Text

Consultation for Safety-Related Electrical Equipment at Palisades Nuclear Power Plant
	ML18046A812
Person / Time
Site:	Palisades
Issue date:	05/31/1981
From:	; URS CORP.
To:	;
Shared Package
ML18046A813	List: ML18046A812; ML20009E372;
References
	TASK-03-06, TASK-3-6, TASK-RR URS-JAB-8013, NUDOCS 8107280102
	Download: ML18046A812 (186)
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URS CONSULTATION FOR SAFETY-RELATED ELECTRICAL EQUIPMENT AT PALISADES NUCLEAR POWER PLANT Final Response To USNRC Information Notice Dated January 1, 1980 prepa*red for consumers Power Company prepared by URS/John A. Blume. & Associates, Engineers 130 Sylvan* Street Danvers, Massachusetts 01923 1 ,.--8107280102 810722 PDR ADOCK 05000255 P PDR May 1981

ATTACHENT 1 URS/John A Blume & Associates, Engineers Consultation' for Safety-Reiated.rElec:::trical, Equipment at Palisades Nuclear Plant REGULATORY DOCKET FILE COPY /

ATTACHMENT 2 Palisades Plant Remaining Equipment Anchorage Modifications L D-10, D-20

2.

2400 volt buses lC, lD

3.

C-33 (in progress)

4.

C-40 (in progress)

5.

C-101 (in progress)

6.

C-07

7.

YOl

8.

C-04, C-06 9, C-207, C-115

10.

C-11, C-12, C-13

11.

Diesel Generator 1-1, 1-2 Skids It is expected that these modifications will be completed by the end of the 1981 Palisades refueling outage. _ __j

URS I JAB 8013 URS CONSULTATION FOR SAFETY-RELATED ELECTRICAL EQUIPMENT AT PALISADES NUCLEAR POWER PLANT Final Response To USN RC, Information Notice Dated January 1, 1980, prepared for Consumers Power Company prepared by URS/John A Blume & Associates, Engineers 130 Sylvan Street Danvers, Massachusetts 01923 May 1981

CONSULTATION FOR SAFETY-RELATED ELECTRICAL EQUIPMENT AT PALISADES NUCLEAR POWER PLANT (FINAL RESPONSE TO USNRC INFORMATION NOTICE DATED JANUARY 1, 1980) Prepared for CONSUMERS POWER COMPANY Jackson, Michigan May 1981 Prepared by URS/John A. Blume & Associates, Engineers 130 Sylvan Street Danvers, Massachusetts

FORM DA-I DOCUMENT APPROVAL SHEET DOCUMENT TITLE: Consultation for Safety-Related Electrical Equipment at ~~~~~~~~~~~~--'-~~~~~~~~~~-'----'-~~~~~~~ Palisades Nuclear Power Plant PROJECT NAME: Palisades Electrical Equipment JOB NO.: 8013 This document has been prepared in accordance with the URS/Blume Project Control System and project requirements. Initial issue (Rev.O): Prepared by: Reviewed by: Approved by: Date: '5/ta/81 I REVISION RECORD: Revision Prepared Reviewed Approved By/ Description of'Revision No. By By Date DA-I (3/27/81)

CONTENTS INTRODUCTION *...........................*...........................** EQUIPMENT CH ECKL I ST................................................... 2 METHODS AND CRITERIA............................................*..... 6 Seismic Inputs *...... *.............................. * *............* 6 Other Loads *.... * *.. *....... *...................................... 7 Load* Combination.... *....... *...................................... 7 Equipment Weights.................................. *............... 8* Structural Acceptance Criteria..................................... 8 Cable Trays.*.................................*................. * *

9 TESTING 11 RESULTS............................................................... 25 Safety-Related Equipment.......................*...................

25 Cab 1 e Trays.................... *............. *..................... 25 Non-Category I I terns............................................... 30 REFERENCES............................................................ 34 APPENDICES A Non-Category I Equipment B Equipment Weight Study c Anchor Bolt and Base Plate Criteria D Anchor Bolt Bending Criteria E Remedial Design Drawings F Guide! ines for Non""Category I I terns TABLES Equipment Check 1 i st..................... *... *................ *..... 3 2 Summary of Low-Impedance Vibration Testing......................... 12 - ii -

CONTENTS (Continued) page 3 Summary of Anchorage Study and Remedial Designs.................... 26 4 Non-Cate.gory I I terns...... *...... *....... *....... *................. 31 2 3 4 5 6 7 8 9 10 11 12 13 FIGURES Control Panels COl, C02, C03, Mode Control Panels COl, C02, C03, Mode 2............................... Control Panels COl, C02, C03, Mode 3............................... DC Bus and Distribution Center, Mode DC Bus and Distribution Center, Mode 2 DC Bus and Distribution Center, Mode 3 Cable Tray Adjacent to Diesel Generator Cable Tray Adjacent to Diesel Generator Cable Tray Adjacent to 2,400-V.Bus I -:-C, Cable Tray Adjacent to 2,400-V Bus 1 -c' Station Battery Racks, Mode Station Battery Racks, Mode 2 1 - ] ' Mode 1 -1 ' Mode 2................ Mode 1....................... Mode 2..................... Typical Anchorage Detail for Restraint of Non-Category I Items..... - iii - 13 14 15 1 6 17 18 19 20 21 22 23 24 33

INTRODUCTION In response to the U. S. Nuclear Regulatory Commission 1 s (NRC) lE Information Notice, dated January 1, 1980, Consumers Power Company (CPCO) retained URS/ John A. Blume & Associates, Engineers (URS/Blume), to provide seismic consul-tation for safety-related electrical equipment at the Palisades Nuclear Power Plant, Covert, Michigan. The program performed at the Palisades Plant included the following elements:

1.

Identification of safety-related electrical equipment and non safety-related equipment which could interfere with or damage safety-related equipment during an earthquake.

2.

Inspection of the existing anchorage for items identified in Step 1.

3.

Evaluation of existing anchorages for seismic and other loads.

4.

Modification of anchorages for items not satisfying the acceptance criteria. The completion of this work satisfies the intent of the information notice. EQUIPMENT CHECKLIST Table 1 is the equipment checklist1 that was compiled during the plant walk-* down. It includes all safety-related equipment addressed in this study. At-tachments 1 through 27 of the checklist tabulate non-Category I items in the vicinity of safety-related equipment. These attachments are presented as Appendix A. This check] ist was used as the basis for the evaluation of equipment anchorages. Item~ having no positive anchorage were the first considered. Anchorage schemes were designed for these items and construction drawings were issued. The ade-quacy of items with positive anchorage was also investigated. Strengthening schemes were designed and construction drawings were issued for items which did not satisfy the acceptance criteria. Other items on the check] ist were found to be adequately anchored, and the calculations document the acceptability of the existing support conditions. Item TABLE 1 EQUIPMENT CHECKLISTa Description of Equipment Identification Positive Anchorage I ---------1-~A~-~1~. ~I -ll-~D~le~s~e~l_G~e:n:e~r~a:to~r~S~k:i~ds~~=:-:.~--i--1--1,--1-2-- --yes-1- A.1.2 Diesel Generator Control Panels G2Dd Yes A.1.3 Diesel Generator Control Panels A.1.4 Static Exciters A.1.5 Air Tanks A.1.6 Fuel Oil Day Tanks A.2.1 2,400-V Busses (Switchgear) A.2.2

A.2.3 A.3.1 A.3.2 A.4 A.5 A.6 A.7 A.9 A.11 A.12 A.13.1 A.13.2 A.14.1 A.14.2 A.14.3 A.15 8.1.1 8.1.2 e.1.3 B.1.4 B.1.5 B.1.6 B.1.7 8.1.8 B.1.9 B.1.10 8.1.11 B.l.i2 B.1.13 B.1.14 Relay Test Panels Relay Test Panels Station Power Transformer (2,400 V)

Station Power Transformer (2,400 V) 480-_V Susses (Load Centers) 480-V Motor Control Centers _Station Battery Supports (Ho. 1 & 2) Battery Chargers No. 1, 2, 3, & 4 Inverters No. I, 2, 3, & 4 DC Susses & DC Distribution Panels Preferred AC Susses No. 1, 2, 3, & 4 Bypass Regulator, YOl Bus & Instrument AC Transformers 48D-V Motor Control Centers Pressurizer Heater Transformers No. 15 & 16 Load Center Susses No. 15 & 16 Data Logger Batteries Chargers Inverters Control Rod Drive Transformers Control Room Panel Control Room Panel Control Room Panel Control Room Panel Control Room Panel Control Room Panel .Con.trol Room Panel Control Room Panel

control Room Panel Control Room Panel (Reactor Drive Cal_lbration Cabinet)

Control Room Panel (Noise Analyzer) DELETED Control Room Panel Control Room Panel (Feedwater Pur I ty) G21d C22, C26 T25A, T25B 1-C, 1-D C18, CIBA C19, C19A XII X12 Bil, 812 BOT, 802 DOI, D02 DIS, D16 D17. D18 D06, D07 DOB, D09 DIO, Off 020, D21 Y10, Y2D Y30, Y40 X21, X22 BD7, BOS XIS, X16 D204 02D6, D207 Y210, Y220 X45, X46 COl C03 C02 Cl3 Cll C12 C04 C06 C07 C27 C115 C207 *Yes No Yes Yes Yes Yes Yes Yes No No Yes Yes Yes Yes Yes Yes Yes No No No 'Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Type of Anchorageb BTCS BTE BTE BTCS BTCS WTEC BTE BTE

WTEC WTEC BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCW BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCS BTCS Attachment Number for Non-Category ltemC 5 and 6 5 and 6 5 and 6 5

5 4 for 1-C, 9 for T-0 4 9 12 12 12 13 10 13 13 13 13 13 7 2 9 9 14 19 19 19 20 20 21 22 23 23 (continued)

Item B. 1. 15

t-e-:-Cf6 B.1.17 B.1.18 B.1.19 B.2.1 B.2.2 B.3 a.It B.5.1 B.5.2 B.S.3 B. 6.1 B.6.2 B.7 B.8 B.9 B.10 B. 11. 1 B. 11.2 B.12 B.13

c. 1 C.2. 1 C.2.2 c.2.3 c.. 2.lt c.2.s c.2.6 C.2.7 c.3.1 c.3.2 c.3.3 c.3.1t c.3.5 c.3.6 c.3.7 C.3.8 TABLE Description of Equipment (Continued)

!dent I ficat ion Pos It Ive Anchorage Type of Anchorageb Attachment Number for Non-Category I ltemC Control Room Panel ____________ Cl.9~6 _____ Yes-- ---BT.cs-- ----2~- Control Room Panel C126 Yes BTCS 24 Control Room Panel Control Room Panel Control Room Panel Control Panel Control Panel Speed Control for P55A Charging Pump Air Compressor Panel Diesel Fire Pump Control Panel Diesel Fire Pump Control Panel Diesel Fire Pump Batteries Hydrogen Recombiner Power Panels Hydrogen Recombiner Control Panels DELETED Conltel 2100 Computer Cabinet Control Room HVAC Panel Rod Drive Control Logic & Contactor Panel Fi re l\\od. Panel in Battery Room 1 Fire Hod. Panel in Battery Room 2 Sample Station Sample Station Refueling D.lsconnect Panel C.1ble Trays Above Bus 1-C Cable Trays at Tunnel Cableway (Room 332) Cable Trays at North Penetration (Outside Containment, Cable Penetration Room) Cable Trays Over Cable Spreading Room Cable Trays at North Penetration (Inside Containment) Cable Trays at North Penetration (Inside Containment, on Shield Wall) Cable Trays at Southwest Penetration (Inside Containment) Terminal Board Near 1-D Terminal Board Near 1-D Terminal Board Near 1-D Terminal Board Data Logger Bypass Swl tch Noah Tank Piping Protection Panels Power Available Light Boxes Terminal Board Terminal Board at Load Centers 15 ' 16 SCR Control C125 CS! C302 C33 cite C17 C35 C37 C137 D36, 038 C121, CT 24 C122, C123 C09 CTS C101 C103 J9401 JL275 JL274 C145, C146 TCAC2 Yes Yes Yes Yes Yes Yes Yes No No No Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes BTCS BTCS BTCS BTCS BTCS BTCW BTEf BTCS BTCS, BTCW BTCS BTCW BTCS BTCW BTBW BTCS BTCS BTCS BTCS BTCW BTCW BTCS BTCW BTCW, BTCS BTCS BTCW BTCW BTCW BTCW BTCW BTCW BTCW BTE 25 25 7 7 16 15 18 11 11 13 8 13 10 10 27 27 3 4 26 11 11 2 (continued)

TABLE 1 (Continued) NOTES:

a.

An early version of this list was published with Interim Report 1. Since that time, some minor changes have been made to the equipment names and identification numbers. 1 _____________ b_._6bbre.v.i.at.ions-used-to-descr i*be-type-of-ancnorages as fo 11 c:>o<s: STE Bo I ted to Equipment \\lTEC. Welded to Embedded Channel BTCW. Bo I ted to Concrete Wall BTCS Bo I ted to Concrete Slab BTBW - Bo 1 ted to Block Wall

c.

Dashes in this column indicate no non-Category I items in vicinity.

d.

One attached to Generator 1-1 and one to Generator 1-2.

e.

Items A.8 and A.10 in same cabinet (Inverter No. 1 with Bus No. 1, etc.).

f.

Bolted to Hotor Control Center 4

METHODS AND CRITERIA Seismic Inputs Seismic loadings for the SSE were used to analyze and design equipment anchorages.

Seismic response spectra for all levels of the containment and auxiliary buildings were provided by Consumers Power Company. Z,3 These curves were multiplied by 2.0 to obtain full SSE loadings. The vertical response spectrum at all levels was assumed to be two-thirds of the SSE free-field ground response spectrum. 2*3 For equipment in the intake structure, the SSE ground response spectra were used to determine horizontal seismic de-sign forces, and the ground response spectra multiplied by two-thirds were used for vertical seismic forces. 4 All equipment was assumed to be 5% damped. 5 With four exceptions, seismic design forces for all equipment were determined by multiplying the peak acceleration of the applicable floor response spec-6 trum by 1.0. This approach is adequately conservative for several reasons. Firstly, it assumes that the frequency of vibration of the equipment being considered is the same as the frequency of the peak of the floor response spectra. The actual freque~cy of a particular item could be outside the peak range of the floor spectra and this would result in drastic reductions in the design forces compared to those used in the analysis. In addition, this approach assumes the entire mass participates in the fundamental mode (the fundamental mode contributes most significantly to the anchorage forces). Typically, only between 70 to 90 percent of the mass participates in the fundamental response mode. The four exceptions noted above are the diesel generator, the starting-system air tanks, the station battery racks, and control room consoles COl, C02, and C03. For these four, seismic forces were determined by taking.l.0 times the spectral acceleration at the fundamental frequency of th~ equipment. Higher modes of these equipment were found to have lo~er spectral accelerations and modal weights than the fundamental mode so they were conservatively ignored

For the air tanks, the fundamental frequency was calculated by an approximate and conservative method.

For consoles COl, C02, and C03 and the battery racks, the fundamental frequency was derived from the results of low-impedance testing. The diesel engines and generators were assumed to be rigid; however,

th-e-suppo-rt-ing'i/2-4-Sl<ia was considered non-rigid.

(The W24 skid was subsequently stiffened.) Low-impedance testing was also instrumental in determining the fre-quencies of the DC busses and distribution centers and two cable tray systems. Equipment supported at multiple locations was analyzed, and anchorages were designed for the upper-bound envelope of the individual response spectra for the support locations as well as for maximum relative support displacement. This criterion was waived for items of electrical euqipment less than 10 ft high that were anchored at the base and braced to a concrete wall at the top. In these cases, the use of the peak spectral ordinate of the base elevation resulted in adequately conservative seismic design forces. Other Loads Equipment dead load was the only other load included in the analysis and design of seismic anchorages. For most electrical equipment, the operating loads other than dead load are small and may be ignored; however, this is not true for the diesel generators. The new anchorages for this equipment were designed to resist the seismic forces, while it was assumed that the existing anchor bolts would resist the operating loads. Load Combination The load combination for the evaluation of existing anchorages and the design of new anchorages is the worst combination of D, ~H, ~V: where: D = the equipment dead load H the horizontal earthquake load in the most critical direction (SSE) V the vertical earthquake load (SSE) This combination is essentially the same as that given in the NRC Standard Review Ptan, Section 3.8.4,7 equations (b)4 through (b)B for concrete struc-tures and b(i)4 through b(i)7 for steel structures. 'Equipment Weights Equipment weights were compiled from CPCO files, consultations with vendors, and field measutements; however, it was impossible to determine the exact weight of every piece of equipment included in this study. Some anchorages w~re analyzed and redesigned using an assumed weight that was based on an equipment density of 35 lb/ft3* ~his density value was de~ived from a probabilistic study of equipment weights; it is estimated that there is a 96% chance that the actual density of an item will be less than 35 lb/ft3. (See Appendix B for details of this study.) The centers of gravity were calculated rigorously in cases where the distri-bution of equipment weight was known. However, when the lack of sufficient data precluded rigorous calculations, the center of gravity was simply assumed to be at the geometric center of the equipment. Structural Acceptance Crite~ia The basis of the structural acceptance criteria for this work was NRC Standard Review Plan, Section 3.8.4, which states that the allowable limits for concrete structures are to be derived from strength design methods described in American Concrete Institute code ACl-318-71 8 and that the allowable 1 imits for steel are to be 1.6 times the allowable stresses for elastic design defined in Part 1 of the American Institute of Steel Construction's Specifications for the Design, Fabrication, and Erection of Structural Steel for Buildings, February 12, 1969. 9 Allowable stresses for reinforced concrete masonry were taken from the 1979 edition of the Uniform Building Code. lO Guide I ines for the evaluation and de-sign of expansion anchors and base plates (see Appendix C) were taken from Reference 11 which is based on work performed at Palisades Plant in response to U. S. NRC IE Bulletin 79-02 and its revisions. This extensive program12 included the testing and inspection of approximately 3,000 concrete expansion anchor bolts and the subsequent development of acceptable design loads and evaluation procedures. Several existing anchorage details involved a gap between the bottom of the

1

_______.b_a_S_e_pJ_ate-and-t-he-GGne-r:e-1;e-sur-f-ace-. -'fh-i-s-dera_i_] requ i reatfie anchor bo] t to carry tension, shear, and bending. A special criterion (see Appendix D) was developed to evaluate this anchorage. Cable Trays The methods of analyses and structural acceptance criteria used for cable tray systems were quite different from those used for other safety-related equip-ment. For cable tray systems with some degree of lateral restraint (e.g., cable trays that are braced to reinforced concrete walls) a linear-elastic anaiysis was used. For cable trays without lateral restraint (e.g., the trapeze system) either a displacement-bound analysis or an analysis based on comparison with test results was used for seismic qualification. The follow-ing paragraphs elaborate on these three methods. Linear-Elastic Analysis. This form of analysis was used for cable tray sup-ports that have some form of lateral bracing. Systems of this type carry the majority of the seismic loadings via direct stress so that bending stresses are small and typically within the elastic range. Because element bending is small, unknown rotational stiffness of the clip connections becomes less of a factor, making standard analysis assumptions viable. Displacement-Bound Analysis. Experimental results obtained from the ANCO/ Bechtel Power Corporation report, Cdble Tray and Conduit Raceway Seismic Test Program, 13 indicate that nonlinear behavior of the clip connection strongly influences the response of hanging cable tray systems. Significant inelastic action of the clips (with rotations of 5° to 6°) can be sustained before struc-tural failure occurs. Since it is beyond the scope of this study to perform detailed nonlinear analysis, the procedure used estimated the upper and lower bounds of maximum clip rotation. These bounds were compared with clip rota-tion capatity as determined in the ANCO/Bechtel report. The lower-bound estimate of maximum clip rotation is found from a linear-elastic model of the hanging tray system in which _l_Lb_q_s_s_J.JnJ_e_d_tba_t_the-sup-----------

port:cnps have-z~ro ~~tatlo~~tiff~es;(i.e., pins) and that the connection clips have infinite rigidity.

The upper-bound estimate is found by assuming that all clips have zero rotational stiffness, thus creating lateral insta-bility and forcing the system into a 11pendulum 11 mode of behavior. In both cases, the maximum clip rotation is assumed to occur at the support with a value equal to the rotation of the unistrut at that location. To ensure that an upper-bound estimate is truly achieved, the equivalent dynamic load on the pendulum is taken as that load corresponding to a natural period of the stiffer system (l.e., the tray with rigid connection clips) rather than as the lower spectral acceleration associated with the longer natural period of a true pendulum. Modal analysis procedures assume that typical cable tray configurations deform in a sway-type mode with minimal tray distortion; hence, high system modes are neglected. Higher hanger modes (i.e., the modes of the individual hangers) are considered only if it is determined that there is significant mass in the higher modes that might be excited by a building resonance. Analysis by Comparison. Cable tray systems that failed to qualify by the linear-elastic analysis and by the displacement-bound analysis were compared with the systems tested in the aforementioned ANCO/Bechtel report. Systems were grouped according to configurations, mass, and fundamental frequency a~d then compared to determine their similarity with systems that were proof and fragility tested in the shake-table test program. 10 - . -*--*-------*- - - ---** *-*-- --- ---- ---*- ~------------*----------- ------ -

TESTING Low-impedance in-situ eigenparameter testing was performed for several pieces of equipment. This technique involves the measurement and analysis of the low-amplitude vibrations that occur when a specimen (electrical equipment in this case) is lightly struck with a force-calibrated mallet. Table 2 provides a summary of the equipment included in the test program and the measured frequencies. Mode shapes are given in FiQures l through 12. Frequency and mode shape data were obtained for control panels COl, C02, and C03, the station battery racks, the DC busses and distribution centers, the cable tray near the diesel generator and the cable tray near the 2,400-V bus 1-C. The test results were quite useful in determining the anchorage design loads for the tested equipment. The test results for the cable trays were useful in verifying the analytical models used in the analyses of these systems

11 -

TABLE 2

SUMMARY

OF LOW-IMPEDANCE VIBRATION TESTING Mode 1 Mode 2 Mode 3 Equipment f 1 f 2 f 3 (Hz) (Hz) (Hz) Control Panels COl, C02, C03 16.4 22,9 38.8 Station Battery Racks 57.0 226.7 N DC Busses and Distribution Centers 7,4 14.9 22.2 Cable Trays Near 2,400-V Bus 1-C 10.9

28. I Cable Trays Near Diesel Generator 1-1 17.2

28. I

~-------------------

FIGURE 1 CONTROL PANELS COl, C02, C03, MODE 1 Drl'.?00

8. 87 s

FIGURE 2 CONTROL PANELS COl, C02, C03, MODE 2 2 FRE~<H?'.)

22. 94 Dr.t~f' ru

2. BZ s

FIGURE 3 CONTROL PANELS COl, C02, C03, MODE 3 --*----------- -~---- --*-** ---*-***-*.... -

l \\ \\ FIGURE 4 DC BUS AND DISTRIBUTION CENTER, MODE 1 MOOE 1 FREQCHD

7. 44 s

y

FIGURE 5 DC BUS AND DISTRIBUTION CENTER, MODE 2

MOOE 2

FREQQiZ) 14.85 DAMPOO

a. 44' s

y

FIGURE 6. DC BUS AND DISTRIBUTION CENTER, MODE 3 MOOE a FREQQID

22. 26 DAMPOO

2. 41 s

y

MOOE 1 FREQCHZ) 10.94 DAMPOO 10.62 FI GU.RE 7 CABLE TRAY ADJACENT TO DI ES EL GENERATOR 1-1, MODE 1 s

MOOE 2 FREQ<HZ) 2.S.36 Of.MP 00

7. 3e FIGURE 8 CABLE TRAY ADJACENT TO DIESEL GENERATOR 1-1, MODE 2 20 -

s

MODE 1 FREQOID 17.19 FIGURE 9 CABLE TRAY SUPPORT ADJACENT T02400 V BUS 1-C, MODE 1 s

I FREQQID 28.12 FIGURE 10 CABLE TRAY ADJACENT TO 2400 V BUS 1-C, MODE 2 s

I-FIGURE 11 STATION BATTERY RACKS, MODE 1 MOOE 1 FREQQiZ)

55. 53 DAHPOO 3.30 s

FIGURE 12 STATION BATTERY RACKS, MODE 2

MODE 2

FREQQiZ) 225.. 69 0/\\Hf) 00

e. 18 s

X~Y

RESULTS Safety-Related Equipment The anchorages for all the equipment listed in Table l (the equipment check- ] ist) were evaluated in accordance with the criteria described earlier. The results of these evaluations are summarized in Table 3. Table 3 shows which items of equipment were found to be adequately anchored and which items require anchorage modification. For the latter group, the modification drawing numbers are shown in Table 3, the drawings may be found in Appendix E. The implementa-tion of these modifications insures-adequate anchorage for the safety-related electrical equipment at the Palisades plant. Cable Trays On the basis of extensive site walk-downs conducted by URS/Blume, seven cable tray systems were selected as representative of the Palisades plant. All systems selected were strut hanger configurations utilizing ladder-type trays. The seven. systems chosen were as fol lows: Item No. 2 3 4 5 6 7 Location Room 332 (tunnelway) North penetration inside containment Near north penetration on sh i e 1 d wa 11 North cable penetration room Elevation 590' below southwest penetration inside containment Adjacent to 2,400-V bus Cable spreading room Type Wall-braced frame Wall cantilevered Wall cantilevered Wal 1-braced frame Trapeze-hanger frame Trapeze-hanger frame Trapeze-hanger frame The first four items listed were analyzed using linear-elastic_ analysis techniques. All stresses remained below the recommended allowable value of 14 25 ksi and are therefore acceptable. Items 5 through 7 were analyze~ in accordance with the techniques described in the section on cable trays in the Methods and Criteria chapter. The re-sults of the analyses indicate base angular rotations in excess of 6°. The '

N Item A. 1. 1 A. 1.2 A. 1.3 A. 1.4 A.1.5 A.1.6 A.2.1 A.2.2 A.2.3 A.3.1 A.3.2 A.4 A.5 A.6 A.7 A.B A.9 A.10 A.11 A. 12 A. lJ.1 TABLE 3

SUMMARY

OF ANCHORAGE STUDY AND REMEDIAL DESIGNS URS/Blume Calculation Description of. Equipment I dent i f i cation Sheet a Diesel Generator Skids 1-1, 1-2 8013-A. 1.1 Diesel Generator Control Panels G20 B013-A.1.2, 3 Diesel Generator Control Panels G21 8013-A.1.2, 3 Static Exciters C22, C26 BCl13-A. 1. 4 Air Tanks B013-A.1.5 Fuel Oi I Day Tanks T25A, T25B B013-A.1.6 2,400-V Busses (Switchgear) 1-C, 1-0 B013-A.2.1 Relay Test Panels ClB, CIBA B013-A.2.2, 3 Relay Test Panels C19, C19A B013-A.2.2, 3 Station Power Trans former (2,400 V) Xll B013-A.3.1, 2 , Stat ion Power Transformer (2,400 V) X12 B013-A. 3. 1, 2 4BO-V Busses (Load Centers) Bll, B12 B013-A.4 4Bo-v Motor Control Centers BOl, B02 B013-A.5 Station Battery Supports No. 1 & 2 DOl, D02 B013-A.6 Battery Chargers No. 1, 2, 3, & 4 D15, D16 B013-A. 7, 8, 10 D17, DlB Inverters No. l, 2, 3, & 4 D06, DO] B013-A. 7, 8, 10 DOB, D09 DC Busses & DC Distribution Panels DlO, Dll B013-A.9. D20, 021 Preferred AC Busses No. 1, 2, 3, & 4 YlO, Y20. B013-A.7, B, 10 Y30, Y40 Bypass Regulator, YOl Bus & Instrument X21, X22 8013-A.11 AC Trans formers 4BO-V Motor Control Centers BO], BOB 8013-A. 12 Pressurizer Heater Transformers X15, X16 8013-A. 13. 1, 2 No. 15 & 16 Modifi-Modification cat ion Drawingb Needed Yes

33. Rev. 0 No N/A No N/A Yes 8, Rev. 0 No N/A Yes 10, Rev. 1 Yes 16, Rev, I No N/A No N/A Yes 12, Rev. 0 Yes 3, Rev. 0 Yes 4, Rev. 0 Yes 13, Rev. 0 Yes lB *, Rev. O Yes 14, Rev. 1 Yes 14, Rev. 1 Yes 15, Rev. 1 Yes 14, Rev. 1 Yes 27, Rev. 0 Yes 7, Rev. 0 Yes 1, Rev. 0

(continued)

I

I Ni -.....JI I I

I tern A.13.2 A.14. I A. 14.2 A. 14.3 A.15 B~ 1. 1 B. 1.2 B. 1.3 B. 1.4 B. 1.5 B.1.6 B.1. 7 B.1.8 B.1.9 B.1.10 B.1.11.1 B.1.11.2 B. 1. 12 B. 1. 13 B. 1. 14 B. 1. 15 B. 1. 16 B.1.17 B. l. 18 B.1.19 B.2.1 B.2.2

' B. 3 B.4 Description of Equipment Load Center Busses No. 15 & 16 Data Logger Batteries Chargers Inverters Control Rod Drive Transformers Control Room Panel Control Room Panel Control Room Panel Control Room Panel Control Room Panel Control Room Pan~! Control Room Panel Control Room Panel Control Room Panel =tnrr:t:ral-::Raom=P.anel.=(.Re.a<:i:i£ "llr~lh£

-Ealihr

.. afitiit G"a1i..i11 a-}:* DELETED Control Room Panel (No I se Ana I yzer) Control Room Panel (Noise Analyzer) DELETED Control Room Panel Control Room Panel (Feedwater Purity) Control Room Panel Control Room Panel Control Room Panel Control Room Panel Control Room Panel Control Panel Control Panel Speed Control for P55A Charging Pump Air Compressor Panel - I dent if i cation D204 D206, D207 Y210, Y220 X45, X46 COl C02 C03 C13 Cl 1 C12 coli C06 CO] C27 C115 C207 C106 C126 C125 CSI C302 C33 c4o C17 C35 URS/Blume Calculation Modifi-Modi f i cation Sheeta cat Ion Drawingb Needed 8013-A.13.1, 2 Yes 2, Rev. 1 8013-A.14.1 No N/A 8013-A.14.2 No N/A 8013-A.14.3 No N/A 8013-A.15 No N/A 8013-B.1.1, 2, 3 No N/A 8013-B.1. 1, 2, 3 No N/A 8013-B.1.1, 2, 3 No N/A. 8013-B.1.4, 5, 6 Yes 32, Rev. 0 8013-B.1.4, 5, 6 Yes 32, Rev. 0 8013-a. 1.4, 5, 6 Yes 32, Rev. 0 8013-B.l.7, 8 Yes 28, Rev. 0 8013-B.1.7, 8 Yes 28, Rev. 0 8013-B.1.9 Yes 26, Rev. 0 8013-B.1.IO N/A 8013-B. 1.11.1 Yes 19, Rev. 1 8013-a. 1.11.2 Yes 9, Rev. 0 8013-B.1.13, 14 Yes 30, Rev. 0 8013-B. 1. 13, 14 Yes 30, Rev. 0 8013-B. 1. 15 No N/A 8013-B.1.16 No N/A 8013-B.1.17 Yes 21, Rev. 0 8013-B.1.18 Yes 29, Rev. 0 8013-a.1.19 No N/A 8013-B.2.1, 2 Yes 23, Rev. 1 8013-B.2.1, 2 Yes 23,* Rev. I - 8013-B.3 No N/A 8013-B.4 No N/A (continued)

I N co I Item B.5.1 B.5.2 B.5.3 B.6.1 B.6.2 B.] B.8 B.9 B.10 B.11.1 B. 11.2 B.12 B.13 C.1 C.2. I C.2.2 c.2.3 C.2.4

.2.5

.2.6

.2. 7 c.3.1 c.3.2 c.3,3 c.3,i, TABLE 3 (Continued)

Description of Equipment Identification Diesel Fire Pump Control Panel C37 Diesel Fi re Pump Control Panel C137 Diesel Fire Pump Batteries D36, D38 Hydrogen Recombiner Power Panels C121, CJ24 Hydrogen Recombiner Control Panels Cl22, C123 DELETED Con Itel 2100 Computer Cabinet C09 Control Room HVAC Panel Rod Drive Control Logic & C15 Cont actor Panel Fire Mod. Panel in Battery Room 1 Fi re Mod. Panel in Battery Room 2 Sample Station C101 ~ ...suaton: DELETED C103 Refueling Disconnect Panel Cable Trays Above Bus 1-C Cable Trays at Tunnel Cableway (Room 332) Cable Trays at North Penetration (Out-side Containment, Cable Penetration Room) Cable Trays Over Cable Spreading Room Cable Trays at North Penetration (Inside Containment) Cable Trays at North Penetration (1.nside Containment, on Shield Wall) Cable Trays at Southwest Penetration (Inside Containment) Terminal Board Near 1-D J9401 Terminal Board Near 1-D JL275 Terminal Board Near 1-D JL274 Terminal Board Data Logger Bypass Switch URS/Blume Calculation Modifi-Mod I f i cat ion Sheet a cat ion Drawingb Needed 6, 8013-B.s.1, 2 Yes Rev. 1 8013-B.5.1, 2 Yes 6, Rev. 1 8013-B,5.3 Yes 5, Rev. 0 8013-B.6.1 Yes 17, Rev. 1 8013-B.6.2 Yes 35 *, Rev. 0 8013-B.8 Yes 11

Rev. 1 8013-B.9 No N/A 8013-B.10 Yes 22, Rev. 1 8013-B. 11. 1 No N/A 8013-B. 11.2 No N/A 8013-B. 12 Yes 24, Rev. 0 -

8013-B.13 N/A 8013-c.1 No N/A 8013-c.2 Note c 8013-c.z No NIA 8013-c.2 No N/A 8013-c.2 Note C . 8013-C.2 No N/A 8013-c.2 No N/A 8013-C.2 Note c . 8013-c.3.1 No NIA 8013-c.3.2, 3 No N/A 8013-c.3.2, 3 No N/A 8013-c.3,i,, 5, 6, 7 No N/A (continued)

N. l.O TABLE 3 (Continued) URS/Blume Calculation Mod ifi-I tern Description of Equipment Identification Sheeta cation Needed C.3.5 Noah Tank Piping Protection Panels Cl45, Cl46 8013-c.3.4, 5, 6, 7 No C.3.6 Power Available Light Boxes 8013-c.3.4, 5, 6, 7 No c.3,7 Terminal Board TCAC2 8013-c.3.4, 5, 6, 7 Yes c.3.8 Terminal Board at Load Centers 15 & 16 8013-c.3.8 No SCR Control NOTES:

a.

See Appendix F.

b.

See Appendix G.

c. Analyses of these systems were inconclusive due to lack of test data.

These issues will be resolved by the development of comprehensive cable tray acceptance criteria. This effort Is currently In progress. Modification Drawingb N/A .N/A 34, Rev. 0 N/A

Bechtel cyclic load testing was not conducted at angular rotations in excess f 5° 1 3 1 5 h f 1

d.

d f h h 1 d o t ere ore no cone us 1 ans rega r 1 ng a equacy o t e angers cou be formulated on the basis of displacement-bound analyses. An attempt was made to evaluate the systems by comparing them with prototypes shake-table tested in the Bechtel test program; however,.the systems tested differed in anchorage detail and size from those at the Palisades plant. Thus, further testing, specifically cyclic load testing in which base angular rotations ex-ceed 6°, should be conducted for hanger strut systems similar to those at the Palisades plant. This will be performed as part of the SEP owners group program study on* rciceway systems, which is presently under way. Non-Category I Items Non-Category I items that might interfere with safety-related equipment dur-ing an earthquake are documented in Appendix A and are summarized in Table 4. Many of the items in Table 4 were judged to be adequately anchored. This conclusion was initially formed by a visual inspection of the items during the plant walk-down and was subsequently reinforced by the calculations for similar safety-related equipment. The following items were judged to be ade-quately anchored: Lights Ducts Piping Air f i 1 ters Vent fans Dampers Terminal boxes Refueling platforms The following items were found to be unanchored or inadequately anchored: Filing cabinets Book cases Teletypes Instrument racks Desks Chai rs Portable hoist Dry bulb sensor The potential hazard that these items present to safety-related equipment will be effectively eliminated by the implementation of th~ ~uid~Tihe~.~iven in Appendix F. These guide] ines (or housekeeping rules) require minimum clearance between potentially hazardous non-Category I items and safety-related equipment. If minimum clearance cannot be maintained, non-Category I items can be anchored TABLE 4 NON-CATEGORY I ITEMS Gas bottles Lights File cabinets Bookcases Ducts Teletype Instrument racks Desks Chairs Piping (noncritical) Portab 1 e ho i*st Planks/scaffolding Dry bulb sensor Dollies Air filter 4-ft-diameter vent fan 3-ft-diameter damper Terminal boxes Refueling platform Fan near load center 16 using a detail such as that shown in Figure 13. This detail consists of a 4-in. x 4-in. x 3/4-in. angle attached to a reinforced concrete wall or slab with a 3/4-in.-diameter expansion anchor. A length of 1/4-in.-diameter wire rope is attached to the angle through a 1/2-in.-diameter hole and is also attached to the equipment being supported. This connection will sustain a tensile working level load of I,200 lb (with a factor of safety of S) and an ultimate tensile load of 6,000 lbs, which makes it more than adequate to anchor any of the items listed in Table 4. Implementation of the housekeeping rules and/or Figure 13 will prevent the interference of non-category I items with safety-related equipment during an earthquake

w w

Q! 'Z II ~ ~ ~~ . ':) ~.. ~"?HOLE CONSU!.."t CLIP MANUt=ACTUR.E!e. !=OR CO!eR.eCi /VUM8f!R AND .f PACING Or CA6'-e Ct...IPS .

a "l

--~~~~...._--.-~--..-~~-- I "ZOO t,f: *eqUIPMeNT L.OA 0. Wlil-I !=ACiOl<. OF SA/:c T"t )(

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~ ~~: ~:

0. '

().. 0. .. 0 o;= 5', '-/(.T/MATe l..OAO

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FIGU~e I :3 --- -- !:,." ¥> i!JerHLE HeM r;, x IC/ PU!<Ple Pl.US Fl~t:I:.. . co;ee W/R.S ~OPE OR.. EQUAL. /YPICAl... ANCHOR.AGE D8TAll... FOR

es.sr~AINT OF NON~ *cArcGO!<. y I

IiEMS

REFERENCES

1.

URS/John A. Blume & Associates, Engineers, Seismic Consultation for Safety-Related Electrical Equipment, Conswners Power Company, Palisades Plant, Covert, Michigan, Interim Report l, Equipment Check] ist, San Francisco, California, March 1975.

2.

Bechtel Engineering Corporation, Reactor Building Seismic Analysis, Consumers Power Company, Palisades Plant, CPCO-GW0-8428, Bechtel Job No. 10512-031, San Francisco, California, 1969.

3.

Bechtel Engineering Corporation, Seismic Design Requirements for Equipment Located in the Auxiliary Building, Consumers Power Company, Palisades Plant, Specification No. 10512/034-C-17507, Attachment 2, Revision 0, San Francisco, California.

4.

Letter from D. P. Hoffman, Consumers Power Company, Jackson, Michigan, to D. L. Ziemann, U.S. Nuclear Regulatory Commission, Washington, D.C., dated June 8, 1979, enclosure 2, p. 2.

5.

Institute of Electrical and Electronic Engineers, Inc., Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations, IEEE Standard 344-1975, New York, New York, 1975.

6.

U.S. Nuclear Regulatory Commission, Stand.a.rd Review Plan, Section 3.7.2, Office of Nuclear Reactor Regulation, Washington, D.C., June 1975.

7.

U.S. Nuclear Regulatory Commission, Standard Review Plan, Section 3.8.4: Other Category I Structures, Off ice of Nuclear Reactor Regulation, Washington, D.C., November 1975.

8.

American Concrete Institute, Building Code Requirements for Reinforced. Concrete, ACl-318-71, Detroit, Michigan, 1971. 9, American Institute of Steel Construction, Specification for the Des-gn, Fabrication, and Erection of Structural Steel for Buildings, New York, New York, 1969.

10.

International Conference of Building Officials, Uniform Building Code, 1979 edition, Whittier, California, 1979.

11.

Bechtel Associates Professional Corporation, _Design Criteria for Evalua-tion of Expansion Anchors and Base Plates for Seismic Safety System I'ipe Supports, Consumers Power Company, Palisades Plant, Bechtel Job No. 12447-033, Ann Arbor, Michigan, January 1980.

12.

Bechtel Associates Professional Corporation, Final Response to USNRC IE Bulletin 79-02 and ~ts Revisions for Conswners Power Company, Palisades Nuclear Power Plant, South Haven, Michigan, Ann Arbor, Michigan, July 1980.

13.

ANCO Engineers, Incorporated, Cable Tray and Conduit Raceway Seismic Test Program, Report No. 1053-21.1-4, Release 4 (final), 2 Vols., Los Angeles, California, December 15, 1978.

14.

11Unistrut, 11 General Engineering Catalog, No. BA, 1977.

15.

Bechtel Power Corporation, Cable Tray and Conduit Raceway Test Program, Development of Analysis and Design Techniques from Dynamic Testing of Electrical Raceway Support Systems, Revision 0, San Francisco, California, July 1979. APPENDIX A Non-Category I Equipment (Attachments 1 through 27)

I Category I Non:- Category I Equipment Type & ID# Equipment 'Type Pressurizer Fan Heater Transformer X15 & Xl6 II File Cabinet I I ent I Non-Category I Equipment Off set Di st. (ft) 1

from X16 611 from X16 Positive Anchorage (yes/no)

No No i ( .......... ~

At Non-Category I Equipment I Category I* Non-Category I Off set Dist. Positive Anchorage Equipment Type & ID# Equipment Type (ft) (yes/no) Load Center Ducts 3' Up Yes Busses 15 & 16 Terminal Box at Load Center (Same As Above) Busses 15 & 16 ~

Category I Equipment Type & ID U Refueling Disconnect Panel Non-Category I Equipment Type Refuel i ng Pl at form ent 3 Non-Category I Equipment Off set Dist. (ft) 6* Positive Anchorage (yes/no) No

A ent 4 Non-Category I Equipment Category I Non-Category I Offset Dist. Positive AnchoraQe Equipment & ID # Equipment Type (ft) (ye:;/no) 2400V Terminal Box a* Up Yes Buss 1-C 4 x 2-1/2 x 1 1/2 2400V Heating Steam Duct a* Up Yes Buss 1-C 11 d I a. 3' Off Relay Test Panel Cl 8 & Cl 8A (Same As Above) Cable Trays Above Buss 1-C (.Same As Above)

, L ent 6 I Equipment Non-Cat ego Category I Non-Category I Off set Dist. Positive Anchoraqe EGulpment & ID# Equipment Type {ft) (yes/no) Diesel 41 dia. Vent 1 I Up Yes Generators Fan 1-1 and 1-2 Diesel Generator Control Panels G20 and G21 (Same As Above)

~~~--~~~~-

f\\ t t. t 7 Non-Category I Equipment Category I Non-Category. I Offset Dist. Positive Anchoraqe EGulpment & ID # Equipment Type (ft) (yes/no) Alternate Air Duct 2' Up Yes Shutdown 3' Off C33 and C40 480V MCC 7 & 8 (Same As Above) (807,808)

A ent 8 Non-Category I Equipment Category I Non-Category I Off set Dist. Positive AnchoraQe Equipment & ID # Equipment Type (ft) (yes/no) Control Room Air Filter 3* Up Yes HVAC Panel

ent 9 Non-Category I Equipment Category I Non-Category I Offset Dist. Positive Anchoraqe Equipment & ID# Equipment Type {ft) (yes/no) 2400V Duct 3* Up Yes Buss 1-D 2400V Buss 1-D Lights

3 1 Up Yes (Chain) 2400V Dry Bulb 10 1 Away No (Ro 11 e rs)

Buss 1-D Sensors 2400V Do 11 y 10 1 Away No (Rollers) Buss 1-D 2400V Cabinet o* Yes Buss 1-0 36 11W x 7811H x 21 11 D {Bolted to 1-D) Relay Test Panels (Same As Above) C19 & C19A Chargers (Same As'-'Above) 006 & 007 Inverters (Same As Above) Y210 & Y220

Category I Equipment & ID# Station Batteries DOl & 002 Fire Mod. Panel In Battery Rooms 1 & 2 Non-Category I Equipment Type Ducts (.Same as above) nLt.nt 10 Non-Category I Equipment Offset Dist. (ft) 5' Up Positive Anchoraqe ' (yes/no) Yes

At ent 11 Non-Category I Equipment Category I Non-Category I Off set Dist. Positive Anchoraqe Equipment & ID # Equipment Type (ft) (yes/no) Hydrogen Planks 6' Up Yes Recombiner Scafolding Power Panels Hydrogen Piping 6' Up Yes Recombiner Sprinklers? Contra 1 Panels Hydrogen Portable Hoist No (Rollers) Recombiner Centro 1 Panels Noah Tank Piping (Same as above) Prot. Panels C145 and C146 Power Available Light Boxes (Same as above)

At ent 1 2 Non-Category I Equipment Category I Non-Category I Offset Dist. Positive Anchoraqe EGulpment & ID # Equipment Type (ft) (yes/no) 2400V to 480V Duct o* Up Yes Power Trnsf. 2* Off Kl 1 andXl 2 480V Lights o* Up Yes Buss es B 11 and B 12 2* Off

Att t 1 3 Non-Category Equipment Category I Non-Category I Offset Dist. Positive Anchora9e Equipment & ID # Equipment Type (ft) (yes/no) 48ov Motor Duct 2* Up Yes Control Centers 801 & 802 480V Motor Portable Hoist No,(Rollers) Control Centers. 801 & B02 Battery Chargers (Same as above) No. 1,2,3, & 4 Inverters (Same as above) No. 1,2,3, & 4 DC Busses and (Sarne as above) DC Distribution Panels Preferred AC Busses No. 1,2,3, & 4 (Sarne as above) Conitel 2100 Computer Cabinet ( S~me as above) Rod Drive Control Log I (Same as above) end Contactor Panel Cl 5

r Category I Equipment Type & ID U Control Rod Drive Transf *. X45 & X46 Non-Category I Equipment Type Duct A.ment 14 Non-Category I Equipment Off set Di st. (ft) 1211 Positive Anchorage (yes/no) Yes

I Category I Equipment Type & ID# Fire Pump Control Panel C137 Fire Pump Control Panel C137 Fire Pump Control Panel C137 Non-Category I Equipment Type Lights front & back Fire System Pipe 1811 di a. ent J 5 Non-Category I Equipment Off set Dist. (ft) 3' Offset 12 1 Up above floor 8' Above Controller Steam & Condensate Lines JO' Above Cont ro 11 er ~ Positive Anchorage (yes/no) Yes (Chain) Yes Yes

Category I Equipment Type & ID U Fire Pump Control Panel Cl7 Non-Category I Equipment Type Condenser Attachment J:6 Non-Category I Equipment Off set Dist. (ft) 5* Above Panel Water Pipe non-Cr it Serv-Hdr.. Positive Anchorage (yes/no) Yes

At t nt 17 Non-Category I Equipment Category I Non-Category I Off set Di st. Positive Anchorage Equipment Type & ID II Equipment Type (ft} (yes/no} VOID - Thi~ Attachment Numbe '" Was Not Used.

Category I Non-Category I Equipment Type & ID# Equipment Type Fire Pump Cable Tray Battery Tray D36 511 x 1211 w Fire Pump Light Fixt4re Battery 038 Ai:. tac ment *J 8 Non-Category I Equipment Off set Dist. (ft) I 8 1 + Overhead 12 1 Overhead Positive Anchorage {yes/no) Yes Yes (chain)

.ment 19. Non-Category I Equipment I I Category I Non-Category I Off set Dist. Positive Anchorage Equipment Type & ID H Equipment Type {ft) (yes/no) Cont ro I Rm Desk Bi-10 1 No Panels COi, C02, C03 Control Rm Chairs 81 -10 1 No Panels (Ro 11 ers) COl, C02, C03 Control Rm Panels Bookcase 8 1-10 1 No COl, C02, C03 (Rollers)

20 Non-Category I Equipment I Category I Non-Category I Off set Dist. Positive Anchorage Equipment Type & ID II Equipment Type (ft) (yes/no) Control Rm Panel Teletype 5' No co4, C06 11 Tools 5' No

ment 21 Non-Category I Equipment Category I Non-Category I Offset Dist. Positiye Anchorage Equipment Type & ID # Equipment Type (ft) (yes/no) Control Rm Panel Lights I' Up Yes C27 (Reactor Drive 3' Off set Cal lb. Cabinet)

~ategory I Non-Category I Equipment Type & ID # Equipment Type Control Rm Light Panel Noise Analyzer Control Rm Panel Teletype Noise Analyzer II Instrument Rack ment 22 Non-Category I Equipment Off set Dist. (ft) 4' Up Adjacent Adjacent Positive Anchorage. (yes/no) Yes No No (Ro 11 ers)

Category I Non-Category I Equipment Type & ID # Equipment Type Control Rm Panels Supply Cabinet C115 and SP-4 (Feed Water Purity) Control Rm Panels C115 and SP-4 Lights (Feed Water Purity) Control Rm Panels ~115 & SP-4 Vent Ducts (Feed Water Purity) A.ment 23 Non~Category I Equipment Off set Di st. (ft) 2' 2 1/2' Up 2 1/2' Up Positive Anchorage (yes/no) No Yes (Chain) Yes

Category I Non-Category I Equipment Type & ID # Equipment Type Control Rm Panels 2 Fi le Cabinets CI06 and C126 Control Rm Panels Lights C106 and C126 Control Rm Panels Ducts C106 and c126 Control Rm Panels C106 and C126 Teletype Adjacent to 106 A.ment 24 Non-Category I Equipment Off set Dist. (ft) 4-112 1 Off set 3* Up 3' Up Adjacent Positive Anchorage (yes/no) No Yes (Chain) Yes No

Category I Equipment Type & ID# Control Rm Panels C51 and C302 Non-Category I Equipment Type Fi le Cabinet A.ment 25 Non-Category I Equipment Offset Dist. (ft) 2' Positive Anchorage (yes/no) No

At nt 26 Non-Category I Equipment Category I Non-Category I Off set Di st. Pos*itive Anchorage Equipment Type & ID # Equipment Type (ft) (yes/no) Tunnel Lights 2* Off Yes Cableway 1

Up

Category I Non-Category I. Equipment Type & I D II Equ.i pment Type Sample Stations Gas Bottle Cl 01, Cl06 2* TC! 11 I s** d ia. 'At tac ment 27 Non-Category I Equipment Off set Dist. (ft) 31 Positive Anchorage (yes/no) Yes (Chain *to Wa 11)

APPENDIX B Equipment Weight Study

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APPENDIX ( Anchor Bolt and Base Plate Criteria
Revision 0 CONSUMERS POWER COMPANY PALISADES NUCLEAR PLANT CIVIL/STRUCTURAL GROUP DESIGN CRITERIA FOR EV~;J..,rJAT!Oi~ OF EXPANSION ANCHORS AND BASE PI.ATES FOR SEISMIC SAFETY SYSTEM PIPE SUP! mt:.*s Bechtel Job 12447-033 {\\! ~ ~*'"' l ~ I,~. JI.ii~*- ~,, ~~,:-ap;;.; **~,j By ' ~_~...---...,..-~-..,....~---- (Nate §f>lanki) ... i*H"!<.::-.~~I By -~'j_,,~~ */u/eo (Malay J.:;asGupta) Revi~~wed By ~4~ * ~/& (Sur~nder K~pur) .l\\ppxr.veC: By
tid):f~-. I/? rff6
,C.A. ~ Project Engineer)
1.

2.

3.

4.
A B c Criteria for Evaluation of Expansion Anchors Revision 0 PALISADES NUCLEAR PLANT CIVIL/STRUCTURAL GROUP DESIGN CRITERIA FOR EVALUATION OF EXPANSION ANCHORS AND BASE PLATES FOR SEISMIC SAFETY SYSTEM PIPE SUPPORTS CONTENTS SCOPE CODES, STANDARDS, AND REFERENCES ALLOWABLE STRESSES DESIGN OF EXPANSION ANCHORS AND BASE PLATES ATTACHMENTS Responsibility of Originator in Performing Calculations for Base Plates and Expansion Anchors Responsibility of Checker in Performing Checking of Calculations for Base Plates and Expansion Anchors Sample Calculation Package ii
Criteria for Evaluation of Expansion Anchors Revision 0 PALISADES NUCLEAR PLAN~
1.
SCOPE CIVIL/STRUC~URAL GROUP DESIGN CRI'l'ERIA FOR EVALUA'l'ION OF EXPAi1SIOr*l AIJCHORS AHD BASE PLATES FOR SEISMIC SAFETY SYSTEM PIPE SUPPORTS Bechtel Job 12447-033 This document provides guidelines for design calculations for evaluating expansion anchors and base plates for seismic safety system pipe supports in fulfilling the requirements of U.S. NRC IE Bullet1n 79-02 and its revisions.
2.

CODES, STAIJDA~DS, AilD REFEREHCES A.
U.S. NRC Bulletins, Rev O; Supplement 1, Revisions 1 and 2 B. Palisades :Juclear Plant, FSAR, Volume III, Appendix A C. G~idelines for Implementation of Tests, Inspections, and Design Calculations in Fulfilling Require101ents of NRC IE Bulletin 79-02, Dated March 8, 1979 Prepared by: _Approved by: M. Elgaaly T.E. Johnson D. Anchor Bolt and Anchor Plate Analysis Programs: GRILL and BOLTS E. An Analysis of Pipe Support Base Plates and Expansion Anchor Bolts Using BSAP Program F. Utility/TES Owner's Group Surnr.iary Report, Generic Response to U. s. _l1RC IE Bulletin 79-02, Base Plate/Concrete E.xpansion Anchor Bolts, Technical Report 3501-2, prepared by ~eledyne En~ineering Services 1
Criteria for Evaluation of Expansion Anchors Revision 0 G. Technical Specification for Repair of Expansion Type Concrete Anchors, Base Plates, and Rebar Cutting Allowances for Seismic Safety System Pipe Supports, Specification 12447/033-C-92(0) H. Technical Specification for Inspection, Testing, and Acceptance of Expansion Type Concrete Anchors, Specification 12447/033-C-98(0) I. Manual of Steel Construction, AISC, Seventh Edition J. Anchor and Fastener Design Manual by Hilti K. Concrete Anchoring Handbook by Phillips Red Head L. Procedure for Locating and Resolving Daily Dis-crepancy Reports
3.
ALLOWABLE STRESSES A. EXPANSION ANCHORS
1)
Verify that the expansion anchors have the following minimum factors of safety: a) Stud type anchors (wedge or sleeve): 4 b) Shell type anchors (self-drilled or pre-drilled) : 5 c) The safety factor is between the bolt de~ign load and the bolt ultimate capacity determined from static load tests (e.g., anchor bolt manufacturers) which simulate the actual conditions of installation (i.e., type of concrete and its strength properties). d) The allowable load capacity for tension or shear for expansion anchors is listed in Table 1. Adjustments to tension and shear allowables for center-to-center spacing and concrete edge distances shall be made, if required as noted. e) For replacement of wedge type anchors, the capacities may be determined from the manufacturer's published ultimate loads using a safety factor of 4 (in lieu of values shown in Table l)
2
Criteria for Evaluation of Expansion Anchors Revision 0 TABLE 1 ALLOWABLE LOAD CAPACITIES FOR EXPANSION ANCHORS Minimum Allowable Expansion Minimum Minimum Distance Embedment Capacity Anchor C-to-C* from Center of for. Shear or Diameter Spacing Anchor to Edge of Wedge Tension (in) (in) Concrete (in) Anchors(in) (kips) 1/4 3 3 1-1/8 0.30 3/8 4 4 1-5/8 o.so 1/2 5 6 2-1/4 1.20 5/8 6-1/2 6 2-3/4 1.60 3/4 7-1/2 6 3-1/4 2.40 7/8 9 6 4 3.00 1 10 6 4-1/2 3.60 l-1/4 12-1/2 6 5-1/2 s.oo
Center-to-center NOTES:
l.
The values given are for concrete with a compressive strength of 3,000 psi or gr~ater.
2.
The minimum center-to-center spacing or edge distance as specified must be maintained to use the allowable values given.
3.
Spacing and edge distances may be reduced to 50% with an equal reduction in capacity. Linear interpolation for intermediate spacing and edge distances shall be used. 3 in
a.
BASE PLATE Criteria for Evaluation of Expansion Anchors Revision 0 l)
Allowable stresses on base plates shall be as follows: a) Normal Condition - Allowable stresses in accordance with AISC Manual of Steel Construction for Bending, Tension, and Shear, as applicable b) Accident Condition - Allowable stresses for following severe conditions: 1.250 + l.OR + l.25E = ~ x Y 1.250 + l.25H + L2S:i: = ,p x Y (Use 0.90 where dead load subtracts from critical stress in the above two equations.) l.OD + l.OR + l.OE' = o x Y l.OD + l.OH + l.OE' = ~ x Y where D = dead load of structure und equipment plus any other per~anent load con-tributin~ stress. In additionr a portion of "live load" is added when such load is expected to be present when the plant is operating. An allowance is also cade for future permanent loads. R = force or pressure on the structure due to.a ruptur~ of any one pipe H = force on the structure due to ther.n*al expansion of pipes under operating conditions E = design se isrnic load for Category I structures E'
maximum seismic load for Category I structures o = yield capacity reduction factor (0.9 for fabricated structural steel)
Y = required yield strength of the structure 4
/ ~r1tcria for Evaluation of Expansion Anchors Revision 0
2)
Seisnic forces are applied simultaneously in the vertical and any horizontal direction. The vertical component of acceleration at any level is taken as two-thirds of the horizontal ground acceleration.
4.
DESIGN OF EXPAUSION ANCHORS AHD BASE PLATES A. EXPA~~S ION AHCHOR SUPPOR'l'S l) Uniaxial Tension a) The effect of prying action in a base plate to a concrete connection using expansion anchor bolts is considerably less than the same phenomenon in steel-to-steel connections, mainly because of the expansion anchors having much lower stiffness. If the bending stresses in the base plate are within the allowables, the plate is then thick enough for the prying action to be negligible. Flexibility of the base plate, however,* shall be considered in distributin3 the load among the bolts as follows: ':'Y.10-bolt connection Four-bolt connection Six-bolt connection Eight-bolt connection All other connections
2)
Tension and Shear Tension/Bolt Shear/Bolt One-half One-half One-fourth One-fourth Use BOLTS and GRILL programs, and use maximum value from output. Use uOLTS and GRILL prograns, and use maxi~un value from output. Use BSAP progran (Reference 2E). a) All expansion anchors in new designs subjected to both shear and tension must satisfy a linear interaction as follows: + s 5all 5 < 1.0
where T and S are the applied tension and shear load values, and Tall and Sall are the allowable tension and shear values, respectively. b) When evaluating existing expansion anchors loaded both in shear and.tension, the following formula may be used in lieu of the linear interaction: 5 5 (T:11) 3 + (s:ll) 3 < 1.0 NOTE: Where such calculated a1lowable combinations of shear and tension exceeds the test results re-ported in Teledyne Engineering Services, Generic Response to U.S. NRC IE Bulletin 79-02, the test result curve shall be taken as an upper bound (see Reference 2F).
3)
Supports with Bending a) For two-and four-bolt connections, the tension in the expansion anchor bolt for support having bending moment can be de-termined as follows: M T = c where* T = applied tension in the bolt M = applied moment for support C
distance from the centerline of the tension bolts to the compression edge of the attachment (see Figure 1)
FIGURE 1 M 6
Criteria for Evaluation of Expansion Anchors Revision 0 b) For six-and eight-bolt connections, use the GRILL and BOLTS programs on the terminal and use the maximum value obtain~d from these outputs. c) For all other connections, use the BSAP program on the terminal as detailed in Reference 2E. B. BASE PLATES
1)
For a base plate design, review the bolt hole sizes and the edge distance from the.edge of the hole to the edge of the plate as required by Specification 12447/033-C-92(0). FIGURE 2 Pt. ATE T HI C.K ~ E '5 s ~ t -0 --+-- p{~TE.
2)
For checking plate bending stress other than doubly symmetrical attachments, use the following approach. a) For two-bolt connections, the following applies: M = T x d where T = applied tension value as determined earlier for the expansion bolt d = distance from the centerline of tension bolta to the centerline of the base plate (maximum dimension) M = bending moment at the centerline of the base plate 7
Criteria for Evaluation of Expansion Anchors Revision 0 Then determine the bending stress in the base plate as follows: where M f b = s fb = bendi~g stress in t~e base plate s = section nodulus at section taken (3t 2/6) B = width of plate t = thickness of plate Fb = allowable bending stress b) For four-bolt connections, the fol lowing applies: M = 2 x T x d fb < Fb c) For six-and eight-bolt connections, the following applies. o Use the GRILL program on t!1e ter;ninal to determine bolt loads, and the in-teraction values for shear, tension, and plate bending stresses. o Use the BOLTS program on the ter~inal to determine bolt loads and the in-teraction values for shear and tension. o Use the maxi~un value of bolt loads obtained from either the GRILL or BOLTS program as an applied load. d) For all other cases, refer to the.BSAP program as detailed in Reference 2E. a
Lr1ceLld Lu~ LVa~ud~lun of Expansion Anchors Revision 0
3)
Where the attachment is doubly symmetrical and is continuously welded to the base plate, plate bending stresses may be calculated at Section 1-1 or Section 2-2 (at 45 degrees) that corresponds to the edges and corners of the attachment (see Figure 2). a) For two-bolt connections, the following applies: Plate bending stress for JT (B-b) Section 1-1, fb = Bt2 b) For four-bolt connections, the following applies: Plate bending stress for 6T (B-b) Section 1-1, fb = Bt2 Plate bending stress for Section 2-2, fb = 3T t2
4)
For pipe supports with four-bolt connections, if the bolt loads are required to be calcu-lated because of one bolt missing on that connection, either a BSAP analysis may be performed, or the following approach may be utilized. FIGURE 3 1 y .+'
2.
x lb I ~ 3 irl. 1 0- ~ 1 MISSIN~ S=-i 9
Criteria for Evaluation of Expansion Anchors Revision 0 a) Assume that bolt 3 is missing from the plate (as shown in Figure 3) and that the support has applied tension P. Then the load in the bolts will be as follows: Bolt Load on Bolt
1 2
3 4 0 ~2 P/2 b) If the applied moment is about the X axis, assuming a concrete reaction at bolt line 1-2, the following applies: Mx Load. in bolt 4 = S-Load in other bolts = 0 c) If the applied moment is about the Y axis, assuming a concrete reaction at bolt line 1-4, the following applies: Load in bolt 2 = t1Y a Load in other bolts = 0 d) If the appli~d moment is about the X and Y axes, assuming a concrete reac~ion at bolt 1, the following applies: Load in bolt 2 = My/a Load in Bolt 4 = Mx/b Load in other bolts = O 10
ATTACHMENT A DESIGN CRITERIA FOR EVALUATION OF EXPANSION ANCHORS ORIGINATOR'S RESPONSIBILITY (l} Receive the stress package. (2) Review the stress package for inconsistencies as follows: (a) All loads available for all node points (b) Consistency between walkdown and as-built sketches (3) Locate DOR for the above stress package. (4} Perform analysis (BOLTS - GRILL programs, if required). (Fill in all of the blanks on the calculation sheet completely.) (Refer to EDP 4.37 for design calculation procedures.) (5) Develop modification, if required. (6} Develop response to DDRs * (7) Fill cover sheets for each hanger and prepare calculation index. (8) Fill out the "Memo to Issue" and "Summary of Design Status" forms. (9}* Return the design calculation package to the group leader for checking.*. (10) Receive the ~pproved design calculation package from the group leader. (11) Xerox the complete design calculation package after receiving from the group leader. (12) Distribute the following: (a) Xerox package of calculations with the *Memo to Issue* form (b) DDR originals with the memorandum to OE and a copy of the DDR and memorandum to the mechanical group (c) Memor~ndum to assigned distribution (13) File the original design calculation, DDR copy with the memorandum, and *Memo.to Issue" copy in the binder.
ATTACHMENT B DESIGN CRITERIA FOR EVALUATION OF EXPANSION ANCHORS CHECKER'S RESPONSIBILITY (l) Verify completeness of the design calculation package received from the group leader. (2) Check the design calculation package. (3) Sign all design calculation sheets and date. (4) Sign the calculation cover sheet and date.* (5) Write the date on the calculation index in the check date column. (6) Check the DDR response; sign and date. (7) Check the *Memo to Issue" and "Summary of Design Status" for its veracity. (8) Return the package to the group leader for approval
ATTACHMENT C TO DESIGN CRITERIA FOR EVALUATION OF EXPANSION ANCHORS AND BASE PLATES SAMPLE CALCULATIONS
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Instnllation per Detail INg. Yc9 _ Ho X 1_T.:;:_*v.Llo'--'e-.. ---....~ If no, As-lluilt Dvc. Complete Yes ~ No_ Wall IX. I Evidence of Concrete Crocking or Failure Floor If yes, sho\\I on sketch Yes_ No~
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APPENDIX D Anchor Bolt Bending Criteria
SUBJECT CALC. NO. SHEET NO I BY fUvtc. DATE
URS/BLUME 130 Jessie St~eet (at New Montgomery)
San Francisco, California 94105 SHEET NQ J NO. \\ .XJB YA \\;sAdt:s t Slv; f?tY!C"-li Auc_h-,rA0y-BY *12.11-AG DATE 6/z/ft? UENT GPCo suruEc'iProCQ~J1u ]; .... A 0~
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URS/BLUME SHEET NO 3-- F--'-'-::..:____.::...:::..:::.---=--<-~.:.......L-..!.-=--=>..:,i-~~J...L.!-...!....-!!.--"-'--'-..l..>.:L-L~:!!__- Si 1eul(__;. DATE q__, Js:u SUBJECT CHK 0D..(;./ 6 DATE _j-;3-J' tJ

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APPENDIX E Remedial Design Drawings
ITEM I QUAN. I DESCRIPTION ELECTRICAL EQUIPMENT ANCHORAGE SEISMIC QUALIFICATION PALISADES NUCLEAR POWER PLANT REV DATE BY CH K APRV
TITLE SHEET CONSUMERS POWER COMPANY JACKSON, MICHIGAN INITIAL RELEASE DESCRIPTION URS/JOHN A. BLUME & ASSOCIATES SAN FRANCISCO, CA.
JOB NO. DWG NO. SHT REV 8013 A 1/1 0
( ITEM I QUAN. I DESCRIPTION ELECTRICAL EQUIPMENT ANCHORAGE SEISMIC QUALIFICATION PALISADES NUCLEAR POWER PLANT CONSUMERS POWER COMPANY Title Sheet Drawing Index General Notes Subject JACKSON, MICHIGAN DRAWING INDEX Pressurizer Heater Transformer Xl5 and Xl6 Load Center Busses 15 and 16 Station Power Transformer Xl2 Load Centers 811 and 812 Diesel Fire Pump Batteries D 36 and D 38 Fire Pump Controllers C37 and 137 Motor Control Centers 7 and 8 Static Exciter Control Panel Control Room Noise *Analyzer Fuel Qi l Oay Tank T 25A and T 258 Conitel 2100 Computer C 09 Station Power Transformer Xll Motor Control Centers l and 2 Battery Chargers 1, 2, 3 & 4 Inverters l, 2, 3 & 4 Preferred AC Susses l, 2, 3, & 4 Drawing A B c l 2 3 4 5 6 7 8 9 10 11 12 13 14 No. Sheets 1 2 3 2 3 2 4 1 1 3 l 1 l l 2 l 2 4 b/zo/8i> f,r.1(. t?rhJ ~ Issue 10, 11, 13, 14, 17' 18, 19, 20, 21 ' 3 '1/2'1/aJRf.)(. ~ /:J(\\ Issue 12 2 l///(j&.. /e,J14C ~ j.}/\\ Issue 4 and 9 l t//;J/ ~a /2.).),(.. /...k,.J) fffl<::. Revise B, C, 2, and 6, Issue-7 and 8 O o/-p./;O /t.J;(C.-.//7zJ n.-Y(h INITIAL RELEASE REV DATE BY CHK APRV DESCRIPTION Rev 0 7* 1 0 l 0 0 0 l 0 0 0 li l' 0 0 l and 22 PALISADES NUCLEAR POWER PLANT SEISMIC ANCHORAGE FOR SAFETY-RELATED ELECTRICAL EQUIPMENT URS/JOHN A. BLUME & ASSOCIATES SAN FRANCISCO, CA. DRAWING INDEX JOB NO. DWG NO. SHT REV 8013 B 1/2 T
r** ~l!_EM- "J aLJAN. }------ --=-~--~~-=-----_-_..,-_--D~E~S_-c_-R_l-P_ -T_t=O=N_*-===~--==--=~~~--~-::_'* -_-_-_----; DRAWING INDEX (Continued) Subject Drawing No. Sheets Rev DC Susses and Distribution tenter 2400 V Switchgear l C and l D Hydrogen Recombiner Power Panels C 121 and 124 Station Battery Supports Control Room Noise Analyzer (next to C-06) Deleted Control Room Panel C 125 Rod Drive Control Logic and Contactor Panel Control Panels C33 and C40 Rad. Waste Sample Station ClOl Deleted Control Panel C 07 Bypass Reyulator, lnstrument AC Panel Y01, Transformers X21 and X22 Panel C04 and C06 - Control Room Panel C 51 Control Room Pah~ls C207 and Cll5 Deleted Control Panel Cll, Cl2, and Cl3 Diesel Generator Skid TCAC2 Hydrogen Recombiner Control Panel Cl22 and Cl23 \\ Edit Drawing Titles 15 16 17 18 19 20 21 22* 23 24 25 26 27 28
29.
30 31 32 33 34 35 Issue Dwgs 15, 16, 23 through 30, Issue Dwgs 14, 17, rev. 1 3 1 1 1 - 1 1 l 0 l i 1 0 1 l 1 1 1 0 1 1 5 l l 3 2 1 l 0 0 0 0 0 0 0 0 0 32 through 35, all rev 0. Issue Drawing 10, Rev. l REV DATE BY CHK APRV PALISADES NUCLEAR POWER PLANT SEISMIC ANCHORAGE FOR SAFETY-RELATED ELECTRICAL EQUIPMENT DRAWING INDEX DESCRIPTION URS/JOHN A. BLUME & ASSOCIATES SAN-FRANCISCO, CA. JOB NO. 8013 DWGNO. B SHT 2/2 REV 7
ITEM I QUAN. I DESCRIPTION GENERAL NOTES A. General
1.
The Contractor shall verify all conditions and dimensions of existing con-struction and shall notify the Engineer of any variations before proceeding with new work.
2.
Shop fabrication and erection details shall be submitted to the Engineer for approval before fabrication. B. Design Criteria
1.
Design is in accordance with the following:
a.
Bechtel report 11Palisades Plant Reactor Building, *seismic Analysis, 11 June 1969.
b.
Bechtel report 11Seismic Design Requirements for Equipment Located in the Auxiliary Building, 11 Specification No. 10512/034-C-175.07, Attachment ,2, Rev. 0.
c.
Bechtel report 11 Design Criteria for Evaluation of Expansion Anchors and Base Plates for Seismic Safety System Pipe Supports, 11 12447-033-DC-l, Rev. 0.
d.
Plant FSAR, Appendix A.
e.
URS/Blume Methods and Criteria Document. C. Structural St~el
1.
Structural steel shall conform to ASTM A-36.
2.
Galvanized cold formed channels, pressed fittings, and special toothed nuts shall be as manufactured by Uni strut Corp. or approved equal. 3.. Fabrication and erection shall be in accordance with the latest AISC Specification for the Design, Fabrication, and Erection of Structural Steel for Buildings and the AISC Code of Standard Practice for Steel Buildings and Bridges. -1 11/11/t, o Mvl f3'//.(.. A'R::> Rev.. Notes A.2. C.5, C.6. C.7, E.1.C. E.2. F.La., G n %8.'~~o HSW RMC RPG INITIAL RELEASE REV DATE BY CHK APRV DESCRIPTION PALISADES NUCLEAR POWER PLANT SEISMIC ANCHORAGE FOR SAFETY-RELATED URS/JOHN A BLUME & ASSOCIATES i--E=L=E~CT~R~IC~A=L~E~:o~u~IP~M~E~NT:..._~~~~~~~~~-1-~~~-SA_N.,.--F_RA~N~C~IS~CO~,C=A-=---~_J GENERAL NOTES JOB NO. DWG NO. SHT REV 8013 c 1/3 1
ITEM I QUAN. I. DESCRIPTION GENERAL NOTES (continued)
4.
Bolt sizes shall be as noted on the drawings, conforming to ASTM A307 unless otherwise noted (U.O.N.). Nuts and lock washers shall be supplied with bolts.
5.
Welding shall be performed by qualified welders and shall conform to Newkirk Electric Welding Procedures, NEAI-Dl!l-1 and NEAI Dl.1-2, latest revision. Electrodes shall be E70 1 ow hydrogen.
6.
Self-drilling or self-trapping screws shall be Fabco, Teks, or approved equal.
7.
All structural steel shall be painted in accordance with the following: Newkirk Electric Hark Instruction rfo. 14740-01, Procedure for 11 Installation of Seismically Qualified Anchors for Class lE Electrical Equipment, 11 issued March 25, 1980. D. Concrete
1.
Concrete shall conform to ASTM C-94 for Ready-Mixed Concrete and shall have a minimum compressive strength of 3000 psi at 28 days.
2.
Reinforcing steel shall conform to ASTM A615, Grade 40.
3. Existing concrete surfaces to receive new concrete shall be thoroughly cleaned, roughened, and coated with a concrete bonding agent before new concrete is placed.

4.
Concrete bonding agent -shall be Concresive, Weld-Crete, or approved equal. E. Concrete Expansion Anchors
1.
Type
a.
The following stud-type anchors may be used: HILTI KHIK-BOLT, Phillips Red Head Wedge Anchors, or approved equal, conforming to the requirements of Specification 12447-033-C-93(Q), Rev. 1 11Technical Specifications for Purchasing of Expansion Type Concrete Anchors for the Consumers Power Company Palisades Nuclear Power Plant, South Haven, Michigan. 11
b.
Anchor size shall be as shown on the drawings.
REV I DATE J BY I CHK I APRV 1 DESCRIPTION PALISADES NUCLEAR POWER PLANT SEISMIC ANCHORAGE FOR SAFETY-RELATED URS/JOHN A. BLUME & ASSOCIATES r-EL_E_CT_R_I_CA_L.;.._E~QU_I_P_ME_~_IT~----------~--------+-~~~s_A~N_F_RA N_c_1s_co__,._c_A_._,..~--1 JOB NO. DWG NO. SHT REV GEtlERAL NOTES 8013 c 2/3 1
ITEM I QUAN. I DESCRIPTION GENERAL NOTES (continued)
c.
Unless otherwise noted, minimum ernbedment of anchors shall be: Anchor Dia. (in. ) Min. Embed. (in. ) 3/8 1-5/8 1/2 2-1/4 5/8 2-3/4 3/4 3-1/4 7/8 4 l 4-1/2 1-1/4 5-1/2
2.
Installation of anchors shall be in accordance with the aforementioned Newkirk Electric Work Instruction No. 14740-01. F. Nonshrink Dry Pack or Grout
1.
The following shall be used in accordance with the manufacturer's written instructions. For patching, use a nonstaining dry pack.
a.
Five Star Grout, by U.S. Grout Corp. G. Safety precautions, coordination of work \\'iith the Owner, testing and inspection of anchors, the documentation of the testing and inspection and all other work related to the installation of seismically qualified anchors shall be as specified in the aforementioned Newkirk Electric Work Instruction No. 14740-01. REV I DATE I BY I CHK I APRV I PALISADES NUCLEAR POWER PLANT SEISMIC ANCHORAGE FOR SAFETY-RELATED ELECTRICAL EQUlPMENT GENERAL NOTES DESCRIPTION URS/JOHN A. BLUME & ASSOCIATES SAN FRANCISCO, CA. JOB NO. DWG NO. SHT REV 8013 c 3/3 1
ITEM QUAN. DESCRIPTION I 2 ~U~NilTY 1..1sr~~ IS t=O~ ONG il<ANSl=OR.ME{( ON<."(, f:QU/P,.J'~/t:J -- '-OCIJi/ON MAY ae VARttSO te" TO SUI r t=u:r..o CONt:JlilON ~-;-*--~--$,____.. ~ P'-A N (j) /V~W FC.OOR. !.INS SECTION A*A (TY/:>. CtJR.e) J"CAt..l!I f 11e. '1=1'-0 0 3*28*8a (l.~C. REV DATE BY CH K APRV /OAll.!'AOes NUC(.~A~ por-,*et~ Pt.ANT CONTA.INM$HT BU!?..OING ---=-* - f'R.c.J'J'(.J R.I ~t$R l-lt!A Te~ TR.ANS~OR.M~R X 15 '¢XIO, DESCRIPTION URS/JOHN A. BLUME & ASSOCIATES SAN FRANCISCO, CA. JOB NO. DWG NO. SHT REV 8 0 I 3 I l/e 0
ITEM QUAN. DESCRIPTION F-Ul.'- ~ P~N'irR.ATION ' GROUT !.S VE(. I= OR t= (,J(,, (. F!P..NS. s'?." 3" +s* c--, sec110N 15-IS ( -ryP, ANCffOte) ..rcA'-e; 1'e:1'-o" REV DATE BY CHK APRV /CA,l.SA(;)~J' N(..IC(..eAte POW~.'~,QJ-ANr
CO'NiAINMeNT 8U/..l..lJltyG.
,cRe.1'.StJRl2eR. H~AreR TRAN.J't=ORM!ite X/5 'XIG ?. e ~ l r:J i t ~ f:J t\\); I view c-c. DESCRIPTION URS/JOHN A. BLUME & ASSOCIATES . SAN FRANCISCO, CA. JOB NO. so rs DWG NO. SHT REV I 2/t. 0 /
r--~~~~~~~~~~~~~~~~-~~~~--~~----- ITEM QUAN. DESCRIPTION I ~ Q() ..., I ~
- II co -* -
@J c,,,... - ~ ~ 10 58 "¢ coNc. tJJ:P, ANCHORS, e.34 M111, 5~1~e1::J, 1 11 ~ -rYP. ~t..Te-te.NAre ,$0<. 'T ~OCATION . AS /?. e~' t:J l:J Y. 1=1er..o CONOIT/ON t:J&i, I L A Q lt UJJ OQ'b ~ ~ --r--'lI.-ii-1'_J ce~ ~~~ g~~ e)<tST, 1e, 11~ Hoe.es IN ~QUIP. /:JASS.* Pl..UG We'9.0 70 eM~SO(.)ef:J CHANNeC.. 1'R/ f. (. N~W H0<.5.S THRf.J CHANNEr.. * ~INTO CONC. FCH. 5'6 ~ ~x P, P..Jo t.rs ..J/.llM AS R~G1'0, --~7 E Cit ~ QJQJ c.," a@ t:Jt:iAI'--* *1* J" CA (. e : I 1e 11 ; I '- 0,, u"> fl) . "'0 ~o.. 1~ 1~ ~ 's ;vew sx.P~ Jaae.rs 5 ~A.!'Ir.JS VA~l~S iYPICAt.. Pt..AN J"'cAc..e ~ 1e 11:.1 1-o" TOP OF-Ct.JR~ 11* ex1.sr. c/./ANNe!.. CUR.P.> R~JNl=.- .. :~ (/)_ 23+u MIN* ~M l?J ~ t:)M$N T S&CTION A-,<.\\ J"CA c. e : /1e 11= 1 1*0" I I 4*11*3al /h.IL
A(.)~ I.11-/T. 'Z tJet..cTC:t:J (4), SHT. =
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LOA t:) c. e N Te re.
/QLJ..SS~S 15 fl /G DESCRIPTION URS/JOHN A. BLUME & ASSOCIATES SAN FRANCISCO, CA. JOB NO. I DWG NO. I SHT I REV 8 o I~ 2 1/3 I
ITEM QUAN. DESCRIPTION P/000 UHl.Srl~Ui CNA.NN~t. >< 14 '*I t J VERlt=Y 5 /0' (j)UNISTl?.UT PIOOO ~~ACING ~ 11:=======~~~~====~==;;;¢:+=====~$~~-----=-+ ~-- ~' L:1=====:3:=====~~=¢::=====f.::;t===~~=============*=~~--~:~ 'o oO o* I + L.3 x 3J'.3& 5 II G Z* a if; GJ<P, Sot.TS ..!'t:.C710N IQ.. ~ St:CTION C *C .SCAl.e: !'-:: 1'.0 11 SCAt.e: 112' 1
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CHK APRV P.At..ISA o~s NUCC.l!iA~,oowe.te' Pt..A/'.,'i
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DESCRIPTION .. I ~~
r
'9* -~-* 1:- U.RS/JOHN A. BLUME & ASSOCIATES SAN FRANCISCO, CA. . JOB NO. DWG NO. SHT REV S 0/ 3 . 2 ~/3 I
ITEM QUAN. ) lJ <:: 8 ,0 -~ 0 ~ c DESCRIPTION r ~t_f:) P/000 ~~Ace: -ro P/000 TRUT@ eA.f'OIN/ Or CON/ACT q '- q,, © /Q/000..f rRUT ~ coNr..:11.vM~ti I" I I t:(.., 5'iO -o II. I r;7' \\. ~ view (..OOl<INfS NORTH ..r CA C. S. ~.S&": J '. O" t r-REV DATE BY CHK APRV DESCRIPTION . PA(.l..S'Al;)~.S" lvuct..e~R POWE!r.,c<.AN*r URS/JOHN A. BLUME &ASSOCIATES i---~~-c_o_N__,r._~_l_N._11"-_f_~_N_T~~~u_1~_~~'N~G_*._*_.* ________ s_A_N_F_RA_N_c_1s_co--.-,_cA ____ ______. l.0'4 /:) CeN Te~. ~UJ".S~.! JOB NO. DWGNO. SHT REV I 6 ~ I G 8 O 1.3
2.
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ITEM QUAN. DESCRIPTION I 10 wet.r:Jeo ANCHOte P/?.0.kf ~4 " P(.AT~ 2 10 14 11 ¢ CONC. 5XP. ANCHOR:. I 7 11 MIN* SMl?>ea,
3
/'(. 12,, ¢ CONC, 5XP, ANCHOlt, e 14 MIN, SM~&(.),* + 2 I~ If cP 1<e1NI=. Si5~'- NOTS: QuA.N rrrY (.1sr~c IS l=O IC ON~ i~AN.S /:'OltMSIC CN<.Y, eevu1 p,.s~10 ~ f'D" I~ 3 I ~a " 1 1
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POW.<!~ TR.ANS,t:.Ol(M~R X/2 JOB NO.
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ITEM QUAN. DESCRIPTION I

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CONC, WA~

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AUXIC.IAl(Y' ~(.J/:.t:)/NG URS/JOHN A. BLUME & ASSOCIATES SAN FRANCISCO, CA.

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APPENDIX F Guidelines for Non-Category I Items
GUIDELINES FOR NON-CATEGORY I ITEMS, PALISADES NUCLEAR POWER PLANT Scope This document gives guidelines for the placement and anchorage of non-Category I items in relation to safety-related equipment at the Palisades Nuclear Power Plant. The guidelines consist of recommended minimum clearance and other de-tails intended to mitigate the interference of non-Category I items with safety-related equipment in the event of any of the earthquakes that are postulated for the site (including the SSE). These recommendations are based on observations and records of the damage and movement of building contents during past earthquakes ranging in Richter magnitude from about 5.2 to 8.4. Guidelines (a) Except for items on rollers, items that cannot topple [see k), below] can move -during earthquakes only by sliding. Sliding depends upon the coefficient of friction between contact surfa~es and the horizontal and vertical accelera-tions of the seismic motion. Photographs taken after very strong earthquakes (see references) show only very limited sliding. (Certain exceptions have been noted, but these cases involve very high accelerations and/or very low coefficients of friction.) Recommendation: Items that cannot topple shall be no closer to safety-related equipment than 4 ft in any horizontal direction. This distance shall be mea-sured from the nearest faces~ with all drawers and doors in the fully open position. (b) Two hazards are.presented by items that can topple [see (c), below]: the first is the toppling itself, and the second is sliding after toppling. Sliding after toppling is somewhat more critical than the case discussed above because bouncing of the toppled item tends to minimize the coefficient of friction for a short period of time. Recommendation: Items that can topple shall be securely anchored to prevent overturning* or, if freestanding, shall be at a minimum distance equal to the 1 -
height of the item plus 5 ft from any safety-related item. This distance shall be measured as specified above. (c) Toppling or overturning depends on the aspect ratio (height to minimum width) of an item and the peak horizontal and vertical floor accelerations. Hence, the critical aspect ratio is different for different earthquakes, buildings, and elevations. Recommendation: The following critical aspect ratios may be used to determine toppling potential of unanchored items at the Palisades Nuclear Power Plant for a 0.2g SSE: Containment Building Auxiliary Building Elevation Critical H/B Elevation Critical H/B 590' 2.7 590' 2.7 606 1 and 607 1-6 11 2.7 598*1 2.0 622 1 and 625' 2.7 601 1
1. 7 649' 2.3 624 1

1. 7 640 1 1.3 649 1 1.3 These values include a factor of safety of 1-1/2, and linear interpolation may be used for elevations not shown.
The critical aspect ratios shown above are based on the assumption that the centers of gravity of items being considered are at mid-height: These values may be adjusted for top-heavy or bottom-heavy items. (d) It has been observed that items on wheels, such as chairs, carts, dollies, etc., do not roll great distances during earthquakes. Generally, the floor simply moves beneath them. However, due to the possibility that the wheels may not roll properly, the minimum distances and other criteria of (a), (b), and (c) above sha l 1. be fo 11 owed for i terns on whee 1 s. (e) Miscellaneous: All items shall be placed or stored in a manner that provides th~ greatest resistance to sliding and toppling. Ladders and equip-ment covers shall not be placed in such a manner as to create a potential 2 -
hazard to safety-related equipment. All equipment doors shall be secured to prevent slamming during an earthquake. No books, tools, or other loose items shall be placed on top of or above safety-related equipment. (Minimum horizontal offsets also apply to these items.) Bibliography American Society of Civil Engineers, Structural Division, Structural Design of Nuclear Plant Facilities, Vol. 1, New York, New York, 1975. Earthquake Engineering Research Institute, Managua, Nicaragua, Earthquake of December 23, 1972, EERI Conference Proceedings, Vols. 1 and 2, Berkeley, Ca 1 i fo rn i a, 1973. Leeds, D. J., ed., Reconnaissance Report, Imperial Covnty, California, Earth-quake, October 5, 1979, Earthquake Engineering Research Institute, Berkeley, California, 1980. Steinbrugge, K. V., E. E. Schader, H. C. Bigglestone, and C. A. Weers, San Fernando Earthquake, February 9, 1971, Pacific Fire Rating Bureau, San Francisco, California, 1971. U.S. Department of Commerce, San Fernando, California, Earthquake of Febru.a.ry 9, 1971, Vol. 1, National Oceanic and Atmospheric Administration, Washington, D. C., 1973. tJ.S. National Academy of Sciences, The Great Alaska Earthquake of 1964-- Engineering, \\./ash i ngton, D. C., 1973. URS/John A. Blume & Associates, Engineers, Earthquake Hazard Study of Four Existing Buildings, JABE-USGS-01, San Francisco, California, 1973. URS/John A. Blume & Associates, Engineers, File No. 8013, telephone communi-cations in May 1980 between P. I. Yanev (URS/Blume) and various representatives of Lawrence Livermore Laboratory and Intel Corporation regarding the February 1980 Liverm0re, California, earthquake. }}

ML18046A812

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