEDURE 1.1 Inspection of supports and piping geometry of Seismic Category I systems shall be 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 procedure. 1.3 Piping geometry 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 the 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 shall 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 THI-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 shall be provided (on a separate sheet if necessary) to allow an Engineering Evaluation and to allow drawing changes to be made. i

TDR-TMI-194 APPENDIX II Page 2 of 10 1.8 Data which has been obtained by way of visual estimation in ileu of measurement will be identified in the final report prepared by GAI 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. l 1.11 Observe Radiation Work Permit (RWP) requirements for all radiation / contamination areas. 2.0 PIPING INSPECTIO!3 2.1 PIPINJ INSPECTION REPORT A PIPING INSPECTION REPORT shall be completed for each piping isometric. If a portion of a system appears on more than one isometric, the isometric on which that system portion was inspected shall be referenced on the other isometric's system evaluation data sheet. 2.2 PIPE SUPPORT ATTACHMENT l 2.2.1 Location of pipe support attachment to pipe shall be inspected and compared to the piping isometric. i l 6 l l

TPR-TMI-194 APPENDIX II Page 3 of 10 2.2.2 The following axial tolerances are allowable: PIPE SIZE TOLERANCE To 6" 4" 8" to 18" 8" 20" to 36" 12" 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. 2.2.4 Supports not shown on the piping isometrics shall be located on the 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 interferencea 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 2.3.1 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 dimensions / angular rotation recorded on the piping isometric and referenced on the PIPING INSPECTION REPORT.

TDR-TMI-194 APPENDIX II Page 4 of 10 2.4 SUPPORT ORIENTATION 2.4.1 Support structural attachment orientation with the pipe attachment 'shall be within 7 of specified orientation. 2.4.2 Beam brackets or the equivalent may be rotated 90 for rigid rod hanger supports. 2.4.3 Beam brackets used with sway braces shall be oriented so as not to hinder axial movement, unless otherwise specified on the drawing. 2.4.4 Restraints designed to act in pairs shall provide the same function as the designed supports. 2.5 PIPE GEOMETRY 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 3.1.1 A SUPPORT INSPECTION REPORT shall be completed for each support inspected. 3.1.2 The support including attachment to plant structure shell be as shown on the support drawing. Deviations not allowed within this procedure shall be recorded on the SUPPORT INSPECTION REPORT and evaluated by Engineering.

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. 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. 3.2.6 Edge distance of anchor center-line to edge of concrete shall be l 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. I i I

TDR-TMI-194 APPENDIX II Page 6 of 10 J 3.3 SUPPORT TYPE 3.3.1 Support shall be that shown on drawing except as noted 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 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", "3" OR "C" spring may be different. 3.3.4 Hydraulic Snubbers 1 l 1. A large bore snubber may be substituted for a smaller bore snubber. I 2. The fluid reservoir may be reversed from the drawing provided the vent hole is on the 'high' side of the snubber. 3. Threaded end of the snubber shall be on the support structural l attachment (building) side. 4. Snubber shall be 1/4" from full extension or full compression. l l

TDR-TMI-194 APPENDIX II Page 7 of 10 3.4 WELDED ATTACHMENTS 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. 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.) l l i. l

TDR-TM1-194 APPENDIX II Pags 8 of 10 3.6.2 Lengths of structural shapes used to form a support bracket (e.g., knee brace) shall be as shown on drawing. 3.7 WEl. DING 3. 7.~ 1 WELDING - Symbol Shown 1 Welding shall be in accordance with symbol shown or develop the strength of the weaker member. i 3.7.2 WELDING - Symbol Not Shown Welding shall be 1/4" fillet all-around or develop the strength of the weaker member. 3.7.3 Cracked or damaged welds shall be recorded. 3.8 THREADED NENBERS 3.8.1 LOCKNUTS 1. Locknuts shall be tight and in accordance with the drawings except as specified herein. j 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. 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. - -, ~ w .m

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TDR-TMI-194 APPENDIX II 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). 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-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.

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

TDR-TMI-194 ATTACHMENT NO. I to APPENDIX II PIPING INSPECTION REPORT PIR-s System Recommended Disposition ME Yes/No - Comp. Dwg. Rev. Acceptable Reference Dwg. Analysis Required Drawing Revision Reg'd Within INSPECTION Tolerance 1. Support Location 2. Support Orientation 3. Valve Location 4. Valve Operator Orientation 5. Pipe Geometry Date Engineer / Inspector DEVIATIONS ANALYSIS Date Engineer / Analyst t i

TDR-TMI-194 ATTACHMENT NO. 2 to APPENDIX II SUPPORT INSPECTION REPORT SIR-Support No. Recommended Disposition Drawing No. Rev. Acceptable Drawing Rev. Req'd Repair /Reqork Req'd INSPECTION Yes/No 1. Structural Attachment Per Dwg. 2. Concrete Expansion Anchor Bolts Used No./ Size / 3. Unistrut Attachment Bolts Used No./ Size- / 4. Support Type Per Dwg. 5. Spring / Snubber Correct Size 6. Structural Components per Dwg. 7. Welding per Dwg. 8. Locknuts Installed per Dwg. AIR 9. Full Thread Engagement MIR Date Inspector DEVIATIONS DISPOSITION Date Engineer / Designer

TDR-TMI-194 ATTACHMENT NO. 3 to APPENDIX II MAINTENANCE ITEM REPORT MIR-Support No. Drawing No. Rev. DESCRIPTION OF PROBLEM Date Inspector MAINTENANCE ACTION Date DISPOSITION 4 Date

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i. ,s s s.,. s. g 4 sV s \\ ' .s s. 3 TDR-TMI-194 .y 's.* ATTAC19fENT NO. 4 i s . Lu. s, EPENb'IX II s No. 14-l A NIONsITEM REPORT t s e i , s A - tig i Support No. HE No. b Drawing No. Rev. 1 ., s ~ ,.u m x i DESCRIPTION OF FINDING ~ 1 1* n ,A s 3 ,Y .\\1 j s - 3 x ';. 'w i .n s t -,c s s s, '\\ q V g g -s 1 .s-g .. w J i y N. - 3 \\ t s %.4 sa ~ Gn,- t s ~ i %.\\ l

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L s \\ i 1 s .: - b \\ N TDR-TMI-194 APPENDIX IIIA s

SUMMARY

OF NON-CONFORMANCES i AND RESULTS OF REANALYSES s, v. l l \\ l l

SUMMARY

OF NONCONFORMANCES AND RESULTS OF REANALYSIS 3 Results of Reanalysis Nonconfo rmance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-1A 2, 11, 12 D.H. Pump 'A' Suction See ME-96 e ME-3 1 D.H. Pump 'A' Discharge 4 0 0 4 ME-04A 11, 12 12" D.H. Pump Suction 6 2 0 8 ME-5 None D.H. Pump 'B' Discharge 4 0 0 4 3 ME-6 1, 5, 6, 12 Cold Leg of Pump C to 30 1 1 31 3 Cold Leg of Pump B ME-7 1, 4, 12 MU-V-89A to Filters 22 0 0 22 3 MU-F4A and MU-F4B ME-8 1, 4, 12 From Filters MU-F4A and See ME-7 MU-F4B to Reactor Wall Pen. #337 ME-10 1, 2, 12 D.H. Removal 6" Crossover 16 1 1 17 3 ME-11 1, 2, 6, 12 From Pen. #309 to Anchor 35 0 0 35 ME-14* None R.B. Emergency Cooling Water 4 0 0 4 Pump Discharge from Pump RR-PIB ME-15* None River Water System 3 0 0 3 3 E 7 i; y NR-PIA to NR-SIA $%yy NR-PIB to NR-SIB $,,y y NR-PIC to NR-SIC @oyy

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-16* None River Water System 2 0 0 2 DR-PIA to DR-SIA DR-PIB to DR-SIB ME-17* None River Water System 2 0 0 2 RR-PIA to DR-SIA RR-PIB to RR-SIB ME-18* None 24" Deicing Line 4 0 0 4 Intake Pump House ME-20 12 R.B. Spray Pump Suction 17 0 0 17 (Pump B) ME-21 1, 4, 5, 12 Aux. Feedwater to Steam Gen. 28 4 6 32 ME-22* 1, 2, 4, 5 Auxiliary Feedwater to 25 0 1 25 Steam Gen. ME-24* 1, 2 Main Steam from Sta. Gen. 14 0 0 14 A to Anchor at Reactor Bldg. Wall ME-25* 1, 2 Main Stm. frce Stm. Gen. 12 0 0 12 A to Anchor at Reactor Bldg. Wall ME-26 1, 2, 12 Main Steam from Steam 13 0 0 13 Gen. B to Anchor at p?%y Reactor Bldg. Wall

$ 'y ** y Es m

s u o :s ME-27 1, 2,-12 Main Stm. From Stm. 14 0 0 14 @op7 Gen. B to Anchor

gg w

g m e. ME-28* 1, 2 Decay Heat Service 12 0 0 12 5 Cooling Water i

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-29* 2 Feedwater from Anchor at 10 0 0 10 Reactor Bldg. Wall to Stm. Gen. B ME-30* 2 Feedwater from Anchor Reactor 18 0 0 18 Bldg. Wall to Stm. Gen. B ME-32 1, 2, 4, 6, 8, 12 R.B. Spray Pump Dicch. 26 4 0 30 (Pump A) ME-33* 1 Decay Heat Removal Service 6 0 0 6 Cooling Water (River Wtr.) ME-34* None Core Flooding and Decay Heat 19 0 0 19 Removal Piping to Reactor (South) ME-35 2 Core Flooding and Decay 14 0 0 14 Heat Removal Piping to Reactor ME-36 1, 2, 12 D.H. Service Cooling, 33 2 0 35 River Water ME-37 1, 4, 8, 12 D.H. Service Cooling, 29 1 0 30 River Water ME-38 2, 12 Main Steam Piping from 14 0 0 14 Reactor Bldg. to gygg Turbine Gen. gg 4 7 ME-39 2, 12 Main Steam Piping from 14 0 0 14 Reactor Bldg. to m g Turbine Gen. g s e-

4 Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-40 2, 4, 12 Main Steam Piping from 13 1 0 14 Reactor Bldg. to Turbine Gen. ME-41 1, 2, 12 M.S. Piping from R.B. to 13 0 0 13 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, 4, 8, 12 M.S. from Stm. Gen. A 24 0 0 24 to Header ME-44 2, 6, 12 M.S. from Steam Gen. 13 0 0 13 B to Header at 297'-0" ME-45 1, 12 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 B) ME-47* 2 Condensate from Storage Tank 7 0 0 7 'A' to Emergency Feedwater Pumps ME-49 1, 4, 12 Condensate from Storage 27 0 0 27 TK. B to EFW Pumps N E' @i El (Inside Struc.) $$g7 Oe-cE! ME-51 1, 2, 8, 12 12" D.C. Piping from 6 1 0 7 @ o y 7* Secondary Shield Wall u "' s G to 36" R.C. Pipe G g #'

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-52* 1, 2, 4 River Water from Emerg. 19 0 0 19 Cooling Coils ME-53* 1 River Water from Emerg. 24 0 0 24 Cooling Coils ME-54* None Intermediate Cooling 1 0 0 1 Supply from Pen #302 to Coolers ME-56 12 D.H. Closed Cycle Cooling 16 0 0 16 Water from Cooler DHE-1A ME-57 1, 4, 6, 11, 12 D.H. from Cooler DHC-1B 25 0 0 25 to Cooler DCH-2B ME-58 12 D.H. Closed Cycle Cooling See ME-56 Wtr. from Pump DH-RIA to Cooler DH-CIA ME-59 1, 4, 12 D.H. from Pump DH-1B to See ME-57 Cooler DH-CIB i ME-60 2 D.H. Removal 24" Borated 7 0 0 7 Water Tank Discharge ME-61 1,2,6 D.H. Removal 8" Borated 10 0 0 10 Water Line Inlet Line E5NY ME-62 2, 8, 12 E.F. Pump "A" Discharge 13 0 0 13 gg gy, to Header $,gy OoMI ME-63 1, 2, 6, 12 E.F. Pump "B" Disch. to 6 0 0 6 g Header g g :- ME-64* 1, 3 Turbine Drive Emerg. 10 0 0 10 Fewtr. Pump Disch.

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-65 2, 8, 12 E.F. from Header to See ME-62 Reactor Bldg. Wall ME-66 8, 12 E.F. from Header to R.B. Wall 3 2 0 5 HE-67 6, 12 E.W. Pump Disch. to Header 4 0 0 4 ME-68 4, 6, 12 E.W. Pump "A" Suction See ME-49 ME-69 1 Turbine Driven Emerg. 3 0 0 3 Fdwtr. Pump Suction ME-70 1, 12 E.F. Water Suction 10 0 0 10 Anchor to Anchor ME-71* None Emerg.'Fdwtr. Pump B 7 0 0 7 Suction Piping HE-72A 1, 2, 6, 8, 12 D.H. Cooler DH-CIA Outlet See ME-10 to R.B. ME-73 1, 8, 12 D.H. Cooler DH-CIB Outlet See ME-10 to R.B. ME-74 1, 8, 12 D.H. from Reactor (Between 1 1 0 2 Shield Wall & R.B.) ME-75* None R.B. Spray Piping Spray 11 0 0 11 Ring #1 g2%y N$ "7 $,hy ME-76* None R.B. Spray Piping Spray 14 0 0 14 Ring #2 @oyy Us

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-77* None R.B. Spray Piping Spray 17 0 0 17 Ring #3 ME-78* None R.B. Spray Piping Spray 21 0 0 21 Ring #4 ME-79 None R.B. Spray Piping Spray 23 0 0 23 3 Ring #5 ME-80* None R.B. Spray Piping Spray 23 0 0 23 Ring #6 ME-81* None R.B. Spray Piping Spray 29 0 0 29 Ring #7 ME-82* None R.B. Spray Piping Spray 32 0 0 32 3 Ring #8 ME-83* None R.B. Spray Piping Spray 32 0 0 32 3 Ring #9 ME-84 1, 2, 3, 9, 12 R.B. Spray Wtr. Piping from 19 0 0 19 3 Pen. #308 to Header D at El. 417'-6" ME-85 1, 4, 9, 12 R.B. Spray Wtr. Piping from 13 0 0 13 3 Pen. #301 to Header at El. 417'-6" 3 < oo % $ E5 ME-86* 1, 2, 3, 6 Decay Heat Closed Service 13 0 1 13 m :c Cooling Wtr. from Cooler 5 Eh DC-C2A to Pump DC-PIA o"

aEr1 4

02 'C

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-87 1, 2, 12 D.H. Closed Service Cooling 9 0 0 9 3 Wtr. From Cooler DC-C2B to Pump DC-PIA NE-88 1, 2, 3, 12 Pressure Relief Valve to 9 0 0 9 Shield Wall ME-89 1, 3, 4, 12 6" Pressure Relief from 38 0 0 38 Secondary Shield W'all to Drain Tank ME-91 1, 4, 12 6" Pressure Relief from See ME-89 Wall to Drain Tank HE-92 1, 2, 3, 12 Pressure Relief to Shield 10 0 0 10 Wall NE-93 1, 4, 12 4" Pressure Relief Line See ME-89 from Shield Wall to Drain Tank ME-94 1,2,4,5,6 N.S. Cooling from Ht. 24 0 0 24 Exchangers to Pumps ME-95 1, 2, 4, 6, 12 N.S. Cooling Water 18" 44 0 0 44 Supply to Heat Exchangers HE-96 1,2,3,7,8, DH Removal Borated W'ater Tank 26 0 0 26 3 11, 12 Discharge N s' Ri d ? ?> N i ME-97A 1, 4, 6, 12 2-1/2" High Pressure Injection 10 1 0 11 @ o, @ $ El Piping from Pen. #321 to B&W oy7 Conn. #17 w "" r. G $h*

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Tit,le SI Supports Supports Supports Review __ ME-99* None Reactor Bldg. Normal Cooling 0 0 0 0 Water Supply to Air Handling Unit AH-E-IC from Pen. #421 NE-100* None Incore Monitoring System Piping 0 0 0 0 ME-101* None Incore Monitoring System 5 0 0 5 Piping ME-102* None Incore Monitoring System 4 0 0 4 Piping HE-103* 1, 2 2-1/2" High Pressure Injection 20 0 0 20 Piping from Pen. #322 to B&W Conn. #15 ME-106* None Reactor Bldg. Normal Cooling 0 0 0 0 Water Supply to Air Handling Unit AH-E-1B from Pen. #421 ME-107* None Reactor Bldg. Normal Cooling 0 0 0 0 Water Supply to Air Handling Unit AH-E-1A from Pen #421 ME-108A* None Reactor Bldg. Normal Cooling 0 0 0 0 Water Supply to Air Handling Unit AH-E-1C to Pen. #422 i NE-109* None Reactor Bldg. Normal Cooling 0 0 0 0 g Water Return from Air Handling < g g, jj Unit AH-E-1A to Pen. #422 gop8 oz o, 5 s, ME-110 1, 12 React. Bldg. Emerg. Cooling 18 0 0 18 Wtr. Return from Air Handling u,p* Unit AH-E-11A to Pen. #407 ep ME 99,100,106,107,108A,109 is a class SIII system evaluation not required

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Si!pports Review ME-111* 1 R.B. Cooling Water from Pen. 17 0 0 17

410 to AH-E-1A ME-112*

1,3,4 React. Bldg. Emerg. Cooling 15 0 0 15 Wtr. Return from Air Handling Unit AH-E-1C to Pen. #409 ME-113 1, 6, 12 R.B. CoolinC Water from Pen. 14 0 1 14

412 to AH-E-1C ME-114*

1, 4 React. Bldg. Emerg. Cooling 16 0 0 16 Water Return from Air Handling Unit AH-E-1B to Pen. #408 ME-115* 1 React. Bldg. Emerg. Cooling 16 0 0 16 Wtr. Supply from Pen. #411 to Air Handling Unit AH-E-1B ME-116 1,2,3,4,6, N.S. CoolinC Water Pump 63 3 0 66 8, 12 Disch. to Anchors ME-117 1,2,3,4,6, N.S. Cooling Water Return from See ME-116 8, 12 Spent Fuel Coolers "A"&"B" to Anchor Points ME-118* 1 2-1/2" High Pressure Injection 16 0 0 16 Piping from Pen. #338 to B&W Conn. #19 $2Dd HE-119 1, 6, 8, 11, 12 S.F. Cooling from Anchor 34 0 0 34 spy 5 $l,.hy? SFH-116 & 117 to D.H. Piping e Q7 HE-120 1, 3, 5, 8, 12 S.F. Cooling Piping from Base 20 0 0 20 o y g,0; l Supp. SHF-117 to Retaining l Ring in Wall

5 I

Results of Reanalysis Nonconfo rmance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-121* 1 S.F. Cooling from Anchor to 14 0 0 14 Borated Water Storage Tank ME-122 1, 12 Spent Fuel Cooling from 6 1 0 7 SFH-31 to 8" B&W Conn. on Decay Heat Removal Piping HE-123 12 Decay Heat Removal Piping from See ME-32 Seal Plate in Wall to Conn. on 8" Fuel Piping HE-124 1, 4, 6, 8, 11, S.F. Cooling Wtr. Piping to 23 0 0 23 3 12 Borated Wtr. Recire. Pump & S.F. Pumps SF-P-1A & SF-P-1B ME-125 1, 8, 12 S.F. Cooling Water Piping from 33 0 0 33 Coolers SF-C-1A & SF-C-1B ME-126A* None Spent Fuel Cooling Water 1 0 0 1 Piping to Spent Fuel Water Pool SF-T-2A ME-127A* None Spent Fuel Cooling Water 1 0 0 1 Piping to Spent Fuel Water Pool SF-T-2B ME-128 1, 5, 12 S.F. Cooling Piping from 8 0 1 8 3 Pen. #304 Fuel Canal

ouge ME-129*

None Spent Fuel Cooling Piping from 5 0 0 5 E S %, E Spent Fuel Pumps SF-P-1A to 5*@g coolers SF-C-1A Es Z. N r.," 2: "*ME Gy

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-130* None Spent Fuel Cooling from Spent 2 0 0 2 Fuel Pumps SF-P-1B to Cooler SF-C-1B ME-131* 1, 2 Nuclear Services Cooling Water 20 0 0 20 from Spent Fuel Coolers "A" & "B" Anchors ME-132 1, 6, 8, 12 S.F. Cooling from S.F. Pools 17 0 0 17 SFT-2A & 2B ME-133* 1, 6 Nuclear Services Cooling Water 13 0 0 13 from Storage Tank to Pump Suction ME-134* 1 Spent Fuel Cooling from Pen. 8 0 0 8

340 to SFH-37 ME-135 1, 4, 8, 11, 12 S.F. Cooling from SF-T-2A 15 0

0 15 3 ME-136 1, 5, 6, 12 S.F. Cooling from SF-T-2B 4 0 0 4 ME-137 1, 4, 6, 10, 11, S.F. Cooling from Borated 21 0 0 21 3 12 Water Recirc. Pump ME-138 1, 2, 4, 8, 12 Fdwtr. from 30" Hdr. to 4 0 0 4 Recirc. Pump ME-139A S, 12 F.W. from 30" Header to 4 0 0 4 M D' % @ Pen. #227 5% E-g7 eY NE-140 1, 12 Nuclear Services Cooling 9 0 0 9 @"y7 Water from React. Coolant u,&r,-* Waste Gas Equip. ,. [ #' e>

O Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-141 1, 8, 12 N.S. Cooling Water from 9 0 0 9 NSH-100 to R.C. Waste Gas Evap. "B" ~ ME-142 1, 12 Nuclear Services Cooling See HE-140 Water from React. Coolant Waste Gas Evap. "A" HE-143 1, 8, 12 N.S. Cooling Water from Anchor See NE-141 to R.C. Waste Evap. "A" ME-144 1, 6, 12 N.S. Cooling Water to Air 15 0 0 15 Condensers ME-145 1, 3, 6, 8, 12 N.S. Cooling Water from 27 0 0 27 AH-C-4A & 4B ME-146 1, 2, 3, 6, 12 MU & Purification to MU 39 0 1 39 Pumps MU-P-1A, 1B & IC NE-147* None Pressurizer to South Relief No Supports Valve ME-148* None Pressurizer to North Relief No Supports Valve FE-149* 1,4,6 Intermediate Cooling Water 1 0 0 1 Return Piping from Anchor Points to Pen. #302 E$ ge >$ m mE ME-150* None Intermediate Cooling Water 0 0 0 0 5

E! '-

Pen. #334 to Assumed Anchor y CI{ o l ME 149,150 IS A CLASS S II SYSTEM EVALUATION NOT REQUIRED *C$ i U$$2 i I

e Results of Reanalysis Nonconfo rmance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-151* 3 Intermediate Cooling Watesr 0 0 0 0 Pen. #333 to Reactor Coolant Pumps ME-155 1, 4,'6, 12 N.S. Cooling Water Return 27 0 0 27 from AH-E-24A & 24B to Assumed Anchor Point ME-156 1, 3, 6, 8, 12 N.S. Cooling Water Supply to 28 0 0 28 AH-E-24A & 24B ME-157* None 20" Decay Heat River Water 2 0 0 2 Disch. from Pump DR-PIB ME-158 2, 5, 12 R.B. Emerg. Cooling Water Pump 4 0 0 4 Discharge from RR-PIA ME-159* 1 Nuclear Services Cooling 8 0 0 8 Inside Pump House ME-160 1, 2, 5, 6, 12 Pressurizer Auxiliary Spray 37 4 0 41 ME-161* None 20" Decay Heat River Water 2 0 0 2 Disch. from Pump DR-P1A ME-162 1, 12 Electromatic Relief to 5 0 0 5 Secondary Shield Wall ME-163 8 MU from 2-1/2" B&W Conn. to 18 0 0 18 y 7 Q; y Letdown Coolers 5% @7

-. 5 5!

ME-164 1, 4, 6, 12 From Letdown Coolers to R.B. 21 0 0 21 @*py Wall Pen. #309 o, g Os w

s. " "'

ME 151 IS A CLASS S JI SYSTEM EVALUATION NOT REQUIRED t

Results of Reanalysis Nonconfo rmance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review HE-165 8, 12 12" Bypass for D.H. Cooler See NE-56 DH-CIA ME-166 1, 8, 12 12" Bypass for Decay Heat See HE-57 Cooler DH-CIB NE-167 1, 4, 5, 12 Discharge from MU Pumps 15 0 0 15 NU-PIA, PIB & PIC NE-168* None 4" Make-up Pump Suction from 1 1 0 2 Decay Heat Removal Cooler DH-CIA ME-169 1, 6, 12 4" MU Pump Suction from D.H. See HE-146 Removal Cooler DH-CIA NE-170 2, 12 Hake-up Tank HU-T1 to Hake-up See NE-146 Suction Header HE-171 1, 12 6" R.B. Spray Line to See NE-32 Borated Water Recire. Pump HE-172 11, 12 Pen. #354 to R.B. Spray Pump 7 0 1 7 Suction NE-173 2, 12 Pen. #352 to R.B. Spray Pump 7 0 1 7 NE-174 1, 12 Sodium Hydroxide to Anchors See HE-119 E E EE d NE-175* 1 4" Sodium Thiosulphate Tank 14 0 0 14 $g 5y hg BS-T1 Disch. to React. Bldg. @upp wR-G P e>

Results of Reanalysis Nonconformance Total Analysis Code Supports Original Added Deleted Requiring Number (See Section 3.2) Title S1 Supports Supports Supports Review ME-176 12 10" Connection Piping Bldg. See ME-20 Spray Pumps PI A-PIB ME-179 1, 2, 3, 4, 12 N.S. Cooling Water Urn-45 0 3 45 3 RC-P-1C & ME-218 to ME-204 ME-181* 4 8" Discharge IC from Pumps 4 0 0 4 1C-PIA and B to Pen. #333 ME-182* None 4" Line from ME-180 to 3 0 0 3 Pen. #334 Including the Bypass Around IC-F1 ME-183 12 Outlet to React. Coolant 1 0 0 1 Pump Seal Return Cooler HE-185 1, 12 ME-141 to Distillate See ME-141 Cooler B ME-186 1, 12 Distillate Cooler "B" to See ME-140 ME-140 ME-187 2, 6, 12 ME-143 to Distillate See HE-116 Cooler A ME-188 1, 2, 6, 12 Distillate Cooler "A" to See ME-95 ME-142 ME-189 1, 4, 6, 12 Disch. from Make-up Purif. 52 0 0 52 Pump to ME-131 g$ g ; m mE <gag 8 ME-190 1, 5, 6, 12 ME-16 to MU Purif. Pump 38 0 0 38 k 55{1 Suction

o
- U$

G5 i i

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-195 1, 2, 6, 12 N.S. Closed Cycle Cooling 11 0 0 11 Water Outlet of A.H. Units AH-E-15A & ISB to ME-95 ME-196 4, 5, 6, 12 NE-144 to Inlets of Sample See ME-144 Coolers ME-198 4, 6, 12 Outlet of Sample Coolers See ME-145 to ME-197 ME-199 1, 4, 6, 12 Fan Motor Coolers to ME-155 See HE-153 & 131 ME-200 4, 5, 6, 8, 12 NE-166 to Fan Motor Cooler See ME-156 Inlets ME-201 4, 8, 12 ME-53 to ME-70 See ME-49 ME-204 1, 2, 6, 12 8" Line from Pen. #347 to 53 1 1 54 3 to RCP-IA, IB, IC & ID ME-205 1, 4, 12 RC-P-ID to Pen. #346 25 2 2 27 3 ME-206 1, 8, 10, 12 From Condensate Tank "B" 6 0 0 6 ME-209 2, 12 Make-up Water & Purif. Pump See HE-167 Disch. Pipe to Disch. Header ME-210 1, 2, 4, 5, 12 ME-167 to Pen. #321 & #322 15 0 0 15 g,g <: n ns x ME-211 1, 4, 6, 8, 12 Make-up Pump Discharge 28 2 0 30 C; o g i Header to Pen. #338 R$ Es O,E 1 2: " ' d si

M

o' 1 Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Supports Supports Supports Review ME-212 1, 4, 6, 12 Make-up Pump Discharge Header See ME-211 to Pen. #339 ME-213 1, 4, 12 Cooling Water from HE-205 to 18 1 0 19 RC-P-1C & tE-214 3 NE-214 1,2,4,5, N.S. Cooling Water from 21 1 0 22 6, 12 ME-213 to RC-P-1A & ME-215 ME-215 1, 3, 12 N.S. Cooling Water from 20 0 0 20 3' ME-214 to RC-P-1B ME-218 1, 2, 3, 4, 5, 12 Cooling Water from RC-P-1A 42 2 0 44 & ME-214 to ME-179 ME-219 1, 2, 3, 12 Cooling Water from RC-P-1B 39 1 1 40 3 to ME-218 ME-220 2, 12 Make-up Water Fill Line to See ME-167 Make-up Pumps Disch. Header ME-222 1, 2, 6, 12 Decay Heat Cooling Water See ME-189 from ME-189 to ME-223 & ME-131 ME-223 1, 4, 6, 12 Cooling Water from HE-222 to See ME-189 ME-56 and FE-57 ME-224 1, 3, 6, 12 Cooling Water HE-116 to See ME-190 ME-159 & ME-59

.o > q E$E5 ME-225 4, 6, 12 NSCCC-MC-224 to ME-190 See ME-190 E*@g o5 N,.-.L ME-226*

1, 3 R.B. Spray Pump Suction Tank 9 0 0 9

o to Anchor

" "'O $ 5Y 4

Results of Reanalysis Nonconformance Total Supports Analysis Code Original Added Deleted Requiring Number (See Section 3.2) Title SI Support.s Supports Supports Review ME-227* 1 DHCCC-3" Line React. Bldg. 10 0 0 10 Spray Pump to 16" Line from DHR Cooler (DH-CIB) ME-230 2, 8, 12 Main Steam Pump Line to See ME-42 Intermediate Bldg. Wall HE-231 None Makeup & Purification, Hi 14 0 0 14 Pressure Injection Cross Tie (RC-PIB to RC-PID) 3 NE-232 None Makeup & Purification, Hi 9 0 0 9 Pressure Injection Cross Tie (RC-PIE to RC-PIC) ME-234 12, 13 From Emergency Feedwater Pump 7 0 0 7 Turbine to Exhaust Stack ME-235 None NSCCC Ret From Ind. Cooler 1 1 0 2 NE-236 None NSCCC Supply to Ind. Cooler 1 1 0 2 NE-250 1, 4, 6, 12 Chilled Water 60 1 2 61 3 ME-251 1, 4, 6, 12 Chilled Water Pump (AH-P-3A 36 0 2 36 & AH-P-3B) Suction KE-252 1, 4, 6, 12 Chilled Water See ME-250 El5N$

No formal computer reanalysis performed N N E! 7 ma 2

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9 9 9 TDR-TMI-194 APPENDIX IIIB RESULTS OF SUPPORT EVALUATIONS

TDR-TMI-194 APPENDIX IIIB Pr.ge 1 of 19 REVISION 3 RESULTS OF SUPPORT EVALUATIONS 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign HE-1A D.H. Pump "A" Section See ME-96 ME-3 D.11. Pump "A" 4 4 4 0 Discharge ME-4A 12" D.H. Pump Suction 8 8 4 4 3 ME-5 D.H. Pump "B: 4 4 3 1 Discharge ME-6 Cold Leg of Pump C 31 31 24 7 3 to Cols! Leg of Pump B ME-7 MU-V-89A to Filters 22 22 16 6 MU-F4A and MU-F4B ME-8 From Filters MU-F4A Se: ME-7 and MU-F4B to Reactor Wall Pen. #337 ME-10 D.H. Removal 6" 17 17 12 5 3 Crossover ME-11 From Pen. #309 35 35 25 10 to Anchor ME-14 R.B. Emergency Cooling 4 4 3 1 Water Pump Discharge from Pump Rh-PIB ME-15 River Water System 3 3 3 0 [ ME-16 River Water System 2 2 2 0 l ME-17 River Water System 2 2 2 0 ME-18 24" Deicini Line 4 4 0 4 l l 3 l l l l

O TDR-TMI-194 APPENDIX IIIB Page 2 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-20 R.B. Spray Pump Suction 17 17 16 1 (Pump B) ME-21 Aux. Feedwater To Steam 32 32 19 13 Ger.. ME-22 Auxiliary Feedwater to 25 25 19 6 Steam Gen. ME-24 Main Steam from Stm. 14 14 14 0 Gen. A to Anchor at Reactor Bldg. Wall ME-25 Main Stm. from Stm. 12 12 10 2 3 Gen. A to Anchor at Reactor Bldg. Wall ME-26 Main Steam from Steam 13 13 13 0 Gen. B to Anchor at Reactor Bldg. Wall HE-27 Main Stm. from Stm. 14 14 12 2 3 Gen. B to Anchor ME-28 Decay llcat Service 12 12 11 1 Cooling Water ME-29 Feedwater from Anchor 10 10 9 1 at Reactor Bldg. Wall to Stm. Gen. B ME-30 Feedwater from Anchor 18 18 15 3 Reactor Bldg. Wall to Stm. Gen. B ME-32 R.B. Spray Pump Disch. 30 30 21 9 (Pump A) ME-33 Decay Heat Removal 6 6 6 0 Service Cooling Water (River Wtr.) ME-34 Core Flooding and Decay 19 19 17 2 Heat Removal Piping to Reactor (South)

TDE-TMI-194 APPENDlX IIIB Page 3 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesian ME-35 Core Flooding and 14 14 9 5 Decay Heat Removal Piping to Reactor ME-36 D.H. Service Cooling, 35 35 28 7 3 River Water ME-37 D.H. Service Cooling, 30 30 27 3 3 River Water ME-38 Main Steam Piping from 14 14 9 5 3 Reactor Bldg. to Turbine Gen. ME-39 Main Steam Piping from 14 14 10 4 Reactor Bldg. to Turbine Gen. HE-40 Main Steam Piping from 14 14 11 3 3 Reactor Bldg. to Turbine Gen. ME-41 M.S. Piping from R.B. 13 13 9 4 to Turbine Generators ME-42 H.S. Piping from 23 23 19 4 Stm. Gen. A to Emerg. Feedwater Pump Turbine HE-43 M.S. from Stm. 24 24 15 9 3 Gen. A to Header ME-44 M.S. from Steam Gen. 13 13 12 1 B to Header at 297'-0" ME-45 R.B. Spray Pump See ME-20 Suction (for both pumps) HE-46 R.B. Spray Pump Disch. See ME-32 (Pump B) i

TDR-TMI-194 APPENDIX IIIB Page 4 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-47 Condensate from 7 7 7 0 3 Storage Tank "A" to Emergency Feedwater Pumps ME-49 Condensate from 27 27 21 6 3 Storage TK. B to EFW Pumps (Inside Struc.) ME-51 12" D.C. Piping from 7 7 5 2 Secondary Shield Wall to 36" R.C. Pipe HE-52 River Water from 19 19 15 4 Emerg. Cooling Coils ME-53 River Water from 24 24 22 2 Emerg. Cooling Coils ME-54 Intermediate Cooling 1 1 0 1 3 Supply from Pen #302 to Coolers ME-56 D.H. Closed Cycle 16 16 14 2 Cooling Water from Cooler DHE-1A 3 ME-57 D.H. from Cooler 25 25 18 7 DCH-1B to Cooler DCH-2B ME-58 D.H. Closed Cycle See ME-56 Cooling Wtr. from Pump DH-RIA to Cooler DH-CIA ME-59 D.H. from Pump DH-1B See HE-57 to Cooler DH-CIB

TDR-TMI-194 APPENDIX IIIB Page 5 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requirih6 Number Title Review Evaluated to Date Supports Redesign ME-60 D.H. Removal 24" 7 7 1 6 Borated Water Tank Discharge ME-61 D.H. Removal 8" 10 10 7 3 Borated Water Line Inlet Line HE-62 E.F. Pump "A" Disch. 13 13 10 3 to Header HE-63 E.F. Pump "B" Disch. 6 6 5 1 to Header ME-64 Turbine Drive Emerg. 10 10 10 0 Fdwtr. Pump Disch. ME-65 E.F. from Header to See ME-62 Reactor Bldg. Wall ME-66 E.F. from Header to 5 5 2 3 R.B. Wall ME-67 E.W. Pump Disch. to 4 4 4 0 Header ME-68 E.W. Pump "A" Suction See ME-49 ME-69 Turbine Driven Emerg. 3 3 3 0 Fdwtr. Pump Suction ME-70 E.F. Water Suction 10 10 10 0 Anchor to Anchor ME-71 Emerg. Fdwtr. Pump B 7 7 7 0 Suction Piping HE-72A D.H. Cooler DH-C7A See ME-10 Outlet to R.B. ME-73 D.H. Cooler DH-CIB See ME-10 Outlet to R.B. l

IDR-TMI-194 AIPENDIX IIIB Page 6 of 19 REVISION 3 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.II from Reactor 2 2 1 1 (Between Shield Wall & R.B.) ME-75 R.B. Spray Piping 11 11 11 0 Spray Ring #1 ME-76 R.B. Spray Piping 14 14 14 0 Spray Ring #2 NE-77 R.B. Spray Piping 17 17 17 0 Spray Ring #3 ME-78 R.B. Spray Piping 21 21 21 0 Spray Ring #4 ME-79 R.B. Spray Piping 23 23 23 0 Spray Ring #5 ME-80 R.B. Spray Piping 23 23 23 0 Spray Ring #6 ME-81 R.B. Spray Piping 29 29 29 0 Spray Ring #7 ) ME-82 R.B. Spray Piping 32 32 32 0 Spray Ring #8 ME-83 R.B. Spray Piping 32 32 32 0 Spray Ring #9 ME-84 R.B. Spray Water Piping 19 19 18 1 from Pen. #308 to Header D at El. 417'-6" ME-85 R.B. Spray Wtr. Piping 13 13 13 0 from Pen. #301 to Header at El. 417'-6" ME-86 Decay Heat Closed 13 13 5 8 Service Cooling Wtr. from Cooler DC-C2A to Pump DC-PIA l i i

' \\ = \\ TDR-TMI-194 s s APP 8NDIX IIIB s. Page 7 of 19 \\ REVISION 3"x s Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports 7 Redesign ME-87 D.H. Closed Service 9 9 6 3 3 Cooling Wtr. From Cooler DC-C2B to Pump DC-PIA ME-88 Pressure Relief Valve 9 9 8 1 to Shield Wall s ME-89 6" Pressure Relief 38 38 ' 36 2 from Secondary Shield 'T 1 Wall to Drain Tank 's g. ss ME-91 6" Pressure Relief See M9-89 \\ from Wall to Drain x Tank i ME-92 Pressure Relief to 10 10 8 2 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 24 18 6' 3 Exchangers to Pumps ME-95 N.S. Cooling Water 18" 44 44 29 15 3 Supply to Heat s Exchangers \\ I ME-96 D.H. Removal Borated 26 26 20 6 3 Water Tank Discharge ), T - ME-97A 2-1/2" High Pressure 11 11 8 3 3 Injection Piping from Pen. #321 to B&W Conn.

17

\\ ME-99 Reactor Bldg. Normal O Class SIII System Evaluation Cooling Water Supply Nou Required to Air Handling Unit AH-E-1C from Pen #421 ( 4 g ( i s.. L i k, s 3 ,1 ~ t

TDR-TMI-194 APPENDIX IIIB Page 8 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-100 Incore Monitoring 0 Class SIII System Evaluation System Piping Not Required ME-101 Incore Monitoring 5 5 5 0 System Piping ME-102 Incore Monitoring 4 4 4 0 System Piping HE-103 2-1/2" High Pressure 20 20 15 5 Injection Piping from Pen. f322 to B&W Conn. #15 ME-106 Reactor Bldg. Normal 0 Class SIII System Evaluation 3 Cooling Water Supply Not Required to Air Handling Unit AH-E-1B from Pen #421 ME-107 Reactor Bldg. Normal O Class SIII System Evaluation 3 Cooling Water Supply Not Required to Air Handling Unit AH-E-1A from Pen #421 l ME-108A Reactor Bldg. Normal 0 Class SIII System Evalaution Cooling Water Supply Not Required to Air Handling Unit AH-E-IC to Pen #422 ME-109 Reactor Bldg. Normal O Class SIII System Evaluation Cooling Water Return Not Required from Air Handling Unit AH-E-1A to Pen #422 ME-110 React. Bldg. Emerg. 18 18 14 4 3 Cooling Wtr. Return from Air Handling Unit AH-E-11A to Pen. #407 s ME-111 R.B. Cooling Water 17 17 14 3 3 from Pen. #410 to l1 AH-E-1A i

TDR-TMI-194 APPENDIX IIIB Page 9 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-112 React. Bldg. Emerg 15 15 10 5 3 Cooling Wtr. Return from Air Handling Unit AH-E-IC to Pen. #409 ME-113 R.B. Cooling Water 14 14 9 5 3 from Pen #412 to AH-E-1C NE-114 React. Bldg. Emerg. 16 16 13 3 3 Cooling Water Return from Air Handling Unit AH-E-1B to Pen. #408 ME-115 React. Bldg. Emerg, 16 16 16 0 Cooling Wtr. Supply from Pen. #411 to Air Handling Unit AH-E-1B ME-116 N.S. Cooling Water Pump 66 66 43 23 3 Disch, to Anchors ME-117 N.S. Cooling Water See ME-116 Return from Spent Fuel Coolers "A" & "B" to Anchor Points ME-118 2-1/2" High Pressure 16 16 16 0 Injection Piping from Pen. #338 to B&W Conn.

19 ME-119 S.F. Cooling from 34 34 21 13 3

l Anchor SFH-116 & 117 l to D.H. Piping HE-120 S.F. Cooling Piping 20 20 16 4 from Base Supp. SKF-117 to Retaining Ring in Wall

TDR-TMI-194 APPENDIX IIIB Page 10 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-121 3.F. Cooling from 14 14 9 5 Anchor to Borated Water Storage Tank ME-122 Spent Fuel Cooling 7 7 3 4 from SFH-31 to 8" B&W Conn. on Decay Heat Removal Piping HE-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. 23 23 19 4 3 Piping to Borated Wtr. Recirc. Pump & S.F. Pumps SF-P-1A & SF-P-1B ME-125 S.F. Cooling Water 33 33 27 6 Piping from Coolers SF-C-1A & SF-C-1B ME-126A Spent Fuel Cooling 1 1 1 0 3 Water Piping to Spent Fuel Water Pool SF-T-2A ME-127A Spent Fuel Cooling 1 1 0 1 3 Water Piping to Spent Fuel Water Pool SF-T-2B ME-128 S.F. Cooling Piping 8 8 3 5 from Pen. #304 Fuel Canal ME-129 Spent Fuel Cooling 5 5 2 3 Piping from Spent Fuel Pumps SF-P-1A to coolers SF-C-1A

I TDR-TMI-194 APPENDIX IIIB Page 11 of 19 REVISION 3 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 2 1 1 from Spent Fuel Pumps SF-P-1B to Cooler SF-C-1B ME-131 Nuclear Services 20 20 16 4 3 Cooling Water from Spent Fuel Coolers "A" & "B" Anchors ME-132 S.F. Cooling from S.F. 17 17 14 3 Pools SFT-2A & 2B ME-133 Nuclear Services 13 13 12 1 Cooling Water from Storage Tank to Pump Suction ME-134 Spent Fuel Cooling 8 8 6 2 from Pen. #340 to SFH-37 ME-135 S.F. Cooling from 15 15 10 3 3 SF-T-2A ME-136 S.F. Cooling from 4 4 2 2 3 SF-T-2B ME-137 S.F. Cooling from 21 21 16 5 3 Borated Water Recire. Pump ME-138 Fdwtr. from 30" 4 4 1 3 Header to Recire. Pump ME-139A F.W. from 30" Header 4 4 2 2 to Pen. #227 ME-140 Nuclear Services 9 9 7 2 Cooling Water from React. Coolant Waste Gas Equip.

TDR-TMI-194 APPENDIX IIIB Page 12 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redecian ME-141 N.S. Cooling Water from 9 9 9 0 NSH-100 to R.C. Waste Gas Evap. "B" 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 15 15 14 1 3 Air Condensers ME-145 N.S. Cooling Water 27 27 24 3 from AH-C-4A & 4B ME-146 MU & Purification to 39 39 35 4 3 MU Pumps MU-P-1A, IB & IC ME-149 Intermediate Cooling 1 1 0 1 3 Water Return Piping from Anchor Points to Pen #302 ME-150 Intermediate Cooling 0 Class SII System Evaluation Water Pen #334 to Not Required Assumed Anchor ME-151 Intermediate Cooling 0 Class SII System Evaluation Water Pen #333 to Not Required Reactor Coolant i Pumps ME-155 N.S. Cooling Water 27 27 18 9 3 Return from AH-E-24A & 24B to Assumed Anchor Point ME-156 N.S. Cooling Water 28 28 21 7 3 l Supply to AH-E-24A & 24B

TDR-TMI-194 APPENDIX IIIB Page 13 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-157 20" Decay Heat River 2 2 2 0 Water Disch. from Pump DR-PIB ME-158 R.B. Emerg. Cooling 4 4 3 1 Water Pump Disch. from RR-PIA ME-159 Nuclear Services 8 8 8 0 Cooling Inside Pump House ME-160 Pressurizer Auxiliary 41 41 20 21 3 Spray ME-161 20" Decay Heat River 2 2 2 0 Water Disch. from Pump DR-PIA ME-162 Electromatic Relief to 5 5 4 1 Secondary Shield Wall ME-163 MU from 2-1/2" B&W 18 18 7 11 3 Conn. to Letdown Coolers ME-164 From Letdown Coolers 21 21 15 6 i to R.B. Wall Pen. #309 ME-165 12" Bypass fro D.H. See ME-56 Cooler DH-CIA ME-166 12" Bypass for Decay See ME-57 Heat Cooler DH-CIB ME-167 Disch, from MU Pumps 15 15 11 4 MU-PIA, PIB & PIC l ME-168 4" Hake-up Pump Suction 2 2 0 2 from Decay Heat j' Removal Cooler DH-CIA I

TDR-TMI-194 APPENDIX IIIB Page 14 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-169 4" MU Pump Suction See ME-146 from D.H. Removal Cooler DH-CIA ME-170 Make-up Tank MU-T1 to See ME-146 Make-up Suction Header ME-171 6" R.B. Spray Line See ME-32 to Borated Water Recirc. Pump ME-172 Pen #354 to R.B. Spray 7 7 3 4 Pump Suction ME-173 Pen. #352 to R.B. Spray 7 7 3 4 3 Pump ME-174 Sodium Hydroxide to See ME-119 Anchors ME-175 4" Sodium Thiosulphate 14 14 13 1 3 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 45 45 26 19 3 RC-P-1C & ME-218 to ME-204 l NE-181 8" Discharge IC from 4 4 3 1 Pumps IC-PIA and B to Pen #333 ME-182 4" Line from ME-180 3 3 3 0 l to Pen #334 Including the Bypass Around IC-F1 ME-183 Outlet to React. 1 1 1 0 Coolant Pump Seal J Return Cooler i

O TDR-TMI-194 APPENDIX IIIB Page 15 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supporto Analysis Requiring or Reviewed and Acceptable Requirir.g Number Title Review Evaluated to Date Supports

Redesian, 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 &

52 52 49 3 Purif. Pump to ME-131 ME-190 ME-16 to MU Purif. 38 38 34 4 3 Pump Suction ME-195 N.S. Closed Cycle 11 11 8 3 Cooling Water Outlet of A.H. Units AH-E-15A & ISB 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 ME-200 ME-166 to Fan Motor See ME-156 Cooler Inlets ME-201 ME-53 to ME-70 See ME-49 ME-204 8" Line from Pen. #347 54 54 34 20 3 to RCP-1A, IB, IC & ID ME-205 RC-P-ID to Pen #346 27 27 10 17 3

TDR-TMI-194 APPENDIX IIIB Page 16 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-206 From condensate Tack 6 6 6 0 "B" ME-209 Make-up Water & Purif. See ME-167 Pump Disch. Pipe to Disch. Header ME-210 ME-167 to Pen. #321 & 15 15 9 6

322 3

ME-211 Make-up Pump Disch. 30 30 24 6 lleader to Pen. #338 ME-212 Make-up Pump Disch. See ME-211 Header to Pen. #339 ME-213 Cooling Water from 19 19 14 5 3 NE-205 to RC-P-1C & ME-214 ME-214 N.S. Cooling Water 22 22 14 8 3 from ME-213 to RC-P-1A & HE-215 ME-215 N.S. Cooling Water 20 20 13 7 3 ME-214 to RC-P-1B ME,218 Cooling Water from 44 44 31 13 RC-P-1A & ME-214 to ME-179 ME-219 Cooling Water from 40 40 22 18 3 RC-P-1B to ME-218 NE-220 Make-up Water Fill See ME-167 l 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

t TDR-TMI-194 APPENDIX IIIB Page 17 of 19 REVISION 3 Results of Evaluation Supports Supports Reviewed Supports Analysis Requiring or Reviewed and Acceptable Requiring Number Title Review Evaluated to Date Supports Redesign ME-224 Cooling Water ME-116 See ME-190 to ME-159 & ME-59 ME-225 NSCCC-MC-224 to ME-190 See ME-190 ME-226 R.B. Spray Pump Suction 9 9 9 0 Tank to Anchor ME-227 DHCCC-3" Line React. 10 10 10 0 Bldg. Spray Pump to 16" Line from DHR Cooler (DH-CIB) ME-230 Main Steam Pump Line See ME-42 to Intermediate Bldg. Wall ME-231 MU&P Hi Press. Ins. 14 14 14 0 Cross Tie (RC-PIB to RC-PID) ME-232 MU&P Hi Press. Ins. 9 9 8 1 Cross Tie (RC-PIA to RC-PIC) ME-234 E.F. from Emerg. 7 7 7 0 Feedwater Pump Turbine to Exhaust Stack ME-235 NSCCC Return from 2 2 0 2 Ind. Cooler ME-236 NSCCC Supply to 2 2 0 2 Ind. Cooler HE-250 Chilled Water 61 61 19 42 ME-251 Chilled Water Pump 36 36 14 22 (AH-P-3A & AH-P-3B) Suction ME-252 Chilled Water See HE-250

+ TDR-TMI-194 APPENDIX IIIB Page 18 of 19 REVISION 3 Results of Evaluation (Cont'd.) Seismic Spacing Criteria 'ExisLing Supports Existing Reviewed or Existing Supports Reviewed and Existing Supports Requiring Evaluated Acceptable Requiring Supports System Review To Date Supports Redesign _ Added Liquid Waste Disposal 56 56 32 24 11 3 Honitoring Post Accident Purge 4 4 1 3 3 Laak Rate 11 11 6 5 2 Instrument Air 25 25 8 17 5 3 Decay Heat Removal 15 15 5 10 6 3 Make-up Purification 91 91 44 47 25 3 Nuclear Services 14 14 9 5 3 3 Closed Cycle Cooling Reactor Bldg. Spray 9 9 1 8' 1 River Water 32 32 17 15 18 Spent Fuel 7 7 3 4 5 3 Chilled Water 14 14 2 12 11 Dscay Heat Closed Cycle Cooling 6 6 6 0 8 Condznsate 7 7 5 2 2 ~

TDR-TMI-194 APPENDIX IIIB Page 19 of 19 REVISION 3 Summary of Pipe Support Rework / Addition Construction Plan Pipe Support Rework Phase 1 - Supports to be repaired prior to restart 659 Phase 2 - Supports to be repaired after restart 59 (42 accessible during plant operation) Total 718 New Pipe Supports 3 Phase 1 - Supports to be installed prior to restart 145 Phase 2 - Supports to be installed after restart 0 Total 145 Total supports requiring construction 863

TDR-TMI-194 APPENDIX IV SYSTEM INSPECTION BOUNDARIES TABLE OF CONTENTS Sheet System 1 Main Steam (Auxiliary Steam) 2 Feedwater (Emergency Feedwater) 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 Contaioment Monitoring 17 Chilled Water 18 Instrument Air 19 Intermediate Cooling Legend l RRRRRRRRRRRR$5 Seismic spacing Criteria ElElElERIE Computer analyzed - -. - - - - - - - - - - -. -, ~,

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(. s e e TDR-TMI-194 APPENDIX V INACCESSIBLE INSPECTION ELEMENTS VISUAL INSPECTIONS
r 9 i J TDR-TMI-194 APPENDIX V Page 1 of 2 REVISION 3 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 MAKEUP AND PURIFICATION MUH-175 SSC High Radiation Area
1. Piping is in low MUH-176 SSC liigh Radiation Area pressure (< 150 MUH-177 SSC High Radiation Area psig) and low NUH-178 SSC High Radiation Area temperature MUH-179 SSC High Radiation Area
(< 200 F) portion of the make-up and purification system.
2. The piping in each cubicle has a re-dundant flow path in the piping through 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.
MUH-79 6 Space Limitations
1. Piping reanalysis was conducted, discounting this support. Results of reanalysis were within code allowances. System operability was justified.
I
t-9 TDR-THI-194 0 APPENDIX V Page 2 of 2 REVISION 3 SYSTEM AND INSPECTION ELEMENT ME NO. BURDEN OF INSPECTION SYSTEM CONSEQUENCES BUILDING SPRAY SBWH-47 SSC (4) Supports totally
1. All supports will SBWH-48 SSC covered by BWST be modified per SBWH-49 SSC Insulation results of SBWH-50 SSC reanalysis.
VISUAL INSPECTION - The following supports were visually inspected due to reasons l i r t. ed. TI2e visual inspect ion etial innlicate existance, integrity, configuration and location of the supports. Visual inspection information was then reviewed and evaluated to consider the impact of as-found deviations on support / system operability. Several Building Spray Ring supports were subsequently inspected and measured. The inspection findings were then considered in a formal reanalysis of the worst case analyses from this grouping. Reanalyses results were acceptable. SYSTEM AND INSPECTION ELEMENT ME NO. BURDEN OF INSPECTION CHILLED WATER CHil-12 250 Space limitations CHE-16 250 Space limitations CllE-58 251 Space limitations CHH-55 251 Space limitations BUILDING SPRAY 75 thru 83 Accessability ALL SPRAY RING SUPPORTS SPENT FUEL COOLING SFH-166 137 Underwater - Spent Fuel Pit SFH-167 135 Underwater - Spent Fuel Pit SFH-168 135 Underwater - Spent Fuel Pit e I - -}}

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