ML19270F779

Responds to 790226-28 Meeting Request for Addl Info Re Seismic Qualification Data on Electrical,Instrumentation & Mechanical Components

ML19270F779
Person / Time
Site:	Salem
Issue date:	03/23/1979
From:	Mittl R Public Service Enterprise Group
To:	Parr O Office of Nuclear Reactor Regulation
References
NUDOCS 7903270503
Download: ML19270F779 (35)

Text

{{#Wiki_filter:- q p ..J LE n %V Public Service Electnc and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201!430-7000 March 23, 1979 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Olan D. Parr Light Water Reactors Branch 3 Division of Project Management Gentlemen: RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 On February 26 - 28, 1979, a meeting was held at the Salem Nuclear Generating Station between Public Service and the NRC Seismic Qualification Review Team relating to the Seismic Qualification data for electrical, instrumentation and mechanical components. ) Public Service Electric and Gas Company hereby submits sixty (60) copies of additional seismic qualification information as identified during the meeting. Ver uly your, j jf R. L. Mittl General Manager - Licensing and Environment Engineering and Construction Attachment 7903270503 The Ener0y People OS 2001 (400M) 9 77 V. n. an

l ~ r SALEM NUCLEAR GENERATING STATION UNIT NO. 2 NRC SEISMIC QUALIFICATION REVIEW RESPONSES TO ADDITIONAL INFORMATION REQUESTS The NRC Seismic Qualification Review Team met with PSE&G personnel at the Salem site on February 26-28, 1979 to conduct a review of the seismic qualification data for electrical, instrumentation and mechani-cal components. The attached Table 1 lists the items reviewed and a summary of the results. The following information is in response to items requiring additional data as identified at the meeting: 1. Motor Control Centers a. Area of Concern: Provide additional justificatio. for acceptance of low frequency test results in the 5 to 10 HZ range in General Electric Test Report 70ICS100 dated 8/21/70.

Response

General Electric 's Test Report 70ICS100 was re-viewed by Southwest Research Institute for PSE&G. The results of this review summarized in their letter of June 7, 1971 (Attachment

1) did question the extrapolation of the test results for the 5 to 10 HZ range.

General Electric prepared a response to the Southwest Research comment via their letter of August 6, 1971 (Attachment 2). Based on this additional information provided by General Electric, Southwest Research accepted the results of General Electric Test Report 70ICS100 in their letter of 2/29/72 (Attachment 3). b. Area of Concern: Clarify the input accelerometer data used to monitor test input on General Electric Test Report 70ICS100.

Response

As stated in Test Report 70ICS100, the input accel-erometer used in this test was designated as #2 on figure 4-2 (Attachment h). Table 3 h of the report (Attachment 5) indi-cates the specific pages which provide the input data for this accelerometer (e.g. pages lA, 13A and 25A). These pages are included at attachments 6, 7 and 8 respectively. 2. 5KV Switchgear and Relays a. Area of Concern: Provide additional data regarding the .following 5KV Switchgear relays 12HFA51Ah2F 12IAC66B6A 12IAV7hA1A Include information on the test procedure, functional monitoring and suitable backup data to support manufacturer statements on the seismic capability of the relays.

. 2. SKV Switchgear and Relays (Cont'd) Restonse: General Electric has performed tests on the above relays and demonstrated their operability when subjected to 1.2 g's horizontal and 1.2 g's vertical. We have contacted the manufacturer to request the actual test data which r.upports this statement. The information will be forwarded to the NRC when received to resolve this matter prior to initial criticality. The plant may continue to proceed with coreload and opera-tions up to initial criticality until this matter is fully resolved. The manufacturer has tested the relays and only confirmatory data is the subject of this concern. Plant and public safety will not be compromised on the basis that no power operation is permitted, no radiation hazards exist with the unit in a suberitical state and a minimum of auxiliary systems are operational. Even if the relays should misoperate during a seismic event and auxiliary systems are lost for a period of time, plant safety can still be maintained. Moni-toring instrumentation will continue to operate and repairs / modifications can be made following the seismic disturbance to restore power to auxiliary systems. Restoration of power within a critical time period is not required with the unit suberitical as it would be during power operation because of decay heat, etc. There is no evidence to suggest that ex-tensive damage would occur during the seismic event which would not permit manual restoration of power. 3 600V Switchgear a. Area of Concern: Provide additional information regarding effect of resonances identified in ITE Test Report #R-8792.

Response

The r es onant conditions identified in the report occurred only on the sheet metal surfaces. ITE Test Report

1. R-8792 prepared by Applied Devices Corporation states that there were no appreciable resonant conditions of the structure frame itself.

(See attachments 9 & 10). Unlike the ITE unit tested there are no relays in any of the safety related 600V switchgear at Salen Generating Station, nor are any required to perform a safety function. Therefore, the high transmissibility of the sheet metal surfaces would nat affect the operation of the 600V switchgear during a seismic event. Based on the above evaluation, the test report was found to be acceptable.

. 4 28V and 125V Batteries a. Area of Concern: Update FSAR Table Q7.18-1, " Summary of Seismic Qualification For Safety-Related Equipment" to reference subsequent testing performed on C & D batteries which supports the functional operability of the batteries. ~

Response

Table Q7.18-1 will be updated to reference the additional testing performed on C & D batteries. A revised table will be submitted shortly. 5 28v and 125v Battery Chargers a. Area of Concern: Update FSAR table Q7.18-1, " Summary of Seismic Qualification For Safety-Related Equipment" to indi-cate that the test results for the 28 volt battery charger were acceptable. Response: Table Q7.18-1.will be updated to indicate the accepta-bility of the test results. A revised table will be submitted

shortly, b.

Area of Concern: Irdic at e the voltage and current values used for the 28 volt C & D battery charger during seismic testing.

Response

Batelle's report on the s eismic testing of the C&D 28 volt battery charger, dated 1/11/72, indicates that the charger was energized as follows: "The battery charger was powered by 240-volt, 3 phase, a-c electrical power, and the charger output was connected to a resistive load bank. The d-c output voltage and current were monitored continuously using both meters and a Brush Mark 260 recorder. The battery charger was set to deliver 28.5 volts and 120 amps." As in-dicated in section A above, the results were acceptable. c. Area of Concern: Indicate the voltage and current values used for the 125 volt Exide battery charger during seismic testing.

Response

Exide Power Systems Division Report, "EPSD Seismic Test Facility", Public Service designation, " Salem Electrical ' Division File / Item #10-2505" provides the following information on the battery charger testing. "The charger is electrically connected to both a nominal AC supply and a test battery. It is then operated at full load at float voltage by applying . resistive load." For Salem's charger this would be an input of 208 volts, 3 phase AC with a DC output of 250 amps at 130 volts.

-. - -. ~ -.. - h-6. Electrical Penetrations a. Area of Concern: Confirmation that the penetration area and containment cable trays and conduit hangers are designed to seis=ic Class I criteria.

Response

Cable trays and conduit hangers which are in seismic Class I structures have been designed and installed as seis=ic Class I. This includes the penetration area and containment. 7 WCAP 7817 - SSPS, NIS, Process Racks a. Area of Concern: Confirm that Sale: is part of the West-inghouse Seismic Requalificat ion Program and that the restric-tions/=odifications resulting from that progra= are not applicable to Sale =.

Response

The seismic requalification of Westinghouse supplied safety-related equipment to higher accelerations does net have an effect on Sale =, Sale = is considered a low seismic plant under the Westinghouse generic qualification program. There are no known modifications or restrictions on operation of Westinghouse safety equipment due to additional seismic testing. Table Q7.18-1 will be updated to include supple-mental qualification data. A revised Table will be submitted shortly. 8. Wyle Report h2kkl-1, Centrol Console a. Area of Concern: Provide a supporting statement regarding the operability of post accident recorders on the console.

Response

A portion of the Unit 2 Control Roc = Console was seismically tested by Wyle Laboratories which included post-accident recorders. The recorders were tested with the console and did not fall structurally. The console was installed on Unit 2 after the test and the indicators and recorders are working satisfactorily. 9 PSE&G Valves - Velan B1235h B 13MS a. Area of Concern: Submit SQRT forms on the valves reviewed during the meeting which have not already been submitted.

Response

The SQRT forms for the above noted valve are attached.

. 10. Service Water Pumps a. Area of Concern: Submit SQRT for=s for the Service Water Pumps based on the qualification data which was reviewed at the meeting.

Response

The SQRT forms for the Service Water Pumps are attached. 11. Diesel-Generators and Vital Annurtenances a. Area of Concern: Provide information regarding the func-tional operability of the diesel-generator differential protection relay 12CFD22A1A during the seismic test of the generator control panel (Wyle Report h2551-1).

Response

During the seismic test of the generator contrcl panel, a number of relays were monitored for operability. The diesel-generator differential protection relay 12CFD22A1A is in the circuit for the diesel unit trip relay (DUTR). Refer to attachement 11 for a portion of the circuitry. The DUTR ciaruS was energized and monitored during the seismic test. Unacceptable operation of the CFD relay would have tripped the DUTR. The DUTR did not trip during the test which signifies that the input relays to the DUTR did not misoperate. Pre-operational and post-operational testing of the DUTR verified its operability. The acceptable opera-tion of the DUTR provides acceptance of the diesel-generator differential protection relay. b. Area of Concern: Provide information on the functional operability of the diesel-generator appurtenances such as the governor when subjected to a seismic disturbance.

Response

ALCO has performed an analysis of the diesel-generators to prove their operability during a seismic event. We have contacted the manufacturer to request supplementary data on the diesel-generators. The information will be for-varded to the NRC when received. Another approach that PSE&G may take is to perform a startup test of the diesel-generators with accelerometers mounted on vital appurtenances = to determine that operational stresses exceed those induced by a seismic disturbance. The information to resolve this item will be submitted prior to initial criticality. The plant may continue to proceed with coreload and operations up to initial criticality until this matter is fully resolved. Plant and public safety will not be compromised on the basis that no power operation is permitted, no radiation hazards = exist with the unit in a suberitical state and a minimum of auxiliary systems are operational. Even if the diesels fail

, 11. Eiesel-Generators and Vital Anpurtenances (Cont'd) b. Response (Cont'd) to operate during a seismic event causing power loss to ~ auxiliary systems, plant safety can still be maintained. Monitoring instrumentation will continue to operate and the diesels restarted following the seismic disturbance to re-store power to auxiliary systems. Restoration of power within a critical time period is not required with the unit suberitical as it would be during power operation because of decay heat, etc. The seismic analysis of the diesel-generators by the manufacturer demonstrated that there are not any unacceptable stress levels. There is no evi-dence to suggest that extensive damage would occur during the seismic event which would not permit restart of the diesels if required.

i TABLE 1 SALEM NUCLEAR GENERATING STATION UNIT NO. 2 NRC SEISMIC QUALIFICATION REVIEW

SUMMARY

Review Item Test Inspect / Data Functional O p e r a b i n _t y Motor Control Centers Response Item 1 Accepted-Control Room Recorder Panels Accepted Accepted SKV Switchgear Accepted Response Item 2 600V Switchgear Response Item 3 Accepted Battery Racks Accepted Accepted 28V and 125V Batteries Accepted Response Item 4 28V and 125V Battery Charger Accepted Response Item 5 Electrical Penetrations Accepted Accepted

• Vital Instrument Bus and Inverters Accepted Accepted WCAP 7817 - SSPS, Process Racks, NIS Accepted Accepted'"

Battele Report of 4/27/73 - Instr. Panel & Misc. Accepted Accepted Wyle Labs Report 42897 - Misc. Transmitters Accepted Accepted Wyle Labs Report 42441 - Control Console Accepted Response Item 8 Wyle Laba Report 42367 - 28V & 125V Distr. Cab. Accepted Accepted Wyle Laba Report 43870 - Unit 2 RMS (Controls) Accepted Accepted Wyle Labs Report 44215 - NEMA 12 Cab. & Misc. Accepted Accepted Wyle Labs Report 43728 - NEMA 12 Cab. & Misc. Accepted Accepted Wyle Laba Report 43166 - Misc. Components Accepted Accepted Typical Safety Related Valve Response Item 9 Accepted Service Water Pump and Aux. Feedwater Motor Response Item 10 Accepted Diesel Generators and Associated Components Accepted Response Item 11

• Required confirm ation of Seismic I design for cable trays - Response Item 6
• Confirmation of Salem in Westinghouse Requalification Program - Response Item 7

mm 6

n..e. c.o... o h.

.) O " ' '. ' - D SOUTIIWltST liESli AliCl1 INSTITUTli P. O. D u x a 7!., DLC O Mi IL LD. CO! :. ;.f.:TI uT Cr.UU. J ATTACHMENT #1! jut! 12107. June 7,1971 g,, d Mr. R. L. Mitti Chief Mcchanical Engineer Salem Elcetric Engineering Department Sectrical Division Public Service Electric and Gas Company Rie f EE E 80 Path Placc f.L/p /f28$0 Newark, New Jersey 07101

Subject:

Southwest Research Institute Project 17-2150-01 Salem Nuclear Generating Station Your Reference QA-66, date'd May 13, 1971,

Dear Mr. Mitti:

General Electric Test Report 70ICS100, vibration Testing and Analysis of 7700 Line Motor Control Center, has been reviewed by our San Antonio offices and the following comments are offered: "The report concludes that the equipment as tested is suitable for applications up to at least O. 5 G base input - acceleration through a frequency band from 5 to 500 Hz. Since the unit was tested under the conditions as ' specified and it appears from a brief investigation that the tests were conducted in a professional and com-pctent manner, the conclusions seem valid. The only question about the data was how accurate was the extrapolation of the test results from 5 to 10 Hz. In this frequency range the input G Icvel was only approxi-Tnately. 25 G. Since this was also near the resonant frequency in the horizontal direction, the extrapolation might not be justified from a ruliability standpoint. One question which must be answered is how well the test depicts the satisfactory operation of the unit under g upset conditions. The horir.ontal and vertical rerponue 'I spectra curves give an indicatic:s of expected initut "G's" as a function of frequency for the ma::iinum credible earthquake (205', G horizontally and 13. 3*/,, G vertically) @ e; \\ . ' pi ' (q;w.

b a M r. It. I.. Matl Junic 7,1971 Is..ge 2 s and design bace carthquahe (10% horizontally and 6.7% G vertically). This data shows that for vertical response the input Icvels will be Ices than. 5 G as long as the damping is 2% or greater. For the horizontal r esponse the input 1cycls will be greater than. 5 G's for both the maximum credibic earthquake and the design base carthquake. These curves have been replotted (Figures 1 and 2) to illustrate the frequencies that the input Icvcis execed. 5 G. Figure 1 indicates that the input Icvel could be 1.1 G at 5 Hz and

2. 4 G at 10 Hz. Figure 2 shows that the G Icyc1 of 1. 0 G at 5 Hz and. 9 G at 12 Hz exceeded the. 5 G input test Icycl.

The significance of these facts are: (1) the motor control unit could be subjected to more seve're vibrations than those to which it has been tested, assuming that thc' damping is less than 5% and (2) the maximum response corresponds j 'to the natural frequency of the motor control unit, which is j unde sirable. " Should you have any questions or comments, please do not hesitate to contact this office. Very truly yours, b R. P. Shimkus

• 5

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=-=-': =. n= d 78 j p, p hb bbkb'%f'i EIbCTDIC soscraic uritiry C0MPANY sAtss .. Titf 7 HONE 376 9000 C P ER ArlON as tast wittow stattT, uittsunN, New HaStf 0704 August 6, 1971 , ATTACHMENT #2 Salem 1;uclear Generating Station ELECTRICAL ! RRB'. I/ Re: DIVISION h-Units #1 and #2 Motor Control Centers AWG IGWS. Seismic Analysis Report AUG111971/ / Mr. R. R. Bast 3 . g.g Chief Electrical Engincer ?P3 Kc Public Service Electric and Gas Company IPRHL SL 80 Park Place Newark, New Jersey 07101 h /l/ g q

Dear Mr. Bast:

1971, we submit In response to your letter of July 1, the following additional information regarding the seismic with-stand capabilities of our Motor Control Centers. The input amplitude between 5-10 h: represents machine A maximum transmissibility capabilities in this frequency span. factor of 3:1 between the base of HCC and the motor starters was Individual tests conducted separately,on motor star-determined. ters indicated that they could withstand considerably more than 0.5 x 3 = 1.5 g's, so that the analysis is substantiated. Individual components have been tested by themselves and thraa pinna = wi m ne found to withstand over 69'm_fnrea._i u.1.1The structure and compone malfunction. and operate normally on more than.these forces without damage, eeturn to normal condition. The MCC bolted structure is, by design,.a good shock ~ab-With the transmissibility measured, the damping f actor sorber. actually greater than 5 a r-This data on the individual components was obtained from tests which were not made part of the formal report previously submitted.

GEllER AL Q ELE IC Public Service Electric and Gas Company August 6, 1971. 't I hope this information will be sufficient to answer thosc questions posed by your Seismic Consultant, Southwest Research Institute, in their June 7th letter to you. 'Very truly yours, J. A. Miller Power ransmission Sales ' h b G. Q Y' O.D. Lee,III/ma 9 W O

5 '= 2* ~ ~ L ~~~, SOUTI-IWES O RESE ARCH IN hTITUTE l s BLOOMFicLD.CONNcCTICUT 0G002 P.O. SQX 375 P S E &'G -l ATTACHMENT #3 k'. I February 29, 1972 qt Ec0cf.vkT; - ~ t f P. S. E. & G. CO. o.

p. A RO'.!py,jg,,y

.dl I Mr. R. L. M[tti< b g2 ' _._ .h Chief Mechanical. Engineer ((/ Electric Engineering Department V\\.7 ' :y,. ;. t = Lyj; 2.*.!L Public Service Electric and Gas Company p. ^ 80 Park Place Newark, New Jersey 07101 p Southwest Research Institute Project I7-2150-01

Subject:

Salem Nuclear Generating Station 26, 1972 Your Reference QA-79, dated January Center - Seismic Calculations 7700 Line Motor Control

Dear Mr. Mitti:

The information contr.ined in General Electric' We br.ve no further comments. . 1971. Very truly yours, b.f.Sk.bnICiW

• i R. P. Shimkus

~ Project Manager ~. RPS:JEG:mj cc: A. Nassman C E. Lautzenheiser j .{ /, O f 0

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l ATTACHMENT #4 Br l 01 440 V,3 0,60 Hz O2 \\ ~ ea NM::::. : ::_:_=__ _.. - - = ENLARGED VIEW 4.- ------, INPUT CONTROL N'. J_- _ _'.:!."C _. _ Z J uo uc ,# 12 ) b ~

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-AGID pg 7 A- #1 -#12 DATA m cajoq, MONITOR CHANNELS ,/ W L:.2 's ' Nl / (ACCELEROMETERS) T .s 2 : ,ca s N 7g 'M STRUCTURAL MONITOR g N5 POINTS Mc Mc UD UD-UNIT DlSCONNECT ir:nr inr:r m o MC-MOTOR CONTACTOR g g A SS-START-STOP SWITCH v:nr m =

1. I CR-CONTROL RELAY

-A O ,4 a : :. Mc .jgt oo .o e VIBRATION FIXTURE s A

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FIGURE 4-2 MOTOR CONTROL CENTER - ACCELEROMETER MOUNTING LOCATION f

-g enes l Sang l Ehum 1 5=5 I bd I tes4 l Gad 1 M l %seS l M i M i U l Ul Ul UI Ut Ol U ATTACIIME!TP #5 RESPONSE ACCEIERATION PIDTS - PG. I A - 36A ACCELEROMETER NO. VERTIC AL ACCEL. l!ORIZ. ACCEL. IIORIZ. ACCEL. HMIREADTII FORE-A ND-A FT (SEE FIG. 4-2) I 2A-14A 26A PAGE ti, fhCE ISA fiscE 25A 2 3 3A ISA 27A 4 4A 16A 28A 5 5A 17A 29A 6 6A 18A 30A 7 ~ 7A 19A 31A 8 8A 20A 32A 9 9A 21A 33A 10 10A 22A 34A 11 11A 23A 35A 12 12A ,,E. - 24A 36A 1 TABIE 3-4 -INDEX - ACCELEROMETER NO'8 & ASSOCIATED X-Y PIDTS. e

massy ans g Suns y Em3 g M) Ml M{ M] Ml N] 1 l l l l l l l r 3 a ATTACIIMENT (l6 = DATE: 12-15-69 e s CUSMv.ER: e s LATA 2-3 SECJENCE VER TI CAL ~ e NiEBER TEST

1. 2 ARTICLE HOTOR CONTROL CENTER..

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i ~ ATTACIIMENT 4f7 ,--s DATE: 12-17-69 CUSTOMER: DATA 2-13 SEQ.TENCE HDRI ZONTAt. NUALER IN-BREADTH TEST

1. 2 AICICLE HOTOR CONTROL CENTER l

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e i e e i e i i i i i i - i 4 ATTACIIMENT fl8 l 1.' \\ g e ~ -l IR72: 12-18-69 e i CUSTG4ER: i IMTA 2-25 ~- SEQUE*iC2 H0R1ZONTAL fiU:BER FORE f, AFT 4 TEST

1. 2 l

ARTICLE MOTOR CONTROL CENTER o e, i [ ,1 0.s . r- ~~ N -...) ,/-^ N ' i / ,j Cravi ty Udtsflh)N s l e e i i ,e e i r e s s r s ,e j l I I e I l 0 t t l - r...u a 3 4 i, < i.. co a i 1 e s e 0'fo e Frequency (liz) 25A O

,f ATTACHMENT # 9 p PACTU/.L DATA (centinued) './ . 10. nrto:rt.!!?.e.tT.TI: At the co"pletion of chock tocts, the 600 V Switchgear was recoved from the chock machinc and then counted to the table of a L. A.B. Low Fr.:quency Vibration J'.achine. s. to unit tras subjected to a vibration ccan in a frequency range from 5 to 33 cps. For thin scan, acceleroneters were attached to the unit at the cc e poll:,c ao monitored during the chock tests. were noted and recorded.Ecconant cor.ditions of theco points, if any, the two horizontal axes: Tais scan 1:Ls performed in cach of Monitored Resonant Transmicsibility _ Points Axis Freq. (c P. ) (ou tnut/innut) 2 Front to back 19.0 29 0 3 Sido to Side 12.0 35 4 Side to Side 10.0 1 75 5 Pront to back 16.0 '* 50 6 Front to back 22.0 '60.0 here were no 'appreciabic resonant conditionc of l Pointa 1 or 7, nor the structure frame, in the frequency range scanned. Note: Transmissibility is defined as a ratio of the output amplitude divided by the input amplitude. 11. SUI'J1ARY : Scro was no apparent physical damage to the unit as a result of the shock tests reported herein nor was there any dio-connect or chatter of the contacts monitored. e O Applied Devices Corporation [o,502-901 PAGE 15 OF 17 PAGES ( ITNCLASSIFIED )

I -l ATTACHMENT =101 .,j I-T-E DiPERIAL con? ORATION PHIL/GELPHIA, I'L:'NSYLVANIA 600 V S1? ITCH 0 EAR Locations of Output Accelerometern During Tests: l _h r i 10.f l 0. < 4 y = (_h P l C y II. 0 A , Front View Front View u.C.'~ f a c.s ** t h k) i T 6 Front Vf'.o \\/ J ' *3 Rear View Side View FIGURE NO. 2 ~ a-3718 en. Applied Devices Corporation . j,o, 502-901 Pact' 11 OF 17 PAGES ( UNCLASSIFIED ) ..s

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Seismic Qualification Sary of Equipment Sa mAkascu Gcos:Ar as sur,oa 1. Plant Name: 1. Utility: Pusuc Scme c Eacn,c. y cis.:, C. rwa / 2. NSSS: h/E s rms Noost 3gg NEMlly 3. A-E: II. Competent Nace Valve Model 1. Nu=ber Velan B12354 B 13MS 2. Vender Velan EncTineering Companies 3. Physical Description 4 - inch - 1500 lb. forged bolted bonnet motor or manually operated gate valve 4. I,ocation: Building: Containment On Plant) Elevation: 145 ft. 5. Natural Frequencies in Each Direction: 59.85 Hz weakest axis 1 6. Functional

Description:

Maintenance valves for pressur,lzer spray valves: no motor operator in this applicatiot. 7. Pertinent Reference Design Specifications: P.S. Specification 72-6347 III. Is Equipment Available for Inspection in the Plant:{X] Yes [ ] No Con =ent s : 9 O e

me. j .- s 27. Seirale Qualifiestion Method: Test: { Analysis: v Combination of Test and Analysis: V. Seismic Input: 1. Required Response Spectra (attach the graphs): Required 2. Acceleration in each Direction: 5.00o in each horirental direction VI. If Qualification by Test, then complete: 1.[ ] Single Trequency [] Multi-Frequency 2.[ ] Single Axis [] Multi-Axis 3. Frequency Range: 4. TRS enveloping RRS using Multi-Frequency Test [] Tes (attsch 17.5 graphs [] No h V" 5. g-level Test at hy 2" = 6. g-level Required g= h V" ~ 2 7. Mounting: 1. Seismic Report: 2. Field Check: 8. Functional verification Performed [ ] Tes [ ] No [ ] Not Applicable VII. If Qualification by Analysis or by the Combination of Test and Analysis then, Complete 1. Description of Test including Resulta: O O

. l 2. Method of Analysis: Sc] Static Analysis ( } Zquivalent Static Analysis I } Dyna =ic A=alysis [ ] Response Spectrum ( l Time-History 3. Model Type (each direction): 4. Computer Codes: 5. Damping: 6. Support Considerations: 7. Critical Structural Elements: Governing Seis=ic Tntal Stre A. Identification location Reseense Co=binatien Stress Stress Alleva 15,0CD 26,250 Yoke-Section 2-2 psi psi Summary of analysis attached ( Effect Upon Functional ~ B. Max. Deflection _ location Operability N/A N

VE,LAN ENGINEERING COMPANES ENGINEERING CALCULATIONS SS 4-15000A-100 4a r0RGED BOLTED B01.aET.<UCLEAR VALVd

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SUMr4ARY OF RESULTS : SECTIO.l 2-2 STRESS IliTEi4SITY: S12 = 15000. ALLO 4ABLE = 24.25o 15000. < 2 4.2 So. CO.iDITION SATISFIED SECTIOd 3-3 STnESS INTE!!SITY: S12 = I4177. ALLS AB LE = 2 o d50. 14177. < 2ob53. CO.'DIT Iuri S ATISrIED SdCTIu.; -4 ST.'4 E SS I.4 TEDS ITY: S12 = 116e2. n LL3.. A 3 LE = d o d :v. Iloe2. < 20n60. Co.40ITI0a SaTI5el d] dtCTIu. 2-3 duLT STedsud5: 2415. ALL-L A L? = 31 Iou. SB = 2416. < 31/... Co.;D I T I-).. SnTI:r!:D ...s i J <., L.- k J J:..C Y : en=0 = ca. AI.Lt~. n 3 L i = 33.

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SUBJECT:

..........E.@EM.k....d.N.d.6.N.([.............. Oate: MANA/ H, /-7 74. SEIS..IC A.4ALY5IS FO:4 4a 1500 La r.ORGED BOLTED BO.J..ET MOTOR OR..iAdUALLY OPERATED GATE VALVL JUCLEAR class I,E/22 i 8, _ Bi _ h i Jb [f 1 = I u / / i a N I _L I i u y Q .L. ? O J J I \\ lb 4 l '1 A L ~ k \\\\ 'h 'h 7 thk 'A % M / / 4 [ ! // n l ,,A =0 os p + + // /@ ff f f i n Y' AY z< @gi @z x< 3 70

,~ Seismic Qualification S e ry of Equipment s b' "* 0## 'M N'# Type: I. Plant Name:

1. Dtiltty: Pasue Scwe e Eaense.

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Fun / 2. NSSS: NE s rw g doo st. 3va NdY6) 3. A-Et II. Component Name Service Water Pump Model 1. Nunber Serial No. D-26081 ( tvo. ) Ouantity: 6/ Unit 2. Vendor Aurora Pump 3. Physical Description Service Water Pump - (vertical wet-cit) 4. Location: Building: Service Water Intake Structure (In Plant) Elevation: 92 - ft. 6 - In. .S. Natural Frequencies in Each Direction: See Attached Table I I 6. Functional

Description:

Supplies river water for safety related plant cooling loads 7. Pertinent Reference Design Specifications: PSE&G Specification 69-6389 n III. Is Equipment Available for Inspection in the Plant:[x] Yes [ ] No Con: ment s : G e

sik-j 2 27. Seismic Qualifiestion Method: Tast: Analysis: X [( Cenbination of Test and Analysis: T. Seismic Input: 1. Required Response Spectra (attach the graphs): See Attach'ed Graohs Required 2. Acceleration in each Direction: VI. If Qualification by Test, the Cecolete: 1.[ ] Single Trequency [] Multi-Frequency 2.[ ] Single Axis [] Multi-Axis 3. Frequency Range: 4. TRS enveloping RRS using Multi-Frequency Test [] Yes (attach TRS graphs Y" 5. g-level Test at g= h 2 6. 3-level Required g= h V" ~ 2 7. Mounting: 1. Seier.ie Report: 2. Field Check: 8. Functional Verification Ferformed[ ] Tea [ ] No [ ] Not Applicable VII. If Qualification by Analysis or by the Combination of Test and Analysis then Complete 1. Description of Test including Results: ( O

e / ( 2. Method of Analysis: [ ] Static Analysis [ ] Equivalent Static Analysis [X] Dynamic Analysis [X] Response Spectrum [ ] Time-History Multi-Degree of Freedom-Lumped Mass 3. Model Type (each direction): CANBM, MDLDF, STRESS 4. Computer Codes: 5. Damping: % Critical Bolted to concrete floor - bolt loads 6. Support considerations: considered in calculations. 7. Critical Structural Elements: Coverning smic Total Stre A. Identification location Reseense Ce=bination Stress Stress Alleva See Attached Table II ( Effect Upon Functional 3. Max. Deflection _ Location _ Operabilit* Dynamic deflections much less than bearing clearances - No effect upon operability n 6

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TABE I TABE OF FRMUDCIES Pump Operating Speed 19 75 Hert: Page Pump Column Transverse 22 75 73 99 228 1148 15 Yortical 58.1 19 Lineshaft Transverse 61.2 25 Yortical 106 24 Shaft Tube Transverse 29.6 27 Discharge Head and Motor Transverse 47.8 720 1735 6 Motor Transverse 177 4 D N e w '9?@5r (

D, " lT ' i MATERIAIS AND STRESSES Icoation Material (3) s(2) M*#8 " (1) i P r l' Head - Motor Assembly Motor Mounting Bolts A 36 14,500 956 14.2 8 I': Base of Head SA516 cr. 70 17,500 1663 95 29 lI Head Mounting Bbits ' SA325 20,200 7354 1.75 29 il Discharge Nossle Flange SA516 cr. 70 17,500 12,652 38 30 l Flange Bolts N. F. 26,290 30 l Solo Plate A 36 14,500 2820 4.14 33 7094 32 Anchor Bolts N. F. Puap and Coluan Assembly Flange (Sta.4) SB148 CDA 954 18,900 5433 2.48 23 Flange Bolts SB164 Gr. 400 54,000(} 15,693 2.45 23 Coluan Pipe SB169 CDA 614 18,000 5173 2.48 23 Discharge Case Flange SB143-2A 8500 6143 38 23 i Linenhaft K500 Monal 21,000(5) 13,728 53 r_6 i Shaft Tube SB143-2A 8500 121 69 2 27 { I Notes: 1. Margin is defined as tld -I l a a r s g 2. Calculated Stress is at WE and includes operating, nossle and eelaaio loads. g -t 3 Allowable Stress is at W E unless noted. N I 4 Allowable Stress at IEE U , E,./ i 5 Based on 30% of Y.S. per ANSI B581. As this is not a pressure boundry, aargin is based rf ((h' if on operational criteria only. y .}}