ML17353A920

Plant Specific Seismic Adequacy Evaluation of Turkey Point, Units 3 & 4 to Resolve USI A-46 & GL 87-02. W/O App a

ML17353A920
Person / Time
Site:	Turkey Point
Issue date:	04/30/1993
From:	STEVENSON & ASSOCIATES
To:
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ML17353A919	List: ML17353A918 ML17353A920
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR 90C1585D, GL-87-02, GL-87-2, NUDOCS 9610090209
Download: ML17353A920 (557)

Text

Controlled Copy No.

90C1585D Turkey.PtFin Final Report 4/30/93 Appendix A of this document contains proprietary information under the provisions of 10 CFR 2.790.

Dissemination or duplication without the permission of Stevenson and Associates is prohibited PLANT SPECIFIC SEISMIC ADEQUACY EVALUATION OF TURKEY POINT UNITS 3 AND 4 TO RESOLVE UNRESOLVED SAFETY ISSUE (USI) A-46 AND GENERIC LETTER (GL) 87-02 Final Report April 30, 1993 Performed for:

Florida Power & Light P.O. Box 14000 Juno Beach, FL 33408 Performed by:

Stevenson & Associates 9217 Midwest Ave.

Cleveland OH 44125 (216)587-3805 Fax (216)587-2205 96l0090209 930715 PDR ADOCK 05000250 p PDR

90C1585d Turkey.PTFin TABLE OF CONTENTS

1.0 INTRODUCTION

2.0 GENERAL PLANT DESCRIPTION .................. 2 2.1 SITE LOCATXON AND GEOGRAPHY 2

2. 2 SITE GEOLOGY 2 2.3 NUCI.EAR STEAM SUPPLY SYSTEM AND CONTAXNMENT STRUCTURE . 3 2.4 MAJOR STRUCTURES AND EQUIPMENT ARRANGEMENT 4

2. 5 PRINCIPAL DESIGN CRZTERXA 2.5.1 Containment Design Criteria

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~ . . . . . . . . . . . . ~ ~ ~ ~ ~ 5 2.5.2 Design Criteria for Other Glass I Structures 6 2.5.3 Design Criteria fot Class 1 Systems and Equipment . 6 3.0 SEISMIC DESIGN BASIS ..................... 7 3.1 SITE SEZSMXCZTY 7 3.2 SEXSMZC INPUT TO STRUCTURES AND EQUXPMENT ........ 8 3.3 SEISMIC ANALYSIS OF NUCLEAR CLASS I STRUCTURES ..... 12 3.4 SEISMIC DESIGN OF MECHANICAL AND ELECTRXCAL EQUXPMENT . 12 3.5 SEZSMXC DESIGN OF TANKS 13

3. 6 SEZSMXC SPATIAL INTERACTION 14 3.7 STRUCTURAL DAMPZNG 14

TABLE OF CONTENTS (continued) 4.0 USI A-46 EVALUATION ........... 15 4.1 OVERALL APPROACH TAKEN ......... .......... 15

4. 2 SCREENING CRITERIA ........... ~.... ..

~ ~ ~ ~ 18 4.2.1 Seismic Capacity Vs.

Demand 18 4.2.2 Equipment Construction Adequacy ~ 21 4.2.3 Anchorage Criteria . . . . . . . . . . . . . . . . . . . . . . 22 4.2.4 Seismic Spatial Interaction Criteria . . . . . . . . . . . . . . . 23 4.3 EauIPNENT NECESSARY TO ACHIEVE AND MAINTAIN HOT SHUTDOWN 25

4. 4 OP ERATZ NG P ROCED0 RES NECESSARY TO ACHIEVE AND MAINTAIN HOT SHUTDOWN 30

4. 5 SEZSNIC REVIEW TEAN 31 4.6 WALKDOWN PREPARATION 31 4.7 SCREENING WALKDOWN 33 4.7.1 Overall Walkdown Conduct . . 33

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4.7.2 Walkdown Results . 33 4.7.2.1 Outlier Identification . . 33 4.7.2.2 Equipment Anchorage 34 4.7.2.3 Seismic Spatial Interaction 35 4.7.2.4 Other Concerns . . . . . . . 36 5.0 RESOLUTION OF CONCERNS 36 6.0 INDEPENDENT PEER REVIEW ................... 36

7.0 CONCLUSION

S AND RESULTS ................... 42

8.0 REFERENCES

........................... 43

TABLE OF CONTENTS {continued)

APPENDIX A WALKDOWN PROCEDURE APPENDIX B SAFE SHUTDOWN

SUMMARY

DATA SHEETS APPENDIX C WALKDOMN CHECKLISTS AND SUPPLEMENTARY CALCULATIONS APPENDIX D PEER REVIEW REPORT APPENDIX E COMPONENT PHOTOGRAPHS

90C1585B Turkey.Pt

1.0 INTRODUCTION

Florida Power 8 Light (FPL) informed the USNRC by letters L-88-333"'ated August 4, 1988 and L-89-441'ated December 12, 1989 that FPL intended to resolve Unresolved Safety Issue (USI) A-46 and Generic Letter (GL) 87-02 (3) by the use of a plant specific program, as permitted by GL 87-02.

The FPL plant specific program was developed based upon understandings reached between FPL and the NRC subsequent to technical and economic presentations made by FPL to the NRC on June 2, 1988 at the NRC's Mhite Flint offices. The technical presentation, used plant specific seismic hazard curves developed using the Electric Power Research Institute (EPRI) methodology'"'ncluding source zones in the Caribbean Basin and demonstrated the very low probability of having an earthquake at the Safe Shutdown Earthquake (SSE) level at FPL's plants. The economic presentation used the Calculation of Reactor Accident

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together with the NRC

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Consequences, Version 2 (CRAG 2) computer code' analytic methodology in NUREG 1211' and demonstrated the very low values of

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potential offsite releases and potential risk reductions given the postulated accident scenarios and seismic hazards. This report documents the implementation of the FPL plant specific program at the Turkey Point Units 3 and 4 facility as it existed in April of 1990 at the time of the walkdown.

This report is organized using the format recommended in Section 8 of EPRI NP-6041 '"'. Some modification of this format was included, as appropriate for GL87-02/USI A-46. Section 1 is this introduction, Section 2 includes the general plant description, and Section 3 is a discussion of the plant's seismic design .basis including the design basis demand earthquake used for the walkdown and evaluation. Section 4, the major section of the report, describes the GL87-02/USI A-46 evaluation including a discussion of the overall approach, equipment selection, walkdown

criteria, i and screening walkdown results. Section 5 describes the resolution of those equipment items that could not be screened out during the walkdown. Section 6 is the discussion of the peer review of the

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alkdown, Section 7 the conclusions and results of the GL87-02/USI A-46 effort, ~

and Section 8 references.

There are several appendices that supplement the report which include; the walkdown procedure in Appendix A, the safe shutdown list of equipment in Appendix B, the walkdown checklists and supplementary calculations in Appendix C, the peer review report in Appendix D, and component photographs in Appendix E.

2.0 GENERAL PLANT DESCRIPTION 2.1 SITE LOCATION AND GEOGRAPHY Turkey Point Units 3 and 4 are located on the west shore of Biscayne Bay in Dade Count~'y Florida. The location is approximately 25 miles south of Miami, eight miles east of Florida City and nine miles southeast of Homestead, Florida.

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The Turkey Point site lies within the coastal lowlands province on the south Florida shelf. The area is practically flat, with elevations rising from sea level at the site to 10 ft. above mean low water in the Homestead area 9 miles to the west.

2.2 SITE GEOLOGY The predominant surface feature near the site is the Atlantic Coastal Ridge, which represents an area of bedrock outcrop of the Miami oolite. This formation underlies the site, where it is overlain by organic, mangrove swamp soils which average 4 to 8 ft. in thickness. Pockets of silt and clay are encountered locally, separating the organic soils and the limestone bedrock.

Local depressions, some of which attain depths as great as 16 feet, are i

occasionally encountered in the surface of the limestone bedrock at the site.

Such depressions are not sinkholes associated with collapse above an underground solution channel.

The Hiami oolite, a deposit of highly permeable limestone, extends to about 20 ft. below sea level. The rock contains random zones of harder and softer rock and heterogeneously distributed small voids and solution channels, many of which contain secondary deposits. This limestone lies unconformably upon the Ft. Thompson formation, which is a complex sequence of limestones and calcareous sandstones.

At a depth of about 70 ft. below sea level, the Ft. Thompson formation unconformably overlies the Tamiami formation, a predominantly clayey and calcareous marl, locally indurated to limestone. The Tamiami formation also contains beds of silty and shelly sands, and is relatively impermeable. The Tamiami and underlying Hawthorne and Tampa formations, comprise a relatively impermeable hydrogeologic unit called the Floridian aquiclude, which is roughly 500 to 700 ft. thick in southern Florida. The bedrock beneath the i is site i competent with respect to foundations and is capable of supporting heavy loads.

2.3 NUCLEAR STEAM SUPPLY SYSTEM AND CONTAINMENT STRUCTURE

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nuclear steam supply system (NSSS) is a pressurized water reactor system'he designed by Westinghouse Electric Corporation. The containment structure consists of a post-tensioned reinforced concrete cylinder, with an inside diameter of 116 feet and an inside height of 170 feet between the base mat and the top of the dome. The cylinder is capped by a shallow dome and has a flat slab base mat. The walls and dome are 3 ft. 9 in. and 3 ft. 3 in. thick, respectively. The base slab is reinforced concrete 10 ft. 6 in. thick. The containment structure was designed by Bechtel Power Corporation.

The rated NSSS thermal core power level is 2200 Hwt. This is the basis for i of the balance of plant and related facilities, including the major he design systems and components, the engineered safety features and for evaluation of postulated accidents. The corresponding net electrical output for the rated power level is approximately 666 Hwe.

2.4 MAJOR STRUCTURES AND EQUIPMENT ARRANGEMENT The nuclear plant installations consist of a containment structure, an auxiliary building, a turbine building, a control building, an intake structure, a radwaste building, an emergency diesel generator building, and switchgear buildings.

The containment structure houses the NSSS, consisting of the reactor, steam generators, reactor coolant pumps, pressurizer, and some of the other reactor auxiliaries. The containment structure is served by circular bridge crane supported on the upper portion of the containment wall.

The auxiliary i building houses the chemical and volume control equipment, the waste management facilities, engineered saFety features components, heating and ventilating system components, laboratories, offices, and laundry.

The control building houses the control room, the reactor control rod drive equipment, motor control center 38 and 4B, both units reactor trip breakers, the cable spreading room, the battery and inverter rooms, the 125 v DC busses and on the ground floor the plant data computer and display system.

The fuel handling building contains the spent fuel pool and new fuel storage facilities, as well as the cooling and purification equipment for the fuel pool. The fuel is transferred from the reactor containment to the fuel handling building through the fuel transfer tube.

The turbine building houses the turbine generator, condensers, feedwater heaters, condensate and feedwater pumps, turbine auxiliaries and certain

switchgear equipment. Administrative offices, health physics facilities, i

maintenance shops and warehouses are all located in separate buildings away from the power generation equipment and structures.

2. 5 PRINCIPAL DESIGN CRITERIA 2.5.1 Containment Design Criteria Appendix 5-B of Turkey Point's FSAR 'escribes the loading criteria for the containment. 'fhe following constituted the design bases including seismic input for the reactor containment:

1. The containment has the capability of withstanding the peak transient pressure and temperature which could occur due to the postulated loss-of-coolant from a double-ended circumferential rupture of a reactor coolant pipe coincident with the design basis and maximum hypothetical earthquake.

, The containment will maintain its integrity during the hypothetical earthquake with simultaneous zero period ground accelerations of .15g horizontal and .10g vertical.

3. The containment is designed to meet the shielding requirements of 10CFR20 during normal operation, as well as the suggested guidelines of 10CFR100 during the unlikely hypothetical incident.

4. The foundation and supports for piping and equipment in the containment are designed to prevent a primary system rupture from propagating a secondary system rupture. The reverse is also true.

The containment structure is designed by both working stress and ultimate strength methods. ACI 318-63 limits were used for the working stress design except that the allowable tensile stress in non-prestressed reinforcing was limited to 0.5 Fy.

.5.2 Design Criteria for Othe} Glass I Structures Class I structures outside of containment are designed for loads resulting from normal operation and hypothetical accident, wind and earthquake conditions. Loading conditions for these structures are defined in Appendix 5A of Turkey k

P oin s FSAR

' The normal operation loads are those encountered during normal opera ion. t'lass I structures are designed in accordance with design methods of accepted standards and codes as they are applicable. For t

hypothetical1 acci'd en , win 'nd and an earthquake conditions the Class I Structures t'

are proportione t o maintain mai elastic behavior when subjected to various combinations of dead loads, thermal loads, and wind or seismic loads. The upper limit of elastic behavior is considered to be the yield strength of the effective load-carrying structural materials.

The yield strength for steel (including reinforcing steel) is considered to be the minimum as given in the appropriate ASTN Specification. Concrete structures are designedi for ductile behavior whenever possible; that is, with steel stress controlling the design. The ultimate strength values for concrete are use d in ' 'ng e t ermining the required yield strength of the structure.

i i Limited yielding is allowable in steel provided the deflection is checked to ensure that the affected Class I'ystems and equipment are not stressed beyond specified limits.

2.5.3 Design Criteria for Class I Systems and Equipment The reactor vessel, steam generators, pressurizer and pressurizer relief tank were designed and fabricated according to the requirements of the ASHE Boiler and Pressure Vessel Code,Section III, 1964 Edition, October 1965 Addenda.

Reactor coolant loop piping and fittings were designed and fabricated in accordance with the requirements of 831.1-1955 Power Piping Code.

3.0 SEISMIC DESIGN BASIS

3. I SITE SEISMlcZTY The earthquake history of the Southeastern United States and the nearby West Indies has been reviewed in detail. The southern part of the peninsula has never experienced earthquake damage.

Florida is far removed from active plate boundaries and other zones of crustal weakness with accompanying earthquakes. The peninsula is characterized by a paucity of seismic events: only six minor tremors that cannot be attributed to blasting or military activities have been identified in the past two centuries. None of the events was recorded on seismographs, and the only reliable estimates of size yield a maximum magnitude of 3.5 Hn and intensity of NM V associated with a 1973 event near Sanford. A similar intensity, generated by the 1886 Charleston, South Carolina, earthquake, was probably experienced in north Florida.

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Five of the six events

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were distributed throughout north Florida, and although most locations are vague, no spacial pattern indicative of subsurface structural control can be identified. No models or reconstructions of the Florida basement include structural features with any potential for significant seismic activity. There is no evidence in the Turkey Point area for basement structures associated with possible earthquakes.

The uniform building code designates the vicinity of the site as Zone 0 on the map entitled, "Hap of the United States Showing Zones of Approximate Equal Seismic Probability". The U. S. Coast and Geodetic Survey indicates Zone 0 as an area of no earthquake damage. Furthermore, an examination of historical earthquake epicenter locations show that a broad segment of south and central Florida are entirely absent of earthquake epicenters. The Turkey Point site is in this region.

he Turkey Point site ranks 67th out of the 69 U.S. nuclear power plant sites in regard to seismic hazards in the Lawrence Livermore National Laboratory study of the seismic hazard characterization of nuclear sites east of the Rocky Hountains.'

3.2 SEXSMXC INPUT TO STRUCTURES AND EQUIPMENT The seismic design was based on the acceleration ground response spectrum curves shown in Figure 3.2.1 for the Design Basis Earthquake, DBE, and Figure 3.2.2 for the Maximum Hypothetical Earthquake, HHE. The curves were derived from the "Housner Spectrum" normalized to 0.05g for the DBE and 0. 15g for the NHE. The FSAR commitment for an MHE of 0.15g was determined at a time when probabilistic definition of seismic input had not been developed with any degree of consistency or confidence. Therefore, the 0.15g PGA was conservatively estimated based on very limited data available at the time.

The basis for this appears to be a letter report from the U.S. Coast and Geodetic Survey. (10)

Earthquake stresses were based on the worse case of a single horizontal ground acceleration acting either in a nominal N-S or E-W direction and a vertical ground acceleration component of two-thirds of the horizontal resultant, with the two acting simultaneously.

0.05g DBE 6% DAMPING 0.20 0.1 8

0. I 6 0

I 0.14 CI" LLI 0.52

0. 5Q 0,08 0.06 0.04 0.02 0.00 0 10 1 6 20 26 30 36 FREQUENCY (Hz)

Figure 3.2.1 Turkey Point Units 3 8 4 Ground DBE, 5% Damping

0.15g MHE HOUSNEFi 5% OAMPING 0.25 0.20 0.15 0.10 0.06 O.OD 6 10 20 25 SO 36 FREQUENCY (Hz)

Figure 3;2.2 Turkey Point Units 3 5.4 Ground MHE, 5! Damping 10

he safety related nuclear Class I equipment originally supplied for Turkey oint Station was evaluated for an equivalent static seismic load that was calculated in accordance with Reference ll. The procedure used accounted for the amplifications associated with potential resonance between the building and the equipment. The procedure was as follows:

1. S (Sb+S) x W Where:

(i) Equipment weight (ii) Equipment acceleration due to building harmonic motion (iii) S 9

Equipment acceleration due to ground motion (iv) S Equivalent static seismic load

2. Sq A~ x C~q Where:

{i) Ab Building acceleration at the elevation of the equipment support due to harmonic motion (ii) C<> A coefficient depending on the equipment and buildings natural frequency

3. S = {H-h) x C~~

H Where:

(i) H Total height of building (ii) h height of equipment from ground (iii) C<z A coefficient for either the OBE (.05g) or HHE (. 15g) for amplifications associated with a damping factor of 0.5%

The acceleration coefficients

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Sb and S are applied in the horizontal

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direction. The vertical

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seismic acceleration coefficient are 2/3 of the

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Sb and S, coefficients.

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After the initial plant design, FPL developed floor response spectra for additional areas of the plant. FPL used these spectra in the re-evaluation or new design of selected Class I equipment, piping, and so forth. When available, the SRT used available floor response spectra. When they were not available, the SRT developed seismic input to the equipment as described in Section 4.2.3.

3.3 SEISMIC ANALYSIS OF NUCLEAR CLASS I STRUCTURES Dynamic models were developed and analysis of the structures were made to determine the natural periods for vibration of each structure using lump mass or distributed mass systems as considered appropriate. In these analyses, periods and mode shapes were determined for each mode. These data were used to define participation factors for each structure. These participation factors were used with the spectral acceleration masses and relative displacement to define resultant seismic forces in each mode. These forces were applied to Nuclear Class I Structures to determine resultant shears and moments for design purposes.

3.4 SEISMIC DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT The equipment furnished for installation at Turkey Point according to the original design basis contained in a 1968 Bechtel Memorandum"" was designed for earthquake loads. The specified ground acceleration in the horizontal direction were a) .05 g with an allowable stress increase of 33/, over normal allowable and b) . 15 g with an allowable stress of 90% of minimum yield stress, with the further condition that the equipment retain the ability to perform its safety function. The vertical ground acceleration specified was 2/3 the horizontal and acts simultaneously with one horizontal earthquake 12

Appendix 5A of Turkey Point's FSAR also states that the mechanical

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component. ~

and electrical equipment has been purchased under specifications that include a description of the seismic design criteria for the plant.

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In the initial plant design, a methodology was developed to consider building amplifications as a function of the equipment and building natural frequency.

This methodology was explained in Section 3.2 of this report.

The mechanical and electrical equipment were purchased under specifications that include a description of the seismic design criteria for the plant.

Hotor control centers, switchgear and load centers have been shaketable tested to demonstrate no-loss-of-function capacity under the maximum hypothetical earthquake. There were no specific commitments with regard to equipment anchorage in the FSAR.

3.5

~ SEISMIC DESIGN OF TANKS According to Appendix 5A Section II-c of Turkey Point's FSAR, Class I

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equipment is to be designed for both the DBE and HHE in accordance with AEC

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Publication TID 7024." 'he percent of critical damping for welded steel plate assemblies that is applicable to tanks is given as I percent for both the DBE and HHE. Tanks included in the GL87-02/USI-A46 effort are the Condensate Storage Tanks, Emergency Generator Diesel Day Tanks, Diesel Oil Storage Tanks, Refueling'Water Storage Tanks, Component Cooling Surge Tanks, Accumulator Tanks, and Boric Acid Storage Tanks. Specific mention is included in FSAR Appendix 5A that a hydrodynamic analysis of the Refueling Water Storage Tank has been performed using the methods of Chapter 6 of USAEC TID 7024. The anchorage design requirements for tanks were not specified in the FSAR. It should also be noted that the TID 7024 methodology did not consider the amplified frequency response of the impulsive fluid mass. For this reason the seismic reevaluation of large tanks was included in Unresolved Safety Issue A-40."~'his issue was addressed in the GL87-02/USI A-46 evaluation performed and therefore USI A-40 has also been resolved at Turkey Point.

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.6 SEISMIC SPATIAL XNTERACTION Seismic interaction with non-seismic equipment is not addressed in Turkey Point's FSAR. FPL has conducted a review of the safety related equipment at Turkey Point Unit Nos. 3 and 4 to assess its susceptibility to loss of function from flooding or release of chemicals caused by the failure of non-seismic category I systems.

As a result of this evaluation some relatively minor modifications as to plan configuration were made. The results of this evaluation are described in Reference 14.

Seismic interaction with block walls was also evaluated by FPL in response to IE Bulletin 80-11."s'The evaluation is documented in Reference 16. A test program was also initiated to support the assumptions made with regard to

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material properties in this evaluation.

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Seismic spatial interactions were addressed in the GL 87-02/USI A-4 evaluation performed as discussed in Section 4.2.4 of this report. Seismic spatial interactions were also the subject of USI A-17 and therefore USI A-17 has also been resolved at Turkey Point.

3.7 STRUCTURAL DAMPING The damping factors used in the analyses of the various structures, equipment and distribution systems at the Turkey Point Plants are as follows:

PERCENT DAMPING PERCENT DAHPING FOR DBE FOR NHE Soil 5.0 10.0 Reinforced Concrete Frames, and 3.0 5.0 Buildin s Concrete Equipment Supports on 2.0 2.0 Another Structure Bolted Steel Framed Structures 2.0 2.0 Welded Steel Framed Structures 2.0 2.0 Welded Steel Plate Assemblies 1.0 1.0 Steel Pi in Systems .5 .5

4. 0 USI A-46 EVALUATION

4. 1 OVERALL APPROACH TAKEN Florida Power 5 Light Company (FPL), decided to resolve GL 87-02/USI A-46 by use of a plant specific program. The proprietary procedure developed and implemented at FPL's Turkey Point Units 3 and 4 to provide final resolution of GL 87-02/USI A-46 is included as Appendix A.

Section 3.0 of this report, describes the original seismic design basis for the mechanical and electrical equipment, and tanks and heat exchangers for the plants. The basic requirement is that this equipment will be able to withstand the design basis HHE at the plant and still provide their safe shutdown function. The procedure used for the walkdown relied on the judgment of an expert seismic review team (SRT) to verify that this basic requirement be met. Substantial benefit was obtained by using experts in the field of seismic engineering and seismic capacity of equipment as seismic review team members.

'Reference 8 Section 5A page 12.

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FPL selected a success path of equipment using safety, and non-safety equipment for achieving hot shutdown for the plants for a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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The relationship drawing, that shows the functions necessary to shutdown the

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reactor and equipment that supports those are shown in Figure 4. 1. 1.

FPL did not include relay evaluations based on the low seismic ground motion, low seismic risk, industry experience and taking credit for operator action should a relay actuate as has been done to date in seismic PRAs. A review of the effects of the Leroy earthquake on the Perry Nuclear Plant indicated that for this earthquake which exceeded Perry Plant's operating earthquake design basis, relays would not present a safety risk since only five non-safety related relays actuated of which three relays were in a de-energized state.

Diablo Canyon, Limerick and Hatch plants have performed relay evaluations involving over 2,600 relays without any of the relays requiring replacement.

When credit is taken for operator action to identify the relay actuation and when following plant operating procedures to address the actuation, relays would not pose a safety risk for FPL sites. In addition, FPL estimated the engineering cost to investigate relays at several hundred thousand dollars, which could not be justified by any reduction in off site risk of radiation exposure to the general public. Also, the NRC exempted Naine Yankee a plant in a much higher seismic area, from GL87-02/A-46 based on the satisfactory completion of a Seismic Nargin Assessment using the NRC methodology in NUREG/CR-4826" 'hich did not require relay evaluations.

Equipment data sheets were developed and used for each equipment item evaluated. The references documenting the criteria and procedures used for this walkdown, were the most recent at the time of the walkdown (the draft SSRAP report

" ', the EPRI margins report ', and URS anchorage report " ').

Another aspect of the overall approach taken by FPL was to voluntarily arrange for an independent peer review. The report was reviewed and a plant walkdown performed by an independent seismic expert. The result of the peer review is included in Section 6 and Appendix D.

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CONTROL ROOM CONSOI.ES CONTROL ROOM VERTICAL PANEL B CHARGING PUMP BORIC ACID TRANSFER PUMP REFUELIHG WATER STORAGE TANK REACTOR CONTROL a .%kr,

. e.':pAM>~.aKMaFalg>

g~w%+j>g~yp~

AUXILIARYFEEDWATER PUMPS CONDENSATE STORAGE TANK pc~ ' 4160V SWITCNGEAR ~4 COMPONENT COOUNG WATER PUMP B A D 480V LOAD CENTERS DITAKE COOLING WATER PUMP B DIESEL GENERATOR 4 AUXIUARIES COMPONENT COOLUIG WATER 3B, 4A da 4S BATTERY CHARGERS HEAT EXCHANGER 3C, 3D, 4C A 4D IHVERTERS

g. COMPONENT COOuNG WATER ~.

SURGE TANK 38> 48 !a 4A BATTERY RACK 3D01, 3D23, 4D01 4 4D23 12$ V DC BUSSES

, ~~yj~ <~,gC SUCCESS PATH FOR REACTOR SHUTDOV/N AND CONTROL

.FOR TURKEY POINT UNITS 3&4

• ~0 Figure 4.1.1 Relationship Drawing of Functions Necessary to Shut Down

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Reactor and Equipment Supporting Those Functions 17

2 SCREENING CRITERIA The four basic requirements for the GL 87-02/USI A-46 review of Turkey Point Units 3 and 4 were addressed in the walkdown. The requirements include; the seismic capacity being greater than demand, the construction 'quipment adequacy of the equipment, anchorage adequacy and seismic spatial interaction.

The specific criteria for satisfying these requirements are discussed in this section of the report.

4.2.1 Seismic Capacity Vs. Demand Seismic Capacity vs. Demand for the equipment was addressed at the plant level rather than an equipment specific level. As described in the draft SSRAP report" ', well anchored industrial grade equipment have performed well in earthquakes with a magnitude much greater than the NHE defined earthquake at Turkey Point. Figure 4.2.1 shows a comparison of the 5% damped HHE design

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asis response spectrum and the 5% damped response spectra for the earthquakes used to develop the SSRAP Bounding Spectrum. ~ As demonstrated by this figure equipment in these facilities were subjected to much greater vibration than

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expected at the Turkey Point site.

The SSRAP Bounding Spectrum recommended for use during GL 87-02/USI A-46 evaluations in Reference 18 envelops the plant NHE ground response spectra over the entire frequency as shown in Figure 4.2.2. SSRAP recommended the use of the Bounding Spectra for equipment whose natural frequency is greater than 8 hz and that are located below about 40 ft. above grade. For equipment that do not meet these qualifiers, the floor response spectra may be compared to 1.5 times the Bounding Spectrum. These limitations did not effect the Turkey Point plant equipment.

The 40'imitation did not effect the evaluation since there is only one item of equipment located significantly above about 40'bove grade. The Component Cooling Mater Surge Tank is located at elevation 71'hich is 53'bove grade.

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C - COALlNGA E - EL CENTRO S - SYLMAR L - LLOLLEO H - 0.86g MHE TP C ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

E S ~4~

5% DAMPlNG 2.00 1.80 0 ~

1.60 0 o o l- 1.40 g ~ 0 o)

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Ct: ~

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LU 1.20 p

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LU ~

5.00 0.80 ~ ~~~ ~ ~

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0.60 e~>>

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e

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e 0.40 0.20 0.00 0 10 20 25 FREQUENCY (Hz)

Figure 4.2.1 Comparison Between 6% Damped Ground Response Spectra Of Data Base Earthquakes and Turkey Point Units 3 5,4 MHE 19

8 BOUNDlNG SPECTRUM TP-~8c+ 0.159 MHE HOUSNER TP 3f+

5 Va DAMP MG 1

5.00 0.90 0 0.80 l 0.70 CC 0.60 0.50 0.40 CC 0.30 r-~Y PO>Q

. l M,W D 0.20 LLl CL K 0.10 0.00 0 6 0 0 5 6 20 25 30 35 FREQUENCY (Hz) i Figure 4.2.2 Comparison Between 5% Damped Bounding Spectra to Turkey Point Units 3 5,4 Ground MHE 20

he seismically vulnerable components of this item were evaluated using a conservative estimate of the floor response.

The 8 hz criteria is not limiting at Turkey Point since all other equipment was located at 24'bove grade and less. At that elevation the floor response spectra available is enveloped by 1.5 times the bounding spectrum, that is recommended in Reference 18 to be used when comparing to the floor spectra.

The question of seismic capacity vs. demand for equipment was therefore judged to be acceptable on a generic basis, and this requirement was not included as an item on the equipment lists or check lists.

4.2.2 Equipment Construction Adequacy Reference 18 contains criteria for equipment construction adequacy for various i

equipment categories in the form of caveats. Because of the low seismicity at the site, construction adequacy was not addressed by specific caveats for each i

type of equipment. Instead, the walkdown emphasized the two issues that have caused the most damage in earthquakes; anchorage adequacy and seismic spatial interaction.

However, the three SRT engineers are experts in the area of seismic adequacy of equipment and equipment performance during earthquakes. They are very familiar with the issues in regard to equipment adequacy from their experience which will be discus'sed in Section 4.5. The SRT engineers inspected each equipment item, and any detail they felt was seismically vulnerable was addressed.

4.2.3 Anchorage Criteria An assessment of the anchorage adequacy was performed on each equipment item included on the safe shutdown list. This included an assessment of the seismic demand on the equipment anchorage (forces and stresses on the 21

anchorage), the seismic capacity of the anchorage components (attachment of he equipment to the anchorage, the anchorage itself, and the development of the anchorage to the foundation), and whether the capacity of the weak link of the anchorage system exceeded the demand.

To perform the anchorage assessment, the guidance contained in Section 7 (Equipment Anchorage) of the draft SSRAP report " ', and the URS anchorage report " 'as used. Other sources for performing the evaluation were knowledge of the design basis ground response spectra, and elevation of the equipment. The main guidance documents referred to above were supplemented when appropriate with references 20 to 23. SRT judgment based on their experience was also used as will be discussed further.

The discussion contained in Reference 19 was primarily used to estimate the seismic demand on the anchorage of mechanical and electrical equipment. The damping used met or was more conservative than the Reference 19 recommendations.

hen floor spectra did not exist, an estimate of the demand for mechanical and electrical equipment was made from the ground response spectra. For example, equipment items less than 40'bove grade used the peak of the 5/. ground spectra times 1.5 for building amplification and 1.25 for conservatism in accordance with Reference 18 [which is 0.45g (.24g x 1.5 x 1.25)].

The anchorage demand for tanks was estimated for the impulsive loads by using the applicable 5/. damped spectra. The large flat bottom tanks located at grade and screened during the walkdown included the Diesel Oil Storage Tank, Condensate Storage Tanks and Refueling Water Storage Tanks. The peak of the 5/. damped HHE ground response spectra of .24g was used for these evaluations.

Equipment weight was either estimated using the drawing weight or the guidance given in Reference 19. Estimates of equipment fundamental frequency were also made during the course of estimating the seismic demand for some items. In general this estimate was very rough and could be made based on the experience of the SRT members. The judgments were made after the construction of the 22

uipment was examined d uring 'he walkdown. When more refined estimates e w of fundamental frequency were required, a calcul calculation was performed.

~

The primary source for cracked concrete considerations are con factor for all expansion b o itss use safety factors of 2.0 and 4.0 containe was used, because the SRT h a d knowledge t'he estima ing no contained-

'ad seismic capacity of the anchorage is Reference 19. The detai'1 s wi'th regard to anchorage allowable loads and

's aine - in this reference. The safety used in this evaluation was 3.0 instea oof thee i ed in Reference e 19. The new safety factor that 3.0 would be included in the updated version of the source reference.

The load path from the center of gravity, c.g., c. . of the equipment was analyzed (by judgment and/or ca 1 cu 1 a t ion ) to the anchorage and ultimately to the supporting structure. On Onl y sstructural ruc components that could either be seen or verified were relied upon for this is assessment.

s Anchorage components a ove foundation were seen and veri'fied ie , thee embedded or buried components were

'f' verifie using ng plant specific documentation (dr awin s).

). When drawings di no exist, ultrasonic tes

~ ~

t'as t ing was performed to determine anchorage a e leneng th or the equipmen t 1'tern was identified as an outlier.

~ ~

The supplemental references 20 too 23 were primarily used in performing evaluations of the capacities of potential weak links in the load pat h an d anchorage system, where Re ference 19 was primarily used for the anchorage i tsel'f.

An anchorage t'as ca 1 cu 1 a ion not performed for several equ'p i ment items. When the anchorage was obviously rugge d , SRT ju judgment was used to assess anchorage adequacy. Th'is gu d gm ent was performed in the 'contex t of the above criteria.

~ 0 4.2.4 Seismic Spatial Interaction Criteria A seismic spatial interac t'ssessment ion as was performed on each equipment item inc luded on the safe shutdown list. Thee following o seismic spatial interaction action issues were evaluated: I) heavy objects falling (sometim etimes referred to as

~ ~

23

ver I interactions), 2) heavy objects sliding, swinging, vibrating or tipping

{proximity interactions)) an d 3)) ina 'dequate e flexibility of lines to accommodate i

seismic-induced relative movements between utility support points. An assessment was ma d e as t o w h e ther a possible interaction existed, and if it did, could the interaction preclude the equipment item from performing it' safe shutdown function. Th ose innteractions identified as possibly precluding the equipment item s sa fe shutdown s u function were identified as outliers.

To perform the h in erac t'on ion assessment for the three above mentioned issues the guidance containe d in ecction ion 6 (Seismic Walkdown) of the draft SSRAP report p

" ' an Appen d'x ix I of the EPRI NP-604l seismic margins reportt' was used. Other sources for performing the evaluation was knowledge of the plant's d esign' asis'round response spectra, elevation of the potential interactions source, w h en avai va'lable the floor response spectra, and SRT judgment.

Reference 7 provi'd es a ver detailed discussion with regard to proximity and very II/I issues. Th e gui'd ance contained and methods described in this discussion i were used during i the walkdown for evaluating these issues. To evaluate the potential for an adverse consequence of differential support motion, the displacement at eac h en d o f th e 1'ne in question (air line, conduit etc.) was estimated. With this estimate the potential for the line pulling out or rupturing and this effect on the component being evaluated was made by t e SRT Attachments of lines to equipment items in the safe shutdown list were evaluated at least to the first anchor point of the line away from the equipment.

Plant specific documentation was relied on by the SRT during the interaction assessment. 'f For examp 1 e i a bl oc k wall was noted adjacent to the equipment, the SRT would either determine that documentation existed with regard to how the wall was rein orce d an d that a seismic evaluation had been performed per IE Bulletin SO-Il , or no t e on thee walkdown data sheets that the block wall

'f' evaluation should be veri ie by FPL. The SRT in any case did not check the details of the evaluations performed, and FPL was a rres p onsible for block wall adequacy.

24

n addition to the evaluation described above, ove the SRT sought examples of poor seismic housekeeping. unlatched Cases ooF un a c latches, unsecured drawers, c li i i hting, unsecured gas bottles, unanchored temporary equipment, and unsecu) ed ceilings and lights were to e no e on sheets.

4.3 EQUXPMENT NECESSARY TO ACH HXEVE AND NAXNTAXN HOT SHUTDOWN Table 4.3-1 corn lete is the complete walkdown wa own list is by system and function for Turkey Point Units 3 an d 4 'uding inc the location, elevation, an d hei eig ht aabove grade for each component.

'n The equipmen t list is gene}

g ated for Turkey Point Uni'ts 3 and 4 to achieve and maintain hot shutdown for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> o was based on the requirements s to:

o:

1. Supervise and control the power plant.

2. Remove decay heat.

34 rovi e emergency Provide e electrical power assum' a loss-of-offsite power.

4. Provide for chemistry and volume control.

5 Provide a heat sink for the reactor auxiliaries.

Su p ervisory an d con t ro 1 functions included vertical panel els "B" and the sequencer panels. Items 49, 50 51, 52, 55 and 56 in Table 4.3-1 of the 9 50, walkdown list reviewe d th'rtion is po of the shutdown requirementt which w ic is housed in the main control building or the 4160V Bus Rooms.

Decay heat removal is accompl'ished b the auxiliary feedwater to the steam geneerators. . The n auxi'1'eedwater ry sary system was previously reviewe or seismic a d eq uacy as part of Generic Letter 81-14nd was therefore exempt from further review. Thee Condensate on en 'ewed on the Storage Tanks were reviewe walkdown as items 12 an d 13 . Thee Condensate Storage Tanks provi ovidee the water source for the Auxiliary Feedwater Pumps.

90c1585B Tab4.3-1 TABLE 4. 3-1 Equipment Walkdown Component List ITEN 0 COMPONENT DESCRIPTION BUILDING/LOC ELEV ELEV ABOVE GRADE Su ervisory and Control E ui ment:

49. 3C23A Se uencer 3A LC-SWGR Pl

50. 3C23B Se uencer 38 LC-SMGR 0'l

51. 4C23A Se uencer 4A LC-SMGR 18'8'8'2'2I

52. 4C23B Se uencer 4B LC-SWGR pl

55. 3C05, 3C06, Vertical Control Panel 3B

56. 4C05, 4C06 Vertical Control 24'4'ecay Panel 4B Heat Removal E ui ment:

12. Unit 3 Condensate Stora e Tank Outdoors, Adjacent EDG 18'8'l

13. Unit 4 Condensate Outdoors, S.W. Pl Stora e Tank of RCB Electrical E B

ui ment:

Diesel Oil Transfer Pum Outdoors, Adjacent EOG 18'l

10. Diesel Oil Storage Outdoors, Tank Adjacent EDG

16. B EDG Day Tank EDG 18'4'8'8'6'f

19. Emergency Diesel EDG Generator Skid

20. EDG Air Start EOG Pl

21. B Tanks EOG Fan Assemblies EDG 18'l

22. 4C12 EDG Panel Local Control B

EDG 18'8'l 3B06 480V Motor Control Control pl Center 3B 26

TABLE 4.3-1 Equipment Walkdown Component List ITEN 0 COMPONENT DESCRIPTION BUILDING/LOC ELEV ELEV ABOVE GRADE

24. 4806 480V Motor Center 48 Control Control 18'8'l

25. 808 480V Motor Control Ol Center D

26. 3AB 4.16V Switchgear LC - SMGR 38 is'0'

27. 4AB 4.16 V Switchgear LC - SWGR 48

28. 3802 480V HVPDS Load LC - SMGR Center 38

( Incl udes i2'2l Transformer

29. 3804 480V HVPDS Load LC-SMGR Center 3D

( Incl udes Transformer

30. 4802 480V HVPDS Load LC-SWGR Center 48

(Includes Transformer 30'0'0'0'0'0'2'0'22I

31. 4804 480V HVPDS Load LC-SWGR Center 4D (Includes Transformer

32. 3811 480V Load Center LC - SWGR PZR Heater

33. 4811 480V Load Center LC - SWGR PZR Heater

34. 3D25 Batter Char er 38 Control

35. 4D25 Battery Char er 4A Control i2'4'4'4'2'4'7

36. D26 Battery Char er 4S Control

37. 3D03 Batter Rack 3A Control

38. 3D24 Battery Rack 38 'Control

0 TABLE 4.3-1 Equipment Mal kdown Component List ITEM 8 COMPONENT DESCRIPTION BUILDING/LOC ELEV ELEV ABOVE GRADE

39. 3D03 Batter Rack 4B Control

40. 4D24 Battery Rack 4A Control

41. 3DOl Distribution Control Panels Bus

42. 3D23 Di str ibuti on Control 30'2'0'0'0'0'2/

Panels Bus

43. 4DOl Distribution Control Panels Bus 24'2'2'2'4'4'4'/

44. 4D23 Distribution Control Panels Bus

45. 3Y05 Inverter 3C Control 42's'2/

46. 3Y07 Inverter 3D Control 42/

47. 4Y05 Inverter 4C Control 42/

48. 4Y07 Inverter 4D Control

57. B Diesel Generator EDG Exciter Cabinet Chemical and Volume Control E ui ment:

2. 3B Char in Pum

3. 4B Char in Pum

8. 3B Bor ic Acid is'8'8's'7/

P/

Transfer Pum

9. 4B Boric Acid P/

Transfer Pum B Boric Acid Storage 9/

14. Unit 3 Tank ReFueling Water Outdoors 18'8'/

Stora e Tank 0'/

15. Unit 4 Refueling Water Outdoors Storage Tank 28

TABLE 4. 3-1 Equipment Malkdown Component List ITEM 0 COMPONENT DESCRIPTION BUILDING/LOC EL EV ELEV ABOVE GRADE Heat Removal E ui ment:

4, 3B Component Cooling RAB is!

Water Pum

5. 4B Component Cooling Water Pum

6. 38 Intake Cooling Intake Struct. is's'8'1l Mater Pum

7. 48 Intake Cooling Intake Struct.

Water Pum

17. Unit 3 Component Cooling Mater Sur e Tank 0'3'3'3.

18. Unit 4 Component Cooling Water Sur e Tank 38 CCW Heat exchan er RAB Ol

54. 4B CCW Heat Exchanger RAB Ol 29

T he electrical power requirements for obtaining hot shutdown included the assumption that the switchyard would be out-of-service placing Units 3 and 4 in a loss-of-offsite-power condition which is covered by existing procedures.

In addition, the pressurizer heaters were included to maintain sub-cooling of the Reactor Coolant System (RCS). Items 1, 10, 16 and 19 through 48 and 57 of the walkdown list addresses the electrical requirements for achieving hot shutdown without offsite power.

Chemistry and volume control to achieve hot shutdown adds equipment necessary to charge the RCS with a boric acid solution to meet hot shutdown reactivity requirements. A charging pump with suction from the Refueling Water Storage Tank will meet the volume change requirements. One train of boric acid solution addition capability was added to achieve the reactivity change requirements. The chemistry and volume control equipment walkdown items 2, 3, 8, 9, ll, 14 and 15 address this requirement.

Reactor auxiliary components and heat exchangers require cooling water to maintain the functionality of this equipment for items like seal cooling, lube oil i cooling and heat removal. This requires one train of component cooling water and intake cooling water for each unit to be operable. These are items 4 through 7, 17, 18, 53 and 54 of the walkdown list.

4.4 OPERATING PROCEDURES NECESSARY TO ACHIEVE AND MAINTAIN HOT SHUTDOWN A review of operating procedures for Turkey Point Units 3 and 4 was performed to verify the equipment list and to identify any additional Equipment which might be required to bring the reactor from 1001 power to hot shutdown. The design basis earthquake is not expected to trip the reactor so equipment to reduce power was also reviewed. Operating procedures to shut down the reactor, take the reactor to hot shutdown, reactor trip response and 1oss of offsite power were reviewed. This review identified that the non-safety pressurizer heaters would be required to maintain sub-cooling during the i

period. To cope with the loss of offsite power, the Emergency Diesel 30

nerators would be required. S' auxiliary equipment wou Generator Exciter

'ew h t Since tne ~rain '8" was selected as the success pa th for obtaining hot shutdown, thee "B" Emergency Diesel Generator andd iitss included in the program. A review of the would bee inc e ui P ment list for th e "8" Emergency Diesel Generator indicate

't indicated that citer Cabinet would nee d t o b e a dded to the walkdown component a thee list. The function of the exciter cabinet is to use tthee 125V DC battery power supply to energize er ize and con ro thee generator field for the Emergency Diesel control Generator. All other components necessary to brin bring thee Unit ni 3 and 4 reactors to hot shutdown have been included.

4.S SEISMIC REVIEW TEAM Theree was su s an ia benefit with regard to walkdown q ualit derived from substantial using wa lkdowno team members who included Drs. J.D. . . Stevenson, e R. P. Kennedy and J.M. Ree d . Their ei resumes are included as part o, of thisi p rocedure. The foregoing team members are i n timatelyima e familiar with seismic walkdown criteria

~ ~ ~ ~ ~

' 'ewed thee source references for this techno010ogy.

~

having a either authored or reviewe

~

Four FPL engineers with mechanical, civil 1 an o p crating ba ckg rounds complete d and

'ers rovided the operating, construction and maintenance details which were use y the SRT used by in their evaluation, The engineers reviewe d thee operating procedures and the Appendix endix "R" Safe a e Shutdown list to develop the equipment 1 is for t or the walkdown. Corrective actions~ ~

identified by the SRT were discussed with these engineers which in turn the corrective actions in o FPL's co} rective action system for enteredd th nd dis osition. Using this process, thee FPL engineers accepted responsi 'b'1'ty i i for the corrective actions. An aadditional i iona benefit derived from this process was t h a t th e FPL engineers gained seismic desi desig n knowledge from the SRT experts.

4.6 MALKOOWN PREPARATION walkdown list of Prior to the walkdown, FPL licensing icen prepared the complete wal equipment to be reviewed by thee SRT. A one day pre-walkdown of the p lant a was 31

erformed, where a video tape was made of the equipment and anchorages. The pre-walkdown aidedi in determining what information and assistance would be required during i the walkdown. A pre-walkdown meeting was held prior to the walkdown with the SRT and cognizant FPL staff. The logistics of the walkdown, and the documentation required for the walkdown were discussed in addition to reviewing the pre-walkdown video tapes.

FPL engineering gathered generic and equipment specific documentation, that was available for review by the SRT during the walkdown. This documentation included the following:

1) Definition of the plant ground response spectra.

2) Seismic design basis for buildings and equipment as defined in the FSAR (damping and stress limits).

3) Site soil conditions

~ ~ ~

and grade elevation.

4) Floor response spectra. ~

5) Drawings showing standard details for anchorages, and foundation drawings.

6) Equipment drawings.

Equipment specific documentation were placed in an individual file folder for each equipment item. Generic documentation (floor response spectra, standard anchorages, etc.) was gathered and available for use during the walkdown.

Part A, Equipment Description, were filled out on Equipment Data Sheets for each equipment item on the equipment list. Computer sketches of each equipment item including type and description of anchorage were also developed. The final complete data .sheets and sketches are included in

~

Appendix C. ~

32

.7 SGREENING MALKDOMN 4.7.1 Overall Walkdown Conduct Each morning of the wal kd own, th e SRT reviewed the equipment included in that

k. Anchorage and foundation drawings were reviewed as required. The equipment data sheets and computer sketches were taken into the ie y e SRT. The equipment data sheets were filled out as much as possible in the t'ade field with notes and correc ions ma e as required to the -computer sketches.

f There was also a video tape ma d e o the walkdown, that included SRT immediate observations.

'd-d an d a t the end of each day the SRT would confer with the Normally, at mid-day cognizant FPL engineer o f wh a t additional information would be helpful, or lt th support engineering about calculations t o be p erformed. At the end of each day, the data sheets where a final judgment could be maadee wi with regard to seismic adequacy, were put in final form and signeed by thee SRT. The i

calculations performed were also attached to the data sheets. Appendix C f'

include the fina signe wa' walkdown sheets and computer sketches for each equipment item. Th e ca 1 c ulations in Appendix C were developed from the computations done the wee k o f th e w alkdown 'l however,'hey were performed again after the walkdown an d pu t in o the FPL guality Program Format at the request of FPL.

4.7.2 Walkdown Results The overall walkdown results are included on the Summary Data Sheets in Appendix B. The summary sheets, are a condensed version of the Equipment Data Sheets contained in Appendix C. Photographs of components included in the walkdown are in Appendix E.

4.7.2.1 Outlier Identification The walkdown resu 1 te d in'he e identification i of thirty-five outlier equipment 33

5 0

~

items. A broad definition for outlier

~ ~

was used in this evaluation. Every concern or recommendation to improve the seismic

~

equipment item where a capacity of the equipment item was made by the SRT was noted as an outlier.

~

This way each issue noted in the walkdown could be tracked until final resolution. The identified outliers, the reason for the outlier and the proposed resolution of the outlier recommended by the SRT are given in Table 5.0.

FPL prudently inspected the anchorage of the similar equipment items in the other plant trains, where anchorage concerns were identified. This resulted in the upgrade of several additional anchorages in the plants.

4.7.2.2 Equipment Anchorage

.The equipment included in the Turkey Point Units 3 and 4 walkdown may be put in three major categories; pumps and rotating equipment, tanks and heat exchangers, and electrical equipment. The pumps and rotating equipment included robust anchorage consisting of cast in place bolts, embedded deep in their foundations. The anchorage for the majority of this equipment were judged acceptable without additional calculations after a review of the foundations drawings and the walkdown inspection.

Using the beyond design basis criteria in A-40 (13), high confidence low probability of failure (HCLPF) calculations were performed for Item 10, the Diesel Oil Storage Tank, Items 12 and 13, the Condensate Storage Tanks, and Items 14 and 15, the Refueling Mater Storage Tanks. The bolt chair capacity limited the HCLPF calculated capacity of the tanks. Nodifying the bolt chairs provided a limiting HCLPF, based on anchor bolt bonding of 0. llg for the Condensate Storage Tanks and the Refueling Mater Storage Tanks. Modifying the bolt chairs on the Diesel Oil Storage Tank provided a limiting HCLPF of 0.207g based on the overturning moment. The Component Cooling Water Surge Tank platforms and Boric Acid Storage Tank platforms could not be screened by the SRT during the walkdown and were referred to FPL for resolution.

34

he anchorage of electrical equipment included in the walkdown was not i

niform, as typical for this type equipment in Nuclear Power facilities of Turkey Point Units i 3 and 4 vintage. This is due to the installation of this equipment by several different vendors with different anchorage schemes.

Electrical equipment anchorage ranged from newly installed expansion anchors, and fillet welds to embedded angle to seal welds and no anchorage at all. When the anchorage was suspect, the SRT either designated the equipment item an outlier or recommended a fix.

When the SRT had a doubt about the anchorage capacity, a calculation was performed. In some instances, the SRT reviewed existing anchorage calculations to judge the anchorage acceptable.

4.7.2,3 Seismic Spatial Interaction Section 4.2.4 discusses the interaction evaluations performed during the Turkey Point Units i 3 and 4 walkdown. There were interaction concerns noted by the walkdown team on equipment items as indicated on the Equipment Data Sheets contained in Appendix C. Outliers were identified because of glass sight tubes for Items 16 and 19, the EDG Day Tank and the Emergency Diesel Generator skid. There was an additional concerns identified for FPL to reconcile with regard to the fossil unit stacks. It was also recommended that FPL should verify that the block wall adjacent to the Items 37 to 40 have been evaluated in the IE Bulletin 80-11 program, that the metal egg crate ceiling should be clipped in, and the lights above the batteries should have tie wires added.

There were instances where overhead cranes were noted adjacent to equipment items. In these cases it was verified that during operation the cranes are parked away from the equipment.

As discussed in Section 4.2.4 the SRT sought examples of poor seismic housekeeping. The plant for the most par t was free from housekeeping seismic interaction concerns. There was a concerted effort to secure fans, miscellaneous gages and gas bottles, These housekeeping seismic supports were overdesigned for their function.

35

4.7.2.4 Other Concerns Section 4.2.2 discusses equipment construction adequacy and identification of potentially vulnerable details during the Turkey Point Units 3 and 4 Walkdown.

Examples of these details resulting in outliers are as indicated in the Appendix C documentation. It is noted for Items 6 and 7 that the pump shaft length and cast iron fittings for the Intake Cooling Water Pumps should be evaluated. Spacers are recommended to be added on the east ends of the Battery Racks (Items 37 to 40).

5.0 RESOLUTXON OF CONCERNS FPL addressed all outlier issues listed and the actions taken are listed in Table 5.0. In many cases, FPL engineering generated Plant Change/Modification (PC/M) Packages which provided for physical modification to plant equipment resulting in additional seismic "hardening" of the equipment. These PC/M packages are available in FPL's Juno Beach offices should the NRC desire to review them.

Operability evaluations were performed by FPL and none of the concerns identified as a result of the walkdown were determined as potential unit operability concerns.

6.0 INDEPENDENT PEER REVlEM Dr. Paul Smith of the Readiness Operation performed the peer review of the USI A-46 evaluation at Turkey Point Units 3 and 4. The review included a detailed review of the draft report, a visit to the plant site to conduct a sample walkdown and a review of the documentation. Dr. Smith concluded that there were no significant deficiencies in the A-46 review effort that was performed on Turkey Points Units 3 and 4. Dr. Smith's review is included as Appendix D.

36

90cl585a Table5.0-1 TABLE 5.0 OUTLIER ISSUES AHD RESOLUTIONS TURKEY POINT UNITS 3 AND 4 ITEH I.D. E UIPHEHT DESCRIPTIOH OUTLIER ISSUES SRT RECOHHEHDED RESOLUTIOH ACTION TAKER

6. Intake Cooling Mater Pump 1) Pump shaft length longer than can be 1) Evaluate Shaft for adequate 1) TBA screened by SSRAP report. length and clearances.

2) Cast iron fittings on pump. 2) Check stresses on fittings from

3) Anchorage needs verification. loads of attached piping.

4) Interaction Fossil Unit Stack may 3) Verify anchorage with fai l. calculat ion.

4) Check adequacy of fossil stack.

7. 4B Intake Cooling Mater Pump 1) Pump length longer than can be 1) Evaluate Shaft for adequate 1) TBA screened by SSRAP report. length and clearances.

2) Cast iron fittings on pump. 2) Check stresses on fittings from

3) Anchorage needs verification. loads of attached piping.

4) Interaction'ossil Unit Stack may 3) Verify anchorage with fail. calculation.

4) Check adequacy of fossil stack.

10. H/A Diesel Oil Storage Tank 1) Anchorage adequacy. 1) Replace chair plates with 1) Chair Plates upgraded per PCH 91-

2) Interaction-fossil unit stack may 1 I/4" thick plates and 169.

fail. evaluate further . 2) Fossil Stack adequate per FPL

2) Check adequacy of fossil stack. Safety Evaluation,TBA.

Boric Acid Storage Tank 1) Platform adequacy for torsional Check platform adequacy for 1) Platform upgraded per PCHS90-440 loads. torsion, and upgrade if and 90-441.

require.

12. Unit 3 Condensate Storage 1) Anchorage adequacy. Replace chair plates with I) Chair Plates upgraded per PCH 91-Tank I'R/4" thick plates, and 170.

evaluate further.

13. Unit 4 Condensate Storage 1) Anchorage adequacy. Replace chair plates with )) Chair Plates upgraded per PCH 91-Tank 13/4" thick plates, and 171.

evaluate further .

14. Unit 3 Refueling Mater 1) Anchorage adequacy. Replace chair plates with 1) Chair Plates upgraded per PCH 91-Storage Tank I S/4" thick plates, and 172.

evaluate further 37

TABLE 5.0 OUTLIER ISSUES AND RESOLUTIONS TURKEY POINT UNITS 3 AND 4 ITEN I.D. E UIPNENT DESCRIPTION OUTLIER ISSUES SRT RECONHENDED RESOLUTION ACTION TAKEN Unit 4 Refueling Mater 1) Anchorage adequacy. 1) Replace chair plates with 1) Chair Plates upgraded per PCH 91-Storage Tank I'R/4" thick plates, and 173.

evaluate further.

16. EOG Oay Tank )) Glass sight tube. 1) Replace glass sight tube with 1) TBA non-breakable material.

17. Unit 3 Component Cooling 1) Platform adequacy. 1) Check platform adequacy, and 1) Platform to be upgraded per PCH Mater Surge Tank upgrade if required.90-471.

18. Unit 4 Component Cooling 1) Platform adequacy. 1) Check platform adequacy, and 1) Platform to be upgraded per PCH Mater Surge Tank upgrade if required.90-472.

19. Emergency Diesel Generator 1) Glass sight tube. 1) Replace glass sight tube with 1) TBA Skid non-breakable material.

20. EOG Air Start Tanks 1) Seismic interaction - threaded pipe 1) Complete plant work'order (PMO) 1) Air supply and supports replaced for air supply not rigidly supported. already written for the per PCHs86-155 and 86-190.

support.

3806 480V Hotor Control Center 1) Seal welded anchorage. inadequate in 1) Upgrade anchorage. 1) Anchorage upgraded per PCH 91-178.

38 tension.

4806 480V Hotor Control Center 1) No anchorage. 1) Add anchorage. 1) Anchorage upgraded per PCH 91-179.

48

25. 808 480V Hotor Control Center D 1) Inadequate anchorage for overturning. 1) Brace top of HCC to concrete 1) Anchorage upgraded per PCH 91-178.

wal'I.

26. 4.16kv Switchgear 3B 1) No anchorage. 1) Add anchorage. 1) Anchorage upgraded per PCH 91-174.

38

TABLE 5.0 OUTLIER ISSUES AND RESOLUTIOHS TURKEY POINT UNITS 3 AND 4 ITEM I.D. E UIPMENT DESCRIPTION OUTLIER ISSUES SRT RECONNEHDEO RESOLUTIOH ACTION TAKEN

27. 4AB 4.16kv Switchgear 4B 1) No anchorage. 1) Add anchorage. 1) Anchorage upgraded per PCM 91-175.

3802 480V NPDS Load Center 38 1) Cannot determine anchorage. 1) Add anchorage. 1) Hew load center installed per PCH (Includes Transformer)89-532 and new anchorage installed per PCM 91-176.

29. 3B04 480V HVPDS Load Center 3D 1) Cannot determine anchorage. 1) Verify anchorage and upgrade if 1) Hew load center installed per PCM (Includes Transformer) required.89-532 and new anchorage installed per PCM 91-176.

30. 4802 480V HVPDS Load Center 48 1) Ho anchorage. 1) Add anchorage. 1) New load center installed per PCH (Includes Tr ansformer)89-533 and new anchorage installed per PCM 91-177.

31. 4804 480V MVPDS Load Center 4D 1) Ho anchorage. 1) Add anchorage. 1) Hew load cente~ installed per PCH (Includes Transformer)89-533 and new anchorage installed per PCM 91-177.

')

37. 3D03 Battery Rack 3A 1) Ho spacers on east end of battery 1) Add spacers on east end of 1) Spacers added per FPL letters JPH-rack. battery rack. PTH-92-5261 and 5707.

2) Shade on lights may fail and fall on 2) Add tie wire to lights. 2) Tie wires added per PCH 91-182.

batteries. 3) Ver ify block wall included in 3) FPL verified wall included in IE

3) Block walls not evaluated by SRT. FPL IE 80-11 program. 80-11 program as block walls C30-

1. C30-2, C30-4.

38. 3D24 Battery Rack 38 Ho spacers on east end of battery 1) Add spacers on east end of 1) Spacers added per FPL letters JPH-rack. battery rack. PTH-92-5261 and 5707.

2) Shade on 'lights may fail and fall on 2) Add tie wire to lights. 2) Tfe wires added per PCH 91-182.

batteries. 3) Verify block wall included in 3) FPL verif ied wall included in IE

3) Block walls not evaluated by SRT. FPL IE 80-11 program. 80-11 program as block walls A42-

2. C42-16, C42-17, C42-18.

39

TABLE 5.0 OUTLIER ISSUES AHD RESOLUTIOHS TURKEY POINT UNITS 3 AND 4 ITEH I.D. E UIPHEHT OESCRIPTIOH OUTLIER ISSUES SRT RECOHNEHDEO RESOLIJTIOH ACTION TAKEN

39. 4003 Battery Rack 48 1) Ho spacers on east end of battery 1) Add spacers on east end of 1) Spacers added per FPL letters JPN-rack. battery rack. PTH-92-5261 and 5707.

2) Shade on lights may fail and fall on 2) Add tie wire to lights. 2) Tie wires added per PCH 91-183.

batteries. 3) Verify block wall included in 3) FPL verified wall included in IE

3) Block walls not evaluated by SRT. FPL IE 80-1) program. 80-11 program as block walls C30-

2. C30-3. C30-4.

40. 4024 Battery Rack 4A 1) Ho spacers on east end of battery 1) Add spacers on east end of 1) Spacers added per FPL letters JPH-rack. battery rack. PTN-92-5261 and 5707.

2) Shade on lights may fail and fall on 2) Add tie wire to lights. 2) Tte wires added per PCH 91-183.

batteries. 3) Verify block wall included in 3) FPL verified wall included in IE

3) Block walls not evaluated by SRT. FPL IE 80-11 program. 80-11 program as block walls A42-2, C42-15. C42-16, C42-18.

41. 3D01 Distr ibut ion Panels/Bus 1) One loose anchor bolt. 1) Tighten loose bolt. I) Bolt disposition per PRO 93-010843.

43. 4D01 Distr ibut ion Panels/Bus 1) Three loose anchor bolts. 1) Tighten loose bolts. 1) Bolt disposition per PMD 93-010844.,

50. 3C238 Sequencer 38 1) Additional top bracket as found for 1) Add top bracket as found for I) Bracket added per PCH 91-180.

sequencer 3A (Item 49) would provide sequencer 3A (Item 49).

added assurance and strength. This item had only one bracket.

51. 4C23A Sequencer 4A 1) Additional top brackets as found for 1) Add two top brackets as found I) Bracket added per PCH 91-18).

sequencer 3A (Item 49) would provide for sequencer 3A (Item 49).

added assurance and strength. This item had no brackets.

52. 4C238 Sequencer 48 1) Additional top brackets as found for 1) Add two top brackets as found 1) Bracket added per PCH 91-181.

sequencer 3A (Item 49) would provide for sequencer 3A (Item 49).

added assurance and strength. This item had no brackets.

40

TABLE 5.0 OUTLIER ISSUES AND RESOLUTIOHS TURKEY POINT UNITS 3 AND 4 ITEN I.D. E UIPMENT DESCRIPTION OUTLIER ISSUES SRT RECONNENDED RESOLUTION ACTIOH TAKEN 3B CCM Heat Exchanger 1) SRT could not verify reinforcement 1) Verify adequacy of pedestal 1) FPL verified pedestal adequacy by steel design of pedestal. design. calculations C-SJSll-01 and 02.

54. 4B CCM Heat Exchanger 1) SRT could not verify reinforcement 1) Verify adequacy of pedestal 1) FPL verified pedestal adequacy by steel design of pedestal. design. similarity with Item 53.

55. 3C05, Vertical Panel 3B 1) Interaction metal egg crate ceiling 1) Clip in metal egg crate 1) TBA 3C06 may fall on operators. sect tons of ceiling.

56. 4C05, Vertical Panel 48 1) Interaction metal egg crate ceiling 1) Clip in metal egg crate 1) TBA 4COB may fall on operators. sections of ceiling.

.0 CONCLUSXONS AND RESULTS FPL t developedd an d imp emen e d a plant specific program to satisfy requirements of GL87-02/USI A-46 as agreed between FPL and the VSNRC. The program consisted of developing a walkdown procedure, contained in Appendix A, that concentrated on anchorage concerns o USI-A46'he seismic spatial interaction ncerns of concerns of USI-A17 and the design concerns for large tanks in USI-A40. The program was developed by FPL to be appropriate and cost effective for addressing GL8 -

L87-02 ms at its low seismic sites. The basic requirement concerns for the walkdown is that the equipment will be able to withstand the design basis SSE at the plant and still provide its safe shutdown function. The procedure used was not overly prescriptive but relied on the judgment of an

~

expert team to meet the basic requirement.

A success f pathh o equipmen using i safety and non-safety equipment was selected for achieving and maintaining hot shutdown of the plant for a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The final equipment list is included in Appendix S.

Documentation for the walkdown was gathered by FPL, and was i available during the walkdown. Equipment specific documentation was placed in individual file folders for each equipment item. Generic documentation (floor response

~

spectra anc spectra, orage details, etc.)

anchorage was available for review during the walkdown.

Equipment Data Sheets for each equipment item on the equipment list were developed and completed during the walkdown. The data sheets consisted of t'

general descrip ions o th e equipment and walkdown observations. Computer sketches of each equipment item including type and description of anchorage f'

were also develope d . Th e ina complete data sheets and sketches are included in Appendix C. Photographs of equipment included in the review are in Appendix E. There was also a video tape made of the walkdown, that included SRT immediate observations.

he overall walkdown results are included on the Summary Data Sheets in ppendix B. The Summary Data Sheets, are a condensed version of the Equipment Data Sheets contained in Appendix C.

The walkdown resulted in the identification of thirty-five outlier equipment items with the majority of the outliers being. lack of anchorage for electrical cabinets which were not previously required to be anchored and were shaker table tested prior to installation. The outliers identified are summarized in Table 4.7.1.

FPL prudently inspected the anchorage of the similar equipment items in the other plant trains, where anchorage concerns were identified.

A peer review was performed of the walkdown report including a sample walkdown. The peer review report is included as Appendix D.

8.0 REFERENCES

, FPL Letter L-88-333, "Verification of Seismic Adequacy of Mechanical Electrical Equipment in Operating Plant," Letter to USNRC, Aug. 4, and 1988.

2. FPL Letter L-89-441, "Unresolved Safety Issue A-46, Generic Letter 87-02," Letter to USNRC, December 12, 1989.

3. Generic Letter 87-02, "Verification of Seismic Adequacy of Mechanical and Electrical equipment in Operating Reactors, Unresolved Safety Issue

{USI) A-46," U.S. Nuclear Regulatory Commission, Washington, D.C.,

February 19, 1987.

EBASCO Report, "Probabilistic Seismic Hazard Evaluation and Uniform Hazard Spectra, St. Lucie and Turkey Point Nuclear Power Plant Sites,"

repared by EBASCO Services Inc. For FPL, December 1989.

prepare 43

CRAC2 Computer Code, "Calculation of Reactor Accident Consequences,"

Version 2.

6. NUREG-1211, "Regulatory Analysis for Resolution of Unresolved Safety Issue A-46, Seismic gualification of Equipment in Operating Plants,"

U.S. Nuclear Regulatory Commission, Washington, D.C., February 1987.

7. EPRI NP-6041, "A Hethodology for Assessment of Nuclear Power Plant Seismic Hargin," NTS Engineering et. al., October 1988.

8. "Final Safety Analysis Report," (FSAR) Volumes I, II, III, IV and V, Turkey Point Units 3 and 4, Rev. 5, 7/87.

9 NUREG/CR-5250, "Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Hountains," Lawrence Livermore National Laboratory, Prepared for USNRC, January 1989.

K

10. U.S. Department of Commerce Environmental Science Services Administration Coast and Geodetic Survey, "Report on the Seismicity of the Turkey Point, Florida Area," From: James C. Tison Jr., To: Hr.

Harold L. Price {USAEC), 12/6/66.

11. Bechtel Inter-office Hemorandum,

Subject:

Florida Power & Light Company Turkey Point, Units 83 & 04, Bechtel Job S610, From R.K. Stade to

{Vendor), April 8, 1968.

12. United States Atomic Energy Commission, TID-7024, "Nuclear Reactors and Earthquakes," August 1963.

13. NUREG/CR-3480, "Value/Impact Assessment for Seismic Design Criteria USI A-40," Lawrence Livermore National Laboratory, August 1984.

K

14. Letter to G. Lear (USAEC) from R.E. Uhrig (FPL), "Failure of Non-Seismic Equipment," January 7, 1975.

5. I E Bulletin 80-11, "Masonry Wall Design," U.S. Nuclear Regulatory Commission, Washington, D.C , 1980

16. Letter to S.G. Brain (FPL) from G.T. Nutwell (Bechtel), RE: Block Wall Evaluation and Repair Program, March 16, 1984.

17. NUREG/CR-"4826, "Seismic Margin Review of the Maine Yankee Atomic Power Station," Lawrence Livermore National Laboratory, March 1987.

18. SSRAP Report, "Use of Seismic Experience Data to Show Ruggedness of Equipment in Nuclear Power Plants," Senior Seismic Review and Advisory Panel, January 17, 1990, Draft.

19. EPRI NP-5228, "Seismic Verification of Nuclear Plant Anchorage, Volume 1: Development of Anchorage Guidelines; Vol. 2: Anchorage Inspection Workbook, URS Corp./John A. Blume 5 Assoc., Prepared for Electric Power Research Institute, Palo Alto, CA, May 1987.

. American Concrete Institute (ACI), ACI 349-85 Appendix Embedments, September 1, 1985.

B - Steel

21. Holmes and Martin, Analysis and Design of Structural Connections For Reinforced Concrete 5. Steel," 1983 Edition.

22. AISC, "Manual of Steel Construction Allowable Stress Design, Ninth Edition," 1989.

23. Moy, Stuart, "Plastic Hethods for Steel and Concrete Structures,"

198).

24. Generic Letter 81-14, "Seismic gualification of Auxiliary Feedwater Systems," U.S. Nuclear Regulatory Commission, Washington, D.C., February 10, 1981.

90cl5858 Appendice APPENDIX B Safe Shutdown Summary Data Sheets

90C1585b/SUH-SHT.3%4 TURKEY POINT UNITS SUHHARY DATA SHEET 3 I4 tern ~O. ui ment Oescri tion Bldq, Approx.

gl ev.

Approx.

Height Anchor-age

'asis for Anchorage Seismic Inter-Status Remarks Above ~de~~uac Asse~s- action Grade* ment j(dequuac

~

6 10 Diesel Oil Transfer Pump Outdoors (Adjacent EOG 18'8'l

2. 3B Charging Pump pl R/J

3. 48 Charging Pump 18.

3B Component Cooling Ol Water Pum

5. 4B Component Cooling Ol Water Pum 18'8'8'Hotor

6. 38 Intake Cooling Water Intake pl C/J I) Check Pump Length.

Pump Structure 2) Check Cast Iron Fittings.

Deepwell 3 FPL should verify anchorage Pump) with calculation.

4) Confirm Fossil Stack Ade uac .

TURKEY POINT UNITS 3 K 4 SUHHARY DATA SHEET-. Cont.

ui ment Des r tio ~Bld . Approx. Approx. Anchor- Basis for Seismic Status Remarks

~1ev. Height age Anchorage Inter-Above Pde~~uac Assess- action

~

'rade*

ment Ade uac 4B Intake Cooling Mater Intake C/J 1) Check Pump Length.

18'Motor Pump Structure 2) Check Cast Iron Fittings.

Deepwell 3) FPL should verify anchorage Pump) with calculation.

4) Confirm Fossil Stack Ade uac .

3B Boric Acid Transfer Ol R/J Pum 4B Boric Acid Transfer Ot Pum N/A Diesel Oil Storage Outdoors Ol 1) Replace Chair Plates with 1-Tank (Adjacent 18'8'8'7'8'8'/ 1/4" thick Plates. Mill EDG) increase HCLPF to 0.20g.

2 Check Fossil Stacks.

Boric Acid Storage gl 1) FPL should check platform for Tank torsion.

Unit 3 Condensate Outdoors Ol 1) Replace Chair Plates with 1-Storage Tank (Adjacent I/O" thick plates. Mill EOG) increase HCLPF for tank to

.11 .

Unit 4 Condensate. Outdoors Ol 1) Replace Chair Plates with 1-Storage Tank (S.M. of 1/4'hick plates. Mill RCB) increase HCLPF for tank to

.11 .

TURKEY PPIHT UNITS 3 K 4

SUMMARY

DATA SHEET Cont.

J.O E ui men esc i ti ~Bid . Approx. Approx. Anchor- 'asis for Seismic ~ttatu Remarks

~lv. Height age Anchorage Intet -,

Above jiveu~ac Asse~s- action

~

Grade* ment Ade uac

14. Unit 3 Refueling Outdoors I) Replace Chair Plates with 1-34'6')

Water Storage Tank l-l/4" thick plates. Mill

15. Unit 4 Refueling 18'l 18'utdoors pl 1) increase

.11 .

HCLPF for tank to Replace Chair Plates with 1-Mater Storage Tank 1/4" thick plates. Mill increase HCLPF for tank to

.11 .

16. EOG Oay Tank ~

EOG Glass Site Tube.

17. Unit 3 Component I ** 1) FPL should check platform Cooling Mater Surge adequacy.

Tank

18. Unit 4 Component Cooling Mater Surge 71'1'8'8'353<*+ 1) FPL should check platform adequacy.

Tank

19. Emergency Diesel EDG pt 1) Glass Site Tube Generator Skid

20. EOG Air Start Tanks EDG pl )) Air supply threaded pipe to be fixed by PWP.

21. EOG Fan Assemblies EOG 18'8'l

22. 4C12 EDG Local Control EDG 0' Panel 8

TURKEY POINT UNITS 3 h 4

SUMMARY

DATA SHEET Cont.

~te J D ui me t Descr tio Approx. Basis for Seismic Status emar s Qev. Height age Anchorage Inter-Asse~s- action 18'pprox.

0'nchor-Above Grade*

f1~de u~ac ment de uac

23. 3B06 480V Motor Control Control Ol 1) Seal welded anchorage, needs Center 3B to u raded.

18'ontrol

24. 4B06 480V Moto< Control Ol 1) No anchorage.

'/J Center 4B

25. 808 480V Motor Control Ol 1) Brace top of MCC to concrete Center D 18'8'C-Swgr wall.

26. 3AB 4.16kv Switchgear 38 1) No anchorage.

27. 4AB 4.16kv Switchgear 4B LC-Swgr 18'l 1) No anchorage.

28. 3B02 480 HYPOS Load Center LC-Swgr Cannot determine anchorage.

3B (Includes Transformer 30'C-SMGR 2) ll'o 8'lock wall included in IE 80-ram.

29. 3B04 480V HVPDS Load 1) Cannot determine anchorage.

30'2'2'2'2'2')

Center 3D (Includes 2) Block wall included in IE 80-Transformer 30'C-Swgr 11 ro ram.

30. 4B02 480V HVPDS Load 1) No anchorage.

Center 4B (Includes 2) Block wall included in IE 80-Transformer 30'C-Swgr ll ro ram.

31. 4B04 480V HVPDS Load 1) Cannot determine anchorage.

Center 4D (Includes 2) Block wall included in IE 80-Transformer 30'C-Swgr 11 ro ram.

32. 3811 480V Load Center (PZR Htr.

TURKEY POINT UNITS 3 K 4 SUMHARY DATA SHEET Cont.

boite ui men Desc o /lid Approx. Basis for Seismic ~Stat s Remarks Elev'. Height age Anchorage Inter-action 12'4'nchor-30'2'pprox.

Above Grade*

~de ~uac Asse~s-ment Ade uac

~

33. 4B11 480V Load Center (PZR LC-Swgr Htr.

34. 3D25 Battery Charger 3B Control

35. 4D25 Battery Charger 4A Control

36. D26 Batter Char er 4S Control

37. 3D03 Battery Rack Control 42'2'0'2'0'4'4'2'4'2') 3)

Spacers needed on east end battery rack.

2) Lights need tie wire.

FPL should verify block wall of in IE 80-11.

38. 3D24 Battery Rack 3B Control 1) Spacers needed on east end of battery rack.

2) Lights need tie wire.

3) FPL should verify block wall in IE 80-11.

39. 4D03 Battery Rack 4B Control 1) Spacers needed on east end of battery rack.

2) Lights need tie wire.

3) FPL should verify block wall in IE 80-11.

TURKEY POINT UNITS 3 I 4 SUHHARY DATA SHEET Cont.

imntDe r o ~id. Approx. Approx. Anchor- Basis for Seismic Statuss remarks Qev. Height age Anchorage Inter-Above ~Ade u~a Asse~s- action Grade* ment Ade uac ~

40. 4024 Battery Rack 4A Control 1) Spacers needed on east end of battery rack.

2) Lights need tie wire.

3) FPL should verify block wall 42'ontrol in IE 80-11.

41. 3001 Distribution Y 1) FPL should tighten one loose Panels Bus bolt.

30'ontrol

42. 3D23 Distribution Panels Bus 30'ontrol

43. 4D01 Distribution 1) FPL should tighten 3 loose Panels Bus bolts.

44. 4D23 Distribution Panels Bus 18'4'2' 30'ontrol 12'2'2'4'4'4'4'l 30'ontrol

45. 3Y05 Inverter 3C

46. Inverter 42'ontrol 3Y07 3D

'42'ontrol

47. ~

4Y05 Inverter 4C Inverter 42'ontrol

48. 4Y07 4D r

42'C-Sw

49. 3C23A Se uencer 3A r

18'C-Sw

50. 3C238 Se uencer 38 Ol 1 Add one more to bracket.

r 18'C-Sw

51. 4C23A Se uencer 4A Ol C J 1 Add two to brackets.

r 18'C-Sw

52. 4C238 Se uencer 48 Ol 1 Add two to brackets.

TURKEY POINT UNITS 3 5. 4 SUNHARY DATA SHEET Cont.

ui me e cr to Approx. Anchor- 'asis for Seismic Status ~Rema ka 18'pprox.

Qev Height Above age

~de ~uac Anchorage Asse~s-Inter-action Grade* ment de uac ~

53. 3B CCW Heat. Exchanger RAB Ol 1) FPL should verify pedestal desi n.

54. 4B CCW Heat Exchanger RAB I) FPL should verify pedestal a

desi n.

55.

56.

3COS, 3C06 4C05, Vertical Vertical Panel 3B Panel 4B 42'l 18'ontrol 42'ontrol 24'4' 1) 1)

Interaction Concern, metal e crate ceilin .

Interaction Concern, metal 4C06 e crate ceilin .

(1) Key for Anchorage and Interaction Adequacy "Y" Yes (Adequate)

"N" No (Not Adequate)

(2) Key for Basis for Anchorage Assessment "R" Drawing and/or Calculation Review) hJh Judgment) hCh (Calculation)

~ Uh Unknown at time of walkdown)

(3) Status 'Y" (Seismically Adequate)

"0" (Outlier)

• "Grade'efers to "Plant G~ade" as identified in the plant Safety Analysis Report.

• • Equipment with anchorage location higher than 40ft. above grade.

90cl585B Appendice APP END IX C Ma1kdown Checklists and Supplementary Calculations

90C158SA/DATASHT P UN S U PM DATA SH EQUIPMENT PART A. EQUIPMENT DESCRIPTION I.D. Number Building Manufacturer Elevation 18 Model Number Other PART B. ANCHORAGE DESCRIPTION I. Is equipment anchoredf Yes X No

2. Condition of nearby concrete a~n embedments

3. Length, size, num er, an soundness o we s

4. Anchor bo t type, size an number

5. Are nuts present an apparent y tight on a o ts7 6s PART C.~ ANCHORA6E ADEQUACY 1.

~ Does Seismic Capacity of chorage Exceed Demands >/<~

a. SRT Judgment

b. URS Tables

c. ANCHOR program

d. Other (explain)

2. Concerns i any PART t,':. SPATIAL SEISNIC INTERACTION CONCERNS (if any) ol4E PART R. CCCECI CREATE OF ICTIOII TO REAIIETE (PART C) AR (PART A) OR CTRER CONCEtSS (if any)

PPR V DATE DATE DATE

Qle~eL nlh~&%P RRP -5 KKi 0 0 D&~mC~ vJAQ -PRAT VH &

~c~wa6.& Rx C ~d0wM DwrnenLQ. Z l-CALC ul A<)o~ ~CRC WW 56. PCCPQRN'EQ A CQEF&lc(F~ F FfC,tc.Sic U Bf .0 uJAS WD l5& USE,XO.

AS-FOUND FIELD CONDITION 3 3 II

@XX .XjX+i )hyÃW%5)i%$%14)hij9%$ %XPAyhhiggii%%%%%%% X jh@%%%%%%I+bh&iishy 'ghhghi

--<<.ai'isa. w~xxkixkA&i.x4i@ix<<.XMMii,~h44 wa4k~ixkakkhi ~ixxQQyx~ip 0

P 1 7a M

<< "5+%A~'<<4 $ 4'i bx4<<%+5@"4 5 'i4444%+%~4i 'j%" iih xA+xi4 1/2" DIA ANCHORS

( typical )

SKID 4 0 x)%%4%%%@'<<~&@>x4+k~i+iiXOAiN@5%L<44%45%q~ih%844 GRADE ELEV 0 II

'iW (~ ~AN"ii~i+ki%4%%>kxihtk"'0"WK 4 i %~ 44ixx~5h" 'c~ '"

DIESEL FUEL OIL TRANSFER PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALK DOWN. PTN 38c4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: DIESEL FUELOILTRANS PUMP DATE: MAR 27 1990 DWG BY: R GOULDY

AS-FOUND FIELD CONDITION THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS 0 0 0 0 C P

DIESEL GENERATOR BUILDING C.

8 PUMP A PUMP DIESEL FUEL OIL TRANSFER PUMP SKID MOUNTED PUMP SEISMIC INTERACTION WORK SHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: DIESEL FUELOILTRANS PUMP DRAWINGS FOR SAFETY RELATED WOFK DATE: APR 14 1990 DWG BY: R. GOULDY

6(

90C1585A/DATASHT PO U 1 ATA H EQUIPMENT Item 2 - Charging Amp PART A. EQUIPMENT DESCRIPTION I.D. Number 3B Building RAB Manufacturer Elevation 1B'ther Model Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored2 Yes No

2. Condition of nearby concrete an embedments

3. Lengt , size, num er, an soun ness o we s

4. Anc or o t type, size and number

5. Are nuts present an apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY I.

~ Does Seismic Capacity go Anchorage Exceed Demandi

a. SRT Judgment

b. URS Tables

c. ANCHOR Program r

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (i f any)

PART E. RECONNENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS ($ f any)

DATE ~/

DATE DATE

CHM.6ikC i=Us ~

Rlo c~d~~-, Desscb 1X~id&

Marw eeA~~ SJ'~~

AS-FOUND FIELD CONDITION 130" 0 0 0

,A., ++i(<:~<~"j~~Q%."iiQigMi~i%igXi'~++~'etp~&@e>

<  %&t'ai

', A~iii>yx>X>whse:gij+WgXi~~iXy+Xj~ki~>X:Pi 4% x4x4%%Xx 4%44 x<%44%%i<&i 3/4" ANCHOR BOLTS

( TYPICAL, 8 BOLTS )

3/4" DIA BOLTS FLOOR ELEVATION 7 II

'ikghi%%iVN4;ix%%k 9 3B CHARGING PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALK DOWN. PTN 38c4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B CHARGING PUMP DRAWINGS FOR SAFETY RELATED WORK. DATE: APR 15 1990 DWG BY:

AS-FOUND FIELD CONDITION POURED CONCRETE WALLS

~+:;z@y~-.gee~"~ex>~~~'~~~>4N~+YN@<~~A4,":NN4~~&4,"$4~~~&>,W~.~. N>~~4%";,"~%~M:;>%4%EC4N~V4!NNI~e:<e<.".&~4)~&ai.>%@K-"W~~YN%N~<N~~.

g>%%i<%ahii<R Biking xx%Rh >ceX<%>: 4%%%%.NCi>y04 q g>%P 'x%%+%+i%i%%PRAAK+3%i@

0 C CHARGING B CHARGING A CHARGING PUMP PUMP PUMP UNIT 3 CHARGING PUMP ROOM THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS FOR THIS PUMP ARRANGEMENT.

3B CHARGING PUMP SEISMIC INTERACTIONS WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B CHARGING PUMP DRAWINGS FOR SAFETY RELATED WORK. DATE: APR 14 1990 DWGBY:

90C1585A/DATASHT U M A SH EqUIPMENT Item 3 - Charging Pump PART A. EQUIPMENT DESCRIPTION I.D. Number 4B Building RAB Elevation

'o Manufacturer 18'ther Model Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored2 Yes

2. Condition of nearby concrete an mbedments

3. Length, size, num er, an soundness o we s

4. Anchor bo t type, size and num er

5. Are nuts present an apparent y tig t on a o tsar PART C. ANCHORAGE ADEQUACY

l. Ones Seismic Capacitygo Anchorage Exceed Oemandi

a. SRT Judgment

b. URS Tables

c. ANCMOR Program

d. Other {expiain) RrT~

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (i f any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

DATE DATE NAME DATE

/gO Cco4~8%5, ~~8&2 Dk'A4JJAJSS

~V) ~~ / g5

AS-FOUND FIELD CONDITION 130" 0 0 0 0 0

((

yq'( (xXgig( y%i,((, xeXi, v%(( xxiXP>i (((.,%wive( a(,. ((X$

eX494N+4%8k@hhhjhgh+Qqwk(ei4@4%4%i: ejk44X~Lj%4@XN~X(045'%@hi'g(

3/4" ANCHOR BOLTS

{ TYPICAL, 8 BOLTS )

3/4" DIA BOLTS P

FLOOR ELEVATION 0

9 4B CHARGING PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES

. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B CHARGING PUMP DRAWINGS FOR SAFETY RELATED WORK DATE: APR 15 1990 DWG BY:

AS-FOUND FIELD CONDITION POURED CONCRETE WALLS

c4i%XiWw4i'a% ~iQW%<Mghx  %%%%+V%'iWN>icN4xb'~  %%%%AW~XXW+%%%%%%%~% iX,

@is (4

iYg i/4

@.KMwxQ%R~+i'iA~4hNN@@ii WiM'~w'W~~Cix<i%i%~~guX~~Nii I~gh~g@gg~i'iiy4~~g~x$ j+g~g%+

I A CHARGING B CHARGING C CHARGING PUMP PUMP PUMP I

gS UNIT 4 CHARGING PUMP ROOM THE SRT DID NOT HAVE ANY SEISlVlIC INTERACTIONS CONCERNS FOR THIS PUMP ARRANGEMENT.

4B CHARGING PUMP SEISMIC INTERACTIONS WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B CHARGING PUMP DRAWINGS FOR SAFETY RELATED WORK. DATE: APR 14 1990 DWGBY:

90CI585A/DATASHT PO U P EqUIPNENT Item 4 - Component Cooling Mater PART A. EJUIPNENT DESCRIPTION I.D. Number 38 Building RAB manufacturer Elevation 18'ther Model Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored? Yes No

2. Condition of nearby concrete an embedments

3. Lengt , size, num er, and soundness o we s

4. Anc or bo t type, size an num er

5. Are nuts present and apparent y tight on a o ts?

PART C.~ ANCHORAGE ADEQUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demand?

a. SRT Judgment b.

c.

d.

URS Tables ANCHOR Program Other (explain) HM C t.

~

eA.

-53(  % it 5s.P ciI W as'F ts

2. Concerns i any PART D. SPATIAL SEIQlIC INTERACTION CONCERNS (i f any)

PART E. RECQIIENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

NAME DATE d J /50 DATE NANE DATE

Ma cau~aM, QEsicd MAM>dM AVI3 s, P~U)e,QK sY SL7 .

AS-FOUND FIELD CONDITION 10' Q~i~yXgQ<',~@i+i,~QixixiM~Xx";:4hi~+ii~~@4%%~ih~'k>k~xx<ii%A>i%@x%iXk'x~A@ii~hi+~;g4<i~i%gga~%~

0 0 0 0 36" P

46 0 0 0 0 g~~+4i~~~~ 4~4+zig4'a,"4%%4%~i~i%%%% 'KX@~c.KQi<%%%%%iixi+iii4h.i4@cwiAx'i4k4 7/8" ANCHOR BOLTS

( TYPICAI, 10 PLACES)

P 0 II grade 38 CCW PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES

. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B CCW PUMP DRAWINGS FOR SAFElY RELATED WORK. DATE'AR 22 1990 DWG BY:

AS-FOUND FIELD CONDITION HEAT EXCHANGERS g%".'i%%&N i':.RihiixÃ~~"'"%%h~ixi~

o o o o o M p j4 0 0 0 0 STRAINERS 3C xx+yig~g%,xiii>+iiigi>i+~qi+~~Wj%ii; '(5".i4%<N%%%ixii4'h&MXiA'%~~ibM>%ji o o o o. o o o o o o P

0 0 0 0 i;>

jc o 0 0 0 WYi%16%%%kii%i ~@%"~i%4 3B 3A THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS PUMP ARRANGEMENT. THE STEEL GRATING ABOVE WAS REVIEWED AND FOUND TO BE BOLTED TO THE STEEL I-BEAMS 3B CCW PUMP SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN KETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVAI UATION. SEE ENGINEERING COMPONENT: 3B CCW PUMP DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 22 1990 DWG BY:

Ccm Ol X

O CO STEYENSON I

8r ASSOCIATES 0 llnhchhhOHl44chohlcol consvhlng onglnoenng tlhm I

I I

~ >

I I I ill K

'W I

~

II

~4 i I.

4 i I f

Pihh I

I

~

~,'~- /3~.~

/ I I I ~

I II 4 ' m' ' ~ '4 I

~ -= ~ - ' 4-I I

+

I

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90C1585A/DATASHT 0 NT tJN U PN TA SH EQUIPMENT Item 5 - Component Cooling Mater Pump PART A. E(UIPMENT DESCRIPTION I.D. Number 4B Building Manufacturer Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an mbedmenta

3. Len g th , si ze, num er, an soundness o we s

4. Anchor bo t type, size and num er - 78'm

5. Are nuts present and apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables c.

d.

ANCHOR Program Other (explain) t C . C SD a

a M~ ~b <<4<<<<

8$ -t I (Sm/ ~&ia2.D i4om

'D~k DIES Qua C Al

2. Concerns {i any PART D. SPATIAL SEISMIC INTERACTION CONCERNS (i f any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

DATE 4 /J Pd'ATE DATE f 0'

c ~~ovnw C~~u~ Qum~Pome 46 NESTS%.

MQ CQRP~~S, ZI~5lC 6 DCAMiAJ65

~ ~~~WubVA UJ~G EEU) &JCQ SU ALAD Pu~~M C A( C.umercum F'&(Wo~e.Q Ag WH.E' )VM MQ (Q AS FaUOH +c be Bcu=PTAl5~ FoW ~l5 4omP AA)CAGE..

AS-FOUND FIELD CONDITION 10' 0 0 0 0 36 46" 0

illi++Ph~6gaj~~X+iyXiiigii Ai~~sigk~hkjxhjixitiiiaV4%+qh)~8(ii~+q+~4gi".~+OiiiiY<iC@hiiNPW 7/8" ANCHOR BOLTS

( TYPICAL, 10 PLACES)

P 1/2" 10" gMd8 4B CCW PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES

. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN-38c4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDEDTOBEANAIDINTHE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B CCW PUMP DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 22 1990 DWG BY:

AS-FOUND FIELD CONDITION HEAT EXCHANGERS o o o o o P

o 0 0 0 STRAINERS 4B 5414%>%%~~~i4xiCii%i~MX<~iKZ'lid o o o o o o o o o o 0 0 0 0 o 0 0 0

>iX4%ii"'" i%'"'i~~i4%"'Xh%%"~ 4~%i+i>i>AiM>44~>Vii~i~4~%%

4A 4C THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS PUMP ARRANGEMENT. THE STEEL GRATING ABOVE WAS REVIEWED AND FOUND TO BE BOLTED TO THE STEEL I-BEAMS 48 CCW PUMP SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATGN. SEE ENGINEERING COMPONENT: 4B CCW PUMP DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 22 1990 DWG BY:

90C1585A/DATASHT EQUIPMENT Item 6 - Intake Cooling Mater Punp PART A. EQUIPMENT DESCRIPTION I.D. Number 3B Building Intake Structure Manufacturer ou Elevation 18'Motdf deepwell paNp)

Model Number Other PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored? Yes ~ No

2. Condition of nearby concrete a~n embedments

3. Lengt , size, num er, and soundness o we s

4. Anc or bo t type, size an number

5. Are nuts present an apparent y tig t on a PART C. ANCHORAGE ADElgACY

'r

l. Does Seismic Capacity of Anchorage Exceed DeBandT

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) ul 8C 04falru /r+.

2. Concerns i any ~ e a6am mme.z+

. ~ 6kdr dA.lCu La. ~.LS]

W PART D. SPATIAL SEISMIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER aeCERNS IT K 'tsp (if any) ~gA 5 Ca 4 SIOf CCD VTI I Eg C'Sm Cars dpi- (Chai sQ O<d-D

--. sg d. I < 0 PA G, C DATE DATE NANE DATE

@+CD/IBM q p~ ~ +~g~ 7

~CA i LEQ&WH pP t~M W &'5 f +Qg~~ p~ p AAC 14~8. A &

az,d ~~a @~md pm,wc PuWP +H~

5HA P i c $

Co@ e.EP-AS - <<C HE.c~ I 86AP <awm 5~A~ Lwc.~e = zz 5waic HAs 5~pP o g AF'}nlrb.HoR+&E (Qy pc~)~@) gp SltcEA-

~ FtRFMM Fo@ P~n P Fog. ~s-, Jg POPE p A&V c ~p LJ g~~~ D~y ~~i g~

C od f- P+ g~ DFQDAGV g D6 FA Ww6 Fos r a- l I +5g/~jC)~gp

AS-FOUND FIELD CONDITION 0 0 4 - 1 1/4" ANCHOR BOLTS 54 3B K:' 0 0

'%P~+jXQW"QxQYa~X, i'd%>$, x>ij%to~~+~t: 4gqX 3B MOTOR DISCHARGE PIPING 3B PUMP ASSEMBLY 5 1/2" ~ 2 1/4" STEEL PLATE 3 1/2" concrete and 2'rout pad 3B ICW PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B INTAKECOOLING WATER PUMP DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 22 1990 DWG BY: R.GOULDY

AS-FOUND FIELD NOTES

%a.'ii9<ii.iP(:i$%VxkÃiiibV) 0 3C 3B 3A x~4@XXOAS<4ii'6M@'kg~a~axiv xkahaN>+~4x4%%XX%4%~xN i>.~4~.(A'4@a M; WNXSX<Ma+

P.." .;:, "'; ",3g.'.'( ' ~",~;:;.,';",,:":j'".'j~g,:~j" ~ ~U "c:...q's<: 'j~;::::; .'(',';.',( '",.',,

@gal..-:.':'-'.~",j:;-:-",.';,::.)gj'.::.:.,+MOVINGSCREEN(S,'.",,j:',.i.',:..'..:

?%CA(":Ni "".'S;"(. '(.". "e'~z: i ra((.'AN:)>8'('CN(::N(8 4'p4 '".<;(" 'Nki'i)'B ICW PUMP SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B INTAKE COOLING WATER PUMP DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 22 1990 DWG BY: R.GOULDY

90C1585Ayt'OATASHT EQUIPMENT Item 7 - Intake Coolin Water PART A. EgUIPHENT DESCRIPTION I.O. Number 4B Building Intake Structure Manufacturer vis 4l Elevation 18'otor Dee ell.Rum )

Model Number Other PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored2 Yes No

2. Condition of nearby concrete an embedments c op ~ 6'~

3. Lengt , size, num er, an soun ness o we s e /

4. Anc or bo t type, size an number

5. Are nuts present and apparent y tig t on a o ts2 PART C.~ ANCHORAGE ADEtlUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demand?

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) OPFck duWas- >>~l E+dmo<~

2. Concerns f any cucc~d; ze e~cB~T PART 0. SPATIAL SEIQlIC I ERACTION CONCERNS (if any) 0V /5 PART E. RECOlilBSEQ CNRSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CNCERNS {ifany)

I 7 Ca 2>> scssc.cgD pep. a-seR. A- C. cp i E. e c'- C.&c Rw> rdcrrE.D A c saaD PItdm.E.

DATE DATE RANE DATE ~/* /

SuAFW HA> 5v PP oem~

Fa8- Pew sz P gs F'-~dc~

4 <~6. S, F~R-POPE p 4o<C s~ A 9$ @gA~

AD6 DA~ eo F- L38smd.~yz ~ipse FW WuE F~ssri Uw i-,~ Si etc.<~ w~ <as~P-C.

4)owl. ~ Ppl g c g pg ~95 Qu E.i'd.&

AP EgP-wH CVQArcg hlot6D +6 ~M (gal (gal c-Tiarl QC E@L F04 Gg SP- I PRE I ~ C C

~<~~z~c c~c ~c ~ ~z ~~~~a< c <s w< sc~~~~

gD ~&4 A W~c (cd DM .

4) uEgd ~u N C.BRAS I 5

+~VWPS ~

APER t5 ~6 ~~

AS-FOUND FIELD CONDITION a~4. '~~~i444~ig<gqi+x~i~i++igX4@ '

0 4 - 1 1/4" ANCHOR BOLTS 54 4B g~i 5 1/2" 4B MOTOR DISCHARGE PIPING 4I 4B PUMP ASSEMBLY 5 1/2"

.g4$d o

'g%"'KSa,$

~o o 2 1/4" STEEL PLATE 3 1/2" concrete aod ga grout pad

<~~>~~~~V&s. pal,":.~ph8@

oou aap hap 4B ICW PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B INTAKECOOLING WATER PUMP DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 22 1990 DWG BY: R.GOULDY

0 AS<<FOUND FIELD NOTES

.j'll'".':i::::.:j,"',cIRGULATING':,':.',;!."it, g~ iiMNR~iNiC>~'%%+%MhÃp  %%~%9N+<NRXMRi%

4B c

R I.;.$.>i+g++ci.:~-Di~;cj+;i~"<< 4i

,"'.",:::.-',:i":;j"'".'.".~j~':=::::.:=::4.'.MOVING;:.S<<CREENS"~;:""-",:"'%ij:::;=i<<."~j 4B ICW PUMP SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCAI E, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B INTAKE COOLING WATER PUMP DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 22 1990 DWG BY: R. GOULDY

90C1585A/DATASHT R PO S U PN DA A SH EQUIPMENT Item 8 - Boric Acid Transfer Pump PART A. E(UIPNENT DESCRIPTION I.D. Number 3B Building RAB Manufacturer Elevation 18'ther Model Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedments

3. Length, size, number, and soundness o we s

4. Anc or bo t type, size and number

5. Are nuts present and apparent y tight on a o tsar PART C.~ ANCHORAGE ADEQUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS {if any)

PR NAME DATE RANE DATE DATE

QO Cz>@~~ 5, DE<(6,6 D~wid ~

Pwu>ru)ea. >W wAQ, FJMM QM,lv C

-%C'ALlCZ)QMQ

AS-FOUND FIELD CONDITION 60"

'aigX~4W<~>~i~<++>~+ ~~~<<b4+<Z<<>~~iiiiZgg+++iiW<<<<~ii~XiqX~X<<<<ig>i><<<<.gA~i>4<<~pic<<gg+yi~<<g+4 0 0 1/2" DIA ANCHOR 1/2" DIA ANCHOR BOLT IS BELOW STEEL PLATE 1/2" STEEL PLATE P

4 1/2" 3B BORIC ACID TRANSFER PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 3&4 GL 87-02 WALKDOWN IELD WALKDOWN.

EQUIPMENT ANCHORAGE SKETCH SKETCHES ARE INTENDED TO BE AN AID IN THE ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B BORIC ACID TRANS PUMP DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 22 1990 DWG BY: R GOULDY

AS-FOUND FIELD CONDITION THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS PUMP ARRANGEMENT. THE BORIC ACID STORAGE TANKS ARE LOCATED ABOVE THESE PUMPS AND WILL BE ADDRESSED ON THEIR WALKDOWN ITEM CHECK SHEET. DUE TO LOCAL CONTAMINATION, THESE PUMPS WERE REVIEWED FROM A DISTANCE.

444%<4~~ ex4 0 O O O 0 0 P

0 0 go 3A 3B 3B BORIC ACID TRANSFER PUMP SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 38c4 GL 87-02 WALKDOWN FIELD WALKDOWN.

SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B BORIC ACID TRANS PUMP DRAWINGS FOR SAFETY RELATED WOFK DATE: MAR 22 1990 DWGBY: RGOULDY

90C1585A/DATASHT PO UN T 3 4 U PH NT A EQUIPMENT Item 9 - Boric Acid Transfer Pum PART A. EQUIPMENT DESCRIPTION I.D. Number 4B Building RAB Manufacturer Elevation 18'ther Model Number PART 8. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedments

3. Length, size, num er, an soundness o we s

4. Anchor bo t type, size and num er

5. Are nuts present an apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) lOAAVOS

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART 0) OR OTHER CONCERNS (if any)

NAME DATE NAME DATE NAME DATE

Eaxic Ac.iw lKA~<W Poof 45 Ao ca QMM~.

AS-FOUND FIELD CONDITION 60" 0 0 0 26" 0 hj %X' yyjQgXQQ<~k%+x.xg%i+XgXig<+i"+N%yxxXx>~~4'. i4+~~%4 'Q': y~~gcki'k~, 'xhgxhx%~+xgghk my'.

<i'.:~~ix~ji~Qxxi~x'gx4+i4%~@Q@,kh~>4%%khiqij+>x ~:i)@w@~y<x~&cyq:~~iy@v@~~~%v @~~h<gyj~ij 1/2" DIA ANCHOR 1/2" DIA ANCHOR BOLT 8 BELOW STEEL PLATE 1/2" STEEL PLATE 4 1/2" 4B BORIC ACID TRANSFER PUMP SEISMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 3&4 GL 87-02 WALKDOWN FIELD WALKDOWN.

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH'OMPONENT:

ANCHORAGE EVALUATION. SEE ENGINEERING 4B BORIC ACID TRANS PUMP FOR SAFETY RELATED WORK. 'RAWINGS DATE: MAR 22 1990 DWG BY: R GOULDY

0 0

AS-FOUND FlELD CONDlTION THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS PUMP ARRANGEMENT. THE BORIC ACID STORAGE TANKS ARE LOCATED ABOVE THESE PUMPS AND WILL BE ADDRESSED ON THEIR WALKDOWN ITEM CHECK SHEET. DUE TO LOCAL CONTAMINATION, THESE PUMPS WERE REVIEWED FROM A DISTANCE. THESE PUMPS HAVE THE SAME ARRANGEMENT AS THE 3A & 3B BORIC ACID TRANSFER PUMPS 0 0 ki@

<yii4 0 0 F~N P  %~&i

%%~44."'.%%4%NxM LiLN%+i4%%4 4A 4B 4B BORIC ACID TRANSFER PUMP SEISMIC INTERACTION WORKSHEET GENERAL NOTES NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 38c4 GL 87-02 WALKDOWN IELD WALKDOWN.

SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B BORIC ACID TRANS PUMP DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 22 1990 DWG BY: FL GOULDY

90C1585A/DATASHT tjIP MENT ATA EQUIPMENT Item 10 - Diesel Oil Storage Tank PART A. EQUIPMENT DESCRIPTION I.D. Number N/A Building Outdoors (Adjacent EDG Manufacturer Elevation Model Number Other 18'.

PART B- ANCHORAGE DESCRIPTION I. Is equipment anchoredf Yes s No

2. Condition of nearby concrete a~n embedments Length, size, nu ber, an soun ness o we s u/6

4. Anchor bo t pe, size an number

5. Are nuts present an apparent y tig t on a o ts2 PART C.~ ANCHORAGE ADEQUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demand2 AO.

a. SRT Judgment

b. URS Tables

c. ANCHOR Program I

d. Other (explain) ffJpdi~ sn c'.

Concerns an PART D. SPATIAL SE/SMIC INTERACTION CONCERNS (ff ny)

PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE {PART C) OR {PART D) OR OTHER CONCERNS (if any)

DATE RANE DATE NAME DATE

6 ANCHOR BOLTS TANK HOLE DIA 1 3/8" 4X9" NUT DIA 1 7/8" CHAIR WEIRD 1/2" 12" SIEEL DIESEL FUEL OILSTORAGE TANK 1-1/4" DIA ANCHOR BOLTS

~ GRllDE SEISMlC MOUNTtNG NORKSHEET GENERAL NOTES DO NOT SCALE,'SE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 3&4 GL S7-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: DIESEL FUEL OIL STORAGE TANK DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 27 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS hxx4%',.:

.>i.,a 0'%xXN.@~ii.

i+

"D.

.4 gQ 20'IESEL FUEL OIL STORAGE TANK EARTH BERM ag~~, ~C~C,:qaW qy~ P! ~~pry . g~~)gyes"~ g~'P .el ~mgaiW~P iud Qt,.

DIESEL GENERATOR BUILDING DIESEL FUEL OIL STORAGE TANK SEISMIC INTERACTION WORKSHEET

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN KETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: DIESEL FUEL OIL STORAGE TANK DRAWINGS FOR SAFETY RELATED WORK. DATE: APR 14 1990 DWG BY: R GOULDY

SR,T RRU) FACY %Aalu. I A)SV)RL~~Q; A)J& Pc oat Qcri-M4 QLAuJ~d 6 5, c ~u>A> Foa Sot w>U C AAl& l5QwW ~AS~

~) +<>k I4 Z HMDkC CAQ~ Mals t'ai c I nJ(K~~Lek3 Ag m Alien ~H< ~ACR% MQFESSEQ EaP~w Gum,mACY-

~><CD~*. ~ i PPEF~em<O v Cm<c~uDFD /RA w SoPF c

~(q p(g pg Q'T Q + P/Z 8'c ACeg 0

~~)C K ( h+4g FwA gS r

PAGE i CALCULATION COVER SHEET Calculation No: '7 PQ - l~ 3 C. - 9 a - tom Ti tl e:

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0 INITIAL ISSUE i~/i~/~ i/&~i No i Descriptjon By Date Chk/Ver Date Appr Date REVISIONS MAS-4 ~ JPN JPN Form 82A, Rev. 3/90

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l. Is equipment anchored2 Yes No

2. Condition of nearby concrete an embedments

3. Length, size, number, an soun ness o we s

4. Anc or bo t type, size and number

5. Are nuts present and apparent y tig t on a o ts2 PART C.~ ANCHORAGE ADEQUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tab1es

c. ANCHOR Program

d. Other (explain) c km=8- m ~c ~>>

n

2. Concerns i any PART D. SPATIAt. SEISNIC INTERACTION CONCERNS (if any)

PART E. RECOSlENDED COURSE OF ACTION TO RESOLVE {PART C) OR (PART D) OR OTHER CONCERNS {ifany) II C.Art 5 (OCR CO C WC. a C SEC A ~~~C~ C Cubed E<4 S r f DATE DATE DATE Z'O So~~ 5m~ Zmm~ I44< +g~j~ p,gcuceAac iV PLA1Fa~, ~ ~~ p~gQ$ ~~~~@. Q~3 CAW~l7") ar- LECs ~ wndK h,~~ c.H~<eD A)K VD~(bsJ, PLAYFUL)~ -RO FKG CAKCW~ g f PP~~ AS-FOUND FIELD CONDITION STEEL WIDE FLANGES THE SRT WANTED AN ANALYSISOF THE LEGS, BOLTING, ATTACHMENT TO THE TANKAND TO THE STEEL FRAME WORK BELOW. B BORIC ACID STORAGE TANK 1/4" PLATE ~ 1/4" FILLET WELD 7/8" BOLT (TYPICAL, 2 PLACES) 1/2" PLATE ELEVATEDSTEEL FRAME WORK ELEVATEDTANKABOVE THE BORIC ACID TRANSFER PUMPS, FILTERSANDVALVES 8 BORIC ACID STORAGE TANK SEISMIC MOUNTING WORKSHEET GENERAL NO'1ES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATGN. SEE ENGINEERING COMPONENT:B BORIC ACID STORAGE TANK DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 22 1990 DWG BY: R. GOULDY AS-FOUND FIELD CONDITION THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS C BATCH TANK ELEVATED TANKABOVE THE BORIC ACID TRANSFER PUMPS, FILTERSANDVALVES B BORIC ACID STORAGE TANK SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN A(D (N THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT:B BORIC ACID STORAGE TANK DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 22 1990 DWGBY: R.GOULDY ll 90C1585A/DATASHT UIPMENT DATA SH EQUIPMENT Item 12 - Condensate Storage Tank A. E(UI PNENT DESCRIPTION I.D. Number 3 Building Outdoors (Adjacent 18'ART EOG) Manufacture er Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored? Yes No

2. Condition of nearby concrete and embedments

3. Length, size, num er, and soundness o we s 0 eb 2 a 0l

4. A c or o t type, size an num er

5. Are nuts present and apparent y tig t on a o ts7 P ART C. ANCHORAGE ADEQNCY

1. Does Seismic Capacity of Anchorage Exceed Demand? /)/~

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Conc ms i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any) e, PART E. RECONVENED CONSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

NAME GATE GATE DATE S~M&e TAdV - D~ik~ MAd>ED CA,LCU FaW: AdckcnV 6 < z3 <op c a MAJ~

5) /by~ ~AT'P Qf~ Sn&C MA(

p,~ g~ +EM~~ 'W PVdk 4 SofAE CAA)k, PLWQS A~ Bema. C p i a. cr a E C.~ ~ c w ~ ~ > ~ ~ FoQ. g~w D go<~ g,.~> p CL PF I6 SPY'.458 p C ~p(~ p~ p . Il g UJ>~~ AS-FOUND FIELD CONDITION yQ)Qs+X@+Qp++XpQQ+%)X)x Q Xgyg>j(~XxXXKNQQQIO j+QyjQXjx SEVERAI CHAIRS FOR THIS TANKHAVE BEEN BENT AND ARE NOT WELDED TO THE TANK TANK 4X9" UNlT 3 CST CHAIR WEIDED 1/2" STEEL 1 1/4" DIA 12" ANCHOR BOLTS k4%%++y>) 1 5lt 4%~xhhheix@ii i4w<ahh%44LXX. 46" UNIT 3 CST TANK TANK MOUNTING WORKSHEET

1. DO NOTSCALE, USE DIMENSIONS TAKENDURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFElY RELATED WORK COMPONENT UNIT 3 CST DATE:MAR 22 1990 DWG BY: R. GOULDY

AS-FOUND FlELD CONDlTlON TURBINE DECK S@g%vg~?~ @"~'">$>$gPi< > .~'8% yV '. ~ra >,Y$ .?'an) D/G BUtLDlNG r CST gaP~y FEEDWATER PLATFORM THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS j UNIT 3 CST TANK SEISMIC INTERACTION WORKSHEET GENERAL NOTES . DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING ~ DRAWINGS FOR SAFETY RELATED WORK. COMPONENT UNIT3 CST DATE:MAR 22 1990 DWG BY: R. GOULDY PAGE i CALCVLATION COVER SHEET Calculation No: T~t' l 53 C '3 o - oc a,

Title:

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90C1585A/DATASHT 0 3 U MENT OA A SH EQUIPMENT Item 13 - Condensate Store e Tank PART A. EQUIPMENT DESCRIPTION I.D. Number 4 Building Outdoors S.M. of RCB Manufacturer Elevation Model Number Other 18'.

PART B. ANCHORAGE DESCRIPTION

1. Is equipment anchored? Yes No

2. Condition of nearby concrete an embedments Length, size, number, and soundness o we s

4. Anchor bo t type, size and number

5. Are nuts present and apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demands fy',

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) C 2-C fv ef ~4WJ.

h

2. Concerns i any)

PART D. SPATIAL SEISMIC INTERACTION NCERNS ( f v~

y)

PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART.C) OR (PART D) OR OTHER CONCERNS (if any)

NAME DATE NAME DATE NAME DATE

W~IA l3 Ccdoeus~ S~acass TAxx . QuA 4 Gl~ 'lAI APART CA M~LAT'~ PC)M

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AS-FOUND FlELD CONDlTION SEVERAL CHAIRS FOR THIS TANKHAVE BEEN BENT AND ARE NOT WELDED TO THE TANK TANK 4X9" UNIT 4 CST CHAIR 1/2" STEEL 1 1/4" DIA 12" ANCHOR BOLTS 1

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<<'SP UNIT 4 CST TANK TANK MOUNTING WORKSHEET

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATGN. SEE ENGINEERING DRAWINGS FOR SAFElY RELATED WORK. COMPONENT UNIT 4 CST DATE:MAR 22 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION TURBINE DECK TURBINE GANTRY CRANE RAIL CST FEEDWATER PLATFORM THE SRT NOTED THAT THE TURBINE GANTRY CRANE IS NORMALLY PARKED AND PINNED INTO POSITION AT THE SOUTH END OF THE TURBINE STRUCTURE WHIC IS LOCATED NEAR THE UNIT 4 CST. THERE WERE NO OTHER SEISMIC INTERACTIONS CONCERNS NOTED WITH THIS TANK UNIT 4 CST SEISMIC INTERACTION WORKSHEET GENERAL NOTES 1 ~ DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WAlKDOWN. PTN 38c4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT UNIT 4 CST DATE: MAR 22 1990 DWGBY: R.GOULDY

9OC1585A/DATASHT 0 UN U M T S EQUIPMENT Item 14 - Refueling Mater Stora e Tank PART A. EQUIPMENT DESCRIPTION I.D. Number Building Outdoors Manufacturer Elevation 18'ther Model Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchoredf Yes sr No

2. Condition of nearby concrete and embedments

3. Length, size, num er, an soundness o we s

4. Anc or o t type, size an number

5. Are nuts present and apparent y tight on a o ts'F PART C. ANCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Demands << ~

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

. d. Other (explain)

2. Concerns i y) IV ~7 f dye P

PART D. SPATIAL SEISMIC INTERACTION CONCERNS (if any)

>CXeO ~

PART E. RECONBSED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

NAME DATE NAME DATE NAME DATE

MWh/i l4 WPu~&C LQA~n ~e.7kik QA3 S~ LdA~ P,Q C.AckASG ADm Ctrl M

(~ ~&~l)~~ .

THE. 5PH~ FUeL DMV'MQE. LQ~

Qnv+Q Fad S,n~m(c ld ie~c<i<4 c~~Cz~Q bd-r M~ ~Hau3U iV EK PARK.ED MD S~oaez A~~v Mcw wacm &i~ w~f..

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f-t CcPpp'cP. 8>~~ Sc nP <A lt oC< CA cc ucA-,d p i c 8g PH8 le4 CP-C >SliO C Hp I pg p,

AS-FOUND FIELD CONDITlON ii<<k<<<<<<%~Xi <<,... iQix 'j:i<<<<> ~ <<gQ~XiiNii<<xi'.iP<<,;>i,+i"

'HAIRS ARE NOT WELDED TO THE TANK, ONLY THE GUSSETS ON THE SIDES TANK UNIT 3 RWST 4X9 CHAIR 1/2" STEEL 1 1/4" DIA 12" ANCHOR BOLTS

( TYPICAL, 16 PLACES )

<<.A,, <<<<,~<<<<,,;;iA, XXX<<,

UNIT 3 RWST SEISMIC MOUNTING WORKSHEET

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 354 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFEIY RELATED WORK. COMPONENT UNIT3 RWST DATE'MAR 22 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION AUXILIARYBUILDING SPENT FUEL CASK CRANE RAIL PWST RWST THE SRT NOTED THE SPENT FUEL CASK CRANE RAIL STRUCTURE NEARBY BUT NOTED THAT THIS CRANE IS STORED AND PINNED AWAY FROM ANY ITEM ON THE WALKDOWN LIST. THERE WERE NO SEISMIC INTERACTIONS CONCERNS.

UNIT 3 RWST SEISMIC INTERACTION WORKSHEET GENERAL NOTES

$ . DO NOT SCALE, USE DIMENSIONS TAKEN DURiNG FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK COMPONENT UNIT3 RWST DATE: MAR 22 1990 DWG BY: R.GOULDY

PAGE i CALCULATlON COVER SHEET Calculation No:

Ec iU 4 8 5~oC AGE INITIAL ISSUE >Z/zo/g~ >WS )/zg)

No+ Description By Date Chk/Ver Date Appr Date REVISIONS HAS-4. JPN JPN Form 82A, Rev. 3/90

b RNR KREIS

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PAGE iii TABLE OF CONTENTS CALCULATION NUMBER REV. CO SECTION TITL PAG S Cover Sheet List of Effective Pages

\

Table of Contents ~ ~

1.0 Purpose/Scope 2.0 References 3.0 Methodology 4.0 Assumptions/Bases 5.0 Calculation - P~se~su C~,

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l. Is equipment anchored2 Yes No

2. Condition of nearby concrete an embedmenta

3. Length, size, num er, an soundness o we s

4. Anchor o t type, size and number

5. Are nuts present and apparent y tight on a o ts2 PART C. ANCHORAGE ADEQUACY

l. Does Seismic Capacity of Anchorage Exceed Demand2 A/u.

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) aa mPh A

2. Concerns i any PART D. SPATIAL SEQSNIC INTERACTION CONCERNS (i f any)

C K is D Aw PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) NAME DATE NAME DATE DATE WAD/C A/jcHo/'w*~ MQ CHILI& ~ e- JVAI V'~r LS.A//IW As D~P>3. vo~~ we% %PRAM PUN~ cAsL cf<~MUE, KPw NO~a( ~ocul e, AM% wo 2esoD< S'K/S/Vi! c I LITEILAC<Lc50 GhaJEM . A4= ++ NI+ &MLM 6M' pp I g~pg C 4 r I P+ tpj+PQA++gg~ppp l4. AS-FOUND FIELD CONDITION CHAIRS ARE NOT WELDED TO THE TANK, ONLY THE GUSSETS ON THE SIDES TANK X9~ CHAIR UNIT 4 RNfST 1/2" STEEL 1/4" DIA 12" ANCHOR BOLTS ( TYPICAL, 16 PLACES ) VNlT 4 RWST SE1SMlC MOUNTlNG WORKSHEET

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 354 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK COMPONENT UNIT4 RWST DATE:MAR 22 1990 DWG BY: R. GOULDY

0 AS-FOUND FIELD CONDITION AUXILIARYBUILDING SPENT FUEL CASK CRANE RAIL PWST RWST THE SRT NOTED THE SPENT FUEL CASK CRANE RAIL STRUCTURE NEARBY BUT NOTED THAT THIS CRANE IS STORED AND PINNED AWAY FROM ANY ITEM ON THE WALKDOWN LIST. THERE WERE NO SEISMIC INTERACTIONS CONCERNS. VNIT 4 RWST SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATGN. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT UNIT 4 RWST DATE: MAR 22 1990 DWG BY: FLGOULDY

90C1585Adt'DATASHT EQUIPMENT Item 16 - EDG Day Tank PART A. E(UI PNENT DESCRIPTION I.O. Number Building EDG manufacturer E1evation 34'ther Mode1 Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored? Yes No

2. Condition of nearby concrete an embedments

3. Length, size, num er,. an soun ness o we s

4. Anc or o t type, size an num er

5. Are nuts present an apparent y tig t on a ts?

PART C. ANCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Deaand?

a. SRT Judgment

b. URS Tables ]~go<

c. ANCHOR Program

d. 0 her (e plain) . Bd m.lc;u

2. Concerns i any 4, l5 4hlcc I '5 PART D. SPATIAL SEISNIC INTERACTIN CNCERNS tif any) mls, il 5

PART E. RKCOOIBSED C E ~ V he. Of ACTIN T ~ gVN KAe RESOLVE (PART C) OR (PART D) OR OTHER (if any) COSCERm l<f faut l (o C.deed'SdDC a~A.C-saic. Pa do Ia kE 4'V t h SS Si ~ a t E,k 8fmCAO5 8 yW 6 t-AS> r- RC aAScwJ 2 t u.n C.os~Card S dbms gQ5w P-Kc.c Qc.i ~D 8'v'w c KED i4 t. cvt oh~ t cs-Cs . DATE DATE DATE 0 ~~g)g~~ ~~ Md% lasvAM~~b~ oM* 6>~~ A l2PV)e.~5- et- Ikey DCAuu >4~ w4amid 6, i'd& Co<33, DEEDA ) ( ~A-h Q<64r2 Carne.. 4 +La Axlckzw Kb~& i UelGR r~ CO.&N rCSot ULiD Ce~G~ u3AL, 4D lk QC(CE- Jl~k~nr.&. ~ ~ Ak ~~~ ~U ~ad~~ ~ n 6 "T~ K~CA~ f DFQ1 I PlED. AS-FOUND FIELD CONDITION

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Title:

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90C1585A/DATASHT EQUIPMENT Item 17 - Component Coolin Mater Sur e Tank PART A. EQUIPMENT DESCRIPTION I.D. Number 3 Building RAB Manufacturer Elevation 71'ther Model Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored2 Yes >c No

2. Condition ot nearby concrete a~n embedments

3. Lengt , size, num er, an soundness o we s

4. Anc or o t type, size and num er 7

5. re nuts present and apparent y tig t on a

,s PART C.~ ANCHORNE ADEQUACY l.~ Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) C kgb 4~ I s

+LA

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any) o PART E. RECOWBSED COURSE OF ACTION TO RESOLYE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

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AS-FOUND FIELD CONDITION ISOLATION VALVES NOT SHOWN LOCATED ON EACH SIDE 14'-8 LEVELCOLUMN FOR TRANSMITTER 12'/8" DI A BOLT

( TYPICAL 4 PLACES)

EL WIDE FLANGE (6X12)

SUPPORT BEAMS 21

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STEEL I-BEAM 8 "X8" 3/8" STEEL PLATES 33" 20" UNIT 3 CCW SURGE TANK SEISMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: CCW SURGE TANK DRAWINGS FOR SAFETY RELATED WORK.

DATE: APRIL 14 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION STEEL GRATING SPENTFUEL BUILDING CCW WALL SURGE TANK NEW FUEL HOIST UNIT 3 CCW SURGE TANK SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: CCW SURGE TANK DRAWINGS FOR SAFETY RELATED WORK.

DATE: APR 14 1990 DWG BY: R GOULDY

PAGE i CALCULATION COVER SHEET Gal cul at i on No: TP 4 - I s ~ c. - s c - oz c

Title:

C C. 4I T v ~c.<<oaec s - 1 o.g. 4 I.d c a d ~ c Ac inc.( l-.t l7 INITIAL ISSUE /,,y. @n/x, />g +gu No Description By Date Chk/Ver Date Appr Date REVISIONS MAS-4. JPN JPN Form 82A, Rev. 3/90

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SECTION TITLE ~PAG S Cover Sheet List of Effective Pages Table of Contents 1.0 Purpose/Scope 2.0 Referenc'es 3.0 Methodology 4.0 Assumptions/Bases 5.0 Calculation 6.0 Results ATTACHMENT NO. TIT E UMB R OF PAG S HAS-4.JPN JPN Form jhj82C, Rev. 3/5

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90CI585A/DATASHT M A A EQUIPMENT Item 18 - Com onent Coolin Water Sur e Tank PART A. E(UI PMENT DESCRI PTIOH I.D. Number 4 Building RAB Manufacturer El evati on Other 71'odel Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condlt>on of nearby concrete an embedments <lm

3. Lengt , size, num er, an soundness o we ds

4. Anchor bo t type, size an number 2

5. Are nuts present and apparent y tig t on a o ts7 PART C. AHCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (expiate) cue~

2. Concerns i any PART Q. SPATIAL SEISNIC INTERACTION CONCHNS {if any)

PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE {PART C) OR (PART D) OR OTHER CNCERSS {ifany) s~

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0 AS-FOUND FIELD CONDITION ISOLATION VALVES NOT SHOWN LOCATED ON EACH SIDE 14'-8 LEVELCOLUMN FOR TRANSMITTER 12'/8" DIA BOLT

( TYPICAL 4 PLACES) cEL WIDE FLANGE {6X12)

UPPORT BEAMS 21'-4" STEEL I-BEAM 8" X8" 3/8" STEEL PLATES 33" 20" UNIT 4 CCW SURGE TANK SEISMIC MOUNTING WORKSHEET GENERAL NOTES

. DO NOT SCALE, USE DIMENSIONSTAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: UNIT 4 CCW SURGE TANK DRAWINGS FOR SAFETY RELATED WORK. DATE: APR 14 1990 DWG BY: FL GOULDY

AS-FOUND FIELD CONDITION

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Xkwrrz NEW FUEL HOIST CCW SURGE TANK SPENT FUEL BUILDING WALL STEEL GRATING X+

UNIT 4 CCW SURGE TANK SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING CCW SURGE TANK COMPONENT:

DRAWINGS FOR SAFETY RELATED WORK.

DATE: APR 14 1990 DWG BY: R. GOULDY

0 90CIS85A/DATASHT UPN A EqUIPMENT Item 19 - Emergency Diesel Generator Skid PART A. EQUIPMENT 9ESCRIPTION I.O. Number Building EDG Manufacturer Elevation

'Other 18'odel Number PART B. ANCHORA6E DESCRIPTION

l. Is equipment anchored? Yes Ho

2. Condition of gn orby concrete an embedmenta f

3. Leng h, si , num er, and soun ness o we s

4. Anc or o t type, size and number o.C.

5. Are nuts present an apparent y tig t on a PART C.~ ANCHORA6E ADEQUACY I.

~ Ooes Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISMIC INTERACTION CONCERNS {if any)

L' Jtl 5 PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART'C) OR (PART D) OR OTHER CONCERNS {if any)

)u r

DATE NAME DATE DATE

++~ f ] ENmmA3CY Zl WDE.L.

ALX'AOkA66 $ 5EC>

JVO~Am QPe&h.~w LaAM 5E(d 6, rnu~

G r cAT'aR WlAAQ t'E SNSivl ic GE.l&M( C IAYjjkACf7 ~ Md~kJVS Cmu6a b3ci~n spec,e vAn/K S(C ~i 1) ss Z3 ~omeauM )PEPCACES&v7 bligh P PM517C c)n e)re~ <le.aha msgr )xc.

Inter-Office Correspondence To: Oate: February 17, 1992 K. Greene From: R. Gouldy OePartment: JNL 92 35 Sohject 3A L 3B Diesel Generator Cooling Water Sight Glass Review I Per the request of Nuclear Engineering, a review of the A46 Seismic Review Team's recommendatlon to replace the 3A 8 38 glass sight glass on the skid mounted diesel engine cooling water surge tank with sight glasses made from a plastic material has been completed. A site inspection was performed on February 10, 1992 to review these sight glasses. Mr. G. G. Thomas of Stevenson and Associates was with me to help evaluate any spatial interactions or other problems associated with these sight glasses. During the St. Lucie Unit 1, A<6 walkdown, the same concern of the glass sight glasses was raised by the SRT.

However, during the discussions concerning the ruggedness of glass, it was noted that the diesel engine starting loads imposed by the diesel engine fast starts are much greater than the .1g earthquake loads. Therefore, at St. Lucie, the SRT did not recommend the replacement of the glass sight glasses considering the number of times this diesel had fast started since their installation. At Turkey Point the 3A ED/G has fast started over 700 times and the 38 ED/G over 1000 times without failure of these sight glasses. Therefore, they are rugged enough for continued use.

The next area to be addressed was that of spatial interactions with near by equipment. During the Dual Unit Outage, both emergency diesels received numerous upgrades. These upgrades afong with equipment near by were examined to determine if impact could occur during a beyond-the-design-basis earthquake. We did not find any piping, cabinets or equipment that could come in contact with or was located over head that would create a seismic interaction. Photographs of the diesel area are provided on the attached.

==

Conclusion:==

The replacement of the sight glasses with a plastic material should not be a requirement since the existing sight glasses have demonstrated their ruggedness and there were no spatial interaction concerns identified on the February 10 site inspection following the 3A and 3B diesel upgrade.

Should there be y quest ons egarding thfs inspection and evafuatfon, pfease contact me.

ussell Goul, PE Member, Seismic Review Team Form 100S Istocked) Rcv.!

0 0

AS-FOUND FIELD CONDITION 33 ~

4 tl 2t 5 ~

O GM 20 CYLINDER DIESEL ENGINE 0

THE SRT NOTED THAT OPERATING LOADS VERIFY ADEQUATE ANCHORAGE dpi'@

DIESEL ENGINE GENERATOR 1" DIA ANCHORS 4 'w XX

~Y B DIESEL GENERATOR SKID DIESEL GENERATOR SEISMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 8 DIESEL GENERATOR SKID DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 22 1990 DWG BY: R. GOULDY

90C1585A/DATASHT AT EQUIPMENT Item 20 - EDG Air Start SkH-~~gvVk&

PART A. EQUIPMENT DESCRIPTION I.D. Number Building EDG Manufacturer Elevation 18'ther Model Number PART B. ANCHORAGE DESCRIPTION

1. Is equipment anchored'es No

2. Condition of nearby concrete an embedments

3. Length, size, num er, an soundness o we s s~cA4 %5~ o4 L Au lm

4. Anc or bo t type, size an numbe t " ~

5. Are nuts present an apparent y tig t on a o ts?

PART C. ANCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment v

b. URS Tables

c. ANCHOR Progr am

d. Other (explain) m.vi A,a)c gals ~Et BQ.grv s (C L

2. Concerns i any PART D. SPATIAL S SNIC INTERACTION CONCERf5 ( any)

L PART E. RECOMMENDED CONSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

DATE NAME DATE NAME DATE

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DlESEL GENERATOR AIR START TANKS SEISMlC MOUNTING NORKSHEET G ENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERiNG DRAWINGS FOR SAFETY RELATED WORK COMPONENT: DIESEL AIR START TANKS DATE: MAR 22 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION A DIESEL GENERATOR ROOM

~ POURED CONCRETE WALLS gpx@j?Wgg'a~i~jg(@>>~Yg3pg@pg@V".'gp.,kgb)jv>jq <~q+p(g~ypy i<<'"'~55<<."<<ja+<@4+%$ wX4%%%5'.~4~F~4>>

EXCITER CABINET g

"(

B DIESEL/GENERATOR

gC .ij3:.

qg p$?g ~k AIR COMP gp~

LOCALCONTROL

i PANEL AIR TANKS g pP OOOO ".'; RADIATOR/FANASSEMBLY THERE WERE NO SEISMIC INTERACTION CONCERNS NOTED BY THE SRT. B DIESEL GENERATOR SKID SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38(4 GL 87-02 WALKDOWN . SKETCHES ARE INTENDED TO BE AN AID IN THE EQV I PM ENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: B DIESEL GENERATOR ROOM DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 22 1990 DWG BY: R. GOULDY 90C1585A/DATASHT 0 NT U PM ATA S Item 21 - EDG Fan Assemblies EQUIPMENT PART A. EOUIPNENT ItESCRIPTION I.O. Number building EDG Manufacturer Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored2 Yes No

2. Condition of nearby concrete and embedments

3. Length, size, number, an soundness o we s pic~ t Anc or o type, size and number

5. Are nuts present and paten y tig t on a o ts2 PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other {explain) E)

2. Concerns i any PART D. SPATIAL SEISMIC INTERACTION. CONCERNS (if any)

PART E. RECNNENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART 0) OR OTHER CaeERNS <<f any) PP V DATE DATE NAME,. DATE AS-FOUND FlELD COND1TION SEE DETAILBELOW TYPICAL o o ~ J BOLTS ~ BEARING SUPPORT o o (2 PLACES) SELF-DRILLiMG ANCHORS DlESEL GENERATOR FAN ASSEMBLY SEISMlC MOUNTING WORKSHEET GENERAL NOTES . DO NOT SCALE,'USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38L4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: D/G FAN ASSEMBLY , DRAWINGS FOR SAFETY RELATED WOFK DATE: MAR 22 1990 DWG BY: R. GOULDY 0 AS-FOUND FIELD CONDITION A DIESELGENERATOR ROOM gl% @l>> ~ POURED CONCRETE WALLS >>SR~:4>>>><"4RRi:O'.SAND:<4": <<'aNA%4:e<<t%<gg@N@>><<x""".'~<>XC>>&iz~4~4 EXCITER CABINET B ~Z<< DIESEUGENERATOR AIR COMP ~5 LOCALCONTROL C;gC 'P)- PANEL OOO 0 >>54 g~>>N;:.::~~,<<~@@:! z<<>.gybe,:>greg>>. <~mr ..+a~.y>>gv~gg;P@N): ".,::.-"'ADIATOR/FAN ASSEMBLY THERE WERE NO SEISMIC INTERACTION CONCERNS NOTED BY THE SRT. B DIESEL GENERATOR SKID SEISMIC INTERACTION NOR KSH EET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN . SKETCHES ARE (NTENDEDTOBEAN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: B DIESEL GENERATOR ROOM DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 22 1990 DWG BY: R GOULDY 90C1585A/OATASHT RK POI 4 UPM A EgUIPHENT Item 22 - EDG Local Control Panel B PART A. EQUIPMENT Pj'SCRIPTION I.D. Number st.12 Building EDG manufacturer Elevation 18'ther Hodel Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedments 3.. Len t (i, size, number, an soundness o we s c. KAc 4) aR

4. Anc or bo t type, size and number tV W

5. Are nuts present and apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY 1.~ Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables c.

d. ANCHOR Progr am Other (explain) C ~ (~~la.

2. Concerns (i any PART D. SPATIAL SEISNIC -INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE, (PART C) OR (PART D) OR OTHER CONCERNS (if any) DATE DATE DATE V l 0 S C EGCaggs~a A CAzcuM7mD ~u~~gziac me m~~ Ca~~<<~. CPM<<+ ~ gpss~~ QQGQLNi L MELD CAPACiTJ. AS-FOUND FIELD CONDITION p>i+)K%ig~M~~g~x~~j .,jg~>@sQ<ggxpjx<gx"~@@@'jQj< 4 CABLE CHASE 55" WITH DIAMOND PLATE COVER Cg WE%ED 1 1/2" FILLET WELDS 33 INCHES APART EACH SIDE 40 B DIESEL GENERATOR LOCAL CONTROL PANEL SEISMIC MOUNTING NORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN.

PTN 3L4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE ANCHORAGE EVALUATION. SEE ENGINEERING EQUIPMENT ANCHORAGE SKETCH DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: LOCAL CONTROL PANEL B D/G DATE: MAR 23 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION A DIESEL GENERATOR ROOM O';F;. (pgj ggs'jv)g ~ POURED CONCRETE WALLS p:, ~"':",,?.:,'.",'i<:,'< "m ~ . g~.;;,; EXCITER ei CABINET ?? 4 gaP B " ?? DIESEUGENERATOR g g??4 i~gj e4 AIR COMP LOCALCONTROL PANEL AIR TANKS kx @~xY~g~?'gg@?? ~% zj. 4k ?g~",~? ~?~~:('VP~n'".%~"~ "~'~A)i+I QQQQ @YF4%:~ "AiVV4-Plm:@'@A. %~+.-'"':"4'ADIATOR/FAN ASSEMBLY THERE WERE NO SEISMIC INTERACTION CONCERNS NOTED BY THE SRT. 8 DIESEL GENERATOR SKID SEISMIC INTERACTION WORKSHEET GENERAL NOTES . DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN . SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EYALUATION. SEE ENGINEERING COMPONENT: B DIESEL GENERATOR ROOM DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 22 1990 DlNG BY: RGOULDY SUBJECT JOB No. SHEET QF STEVENSON R ASSOCIATES cohrurtlng engrheerlnp flrrh I~ - - I ~ ~ I J ~ I I ~ N r 1 .~fir<<.- ~ ~ ~ = ~ - N 0, ~1~ 0 f <t s~ (pJAl KQ (0.13)) 20: QpC.>I / << I SUBJECT JOB No. SHEET QF O 438 EO STEVENSON ill R ASSOClATES 0 StIUCtUTOI.EIUEChOAICO1 COIIEUtttITP OIIPIISOEFIIOP tlhlh I +-. 1 l 1 ~ 4 I 4 J f 1 4 I 4 l k i it, II 4 ~ I I I E 1 P 4 I" ~ II 1 I ~ ~~ II ~ ~ ~. I'h = 4 9 0C1585A/DATASHT R PO UN UIPN DATA EQUIPMENT Item 23 - 480V Motor Contro1 Center 3B PART A. EQUIPMENT DESCRIPTION I.D. Number 3B06 Building Contro1 Manufacturer Elevation Other 18'odel, Number PART S. ANCHORAGE DESCRIPTION I. Is equipment anchored? Yes

2. Condition of nearby concrete an embedments

3. Length, size, num er, an soundness o we ds

4. Anc or bo t type, size and number

5. Are nuts present an apparent y tig t on a o ts?

PART C.~ ANCHORAGE ADEQUACY I. ~ Does Seismic Capacity of Anchorage Exceed Demand? +q

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) 'SPAN MQ,Lck Do m.c.

2. Concer ns i any PART D. SPATIAL EISMIC INTERACTION CONCERNS (i f any)

PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) DATE DATE DATE 0 0 4800 N xn. C ~oi C~~a. VcMm MP7 aEA~ uueLWS A~ C~NK AAcA&MSG MQ lv6ms A~a. GLED ~<<~ CAW Q~ g 56'g mod- sraoc roue~ ~ pvO Sr'AW ~ AM Wi'~5 Q<pom gg CKFal& &BLDG JU ~4 POURED CONCRETE WALL AS-FOUND FIELD CONDITION 4" CONDUIT 20 08 giikiYixMKj$ i%k9 ii'g', cM<'c 'j"'i4~a44i@4 >i+>g> Vjwsgp(F(+'jp ~>)(PCP6jPgj~@ggg:c.~N ~~jj~(j(4~a~j)$%&(p(xg)g(j<~@h+<h~<~P>Sgg SEAL WELDS 2" LONG MOTOR CONTROL CENTER 3B 24'TN ELECTRICAL EQUIPMENT MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. 354 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: 3B MCC DATE: MAR 22 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION POURED CONCRETE WALLS 'AM%~~"~%'~4%~~i.'~~4!""'~'>F484~>Y~~~VR5%%%P%%Y%%%mm5S THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERN WITH THIS ROOM OR THE MCC CONTROL ROD POSITION MCC 3B AND COMlROL CABINETS 94Ai!h~%!@8 MOTOR CONTROL CENTER 3B SEISMIC INTERACTION VfORKSHEE GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 354 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B MCC DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 23 1990 DWGBY: R.GOULDY

90G1585A/OATASHT tjlPN ATA EQUIPMENT Item 24 - 480V Motor Control Center 48 PART A. EQUIPMENT DESCRIPTION I.D. Number 4806 Building Control Manufacturer Elevation 18'ther Model Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an~embedmenta

3. Lengt , size, num er, and soundness o we s

4. Anc or bo t type, size an num er

5. Are nuts present an apparent y tig t on a o ts2 PART C. ANCHORAGE ADEQUACY P

l. Does Seismic Capacity of Anchorage Exceed Demand2

a. - SRT Judgment

b. URS Tables

c. ANCHOR Program '

d. Other (explain) 0 id o *M

2. Concerns i any)

PART D. SPATIAL SEIQIIC INTERACTION CONCERNS (i f any) PART E. RECONENDED CONSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS {ifany) NAME DATE DATE NANE DATE ~) INoro~G~~~~ ~~ -~> aucAQMC~~ p,Q Q4gkAS+ i POURED CONCRETE WAG AS-FOUND FIELD CONDITION 1/4" BOLTS (6) CABLE TRAY CABLE TRAY 4" CONDUIT 20" 00 (gpR+Q4 4+< VAYQ'i%ix~c ~X++i <%%%::k"",.@C@%44~~%iX%k4@R~~~':;X% 44Ãk@%4~%>~~ '494@+C<4) NO ANCHORAGE COULD BE FOUND, ONLY SHIMS AT THE BASE MOTOR CONTROL CENTER 4B -24'TN ELECTRICAL EQUIPMENT MOUNTING WORKSHEET

f. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: 4B MCC DATE: MAR 22 1990 DWG BY: R GOULDY AS-FOUND FIELD CONDITION POURED CONCRETE WALLS 4%+'%%%@SMNNWN Ck%P~"~&KM%,.MR4%%~'8k%%FZ~% MCC 4B CONTROL ROD POSITION AND CONIROL CABINETS jC cf THE SRT DID NOT NOTE ANY SEISMIC 4wi4ii~k+x.:~4 INTERACTIONS CONCERN WITH THIS ROOM OR THE MCC MOTOR CONTROL CENTER 48 SEISMIC INTERACTION MfORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT'B MCC DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 23 1990 OWG BY: R.GOULDY

90C1585A/DATASHT 0 M A E(UIP MENT Item 25 - 480V Motor Control Center D PART A. EQUIPMENT DESCRIPTION I.D. Number B08 Building RAB Manufacturer Elevation 18'ther Model Number . PART B. ANCHORA6E DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedments

3. Lengt , size, number, and soun ness o we s

4. Anchor bo t type, size and num er S S,hcowQ Olv

5. Are nuts pr ent an apparent y tig t on a o tsar PART C.~ ANCHORAGE ADElgACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns (i any)

PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any) PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS <<f any)~H ~ ~cr akc ~tl m F c. lee4ncD DATE DATE DATE TB< S~ lQAa@M A SH~ C'AWm~mQ ~ "BD 8E PER A ~En FarZ TOE SeM -33K,<LL 0 C ~ hkc8oM lie~. ~octo 4hcof 6 Ti. E-f5ACK. SQ. CC)UMf& bJR LL le tdSYR LLEW eQ i BC. WP mr- mW N ~. AS-FOUND FIELD CONDITION 4 CONDUIT 20" .C(> 't;~j"~c 4:~4..,. 0 ?? .Pk j.c>iQ g;....,?$ jC 5 ('<<?.q)iAQ??,i+?'???P?'k<ikg?). b~'<<. pl,, NxMqg<<4~?',;:;:?".,:c ?.~ih+? jan%(<<QN'Hi>'i4. +gp%%&AXW~~ +%%%'jR~'~'?$ >~s@g~~gj>C~%>>ggjggN~'-'"" jNP444?;.g<<.+pic'",<<'.<<"'<<?~~<<".'Ã~j4@!C(: gk<<"<<%&p8%+g~~P'"'> 'NCHORED WITH BOLT AND WASHER ARRANGEMENT SEE NEXT PAGE MOTOR CONTROL CENTER D 26'TN ELECTRICAL EQUIPMENT MOUNTING WORKSHEET

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. 38c4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH

~ ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: D MCC DATE: MAR 23 1990 DWG BY: R. GOULDY AS-FOUND FIELD CONDITION 302 262 1" DIA 240 2 3/8" DIA 180'/8" 202" 142" BOLT 120'2'2'/8" SELF-DRILLING ANCHOR BOLT 20'TN MOTOR CONTROL CENTER D ELECTRICAL EQUIPMENT MOUNTlNG WORKSHEET

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: D MCC DATE: MAR 23 1990 DWG BY: R GOULDY AS-FOUND FIELD CONDITION NK@j< THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERN WITH THIS MCC. )jP 4 OPERATORS FIELD ROOM S 0) a X MCC D 4jtg hg>%i%%."'%>>Xi; MOTOR CONTROL CENTER D SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSGNS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: D MCC DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 23 1990 DWGBY: R.GOULDY

SUBJECT JOB No. SHEET OF STEVENSON 8( ASSOCIATES 0 SttVCIVPOSthOChohlCOI CohSVI'Ilhg 4hgIh44tlhg Iltfll I P I h a i 'CP It 'I tt I 'I P It ' h mego 3 0.. 7&g h h*<< /)II I gw = /e p, /r x tt'/5' j'i' 3 " I/F'P/I/' "'/Pt =Boa 90C158SA/DATASHT EQUIPMENT Item 26 - 4.16 kv Switchgear 38 PART A. E(VIPMENT DESCRIPTION I.D. Number 3AB Building LC-Swgr Manufacturer MC Elevation 18'ther Model Number PART 8. ANCHORAGE DESCRIPTION

l. Is equipment anchored2 Yes No

2. Condition of nearby concrete ancC embedments

3. Lengt , size, number, and soun ness o we s

4. Anc or bo t type, size an numbers

5. Are nuts present and apparent y tig t on a o ts2 PART C.~ ANCHORAGE ADEQUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (i f any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) NAME DATE NAME DATE + NAME DATE &34M ~ f (o0 kY l Sbinc86eAR MRAhJGGtnQnJ'T. bio &Jc.fk)~ ARE'lat AU&OQ iH<&~~Pe~, ~ i eL 8K ~SOD Law ~ aAcktoks i~rrau u0 wn neu~ USI - A.-4 P~6,~~ iPGQ.~iaE~~ AS-FOUND FIELD CONDITION p . y~!))<< 3B 4160 BUS 26 36 26 26 36 26 13 CUBICLES AT 26" EACH 3B 4160 v SWITCHGEAR SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B 4160 SWITCHGEAR DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 28 1990 DWG BY: RGOULDY AS-FOUND FIELD CONDITION THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS WITH THIS ROOM OR THE SEQUENCER 3A 4160 BUS ROOM POURED CONCRETE WALL HOT SHUT SEQUENCER DOWN PANEL 3B 4160 BUS 38 4160 v SWITCHGEAR ROOM SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B SEQUENCER . DRAWINGS FOR SAFETY RELATED'WORK DATE: MAR 28 1990 DWG BY: R.GOULDY 90C1585A/DATASHT 0 PM A E(UIP MENT Item 27 - 4. 16kv Switchgear 4B PART A. EQUIPMENT DESCRIPTION I.D. Number 4AB Building LC-Swgr Manufacturer Elevation 18'ther Model Number PART B. ANCHORAGE DESCRIPTION

1. Is equipment anchored? Yes No

2. Condition of nearby concrete a~n embedmenta

3. Lengt , size, num er, an soun ness o we s

4. Anc or o t type, size an num er

5. Are nuts present an apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY

~ 1. ~ Does Seismic Capacity of Anchorage Exceed Demands QC).

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other {explain) A

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS {if any)

PART E- RECONENDED CONSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CNCERNS (if any) DATE 3 0'ATE RANE DATE X%M L- I Q.lhG kv SKI RaU) cw~ i AE. ~ i'd Sew~ KkP Av6,e'~~. Dn A~~ Alt u5~ 4~ Wis i m4 14k~. 'To yv en+ QS l - A-4 h'hn~ ev&iMCF~~ ~~~ "< < AS-FOUND FIELD CONDITION 4B 4160 BUS 26 36 26 26 36 26 116 13 CUB(CLES AT 26" EACH 4B 4160 v SWITCHGEAR SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B 4160 SWITCHGEAR DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R. GOULDY AS-FOUND FIELD CONDITION OUTSIDE TURBINE AREA POURED CONCRETE WALL SHUT DOWN PANEL 4160 BUS A 41 60 v BUS ROOM 48 4560 v SWITCHGEAR SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B 4160 SWITCHGEAR DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 281990 DWGBY: R.GOULDY 90C1585A/DATASHT P N EQUIPMENT Item 28 - 48QV HVPDS Load Center 3B {Includes Transfdemer) PART A. EQUIPMENT DESCRIPTION I.D. Number Building Manufacturer Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored2 Yes No

2. Condition of nearby concrete a~n embedments

3. Lengt , size, num er, an soun ness o we s

4. Anc or o t type, size an num er

5. Are nuts present an apparent y tig t on a ts?

PART C. ANCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEIQlIC INTERACTI pJ N C (if any)

PART E. RECOOIBSKD CNISE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CNCERNS (ff any.) OATE DATE S DATE PW 5 PW MAt Y lXMQ  %="2@A, ~o~ 6 oT lds<ALLKD. R ~ AQV PACH<~C 8 Fo'W %IS 4 akAACSo~a vcn~a Tahar TAL L.C F4& C~aibC ~ 5e ~Oiv IM/&PACED au6dC -1=6% UP.<em~ ~o C ~e<~eC.v'o~a uPC~ ~C c~sc c. Swami c. [D~~mm4 Cmd~~ MERE UO>iO SLo~ Mat ~~ Aac P<we~ i4 'TRK Ra&~ 4 A- 4k'ekQEM hl~ ~oLVEo &cavd bLodc ~ps ~~ &LF +ICKY 4 oJ~ PAW GF cA~ GsNEec. LCD, bIn~ u)a i1 ( wALL. A&&8'KR5 7 3/- /Q Auo ~ z~ C AS-FOUND FIELD CONDITION (>44%45 <<4&ii@4Pi~k@~i%%@i% TRANSFORNER TRANSFORIVER N~~"igk+gXX~gQ((g~y>xg( A LC B LC TRANSFORMER TRANSFORMER $%%%((%%K(wax% NWR%KO>%%-c@w%%%(ON%%(((.@%%ON%%(%%4iÃ4%%%%%%(i%%('WW'RRYA%%RP:: $g gx ~$ 'a M (,',( ~ W:... i~ 'M%, M, 'k~@ ~.'P~ sÃg~,P A <<< ".. QK': i(, %W',XCF ':('x'"" " NO ANCHORAGE CAN BE DETERIIIIINED FROM THE FIELD INSPECTION 480 VOLT LOAD CENTER 38 SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WAI KDOWN "KETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION, SEE ENGINEERING COMPONENT: 480 V LOAD CENTER 3B DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 28 1990 DWG BY:

AS-FOVND FIELD CONDITION THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERN WITH THE LOAD CENTERS OR THE ROOM. CONCRETE BLOCK WALLS WERE FOUND BUT WERE LOW IN THE ROOM AND WERE COVERE D BY THE BLOCK WALL GENERIC LETTER IMPROVEMENTS TRANSFORMERS TRANSFORMERS A C D 480 VOLT LOAD CENTER 3B SEISMIC INTERACTION VfORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN KETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATGN. SEE ENGINEERING COMPONENT'80 V LOAD CENTERS DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: 9OC1585A/OATASHT EQUIPMENT Item 480Y HVPDS Load Center 30 n d PART A. EQUIPHENT DESCRIPTION I.O. Number 3B04 Building manufacturer Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored'es No

2. Condition of nearby concrete a~n embedmenta

3. Length, size, num er, an soun ness o we s

4. Anc or o t type, size and number

5. Are nuts present and apparent y tig t on a PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity of Anchorage Exceed Deaand?

a. SRT Judgment

b. URS Tables

c. ANCHOR Pt ogram

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS i f any) k) mls (e veyio PART E. RECONENED CNRSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CNCERNS (if any)

.NAME OATR P Jr DATE DATE ~ zq 9ec~ HvPls ~ - ED PW ~ PW MAt K.&Md fbi~ ~u~ 6 oW Ft ~ A4V Io,AGH~DC e FoW %IS ldmALLPYuk M~ ~~D TAN %IS LC 'f 7 gANFo~A C~O~QC m fe ~0~~IaQIMWWCn) nuVVC DP cs&w >4 6 ~M.cEAC.Y &uJEA UPC~ Rued C)QTR&G. SB5mi c. I D~kumm4 Mg ~~ ~~ x)0~ SLo~ Ro~ma, ~c P<we~ t0 'TRK l2C3~ LA- khJL. CALCEM h)92k ~oLV~ krauM NEbLo'ck ~N ~re MLF WI64t 0 el~ PAW OF WM GbNMI4 LQ4M. blocIC ural~ g~G Cne. (m4z( M vMZ <Qs 7=Pl- IA ~~a ~ Pl AS-FOUND FIELD CONDITION TRANSFORMER lRANSFORhER 'jhow j<kxjjxx~gi~x+x~+a<w aji@+yPj C LC D LC TRANSFORMER TRANSFORMER SAWS%))N%'<<8>%Six@ SkW .N'w'sx+84%N'<<0%%%; <0 M+M<<<." R<N4%5%iWRNRi<KNNWS5 <5+NN%NN< .<<RN%84<SK4@<lNXh%; "< NO ANCHORAGE CAN BE DETERMINED FROM THE FIELD INSPECT(ON 480 VOLT LOAD CENTER 3D SEISMIC MOUNTING WORKSHEET GENERAL NOWS

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-D2 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 480 V LOAD CENTER 3D DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: ~m 90CI586A/OATASHT 0 UN 3 PM ATA EQUIPMENT Item 30 - 480V HVPDS Load Center 4B Includes Transformers) PART A. EQUIPMENT DESCRIPTION I.D. Number 4B02 Building LC-Sw r Manufacturer Elevation 30'ther Model Number PART B. ANCHORAGE OESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete a~n embedments

3. Length, size, num er, an soundness o we s

4. Anc or o t type, size an number

5. Are nuts present and apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demand? /P~

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (exp?ain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (i f any)

PART E. RECOISENQEQ COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) PR DATE << ~i l~s NAME DATE DATE Wa Z%m M 5 PW PALYThingDEME ~%V ~u~ Q aT outed ygcHmwc e FoW Mls idsrALl.k&. ecn~D MlS LC. 4 TKA&e~~8. hQ& C~o ~dc fD 5E ~Oi v (kQ /&PLACFJ3 C UP.ram& i 4 6 ~FL&FAC.V Wu3EA L)PC> ~C cxmsC C, (v~M~~4 Gnvcx~ P~~ MA~ma, &ac PeWe~ tQ 77K l2QC)~ 4A 44I CALCEM hi0dh ~bLtlEO &eau~ 'T4& bLock ~ l4 ~le'4ALF lklGAT 8 td EPJ OF <~ GsHM(4 LQ4M. blocK ula A Pw6cne. (~Hue. rvuwS'MS ) -3 I-18 beg T- 3(-3 ~g AS-FOUND FlELD CONDlTlON iw w TRANSFORMER TRANSFORMER eNi~44:4')ii~)X'Ak~k%4!': A LC B LC TRANSFORMER TRANSFORMER >) RXCh P >,"0&VA)'W,CN%>N'NNX)M) NW%0%'&WO>'>>)'%%).&>.ANN).NA)A%%)N"NÃN.MA%))':.> '>:KANS><M~'N; )M4%%%N%NN) 4"'O ANCHORAGE CAN BE DETERMINED FROM THE FIELD INSPECTION 48D YOLT LOAD CENTER 48 SEISMlC MOUNTlNG WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 480 V LOAD CENTER 4B DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY:

AS-FOUND FIELD CONDITION THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERN WITH THE LOAD CENTERS OR THE ROOM. CONCRETE BLOCK WALLS WERE FOUND BUT WERE LOW IN THE ROOM AND WERE COVERED BY THE BLOCK WALL GENERIC LETTER IMPROVEMENTS 4~x@i e R. ~i%~ RgiiCCi@ @~M~@ gxQiygxmeN~a+sgii~ic ~~xi~gii~~i~~m ~g'ie ~iiQ~g~~~~g+0 4SO YOLT LOAD CENTER 4B SEISMIC INTERACTION VfORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL S7-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT'80 V LOAD CENTERS 'RAWINGS FOR SAFETY RELATED WOFK DATE: MAR 28 1990 DWG BY: 90C1585Adt'DATASHT U T EgUIPHENT Item - 31 480V HVPDS Load Center 40 Inc1udes Transformer PART A. E(UIPNENT DESCRIPTION I.D. Number 4B04 Building LC-Sw r Manufacturer Elevation 8d'ther Model Number PART B. ANCHORAGE DESCRIPTION

1. Is equipment anchored'es No

2. Condition of nearby concrete a~n embedmanta

3. Length, size, number, an soundness o we s

4. Anc or o t type, size and num er

5. Are nuts present an apparent y tig t on a o ts?

0 PART C. ANCHORAGE ADElgACY

1. Does Seismic Capacity of Anchorage Exceed Oemand2 4o

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) v

2. Concerns i any PART D. SPATIAL SEISNIC INTERAC ION CONCERNS (if any) ants j vI.

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR {PART D) OR OTHER CONCERNS (if any) DATE DATE NAME DATE 5 PW PALY D~Q au%, ~0~ 6 oT p,gq y,QCHomC e PoW %IS IU~ALLRuk ~~a TR< MlS LC 0 Tk4<so~8 IGQ /&PLACFJ3 DUG dC A@M C~D)DC fD 5E 1%50>t c ~v<~ec.v R~w uPc< mam= PC'P.c.em~io DQTR&G. ~SAKI C. t 6 fFAAM~W Cjoy ~~/ IIJ~ l~~ LJ~L ~ &ac P~~e~ ~4 'TRK ~oLIEo kraum RQ~ 4 A 44L M4QEM vJGh NK PA& -h OF PnG'Cne Loden', <~ l.4 we.ee SenlMIC. (~HE(. ~uW8$ 8S za) MLF 4Rkk. iWI C JJT 0 blocK uJall Sl- 5I uJ ekr. AS-FOUND FIELD CONDITION . "w .ww.:. w. w ..w>>>>; eNc&4&>(%% >((i(M&y 'c TRANSFORMER TRANSFORlvER (+iZ>>>>(>!,"'.>>(((iy%@('xP'k(((>>>>'j( C LC D LC TRANSFORMER TRANSFORMER >>>>> >>>A(>>>>..N'(4>> kA(>>>>>(>(>> '>>.>>lh; > (((> N((>>>>. >NSW'::.e,"e> ixminie>>i s>> (e > i(e>>>c"e>eeWaea4%%(%%'>>>>>%5(>>>N a(Ã'>N ~ >(<, . > ~ g~>3 (g ~ ~ ~ '4, +x< >. ~ >> (> ...~ >,. +~@ Q. NO ANCHORAGE CAN BE DETERMINED FROM THE FIELD INSPECTION 480 VOLT LOAD CENTER 4D SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 480 V LOAD CENTER 4D DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: AS-FOUND FIELD CONDITION THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERN WITH THE LOAD CENTERS OR THE ROOM. CONCRETE BLOCK WALLS WERE FOUND BUT WERE LOW IN THE ROOM AND WERE COVERED BY THE BLOCK WALL GENERIC LETTER IMPROVEMENTS '1TNNS FORMERS TRANSFORMERS C D 480 VOLT LOAD CENTER 4D SEISMIC INTERACTION WORKSHEET GENERAL NOTES . DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN . SKETCHES ARE INTENDED TOBE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 480 V LOAD CENTERS DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: 90C1585Adt'DATASHT EQUIPMENT Item 32 - 480VLoad Center (PZR Htr.) PART A. EQUIPMENT DESCRIPTION I.D. Number Building LC-Sw r Manufacturer Elevation 30'ther Model Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored? Yes No

2. Condition of nearby concrete an embedmenta

3. Length, size, num er, an soun ness o we s

4. Anchor bo t type, size and number > '

5. Are nuts present and apparent y tig t on a o ts?

PART C.~ ANCHORAGE ADEQUACY l. ~ Does Seismic Capacity of Anchorage Exceed Demand?

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (expiain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) NAME DATE NANE DATE NAME . DATE AS-FOUND FIELD CONDITION UNISTRUT FRAME THE SRT APPLIED FORCES TO THIS 4" CONDUIT CA8INET AND DETERMINED THAT IT WAS VERY WELL ANCHORED UNIT 3 PRESSURIZER HEATER LOAD CENTER SEISMIC MOUNTING WORKSHEET GENERAL NOTES . DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN . SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT:UNIT 3 PRZ HEATER LOAD CENTER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 3990 DWG BY: R.GOULDY AS-FOUND FIELD CONDITION THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERNS FOR THIS ROOM POURED CXNCRETE WALL NORTH ELECTRICAL PENETRATION ROOM CABLE TRAYS ...~, ...~V,,~$.,b,M.4'p~,;,,:.. ~<a,,g. CONTAINMENTWALL UNIT 3 PRESSURIZER HEATER LOAD CENTER SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 3&4 GL 87-02 WALKDOWN FIELD WALKDOWN.

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUI PM ENT ANCHORAGE SKETCH ANCHORAGE EVALUATGN. SEE ENGINEERING COMPONENT: UNIT 3 PRZ HEATER LOAD CENTER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDV

90C1585A/DATASHT U PNENT A A Item 33 - 480 V Load Genter )PZR'Htr.) EQUIPMENT PART A. EOUIPNENT ffffRIPTION I.D. Number Bui1ding LC-Swgr Manufacturer E1evation Model Number Other PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedmente

3. Length, size, num er, and soundness o we s

4. Anchor bo t type, size and num er S

5. Are nuts present and apparent y tig t on a o tsar PART C.~ ANCHORAGE ADE(UACY l.

~ Does Seismic Capacity of Anchorage Exceed Demand2 ~

a. SRT Judgment

b. URS Tab1es

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART 0. SPATIAL SEISMIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) NAME DATE DATE DATE AS-FOUND FIELD CONDITION <<ei'Vc?)~V'q'Pj@<

ccÃA?<<?<<? '%~%A'<<?ij'~>'k~j""?p$y."~4Sy@$$j'y/p>g'k~, ~P.,:,'j'?'~(/gal'~ay'i" @ppa%r@gi,.@@/<4~ 0 0 0 0 THE SRT APPLIED FORCES TO THIS 4" CONDUIT CABINET AND DETERMINED THAT IT WAS VERY WELl ANCHORED ~ UNISTRUT FRAMING UNIT 4 PRESSURIZER HEATER LOAD CENTER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 3&4 GL 87-02 WALKDOWN FIELD WALKDOWN.

SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT:UNIT 4 PRZ HEATER LOAD CENTER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY 0, AS-FOUND FIELD CONDITION THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERNS FOR THIS ROOM POURED CONCRETE WALL NORTH ELECTRICAL PENETRATION ROOM CABLE TRAYS CONTAINMENTWALL UNIT 4 PRESSURIZER HEATER LOAD CENTER SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 38c4 GL 87-02 WALKDOWN FIELD WALKDOWN. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATGN. SEE ENGINEERING COMPONENT: UNIT 4 PRZ HEATER LOAD CENTER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOUTY 90C1585A/DATASHT 0 PMENT DA A SH EqVIPMENT Item 34 - Battery Char er 38 PART A. EQUIPMENT DESCRIPTION I.D. Number 3025 Building Control Manufacturer Elevation 42'ther Mode1 Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an mbedments

3. Length, size, number, and soundness o we s

4. Anc or o t type, size and num er

5. Are nuts present an apparent y tig t on a o ts2 PART C. ANCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables c.

d. ANCHOR Program Other (explain) d

2. Concerns i any)

'I PART D. SPATIAL SEISNIC INTERACTION CONCERNS (i f any) PART E. RECNNENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) DATE NAME DATE DATE 0 0 AS-FOUND FIELD CONDITION 62" 0 1/2" DIA ANCHOR BOLT "HILTI - P" 0 THIS BATTERYCHARGER WAS REMOVED AND THEN REMOUNTED WHEN THE INVERTERS WERE REPLACED IN 1986. BATIERY CHARGER 72 3/8" STEEL PLATE 8" FLOOR ELEV 58'K~~4~~(>.~<> "~y)Q s>A~g>~>>,~>+~4~ 1/4"THICK 2" ANGLE 38 BATTERY CHARGER SEISMIC MOUNTING WORKSHEET GENERAL NOIES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHESARE INTENDEDTOBEANAIDINTHE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B BATTERY CHARGER DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 23 1990 DWG BY: R. GOULDY AS-FOUND FIELD CONDITION ()W~ o.:)N~?+44%(>>>>N'Rk%+~NNe+8%hp'@@>>+a~'aaS~P.;:W@)p '0?i>>+ ~~ ->> '::(P'='MR+4+~>>RN" 4%>>>>>>WS@%~"+v.".A%R@rSW@@@ge)N 3D23 DC BUS 3YO2 4YO 4YO2 24" .4-I 25 h 3YO5 3YO6 4YO5 38 BATTERY CHARGER RAISED FLOOR BATIERY BATl'ERY FCOM FCOM THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. 3B BATTERY CHARGER SEISMIC INTERACTION WORKSHEET GENERAL NO'IES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 354 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B BATTERY CHARGER DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY 90C1585A/DATASHT 0 3 UIPM AT SH Item 35 - Battery Charger 4A EQUIPMENT PART A. EQUIPMENT DESCRIPTION I.D. Number 4D25 Building Control Manufacturer EK(M Elevation 42'ther Model Number PART l. 2. B. ANCHORA6E DESCRIPTION Is equipment anchored2 Condition of nearby concrete a~n Yes No embedmenta C ~ Coo

3. Lengt , size, num er, and soundness o we s

4. Anc or o t type, size an num er lg Are nuts present and apparent y tig t on a o ts2 PART C.~ ANCHORAGE ADEQUACY

~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any No PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECNNENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) OATE l to DATE NAME DATE QAi7k<Y CALMED ~@~MD P MuaJQ> AD)6, Ca&(~4~ PUG RcvieW ~P %6'>uaoinJC G tc.ulaf~ HMA6,C. (db)(ATCQ ADGROA76 Adc 0 0 AS-FOUND FIELD CONDITION 62 0 0 1/2" DIA GROUTED IN-PLACE ANCHORS 0 0 THIS BATTERYCHARGER WAS REMOVED AND THEN REMOUNTED WHEN THE INVERTERS WERE REPlACED IN 1986. BATTERY CHARGER 72" 3/8" STEEL PLATE 8" +~~%,'<> .' g~ j~+c+ mp~~py~&:..j@p M>:~;~c'<<v +g., PM j~~~~j@w~+x5~P" P; p ','""... j~': g>> ~ ...4,<w '.Ny ';w.'cP'~:.';:,',:"~:,;:~; FLOOR ELEV 58I ~'i,,;;:;;".'.".<<'.;."'.'"'/4"THICK 2" ANGLE 4B BATTERY CHARGER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWiNGS FOR SAFETY RELATED WORK. COMPONENT: 4B BATTERY CHARGER DATE: MAR 23 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION N4>?s'PPw43$ ~~8>?@c:"'>'k(PM4'.i'?PAksi'w>: ++'Nkk?>:::>k+%8kiA?>>C4N8<xw~%?>? 4D23 DC BUS 4YO1 24" 4YO7 ?g 25" 5y 3YO6 3YO4 24 II Cp) 3YO1 3YO7 '??$ k,? 4>>'.;"&M~<>'4+79? NN'MC?>>..??? ..M??:>:M'EN&?:K'WM?M??'g~ %y WMNRPM>?:??.".c '???NN9MKA>:?" BM '.Q??'>?.'> .S+NSN4~?W CONTROL ROOM THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. INVERTERS & BATTERY CHARGERS SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: BATTERY CHARGER DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY SUBJECT JOB No. SHEET OF O CO STEVENSON ut K ASSOCIATES o structurourwchcnlcot CC ccnsunlng cngtn44rlng tum I t r I f ~- f ~ f ~ I e II sf' C I + g(i).g~ f H 'I I H I Ij I 1 H f f~ ~ H 2.f; (2., h H 4 g2 (Q p) D.3)g ClL <<~'tr70 l ~J re'rS/j 4"3 H $ g/p I I I f I ~ e ~ ~ ~ I ~ ~ ~ Hhf r ~hel e p a7 90C1685A/DATASHT U PN EQUIPMENT Item 36 - Batter Char er PART A. E(UIPNENT DESCRIPTION I.D. Number 026 Building on r Manufacturer B 06 Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION 1. 2. Is equipment anchor ed'es Condition of nearby concrete an No embedments

3. Length, size, num er, and soun ness o we s

4. Anc or bo t type, size and num er S. Are nuts present an apparent y tig t on a o ts?

PART C.~ ANCHORAGE ADEQUACY 1.~ Does ~ Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. gabe (explain)

2. Concerns i any Vo PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) 1 DATE DATE O RANE DATE ~~ e 6o~a.~ C4 c.e~ 45 'TB6. S~ mA~D TIE, SHALTktE~~) ~~ Ca. ICU I eel~ fk0 kkodiVCl ) 46 ~ ~ ~4~> QQ QUCn c ]~1~4~ 6 im id'~ G l~l4~s < t ~em,e ~a~a>X 0 AS-FOUND FIELD CONDITION 0 0 1/2" DIA GROUTED IN-PLACE ANCHORS 0 THIS BATTERY CHARGER WAS REMOVED AND THEN REMOUNTED WHEN THE INVERTERS WERE REPLACED IN 1986. BATTERY CHARGER 72" 3/8" STEEL PLATE 8" 1/4"THICK 2" ANGLE 4S BATTERY CHARGER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 354 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: 4S BATTERY CHARGER DATE: MAR 23 1990 DWG BY: R. GOULDY

AS-FOUND FlELD CONDlTlON $%'+%)4%4Ã(4"'"AS'@44xdkdo<>>4%+4~.elc %4%NM %4@>'>>4 4D23 DC BUS 4YO1 24" 4YO7 g~ 25" g 24" 3YO6 3Y04 m5 3YO1 3YO7 vj CONTROL ROOM THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. INVERTERS 8c BATTERY CHARGERS SElSMlC INTERACTlON WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38(4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: BATTERY CHARGER DRAWiNGS FOR SAFETY RELATED WORK DATE: MAR 23 1990 DWG BY: R. GOULDY

31 90C1585A/DATASHT EQUIPMENT Item 37 - Batter Rack PART A. EQUIPMENT DESCRIPTION I.D. Number 3003 Building Control Manufacturer Elevation 30'ther Model Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedmenta

'3. Lengt , size, num er, an soundness o we s

4. Anc or o t type, size and num er

5. Are nuts present and apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other {explain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS QHEG60.

(if any) Sl o M LsPGh + PART E. RECNNENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) DATE DATE DATE Fo '5RW Q+Ui6'wazo VOdooM sasvn ~ C~l~l -r~ @~K QG5LC 6 . LJ lE~C;rW~ ~U~x'l A ~ r / d~(<)8a ~ ~ A, 5&lSMLC-LJ lh id &ouzo LE&dl6e k4 Ce~ l ~~ c -4 IPKSUE~ k4 ShakL ko k, kia.~iree. 4D Illa'. Cn~~~4 4lz>QC &g/Is C dac9 zan b~ kM S~. I AS-FOUND FIELD CONDITION THE SRT NOTED THE LIGHTS IN THESE ROOMS DID NOT NEED TO BE SAFETY WIRED TO THE FIXTURES BECAUSE OF THEIR SHORT LENGTH. THIS MINIMIZED THE PROBLEM OF SWAYING AND POSSIBLY COMING APART AND FALLINGON THE BATTERY BUS BARS. THE BLOCK WALLS IN THESE ROOMS WERE PART OF THE I&E BULLETIN80-11 IMPROVEMENTS FOR BLOCK WALLS. THERE WERE NO OTHER SEISMIC INTERACTIONS CONCERNS WERE NOTED 3A BATTERY ROOM CONCRETE FILLED BLOCK WALLS 4B BATIERY ROOM 30 FOOT ELEVATION CONTROL BUILDING 3A BATTERY RACKS SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN.

PTN 38c4 GL 87-02 WALKDOWN KETCHES ARE INTENDED TO BE AN AID IN THE ANCHORAGE EVALUATGN. SEE ENGINEERING EQUIPMENT ANCHORAGE SKETCH DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: 3A BATTERY RACK DATE: MAR 23 1990 DWG BY: R. GOULDY 90C1585A/DATASHT 0 M DA EQUIPMENT Item 38 - Batter Rack 3B PART A. EQUIPMENT DESCRIPTION I.D. Number 3D24 Building Control Manufacturer Elevation 42'ther Model Numb'er PART B. NCHORAGE DESCRIPTION I. Is equipment anchoredY Yes X No

2. Condition of nearby concrete a~n embedments

3. Lengt , size, num er, an soundness o we s

4. Anchor bo t type, size and number " " '

5. Are nuts present an apparent y tig t on a o tsar PART C.~ NCHORAGE ADEQUACY 1.

~ Does ~ Seismic Capacity of Anchorage Exceed Demand?

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISMIC INTERACTION CONCERNS (1 f any) 6 Cic- lL PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

RANE / DATE NANE DATE DATE SR% PEUlGWGD VQVQM 5Elsm a (elec/1 4~ QG5MQ. EAsw Duo w~s n/<~~ l~~~~ Cu>U~KEJ M~ r J i >Ca ~ A, SEXISM LC-LJkid uouuo PEG)u)k.e kM Ceil>ic 4c 4k'o 4'4 Shac4 & kC ~ LuiMD. A IPKSUENT 4.o C ~ aJ AdRL9 ~H be ~ 4, (h~ ~. 4l COCK kM Sk3 LA)g l/g AS-FOUND FlELD CONDITlON THESE RACKS ARE GOULD SEISMICALLYQUALIFIED MANUFACTURED RACKS. 1/2" HILTI-BOLTS ARE USED ON THE SINGLE HEIGHT BATTERY RACKS AND 5/8" HILTI-BOLTSARE USED ON THE 'OUBLE HIGH BATTERY RACKS AT SUPPORT EACH SUPPORT STEEL COLUMN BARS a'a: YY. p$ C" 'a; <':.>'"::"'.? RN 2'.4 22"

j,l<Na k'"::;:!2 . YN2 2.j

YNT<a aa:: 2? ".."2'v ".:N NY2 a.ca<<'N 'am:'a2 <Y)a.Y.'<:a? N>"'. K'<:l

<<2'a2? $< .'N2 2 "2YN h .a '"Na'. C" <Y.'a..'2 YN4".:M 2 ".. C<'r .aY:; 22" a'a<<Y< YYaY< <<. ': <<alaY< a%a la N < '<al )<'. 'a laY<; AN/ c )v) < 8P'N'0" Y./22+ ~p<<;eyy c'iggy~>? <<pp %%@:!N'<<?kRk~="N%i~4m~%'.-'>ai2i<a@gaE-~~as'4" 'C 24" 24" 14" 24" 24" 24" 3" BOX STEEL STRUCTURAL STEEL SPACING 38 BATTERY RACK SEISMIC MOUNTING WORKSHEET GENERAL NOTES NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 354 GL 87-D2 NALKDOWN IELD WALKDOWN. KETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EYALUATION. SEE ENGINEERING COMPONENT: 3B BATTERY RACK DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 23 1990 DWG BY: R. GOULDY AS-FOOND FIELD CONDITION THE SRT NOTED THE LIGHTS IN THESE ROOMS NEED TO HAVE THE FIXTURES SAFETYWIREDTOTHECONDUITTO PREVENT POSSIBLE FALLING ONTO THE BAKERY BUS BARS. THE BLOCK WALLS IN THESE ROOMS WERE PART OF THE GENERC LETTER IMPROVEMENTS FOR BLOCK WALLS. NO OTHER SEISMIC INTERACTIONS CONCERNS WERE NOTED 3B BATTERY ROOM FILLED CON CREIE BLOCK WALLS 4A BATTERY ROOM 42 FOOT ELEVATION CONTROL BUILDING 3B BATTERY RACKS SEISMIC INTERACTlON WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN.

PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE ANCHORAGE EVALUATION. SEE ENGINEERING EQUIPMENT ANCHORAGE SKETCH DRAWINGS FOR SAFEIY RELATED WORK. COMPONENT: 38 BATTERY RACK DATE: MAR 23 1990 DWG BY: R. GOULDY 90C1585A/DATASHT EQUIPMENT PART A. EQUIPMENT DESCRIPTION I.O. Number Building Elevation 30'anufacturer Model Number Other PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored7 Yes No

2. Condition of nearby concrete an embedmente

3. Lengt , size, num er, an soun ness o we s

4. Anc or o t type, size an number

5. Are nuts present and apparent y tig t on a o ts7 PART C. ANCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Olnd7

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SP TIA SEISNIC INTERACTIO CONCERNS (if any) ck. %AT'tio ar tAOmt l a ~LCta PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

NAME OATE 6 JX JP> 'ATE DATE RW KEUlE'uJGD VOVQM SBSN a Cate>'l~l~ Qss~a. ~s~ ~uo s~~zs aeeoec. / A~ rd~icier ~ ~5M) C. krlE~~~ ~U~KQ ~ A LJk l&k LJOtJLlO LFQ>61 PE 'f4 M~ (I AJ 6 ko be ke.mie8D. -4 IPKhuE~ k4 Shac4 4Q lllbJC . T4 caw~ 4lr ale (dolls LJQW 4< 4M S~. AS-FOUND FIELD CONDITION TWO SETS OF BATTERY RACKS MAKE UP THE 4B BATTERY THESE RACKS ARE GOULD SEISMICALLY QUALIFIEDMANUFACTUREDRACKS 5/8" DIA "J" HILTI- BOLTS AT EACH STEEL SUPPORT SUPPORT BARS

%Kg gc.N, 22" v? .g'> G"C:j "mX> >')8$ S.?:>>'0 """:".S ">> >.'; @zan': ."x".>>".>;>">>>> ".".,'C'<<$ g y)(.": 20" 22 i<. C',> >A >>'.>'M>% rN CN.">>:>>A'CCS>>.'Nri > W >>C'>:'> C

++/~>~<Ak~c'~i+'Pg 5~++'g ' ~,p ~~~~. >~+M~ gM+g+~@~A~gg~g>,p.">'><>." j:(+%XIX 24" 24" 24 14" 24" 24 24" 3" BOX STEEL STRUCTURAL STEEL SPACING 4B BATTERY RACK SEISMIC MOUNTING WORKSHEET GENERAL NOTES . DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 3&4 GL 87-02 WALKDOWN FIELD WALKDOWN. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B BATTERY RACK DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 23 1990 DWG BY: R. GOULDY AS-FOUND FIELD CONDITION THE SRT NOTED THE, LIGHTS IN THESE ROOMS DID NOT NEED TO BE SAFETY WIRED TO THE FIXTURES BECAUSE OF THEIR SHORT LENGTH. THIS MINIMIZED THE PROBLEM OF SWAYING AND POSSIBLY COMING APART AND FALLINGON THE BATTERY BUS BARS. THE BLOCK WALLS IN THESE ROOMS WERE PART OF THE l&E BULLETIN80-11 IMPROVEMENTS FOR BLOCK WALLS. THERE WERE NO OTHER SEISMIC INTERACTDNS CONCERNS WERE NOTED 3A BATTERY ROOM FILLED CONCRETE BLOCK WALLS 4B BATTERY ROOM 30 FOOT ELEVATION CONTROL BUILDING 4B BATTERY RACKS SEISMIC tNTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN KETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH CHORAGE EVALUATGN. SEE ENGINEERING DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: 4B BATTERY RACK DATE: MAR 23 1990 DWG BY: R. GOULDY

9OCI585A/DATASHT UP OAAS EQUIPMENT Item 40 - Battery Rack 4A PART A. EqUIPMENT DESCRIPTION I.D. Number 4D24 Building Control Manufacturer Elevation 42'ther Model Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored2 Yes x No

2. Condition of nearby concrete a~n embedments

3. Lengt , size, num er, and soundness o we s

4. Anc or bo t type, size an num er " uzi

5. Are nuts present an apparent y tig t on a o ts?

PART C.~ ANCHORAGE ADEQUACY l. ~ Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any 4'C PART D. SPATIAi SEISNIC INTERACTION CONC {1 f any) 716 tu~ T Lock & ~ C< hl uo Lo PART E. CNRSE OF ACTION TO RESOLVE (PART C) OR (PART D) c'ECOMMENDED OR OTHER CONCERNS {ifany)

DATE h DATE '/ 5 D DATE 5RW PEUlGLJGD VO 6 6M SEl5no ~ (a lcsJ 1~4~ Q65uK,Q. 6~~ ~ >F'~~~. ~~s~ )c lvm~c;rL m ul ~ rd~if ~ / ~ A LJ 5 i CA LJ os/~ LGCi>01 kE c id'e.i(i~ ko be, k~.~ieeD. A gzsvenrr k4 st& 4n llia3a. Cn~~ 4lz>cK b< 4M SK3 . AS-FOUND FIELD CONDiTiON THESE RACKS ARE GOULD SEISMICALLYQUALIFIED MANUFACTURED RACKS. 1/2" HILTI-BOLTSARE USED ON THE SINGLE HEIGHT BATTERY RACKS AND 5/8" HILTI-BOLTSARE USED ON THE DOUBLE HIGH BATTERY RACKS AT EACH SUPPORT STEEL COLUMN SUPPORT BARS jF:,'<" <<:cA 22 (.(?r'e AY4:Ck<<<<< i>F(N i:a!4 NF~ ~~A>.  ??<".<<<4 'r";,'à 'e5$ ) e5<<a $ ?<<'",M >":C% N( 20" 22" <<" x> v:e< ~ <<<< .<<<<<< .. <<<. r. rr< m> <4 <<<e< ><<e<<> <<:< > <<<<<e o<<<O '~gy'~'jj~v Q'p: Y < 'r@s?<'> +e~<<gr~<><<~??<?r%@..r<pgvg<0~r r<,<.<>s ?yap<~rrI<p ?gà 24" 24" 24" 14" 24" 24" 24" 3" BOX STEEL STRUCTURAL STEEL SPACING 4A BATTERY RACK SE!SMIC MOUNTING WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 354 GL 87-D2 WALKDOWN FIELD WALKDOWN. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE NGINEERING f COMPONENT: 4A BATTERY RACK DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 23 5 990 DWG BY: R. GOULOY AS-FOUND FIELD CONDITION THE SRT NOTED THE LIGHTS IN THESE ROOMS NEED TO HAVE THE FIXTURES SAFETY WIRED TO THE CONDUIT TO PREVENT POSSIBLE FALLING ONTO THE BATTERY BUS BARS. THE BLOCK WALLS IN THESE ROOMS WERE PARTOF THE GENERIC LETTER IMPROVEMENTS FOR BLOCKWALLS. NO OTHER SEISMIC INTERACTIONS CONCERNS WERE NOTED 38 BATTERY ROOM FILLED CONCRETE BLOCK WALLS 4A BATTERY ROOM 42 FOOT ELEVATION CONTROL BUILDING 4A BATTERY RACKS SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE ANCHORAGE EVALUATION. SEE ENGINEERING EQUIPMENT ANCHORAGE SKETCH DRAWINGS FOR SAFETY RELATED WORK COMPONENT: 4A BATTERY RACK DATE: MAR 23 1990 DWG BY: R GOULDY

90CI585Adt'DATASHT EQUIPMENT PART A. EgUIPNENT DESCRIPTION I.D. Number Building Manufacturer Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION I. Is equipment anchoredf Yes )C Ho'. Condition of nearby concrete a~n embedments

3. Lengt , size, num er, an soun ness o ee s

4. Anc or bo t type, size and num er 5 " 0~a

5. Are nuts present an apparent y tig t on a o ts2 PART C.~ ANCHORAGE ADEQNCY l.

~ Does ~ Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E RECOlllENED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) DATE DATE DATE nay) +~ PClkJKL. l EO& C~<~9CQA. &Pl/IHMGQ M)~ CAW~~~ f0~ ACCRP ~ WHP DhtCAIIIAC C ZE5/6A-I . 0 ~ ~ ~ ~ ~ ~0 ~ ~ Ow ~ o ~ 0 ' SO ~ ~ ~ ~ ~ ~ ~ ~0 ~ ~ I ~ 0 ~ ~ ~ ~~ ~ ~ ~ ~ AS-FOUND FIELD CONDITION 3DO1 e< a Pg )>> @ <<g g $>: gN ~::, g) g k a @i~%5%S@+%~'~k4cNigi~iiig+~ii+q j?; THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS WITH THESE ROOMS OR THE ASSOCIATED EQUIPMENT 4DO1 30 FOOT ELEVATION 3DO1 125v DC BUS SEISMIC INTERACTION MfORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN . SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING - DRAWINGS FOR SAFETY RELATED WORK. COMPONENT: 3D01 DC BUS DATE: MAR 23 1990 DWG BY: R. GOULDY 90C1585A/DATASHT PO U PH AT EQUIPMENT Item 42 - Distribution Panels Bus PART A. EQUIPMENT DESCRIPTION I.D. Number 3D23 Building Control Manufacturer El evati on Model Number Other PART B. ANCHORA6E DESCRIPTION

l. Is equipment anchored? Yes No

2. Condition of nearby concrete an embedments

3. Lengt , size, number, an soun ness o we s 4.

5. Anchor bo Ar t type, size and num er ~tfa/4 ' nuts pre e t and apparent y tig t on a o s2 H~ AC'+4 - C.ddt, ~ 14i PART C.~ ANCHORAGE ADEQUACY I. ~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment J

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns (i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS {if any)

PART E. RECQNBSED COURSE OF ACTION TO RESOLVE {PART C) OR {PART D) OR OTHER CONCERNS (if any) NAME DATE DATE DATE Dl~r/5u77b& PANKC /8~ - ~DM T7fK M~ J2&WB~Sr4=C7 /Id C)v~ CA<m~<i aQ . WAG '<m ZBu') &AN QE, C'ALCm~WL~ 6~ WM~] ~ WC AQCQ543&E a~(ak . SUBJECT JOB No. + + + ~ SHEET OF 2. O sfs STEVENSON F R ASSOCIATES o stiuclutol meChonlcol lSS K consulting engineering firm Pjj Q)! j /~alt. SS. ~ t l I I 'I I li I t W I I ~F It s I t I t II Q( I 4 pit I ~ I It t I I I ' I ~ ~ I

• I I t

) I I h daetttt P i'l/t I~ 7I'P = 0, )/{pe 353 8 s ~- ~ s ~ I I t S I ~ I I ~ ~ SUBJECT JOB No. SHEET OF STEVENSON Ik ASSOCIATES o struciurolrffcchofrlcoi coffsurhrig DfrguTDDflAQ Ilffh I I o I I I I I 4 I f o') qorfrif 4 4 I r ~ I " ~ ' L+~ 4 4 r i 5 l i o '8 I4g' 4 I lr 4 ~ 4.+-I . &P< 5':: I ~ ~ 5 ~ ~~- e., 'i".~ah:0i'(~' /P~lp 8 Hgo Fo FSI '/g . I I ~ <ll. f' <<~WOO /4.-'E~, , .'I 4 4 I, I I ~ I 4 II i 4 '4 ,2,C.~)- Jd. g: ywo; 4 ~J -"' - ---/ hog 'oo "Zg /- OA (~) I 5 Q ~ P/'g "gg~ I ~ I fg ~. =' ~.CIZ) I 4 S I

"1( gw I 5 I I 5 I I I -

I I ~ W ~ =. ~ AS-FOUND FIELD CONDITION THE SRT NOTED THAT SHEET METAL BRACKETS WILL BE THE CONTROLuNG FACTOR FOR ANCHORAGE OF THIS BUS 20" 1/2" DIA BOLTS 1/2 ANCHOR 44" BOLT SHEET METALSCREWS (3 PLACES ) ANGLE BRACKET DETAIL k:,';"( '-'."' ~ ~o.c.,"'+fr.' x',4&'~ !,";4K'%".".;~.';::-:;Ax.:";.'5'.:c 3D23 125v DC BUS SEISMIC MOUNTING WORKSHEET GENERAI NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 3&4 GL 87-02 WALKDOWN FIELD WALKDOWN. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT. ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3D23 125v DC BUS DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY AS-FOUND FIELD CONDITION oC<55oc5'QNSA) YANoo(o <~o+%4Wy><&os Q@cNyg:c o@Xcy&hoA'N>>'AXaMNKN5qicoo&NN >A%co!o&N)M'Yg@>%@C @p?@%Joe p~gg c c" c 3D23 DC BUS ~c?:. 3YO2 4YO 4YO2 24" (Ot @cc 3YO5 3YO6 4YO5 3B g BATTERY CHARGER RAISED FLOOR y% )oo s% (SAN BATTERY BATTERY FCOM FCCM Pg N~ THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. 3D23 125v DC BUS SEISMIC INTERACTION WORKSHEET GENERAL NO'IES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 354 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TOBE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3D23 125v DC BUS DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY 90C1585A/OATASHT U PMENT ATA SH EQUIPMENT Item 43 - Distribution Panels Bus PART A. EQUIPMENT DESCRIPTION I.O; Number 4D01 Bui1ding Control Manufacturer E1evation 30'ther Mode1 Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedments

3. Length, size, number, and soundness o we s

4. Anchor bo t type, size and number So

5. Are nuts present an apparent y tight on a o ts2 PART C.~ ANCHORAGE ADEQUACY 1.~ Does Seismic Capacity jo 'nchorage Exceed Demandf

a. SRT Judgment

b. URS Tab1es

c. ANCHOR Program

d. Other (explain)

C a.l.

2. Concerns i any PART D. SPATIAL SEISMIC INTERACTION CONCERNS (if any)

PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) NAME DATE 4 /> NAME DATE NAME DATE r +3 py-pp)gunaQ Pave~ / B~ - k6J immit PPABL Cn ICcJI ak~s Okla ACCRP7&D A4C Adc+~~&H ZKG(6d ~ AS-FOUND FIELD CONDITION NO CREDIT IS GIVEN FOR UPLIFT RESISTANCE ON LOOSE BOLTS, SHEAR 1/2" DIA BOLTS RESISTANCE ONLY O 20" O O 30" 36" 20" 20" 20" 20 146" 3/8" BOLTS CONNECTING CABINETS 4D01 125v DC BUS SEISMIC MOUNTING WORKSHEET GENERAL NOlES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38<4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT. ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4D01 125v DC BUS DRAWINGS FOR SAFETY RELATED WORK. DATE'AR 28 1990 DWG BY: R.GOULDY AS-FOUND FIELD CONDITION 3DO1 %Yx4>%%x~CMWNNcxi<hi THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS WITH THESE ROOMS OR THE ASSOCIATED EQUIPMENT 4DO1 Si@w>%Ãkk@%iÃkhi."'>%%4~4A%%~>>V~>4~4',M4%i~ii~ 30 FOOT fLEVATION 4D01 425v DC BUS SEISMIC INTERACTION VfORKSHEET GENERAL NOTES . DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIEL,D WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EYALUATION. SEE ENGINEERING COMPONENT: 4D01 DC BUS DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 23 1990 DWG BY: R. GOULDY SUBJECT JOE HF. +O+I ere+ SHEET / OF~ 4/0 f CD z O VD STEVENSON h ASSOCIATES IU p consurrrnp enplneerlnp Irrm l l l~t e I 't hi I CE ~ g Cl ~ 5 I I I I I e.*- I

• lI L%

D Ct I I '4 gd: i%m y (g Pj~ $ vb.~ ~ 3ao w P. <CAN Qj~ v Q I I'MSthe h I 4 I I I I I ~ ~~jr/Tf 4 ' It I ~ I ~ e I' 90C1585A/DATASHT 0 lN 4 UP DT SH Item 44 - Distfibution Panels/Bus EQUIPMENT PART A. EgUI PNENT DESCRIPTION I.D. Number 4023 Building Control Manufacturer Elevation 30'ther Model Number PART B. ANCHORAGE DESCRIPTION

1. Is equipment anchored? Yes No

2. Condition of nearby concrete an embedments

3. Length, size, num er, an soun ness o we s C4

4. Anchor bo t type, size an number s' coW~l (~ Se

5. Are nuts presen n appare y tight on a o tsar PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity Anchorage Exceed OemandZ go

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECOlSENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) DATE DATE DATE h Q~~j~)QLPl2 En Qn/E( I !5~ 4~~ ~v )<Mac> ~(c DLakui'~ AQc~~~ Q~ l &, 4 ~ AS-FOUND FlELD CONDITION THE SRT NOTED THAT SHEET METALBRACKETS WILL BE THE CONTROLLING FACTOR FOR ANCHORAGE OF THIS BUS 20" 1/2" DIA BOLTS 1/2" ANCHOR 44" BOLT SHEET METALSCREWS (3 PLACES ) ~ ~ ANGLE BRACKET DETAIL 4D23 125v DC BUS SEISMlC MOUNTlNG NORKSHEET GENERAL NOTES . DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 3&4 GL 87-02 WALKDOWN FIELD WALKDOWN. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT, ANCHORAGE SKETCH ANCHORAGE EVALUATION, SEE ENGINEERING COMPONENT: 4D23 125v DC BUS DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY AS-FOUND FIELD CONDITION 4D23 DC BUS pg C '4 R~ gh 4YO1 4YO7 25" pj D3YO4 24" 25" 3YO6 ~0 K I x 3YO1 3YO7 g kv) Cg CONTROL ROOM THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. 4D23 125v DC BUS SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38(4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4D23 125v DC BUS DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY Z( 90C1585A/DATASHT PO NT U PM E(UIPMENT Item 45 - Inverter 3C PART A. E(UIPNENT DESCRIPTION I.D. Number Building Manufacturer Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored2 Yes No

2. Condition of nearby concrete an embedments

3. Length, size, number, an soundness o we s

4. Anc or bo t type, size and num er ~aa tt ~

5. Are nuts present an apparent y tight on a o ts2 PART C. ANCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Oemand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) e VAOV f4

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) NAME DATE NANE DATE DATE AS-FOUND FIELD CONDITION 3Y05 REQUIRED EMBEDMENT IS 3 1/2" INYERTER ANCHOR BOLT LENGTH IS 8 1/2" 72" STEEL GUSSET PLATES 3/8" STEEL PLATE ANCHOR BOLTS "P" OR "0" 13" 13" 5/8" DIA 8" 1/4"THICK 2" ANGLE 3Y05 INVERTER SEISMIC MOUNTING WORKSHEET GENERAL NOTES 1 ~ DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 VfALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3Y05 INVERTER DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY AS-FOUND FIELD CONDITION ~$ NSW%@Y.'NCNSN%c.i',Ngv5%%%@g.;.".gc@N~VigigNgc RNNN9$@%$ <~hÃxWN:4%@%'5'4%SNgg@g89NNr+AQR~wY4%@%%~ CCg 5) CVT 3D23 DC BUS 3YO2 4YO 4YO2 ki I ~ ~ ~4 3YO5 I 2~ I ~4. ~~ 3YO6 I~ 4YO5 3B g) @~i ? BATTERY CHARGER RAISED FLOOR g C Fj: i) BATTERY BATTERY RXM FGCM [i THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. INVERTERS SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 354 GL 87-D2 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERiNG COMPONENT: INVERTERS DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY 9OC1585A/DATASHT P 0 0 PH ATA SH EQUIPMENT Item 46 - Inverter 30 PART A. EQUIPMENT DESCRIPTION I.D. Number 3Y07 Building Control Manufacturer Elevation 42'ther Model Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored? Yes Nn

2. Condition of nearby concrete an embedmenta

3. Length, size, num er, an soundness o we s

4. Anc or o t type, size an num er

5. Are nuts present an apparent y tig t on a o tsar PART C. ANCHORAGE ADEQUACY Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. VRS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEIQiIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE {PART C) OR {PART D) OR OTHER CONCERNS {ifany) - DATE DATE DATE AS-FOUND FIELD CONDITION 3Y07 REQUIRED EMBEDMENT IS 3 1/2" INVERTER ANCHOR BOLT LENGTH IS 8 1/2" STEEL GUSSEI PLATES 3/8" STEEL PLATE ANCHOR BOLTS P" OR "0" 13" 13" 5/8" DIA 'jc~Q'jc+j ~<M+M<yg.'W '.%X%Q ??Ãemwy'PC+ ?xQbyp:aXigg5+cc+cD+. 'Cp~sg@vS 1/4"THICK 2" ANGLE 3Y07 INVERTER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3Y07 INVERTER DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY 0 AS-FOUND FIELD CONDITION 4D23 DC BUS YP j$  : Ag 4 O 4Y01 24. 4YOT D 25" 3YO4 24" 3YO6 25" 3YO] 3YO7 5Q p~c THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. INVERTERS 5. BATTERY CHARGERS SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 354 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: INVERTERS DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY 23 9OC15SSA/DATASHT POI UN RK VIP'A A SH EQUIPMENT Item 47 - Inverter 4C PART A. @UIPMENT DESCRIPTION I.D. Number 4Y05 Bui l ding Contr ol Manufacturer El evati on 42'ther Model Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored'es No

2. Condition of nearby concrete an embedments

3. Lengt , size, number, an soundness o we s

4. Anchor o t type, size an num er

5. Are nuts present and apparent y tight on a o tsar PART C.~ ANCHORAGE ADEQUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demand?

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns (f any PART D. SPATIAL SEISNIC INTERACTION CONCERNS <<f any)

PART E. RECONMENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS <<f any) NAME DATE t to RANE DATE d NAME DATE AS-FOUND FIELD CONDITION 4Y05 REQUIRED EMBEDMENT IS 3 1/2" INVERlER ANCHOR BOLT LENGTH IS 8 1/2" 72" STEEL GUSSET PLATES 3/8" STEEL PLATE ANCHOR BOLTS "P" OR "0" 13" 13" 5/8" DIA II 8 yS 1/4"THICK 2" ANGLE 4Y05 INVERTER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4Y05 INVERTER DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY AS-FOUN D FIELD CON DITION 4%YN@VBWPANÃNPWSNWSNP4%%NNA)iiai.M+'M'saV/Fe%N8@%'A.'? '883%<.4%<+~%%ÃiFN%NWNNvVWNARNRNNQW8N4i mg 3D23 DC BUS 3YO2 4YP 4YO2 24" 25" 24'g.[~ 3YO5 SYO6 4YO5 3B BATTERY CHARGER RAISED FLOOR I BATTERY BATTERY FCCM FCOM 3P '3 p.s THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. INVERTERS SEISMIC INTERACTION WORKSHEET A GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: INVERTERS DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY 90C1585A/DATASHT tjlPM DATA SH EQUIPMENT Item 48 - Inverter 4D PART A. EgUIPNENT DESCRIPTION I.D. Number 4Y07 Building Control Manufacturer Elevation 42'ther Model Number PART B. ANCHORAGE DESCRIPTION 1. 2. Is equipment anchoredt Yes + Condition of nearby concrete and embedments No

3. Lengt , size, num er, an soundness o we s

4. Anchor bo t type, size an number

5. Are nuts pr esent and apparent y tight on a PART C.~ ANCHORAGE ADE(UACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) R V DATE DATE DATE AS-FOUND FIEI D CONDITION 4Y07 REQUIRED EMBEDMENT IS 3 1/2" INVERTER ANCHOR BOLT LENGTH IS 8 1/2" 72" STEEL GUSSET PLATES 3/8" STEEL PLATE ANCHOR BOLTS "P" OR "0" 13" 3N 5/8" DIA 1/4"THICK 2" ANGLE 4Y07 INVERTER SEISMIC MOUNTING WORKSHEET GENERAL NOISES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4Y07 INVERTER DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 23 1990 DWG BY: R. GOULDY 0 AS-FOUND FlELD CONDlTlON NC??PNk>%@"45%%$ 4Ã8A<ds%4~8<8s%4SKCSSiAkkCc.""cÃ4'D23 DC BUS

SS pl<

Sp 4YO1 4YO7 W 24 s D 25 N 24" 3YOG 3Y04 25" 3YO1 3YO7 gey@ga@meog@?'.m~>>o>? ewe(??ey-.<<g~e?"R>>?4%V@SWM Wj%;?Yc~($<%(P+KQWÃ><SWNPvg;<?",((P>cN CONTROL ROOM THE SRT DID NOT NOTE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS ROOM OR THE ASSOCIATED EQUIPMENT. 1NVERTERS & BATTERY CHARGERS SElSMfC lNTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT'NVERTERS DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 23 1990 DWG BY: R. GOULDY

90C1585A/DATASHT 0 VIP' EQUIPMENT Item 49 - Se uencer A PART A. EgUIPNENT DESCRIPTION I.D. Number 3C23A Building LC-Sw r Manufacturer El evati on 18'ther Model Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedments

3. Lengt , size, number, an soun ness o we s

4. Anc or bo t type, size and num er

5. Are nuts present an apparent y tig t on a o tsar PART C.~ ANCHORAGE ADEQUACY l.

~ Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain)

2. Concerns i any)

PART D. SPATIAL SEISNIC INTERACTION CONCERNS (i f any) PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART 0) OR OTHER CONCERNS (if any) R V DATE DATE DATE au~em A&FGLATE r3R~M ~ AQ~Coe C l~lof~n. (i-, ~ AS-FOUND FIELD CONDITION 3" CONDUIT lHRU FLOOR THE SRT NOTED THATTHEREWERE ~ TWO BRACKETS ON THE TOP OF THIS SEQUENCERCABINET PHILLIPS SELF DRILLING ANCHORS (5 TOTAL ) 3A SEQUENCER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3A SEQUENCER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY

AS-FOUND FIELD CONDITION I THE SRT DID NOT HAVE ANY SEISMIC INTERACTION CONCERNS POURED CONCRETE WALL 4160 BUS 3A SEQUENCER SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PTN 38c4 GL 87-02 WALKDOWN FIELD WALKDOWN. SKETCHES ARE INTENDED TO BE AN A(D IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3A SEQUENCER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY 90C1585A/DATASHT P T 3 U PNENT OATA SH - 3 EQUIPMENT Item 60 Sequencer B PART A. EQUIPNENT DESCRIPTION I.D. Number 3C23B Building LC-Sw r Manufacturer Elevation 18'ther Model Number PART B. ANCHORAGE DESCRIPTION

1. Is equipment anchoredt Yes Q No

2. Condition of nearby concrete and embedments 3; Length, size, num er, and soundness o we s

4. Anchor bo t type, size and number I

~ ~

5. Are nuts resent and apparent y tight on a o ts2 PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment X

b. URS Tables

c. ANCHOR Progrma

d. Other (explain) k u ~kore

2. Concerns {i any h

PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any) PART E. RECONENDED COURSE OF ACTION TO RESOLYE {PART C) OR (PART D) OR OTHER CONCERNS {ifany) 4~ s as PRY Y DATE DATE DATE koan=asm (Z'~8~ 5') ~ Gdc@c4&C C od VA chlcul~km-MCrr~H) ~A I TQP MAck~~ M Fe udQ oW SA M6U~ Pedi oC AQQ~ ]~ere,vm ~U a ~~6' AS-FOUND FIELD CONDITION 3" CONDUIT lHRU FLOOR THE SRT NOTED THAT THERE WAS ONE BRACKETONTHETOP OF THIS SEQUENCER CABINET PHILLIPS SELF DRILLING ANCHORS (5 TOTAL) 3B SEQUENCER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38<4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B SEQUENCER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY

AS-FOUND FIELD CONDITION THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS ASSOCIATED WITH THIS ROOM OR THE EQUIPMENT 3A 4160v BUS ROOM 4160 BUS 3B SEQUENCER SEISMIC INTERACTION WORKSHEET GENERAL NOTES . DO NOT SCALE, USE DIMENSGNS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN . SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 38SEQUENCER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY 90CI585A/OATASHT TURK PO UIPNENT OA A SH Item Sl - Seqvencer A EQUIPMENT PART A. ERUIPMENT fgQIPTION I.O. Number LC-Swgr Manufacturer Eleyation 18'ther Model Number PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored'es No

2. Condition of nearby concrete an embedmenta

3. Length, size, number, an soun ness o we s

4. Anchor bo t type, size an num er

5. Are nuts present and apparent y tig t on a o ts7 PART C.~ ANCHORAGE ADEQUACY I.

~ Does Seismic Capacity of Anchorage Exceed Demand?

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other {explain) IZ dies/

2. Concerns i any PART D. SPATIAL SEISMIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any) 'Al. ~~ac. 4 D+ PPR V NAME DATE NAME DATE NAME DATE ~D QD QIJMT+~~ Cm l~ (ci+MW kn b8 GS~ FK 0 Pedals) a) G, Ca t~lak~ 4(L k4 SESUWQuLS. T4 ~~i UerraQ ~ ~aha 1Qi'f~~vs Abe >WMQ6,wl. Aa AS-FOUND FlELD CONDITlON THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS ASSOCIATED WITH THIS ROOM OR THE EQUIPMENT POURED CONCRETE WALL o SEGUEN GER O 4160 BUS 4A SEQUENCER SElSMlC lNTERACTION MfORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING PSL 1 GL 87-02 WALKDOWN FIELD WALKDOWN.

2. SKETCHES ARE INTENDED TO BE AN A(D IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EYALUATION. SEE ENGINEERING COMPONENT: 4A SEQUENCER DRAWINGS FOR SAFETY RELATED WORK. DATE'AR 28 1990 DWG BY: RGOULDY

PAGE i CAlCULATION COVER SHEET Calculation No: PA - t 54 C -b4 c o

Title:

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90C1585Adt'DATASHT R POI S 3 4 UIPMENT OATA SH EQUIPMENT Item 52 - Se veneer PART A. EQUIPMENT DESCRIPTION I.D. Number 4C23B Building Manufacturer Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored? Yes No

2. Condition of nearby concrete an embedmenta

3. Length, size, num er, and soundness o we ds

4. A c or bo t IItype, size and number e

/ p

5. Are nuts present and apparent y tig t on a o ts?

PART C. ANCHORAGE ADEQUACY f.

1. Does Seismic Capacity of Anchorage Exceed Demand?

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain (8 ((I

2. Concerns i any PART D. SPATIAL SEISNIC INTERACTION CONCERNS (if any)

PART E. RECONENDED COURSE OF ACTION TO RESOLVE {PART C) OR {PART D) OR OTHER CONCERNS (ff any)

PP V Y NAME DATE

'<<0 DATE DATE

~

0

>P~ ~Ul&irJCZO 442

~~4-A c~(~l-+~

Q0W<~~

~ ckES)6% bK i&%4 48 QCCQP 8535M

~Di&M -r4IAT'4 BMCk~h 5& ~udD od M AQOLJ3 A3Q ~~w6M.

AS-FOUND FIELD CONDITION 0

1" 5 1/2" 0 0 0 16" PHILLIPS SELF DRILLING ANCHORS ( 4 TOTAL )

4B SEQUENCER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DONOTSCALE, USE DIMENSIONSTAKENDURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN 2 SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT. ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4BSEQUENCER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY

0 AS-FOUND FIELD CONDITION THE SRT DID NOT NOTE ANY SEISMIC INTERACTION CONCERNS ASSOCIATED WITH THIS ROOM OR THE EQUIPMENT 4 SEQUENCER 4 4160 BUS 4B SEQUENCER SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE;- USE DIMENSIONS TAKEN DURING 'f PSL GL 87-02 WALKDOWN FIELD WALKDOWN.

SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH f

ANCHORAGE VALUATION. SEE ENGINEERING COMPONENT'B SEQUENCER DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY

90C1585A/DATASHT RK PO UN TS 3 4 UIPN DATA SH EQUIPMENT Item 53 - CCM Heat Exchanger PART A. EDDIPMENT )[SCRIPTION I.D. Number Bui 1 ding R"B Manuf actur er Elevation Model Number Other PART B. NCHORAGE DESCRIPTION

1. Is equipment anchored'es No

2. Condition of nearby concrete an embedments

3. Length, size, number, and soundness o we ds

4. Anchor bo t type, size and number

5. Are nuts pr esent and apparent y tight on a o tsar PART C.~ ANCHORAGE ADEQUACY I.

~ Does Seismic Capacity of Anchorage Exceed Demandl ~/p~

a. SRT Judgment X

b. URS Tables

c. Program d.

ANCHOR Other (explain) N<~ 4 Rc~-C Vs klf4gp

2. Concerns i any)

PART D. SPATIAL SEISMIC INTERACTION CONCERNS (if any) o PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

PPR V DATE 4 ji /c'ATE DATE

C.C M ~ WCAAnJC a &

ICE.LJ) WW

~Qi~~l DESI6.0 ~

Agc.~~Ca+- + 5~

AS-FOUND FIELD CONDITION CCW HEAT EXCHANGER 12"

'@y4,g%+~++xi',Q+ +g~,~4%MX@~K&jpRVp~x++"+gqjQXMs~jX~Qg~Q+ixQgXyX';.~4+~A+P>v' SB CCW HEAT EXCHANGER SEISMIC MOUNTING WORKSHEET GENERAL NOlES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 NALKDOWN

. SKETCHES ARE INTENDEDTOBEANAID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT'B CCW HEAT EXCHANGER DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 28 1990 OWGBY: RGOULDY

0 AS-FOUND FIELD CONDITION HEAT EXCHANGERS g>ix4iiY4%F84)%FiC4+o j%~g+Mhix~~k%i%ig>>

o o o o o o 0 0 0 STRAINERS

'LPGA.:c'4&Ak%&%4!4AY4ii~ii@K4'C i~4%%ii%<8%4<%%<'~YiMig~ii%%  %>N4%X@<'%Ai%>~'iM@4VM:

o o o o o o o o o o P P 0 0 0 0 0 0 o 0

~~i~e%~+i4&%%kiiik~~+~ii~qij+Ai4 '4+%%"i4~XCM%04ii~%3i8i'kXXi.%i~

3B 3A THE SRT DID NOT HAVE ANY SEtSMIC INTERACTION CONCERNS WITH THIS PUMP ARRANGEMENT. THE STEEL GRATING ABOVE WAS REVIEWED AND FOUND TO BE BOLTED TO THE STEEL I-BEAMS 3B CCW HEAT EXCHANGER SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DtMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 3B CCW HEAT EXCHANGER DRAWINGS FOR SAFETY RELATED WOFK DATE: MAR 22 1990 DWGBY:

90C1585A/DATASHT U PM DATA S Item 54 - Heat Exchanger fEQUIPMENT CCM PART A. EQUIPMENT DESCRIPTION I.D. Number 48 Building Manufacturer Elevation 18'ther

~

Model Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored? Yes No

2. Condition of nearby concrete and embedments

3. Length, size, number, an soundness o we s

4. Anchor bo t type, size and number

5. Are nuts present and apparent y tight on a o tsar PART C.~ ANCHORAGE ADEQUACY 1.

~ Does Seismic Capacity of Anchorage Exceed Demands 'l<>

a. SRT Judgment Y

b. URS Tables c.

d.

ANCHOR Program Other (explain) bv llmcRo~ ~ (~(A~s Y'~l

2. Concerns (i any PART D. SPATIAL SEISMIC INTERACTION CONCERNS {ifany)

PART E. RECOMMENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (if any)

PPR V DATE o DATE DATE

T4 S/CT P&l/)wRez> Qdc &c~C e CA,Lc.@Law's Qa)w Adcbh~C Q Q~g w~ MdlEih DGStc U 44'&Di~w

AS-FOUND FIELD CONDITION CCW HEAT EXCHANGER 12"

%ji~gi~~>>~:~@~i+~.'+~.'<ijYi~>g4"~(<<g SA'c>~ 44q<ii%7~%".Jihad>~~~i@":.i44A'~i~k+ii%F~ii~@~P4'~~i%~>>~~<'B CCW HEAT EXCHANGER SEISMIC MOUNTING WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 48 CCW HEAT EXCHANGER DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 28 1990 DWG BY: R GOULDY

AS-FOUND FIELD CONDITION HEAT EXCHANGERS

'44':A%'"%N:%%>.ki~kv%)

0 0 o o o P

STRAINERS 0 o 0 0 44i"'~k .~ 4%8~4+>%i@%~%%~

48 ii~ii~ii4iXP<hi4%4@i@i44%~4ii>ii 'R~+ii:>ill@>kiii%%%%%Nij o o o o o o o o o o h

.P P N o o 0 0 0 0 0 0 ~c Ck%Ni"4"i8i~KVii'i"x~'%84 @isis'iy><i~hg>ij~~+j~i@~gi~gigiiijii~ikiji 4A 4C THE SRT DID NOT HAVE ANY SEISMIC INTERACTIONS CONCERNS WITH THIS PUMP ARRANGEMENT. THE STEEL GRATING ABOVE WAS REVIEWED AND FOUND TO BE BOLTED TO THE STEEL I-BEAMS 4B CCW HEAT EXCHANGER SEISMIC INTERACTION WORKSHEET GENERAL NOTES DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

, SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: 4B CCW HEAT EXCHANGER DRAWINGS FOR SAFETY RELATED WORK.

DATE: MAR 22 1990 DWGBY:

90C1585A/DATASHT U H A A Item 55 - Vertical Pahel 3B EQUIPMENT PART A. EQUIPMENT DESCRIPTION I.D. Number 3C05 3C06 Bui 1 ding Control Manufacturer Elevation 42'ther Model Number PART B. ANCHORAGE DESCRIPTION I. Is equipment anchored'? Yes No

2. Condition of nearby concrete and embedments

3. Lengt , size, number, and soundness o we s

4. Anchor bo t type, size and num er

5. re nuts present and apparent y tig t on a o ts2 PART C. ANCHORAGE ADEQUACY

1. Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) c.u c. s L Cb LT 4 a>0 P a Crc.>c lA~

2. ..Concerns i any PART D. SPATIAL S I IC INTERA ION C NCERNS ($ f any)

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1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 3&4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: VERTICALPANEL B DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28, 1990 DWGBY: R.GOULDY

AS-FOUND FIELD CONDITION NUCLEAR PROTECTION AND ENGINEERED SAFEGUARDS RACKS 1/2 ANCHOR BOLTS 22" TO 24" ON CENTERS oooooooooo pppp

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~ ooooo 00000 OPERATORS DESK NUCLEAR (NSTRUMENTATIONRACKS UNIT 3 VERTICAL PANEL B SEISMIC INTERACTION WORKSHEET GENERAL NOTES

. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38(4 GL 87-02 WALKDOWN

. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: VERTICALPANEL B DRAWINGS FOR SAFETY RELATED WORK. DATE: MAR 28 1990 DWG BY: R.GOULDY

11 90C1585A/DATASHT Item 56 - Vertical Panel 4B EQUIPMENT PART A. EQUIPMENT DESCRIPTION I.O. Number 4C05 4C06 Building Manufacturer Elevation Model Number Other PART B. ANCHORAGE DESCRIPTION

l. Is equipment anchored2 Yes No

2. Condition of nearby concrete an embedments

3. Length, sire, num er, an soun ness o we s

4. Anc or bo t type, size and nu er sc QJ4

5. Are nuts pr esent an apparent y tig t on a o ts2 PART C.~ ANCHORAGE ADEgNCY 1.~ Does Seismic Capacity of Anchorage Exceed Demand2

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) C a, L< knrual6 s

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PART D. SPAT AL SEI MCCOY.

INTBNCTI CONCERNS (if any)

PART E. RECOHNENDED.CNRSE OF ACTIN TO RESOLVE (PART C) OR (PART D) OR OTHER CNCERNS (if any)

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1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING FIELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN

2. SKETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION, SEE ENGINEERING COMPONENT: VERTICALPANEL B DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 28 1990 DWG BY: R.GOULDY

PAGE i CALCULATION COVER SHEET Calculation No: F'i4 - 5J I C - 8 I- oe.

Title:

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No. Description By Date Chk/Ver Date Appr Date REVZSZONS MLS-4 . JPN JPN Form 82A, Rev. 3/90

ST 0 C IVE PAGES PAGE ii E

CALCULATION NUMBER F'~ ~

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PAGE SECTZON PAGE SECTZON PAGE SECTZON t,0 PiAiporc,/S4c ft 2.G P~EPE'm~s Q, O HEceabc a '6 Y

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PAGE iii TABLE OF CONTENTS CALCULATION NUHBER PW- Isa' ( - ~l G REV. o SECTION TITL PAGES Cover Sheet List of Effective Pages Table of Contents 1.0 Purpose/Scope 2.0 References 3.0 Hethodology 4.0 Assumptions/Bases 5.0 Calculation 6.0 Results TTACHMENT NO. UHB R OF PAGES HAS-4.JPN JPN Form 882C, Rev. 3/

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PART A. EQUIPMENT DESCRIPTION I.O. Number Building 0 /Ema P5 u t

> Eb E Manufacturer Elevation Hodel Number Other PART 8. ANCHORAGE DESCRIPTION I. Is equipment anchored'es No

2. Condition of nearby concrete an embedments tao

3. Length, size, num er, an soun ness o we s

4. Anc or o t type, size an number

5. Are nuts present an apparent y tig t on a o ts?

PART C.~ ANCHORAGE ADE CRACY

1. Does Seismic Capacity of Anchorage Exceed Demands

a. SRT Judgment

b. URS Tables

c. ANCHOR Program

d. Other (explain) C'4C I,~ICED

2. Concerns i any PART D. SPATIAL SEIQlIC INTERACTION CONCERNS (if any)

PART E. RECOIQlENDED COURSE OF ACTION TO RESOLVE (PART C) OR (PART D) OR OTHER CONCERNS (ff any)

DATE NANE DATE NAME DATE

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DIESEL GENERATOR EXCITER ELECTRICAL EQUIPMENT MOUNTING WORKSHEET GENERAL NOIES

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DATE: MAR 22 1990 DWG BY: R. GOULDY

AS-FOUND FIELD CONDITION A DIESEL GENERATOR ROOM

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B DIESEL GENERATOR SKID SEISMIC INTERACTION WORKSHEET GENERAL NOTES

1. DO NOT SCALE, USE DIMENSIONS TAKEN DURING IELD WALKDOWN. PTN 38c4 GL 87-02 WALKDOWN KETCHES ARE INTENDED TO BE AN AID IN THE EQUIPMENT ANCHORAGE SKETCH ANCHORAGE EVALUATION. SEE ENGINEERING COMPONENT: B DIESEL GENERATOR ROOM DRAWINGS FOR SAFETY RELATED WORK DATE: MAR 22 1990 DWG BY: RGOULDY

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90cl585B Appendice APPENDIX D Peer Review Report

The Readiness Operation 8%en you need someone to count on.

March 5, 1993 1130029.930305 George G Thomas Project Manager Sfevenson and Associates 9217 Midwest Avenue Cleveland, OH 44125-2415

Dear Gary:

Re: Peer Review of Turkey Point Unit ¹ 3 & 4 A46 Program This letter completes my review of the Turkey Point Unit 3 & 4 A46 Program.

1. Draft Report. The draft report on the A46 evaluation was very complete. This fa-cilitated my review. My review of the draft report on the A46 effort: "Plant Specific Seismic Adequacy Evaluation of Turkey Point Units 3 and 4 io Resolve Unresolved Safely Issue (USI) A-46 and Generic Letter (GL) 87-02, " prepared by Stevenson & Associates for Florida Power &

Light, December 31, 1992, is contained in my letter of February 26th. My comments are minor, and many were editorial in nature, often to clarify my understanding. Ifany of the suggested un-derstandings in my letter are incorrect, I would appreciate it ifyou could bring this to my atten-tion.

Ifthe report is revised to reflect any of my comments, I would be pleased to review the next revision of it.

2. Sample Walkdown. I performed a walkdown on January 22, 1993. I was able to walkdown many of the components in the program. My primary emphasis was on anchorage and seismic spatial interaction. I did not'identify any new issues that were not identified in the earlier walkdowns.

Only some of the modifications identified in the A46 report were complete at the time of my walkdown. The modifications appeared to be carried out in a very conservative manner, es-pecially considering the low seismicity of the Turkey Point site. I later verified that paperwork was in progress for many other modifications.

3. Review of Documentation. FPL has prepared a folder on each of the components in its A46 program. I reviewed several of these folders, some in detail, and others only briefly.

The folders typically contained information/drawings on anchorage, including details that could not be determined from a walkdown.

I identified no new issues in my review.

4. Components in Review. My review was restricted to seismic issues. %hether the appropriate components are included in the St Lucie Unit 1 A46 program is beyond the scope of my review.

3871 Piedmont Avenue Oakland, California 94611-5351 Tel: 510/547-0594 Fax: 510/5474920 Creative Consulting on Earth@cake Readiness

George G Thomas March 5, 1993 Page 2 of 2

5. FPL A46 Progratn. I assume that section 3.2.3.6, which is titled "Miscellaneous" could also have been titled "AllOther Equipment" with the intent of addressing all other pro-gram equipment not specifically identified by type or class. However, GL 87-02 does include ca-ble trays, and I could not find where they are mentioned in the program or report. Ifcable trays have been omitted from the program, the omission may need to be explained.

Conclusion. I found no significant deficiencies in the A46 review effort that was per-formed on Turkey Point Units 3 and 4. I also found no deficiencies in the plant in my walkdown.

Having a draft report to review, and the folders on each component in the program, par-ticularly as complete as. they are, greatly facilitated my review. With this level of detail available, I thought the review was very efficient and proceeded very smoothly.

I did note that some tank outliers had not been resolved at the time of my review.

Thanks again for involving me in this job. I appreciate the opportunity to support Stevenson & Associates in this work.

Sincerely, The Readiness Operation, inc.

Paul Smith President xc John Luke, FP&L SM 8'hen you need someone to count on

APPENDIX E COMPONENT PHOTOGRAPHS

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