ML19031A503
| ML19031A503 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/23/1979 |
| From: | Mittl R Public Service Electric & Gas Co |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19031A503 (35) | |
Text
PS~G*
Public Service Electric 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.
R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction Attachment The Energy People 95-2001 (40DM) 9-77
. '. ~.
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 justification for acceptance of low frequency test results in the 5 to lo 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 70ICSlOO, the input accel-erometer used in this test was designated as #2 on figure 4-2 (Attachment 4). Table 3-4 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.
- I
- 2. 5KV Switchgear and Relays
- a. Area of Concern: Provide additional data regarding the
_following 5KV Switchgear relays -
12HFA51A42F 12IAC66B6A 12IAV74AlA Include information on the test procedure, functional monitoring and suitable backup data to support manufacturer statements on the seismic capability of the relays.
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- 2. 5KV Switchgear and Relays (Cont'd)
Response: 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 supports 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 subcritical 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 au~iliary systems. Restoration of power within a critical time period is not required with the unit subcritical 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. 6oov Switchgear
- a. Area of Concern: Provide additional information re~arding effect of resonances identified in ITE Test Report #R-8792.
Response: The resonant conditions identified in the report occurred only on the sheet metal surfaces. ITE Test Report
- 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 Salem Generating Station, nor are any required to perform a safety function. Therefore, the high transmissibility of the sheet metal surfaces would not affect the operation of the 6oov 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 Ct,7.lB-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-l 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-l, "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: Indicate the voltage and current values used for the 28 volt C & D battery charger during seismic testing.
Response: Batelle's report on the seismic 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 fo~lowing 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.
.. -~- : -.. ~- .
- 6. Electrical Penetrations
- a. Area of Concern: Confirmation that the penetration area and containment cable trays and conduit hangers are designed to seismic Class I criteria.
Response: Cable trays and conduit hangers which are in seismic Class I structures have been designed and installed as seismic Class I. This includes the penetration area and containment.
- 7. WCAP 7817 - SSPS, NIS, Process Racks
- a. Area of Concern: Confirm that Salem is part of the West-inghouse Seismic Requalification Program and that the restric-tions/modifications resulting from that program are not applicable to Salem.
Response: The seismic requalification of Westinghouse supplied safety-related equipment to higher accelerations does not have an effect on Salem. Salem 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-l will be updated to include supple-mental qualification data. A revised Table will be submitted shortly.
- 8. Wyle Report 42441-1, Control Console
- a. Area of Concern: Provide a ~upportin~ statement regarding the operability of post accident recorders on the console.
Response: A portion of the Unit 2 Control Room Console was seismically tested by Wyle Laboratories which included post-accident recorders. The recorders weretested with the console and did not fail structurally. The console was installed on Unit 2 after the test and the indicators and recorders are working satisfactorily.
- 9. PSE&G Valves - Velan Bl2354 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 forms for the Service Water Pumps based on the qualification data which was reviewed at* the meeting.
Response: The SQRT forms for the Bervice Water Pumps are attached.
- 11. Diesel-Generators and Vital Appurtenances
- a. Area of Concern: Provide information regarding the func-tional operability of the diesel-generator differential protection relay 12CFD22AlA during the seismjc test of the generator control panel (Wyle Report 42551-1).
Response: During the seismic test of the generator control panel, a number of relays were monitored for operability.
The diesel-generator differential protection relay 12CFD22AlA is in the circuit for the diesel unit trip relay (DUTR).
Refer to attachement 11 for a portion of the circuitry. The DUTR ctrcu:i:twas 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-warded 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 subcritical state and a minimum of auxiliary systems are operational. Even if the diesels fail
- 11. Diesel-Generators and Vital Appurtenances (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 subcritical 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 islno evi-dence to suggest that extensive damage would occur' during the seismic event which would not permit restart of the diesels if required.
TABLE 1 SALEM NUCLEAR GENERATING STATION UNIT NO. 2 NRC SEISMIC QUALIFICATION REVIEW
SUMMARY
Review Item Test Inspect/Data Functional Oper~bi~~y Motor Control Centers Response Item 1 Accepted Control Room Recorder Panels Accepted Accepted 5KV Switchgear Accepted Response Item 2 6oov 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 Labs Report 42367 - 28v & 125V Distr. Cab. Accepted Accepted Wyle Labs 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 Labs 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 confirmation of Seismic I design for cable trays - Response Item 6
- Confirmation of Salem in Westinghouse Requalification Program - Response Item 7
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- j lATTACHMENT #1 I .
E S. n {; G JUl! 12 i8i I June 7; 1971 Q,f. nccci vcd Mr. R. L. Mittl Chief M.cchanic<.il En6inccr Salem Electric Engineering Department Electrical Division File# . 1t,1m #
Public Service Electric und Gns Company 80 Park Place 40 Li;6!0 Newark, New Jersey 07101
Subject:
Southwest Research Institute Project 17-2150-01 Salem Nuclear Generating Station 0 Your Reference QA-66, date d May 13, 1971
Dear Mr. Mittl:
General Electric Test Report 70ICS100,, Vibration Testing and Analysis of 7700 Line Motor Control Center, has been revic\ved by our San Antonio o!!ices and the following comments are offered:
.i "The report concludes that the equipment as tested is suitable for applications up to at least 0. 5 G base input.
acceleration through a frequency band from 5 to 500 Hz.
Since the unit was tested under the conditi-ons as specified and it appcarf! from a brief investigation that !
the tests were conducted in a professional and com-petent manner,, the conclusions seem valid.
The only question abo~t the data was how accurate was the extrapolation of the test results from 5 to 10 Hz. In this frequency range the input G level was only appro::d-lnatcly
- 25 G. Since this wois also near the rcson~nt * *
. frequency in the horizont*1l direction,, the extrapolation l might ~~ be justified from a reliability st:indpoint.
One question \Vhich mu.st be :ms\";crcd is how well the tcsJ; depicts the satisfo:ictory OIH~ r*,tion of th.l! unit under upset *concl.llions. The hori:.~ontal <ln<l vcrlic:ll r('~pon:.;c spc:clr;1 CUr\'L.:S CiVc an ii~dic;,tlon of c:-:pL.:ctcd input "G'~"
a~ a function of !:-l~qlh.'n.:y fur th ..~ rn ** :-:iJuun1 c1*t*tHbh!
earlhqu.-,l~c {2.Q<~.~ Ci hori:.~ontally ~uld 13. ~% G vcrLic;11ly)
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,,e Mr. H.. J,. Mi.al Julll: 7, J 9'/ l P1:i~c 2 and design bazc earthquake (10% horizont~lly and 6. 7% G vci:.tically). --This ckta shows that for vertical response the input kvds will be lczs than
- 5 G as long 'ts the d<.1.rnping is 2% or greater. For the horizontal response the input levels will be greater than. 5 G's for both the rnnxin1um
- credible e_arthqu<.1.ke an<l the design base earthquake. These curves have been replotted (Figures 1 and 2) to illustrate the frequencies that the input levels exceed
- 5 G. Figure 1 indicates that the input level could be l. 1 G at 5 Hz and
- 2. 4 G at l 0 Hz. Figure 2 shows that the G level of 1. 0 G at 5 Hz and
- 9 G at 12 Hz exceeded the
- 5 G input test level.
The significance of these facts are: (l} the motor control unit could be subjected to more sev~re vibrations than those to which it has been tested, assun1ing that the' dampi_ng is less than 5%, and (2} the maximum response corresponds
- to the natural frequency of the motor control unit, which is undesirable."
Should you have any questions or comments, please do not hesitate to contact this office.
Very truly yours,
-. I I
_**I R. P. Shhnkus I Project Manager
. Prepared by:
J. E. Calli van
- Senior Qualily As surancc Engineer JEG:mj cc: A. Nassm:in C. E. Laul:r.cnhCiscr
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ELECTRIC UTILITY COMPANY SALES.
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- ,5 EAST WILLOW STREET, MllllURM, MEW JERSEY 070 .. 1 *** TELEPHOME 376*9000 OPERATION !
August 6, 1971 Re: Salem Nuclear Generating Station I Units 4~1 and #2 ELECTRJCAL 01\TISION IRRB'///~i-J Motor Control Centers Seismic Analysis Report - AV/G I GWS 4*
.i AUGJ. 1 i971 / /
Mr. R. R *. Bast ~
A F\'I~ v Chief Electrical Engineer rr~
iTnP 'ltHE . ,I!
Public Service Electric and Gas Company KC , ! PS I SL
- IPAHL 80 Park Place I
Newark, New Jersey 07101 J~'?J<~
Dear Mr. Bast:
- rres-- / ' /
. .~/tJ/'/./ .
In response to your letter of July 1, 1971, we submit the following additional information regarding the seismic with-stand c~pabilities of our Motor Control Centers.
The input amplitude between' 5-10 hz represents machine capabilities in this frequ~ncy span. A maximum transmissibility factor of 3:1 between the base of MCC and the motor starters was determined. _Individual tests conducted separately ~n motor star-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 found to withstand ovP.r t;q*,:: _fnr~P. ...in..Jll_l t-hrPP X'l:i:tnP~ ,.,;t-'hnnt- - - - - - - -**-
malfunction. The structu+e and components can stand considerably more than. these forces without damage, and operate normally on tl'return to normal condition.
The MCC bolted structure is, by design, .a good shock *ab-sorber. With the transmissibility measured, the damping factor i~ actually greater than 5%.
This data on the individual components was obtained from tests which were not made part of the formal report previously submitted.
-~ ... -*"*.*-
Public Service Electric and Gas Company August 6, 1971 2 -
I hope this information will be sufficient to answer those questions posed by your Seismic Consultant, Southwest
. Research Institute, in their ~une 7th letter to you.
-very truly yours, J. A. Miller Power~:ansmission Sales O.D.Lee,III/ma By: M':1£iel_...--
P. SE &*G
- . I.
f ATTACHMENT #31 MA~ 6 \SI~*
February 29, 1972 t-'*i Rc~c~.v:'d:
\ . -- "'"'
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Mr. R. L. Mittl Chi~f Mecha.nic:a.1.Engineer Electric Engineering Department Public Se rvic:e Electric and Ga.s Compi!.ny
. 80 Park Place Newark, New Jersey 07101 Southwest Research Institute Project 17-2150-01
Subject:
Salem Nuclear Gener&ting Station
- Your Reference QA-79, dated January 26, 1972
- Seismic Ca.lcu!.a.tions 7700 Li~e Motor Control Center .,
Dear Mr. Mittl:
The inform~tion contc..ined in General Electric's letter of .August 6, 197~ I
- . , has clarified the questions raised in our original conm1'-'nts of June 7, 1971. Vie h~ve no f\;.rther co:n.mento. .Ill/..
Very truly yours,
.". f. Sh.~.,.
. . . \c,,
An .'-."
- 1l. P. Shimkus \
Project Manager I
B.PS:~G:mj . . .
cc: A~ Nat;1sman 11 *C. E. Lautzenheiser .,
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e 1ATTACHMENT #4 l e fl 01 440 V ,30,60 Hz ENLARGED VIEW INPUT CONTROL 02
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- .. 'LEGEND A- #1-#12 DATA MONITOR CHANNELS
. (ACCELEROMETERS)
.. STRUCTURAL MONITOR POINTS UO- UNIT DISCONNECT MC- MOTOR CONTACTOR SS- START-STOP SWITCH
- CR- CONTROL RELAY *
. . VIBRATION
. *--f'.l)CTURE ft FIGURE 4-2 MOTOR CONTROL CENTER - ACCELEROMETER MOUNTING LOCATION
~* .: -*~ ' . - ~ - ~ .
-1~1-1~1~1~1~1~1~1~1~1~1~1~1U1LI1LI,U.i f1 l ATTACHMENT #5) L' '
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RESPONSE ACCELERATION PIDTS "'PO, IA -36A ACCELEROMETER NO. VERTICAL ACCEL, HORtZ. ACCEL, HORIZ. ACCEL.
IN-BREADTH FORE-AND-AFT (SEE FIG. 4-2) 1 2A* 14A 26A 'i
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2 PA'E' *'tA.j tiS<:E 13A ~CE 25A 3 3A 15A 27A
[
- 4A 16A 28A ~*
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8 6A 18A 30A It 7 7A 19A 31A i~
8 8A 20A 32A [
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9 9A 21A 33A e 10 lOA 22A 34A 11 llA 23A 35A 12 12A '*
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24A 36A TABLE I~ - INDEX - ACCEgROMETER NO'S 6 ASSOCIATED X-Y PLOTS
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- ( ATTACHMENT #61 a ...
I
- , DATE: 12-15-69
- I i
CUSTOY.ER:
- DATA 2-t
- SE~iJENCE VERTICAL N"U:t.BER I
I TEST ARTICLE 112 HO TOR CONTROL CENTER
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- -* - DATE: i 2-17-69
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CUSTOMER: ti DATA 2*13 - t SEQUENCE HORIZONTAL I*
NUMBER IN-BREADTH t
"/12.
TES'l' Affi'ICL! HO TOR CONTROL CENTER 'I e.
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- DATA 2-25 I
SEQti.C:~\C:il: HORIZONTAL I
. l\ilf..!BER FORE & AFT ..
I TEST #2 I I' I ARTICLE MOTOR CONTROL CENTER I I ** -
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~CTUl.L DATA (cont1nucu)
.-~
- 10. rJ:~~!U,HT ~!fr~1 At the co~.::>letion of ehoclc tents. the 600 V Sw1 tchr;ear w~s removed f.i*or.i the shock machine and then r.tounted to the table
. ot: a -*L.A.-B. ll:>w Fr~~ut:ncy V1brn.tion J.hchinet *
'lbc unit caa eubjected to a Vibration ccan 1n a rr~~ucney range rror:i 5 to 33 cpa. For thin sc.2n, acce!c:.~o~::etcrn iiK:r-e attachccl to the unit at the (;~!'..i.~ points an mon1 t.o;:ed. during I the shock teats. Rc~or.ant eond1t1ona of the~o points, 1£ any,
- I I
I were noted an.1 racorclcd. Til1s scan i-~ro.G perfomcd in each or I the two horizontal a:-:esz Monitored Resonant 'rran~micsib1lity
( ou t.:nu t/innu tl I
Points 2
AT..18 Front to back
~g.
19.0 (er-fl}
29.0 S1do to Side 12.0 3.5 i Side to Side 10.0 i.75 g Front to back Pront to back i6.o 22.0 35.0 60.o There were no appreciable resonant eond1t1onn or Points l or 7, nor the ~tructure rrame, in the frequency range scGnlled.
Note1 Transm1ss1b1l1ty is defined as a ratio or the .
output ar.iplitude divided by the input amplitude.
ll. Bm!t*tARY z There was no apparent physical damage to the unit as a result or the shock tests reported herein nor was there any dio-oonnect or chatter or the contacts monitored.
ETL _3718 _ _ _ __
Applied Devices Corporation
/s.o.
" 502-901
- PAGE 15 OF 11 PAGES
( VNCLASSIFID> )
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_.,.s.o. 502-901
' PAGE. 11 OF 17 PAGES
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Sei1mic Qualification Summary of !guip?ent
( I. Plant Name: [sA,ui1 N.;.1c.:.,,o;.c:. ~c..ue;z.Ar,µ0 _Sr,,t1 T,&>AJ I ~:
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- 1. Utility: /1;BLIC. Sc.12.IJJC.E [1...C.c..Tli!11:- q (;jA.::. Cc*
- 2. !ill.=
fSEcl IWR
- 3. !:!l.
II. Com2onent Name Model I valve I
- 1. Number Velan Bl2354 B 13MS
.2. Vendor Velan Engineering Companies I
- 3. Physical Description 4 - inch - 15.00 lb. forged bolted I
bonnet motor or manually operated gate valve
- 4. Location: Building: Containment (1 n Plant)
Elevation: _.l=-4.--..5-=f.;::;t.::.*----------------
- 5. Natural Frequencies in Each Direction: 59.85 Hz weakest axis
- 6. Functional
Description:
Maintenance valves for pressurizer spray valves ; no motor operator in this application.
- 7. Pertinent Reference Design Specifications: P.S. Specification 72-6347 III. Is Equipment Available for InsEection 1n the Plant:(X] Yes [ ] No Comments:
...... ..... ~ .... ***
-~*-*--~
'IV. Seismic Qu.alification Method: Test:
AD&ly1is: ~~x..._ _____
Combin&tion of Test and Analy*i1:
"'* Seismic Input:
- 1. .
Required ae1ponse Spectra (attach the graphs):
-~~-~~--~~
Required
- 2. Acceleration in each Direction: 5. OOg in each horizontal direction VI. If Qualification by Test, thenComplete:
1.( ] Single 'Frequency [ ] Multi-Frequency 2.( ] Single Axis [ ] Multi-Axis
- 4. TilS enveloping JtltS using Multi-Frequency Test [ ] Yes (attach 'l'RS graphs)
[ ] No s.. g-level Test at 11.* h 2
- V*
- 6. g-level Required
- 11. - b2 - V*
- 7. Mounting:
- 1. Seismic ~eport:
- 2. Field Check:
- 8.
- Functional Verification Perfonnedl ] Yes [ ) No [ ) Not Applicable VII. If Qualification by Analy*i* or by the Combination of Test and Analysis
~hen, Complete
- 1. l>eacription of Test including Jle*ult1: - - - - - - - - - - - - -
~* ~ .11.
I
-** 2. Method of All&lyaia:
IXJ Static All&ly*ie [ ] Equivalent Static An&ly*i* l 1 Dyn4mic Analysis
( ) Response Spectrum ( ] Time-History
- 3. Model Type (each direction): - - - - - - - - - - - - - - - - - -
- 6. Support Considerations:
~------------------~--
- 7. Critical Structural Elements:
Governing Seismic Tnta.1 Streai A. Identification Location Res~onse Combination Stress Stress Allovab:
Yoke-Section 2-2 15,0CD 26,250 psi psi Summary of analysis attached I. Effect Upon Function.al Max. Deflection Location Operability N/A
(
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I v V~LAN EN.ERING COMPAlllES
.~
ENG-ERING CALCULATIONS BB4- I 50UGA-J 00 411 ~ORGEiJ BOLTED 801~1-~ET &rnCLEAR VALv'!::
- w***********"**
SUMMA~Y OF RESULTS 1 SECTIC>i'J ~-2 ST~ESS Ir~TE16 !TY:
S 12 = I 5000. ALLO~AB LE = ,ZG .Z..So 15000. < .:Z~.ZSo.
COi~D ITHrn SAT! SFIED SECTI01.J
, 3-3 STHESS HffENSITY:
S J2 = 14177. AU.0.*ABLE = 20850.
14177. < 2ob5u.
SECTIO.~ ~-4 STH!:SS Ii:ffbJSITY:
512 = 115b2. ALUJ*. A3LE = 26~j(J.
1 I 502. < 2Cli:SQ.
co~wITIOi~ S;i.TI5rlt:0 SB = 2415. AUf~*. ABL:: = 3 I-/ ,)U *
.2415. < 31 /:.::~.
t-i-H:Q = 'ou. Ali!J.iA:1LE = 33.
oo. > JJ.
IBY:
S. I.
I REY.: I PAGE No.:
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Sheet **.... / ....... of .... !.f~.~
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VELAN ENGINEERING COMPANIES Project: BB<f-IS00GA-1oa I ENGINEERING DEPARTMENT S. IS$1rsKY i Name: I s>G"/S~IC- AAJALYS!S'
SUBJECT:
................................................................... . Date:_....l.M.~'AIC,e.u'eul/2..-LJ.IJ,7-<Ll~CJ'-"'l~4~._ _
SEIS;,;IC A1iALY3IS Fen 4 11 - l:>OO LB H>RGED oOLTED 80.~~~ET MOTOR OR i.IAi*JUALLY O?t:RATED GATE VALVE. &JUCLEAR CLASS I , f i ./"111.
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Sei1n11ic qualification Summary of Equipment Plant Name: [ 5'4'- tJ1 Ni.JcL,~.i.. ~~.u£;;fiT,.1-~~ .Sr,,t17,e-J
( I.
- 1. Utility: foBLIC Sc1211 Jc.E ['-Ec.7l2.1r_ ~ G)A~ Co.
I !z2!.:
PWR j
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W£ STIAJ~ r/&>()S' 2.
-NSSS:
fSEc/
IWR
- 3. .!:!.:.
II. Comeonen t Name (
1.
Model Number Service Water Pump Serial No. D-26081 (typ.) Quant it)..:. 6/Uni t I
.2. Vendor Aurora Pump
- 3. Physical Description Service Water Pump - (vertical wet-pit)
- 4. Location: Building: Service Water Intake Structure (In Plant) Elevation: 92 - ft. 6 - In.
-~--~---.;.;.;....---~--~--------
- 5. Natural Frequencies in Each Direction: See Attached Table I
- 6. Functional
Description:
Supplies river water for safety related plant cooling loads
- 7. Pertinent Reference Design Specifications: PSE&G Specification 69-6389 III. Is Equipment Available for Inspection 1n the Plant:{x] Yes ( 1 No
................ * ~ **.- T* ~.-. '?<J..>'== **-**' . .-;
%V. Seismic Qu.ali[ication Method: Taat:
Analyaia: X Combination of Test and Analyaia:
Y. Seismic Input:
- 1. . (attach the g r a p h s ) : - - - - - - - - -
Sequired 1.eaponse Spectra See Attached Graphs lequired
- 2. Acceleration in each Direction:
~~-------~-----
VI. If qualification by Test, thenComplete: (
1.(] Single"i'requency [ ] Multi-Frequency 2.[ ] Single Axis [ ] Multi-Axis
- 3. Frequency lange: - - - - - - - - - - - -
'*s.. TllS enveloping RltS using Multi-Frequency Test [
g-level Test at b1 - b2 -
[ ) No
) Yes (attach ntS graphs)
V*
- 6. g-level Required
~- b2 - v-
- 7. Mounting:
- 1. Seismic l.eport:
- 2. Field Check:
- 8. Functional Verification Performed[ ] Yes [ ) No [ ) Not Applicable VII. If Qualification by A.naly*i* or by the Combination of Test and Analyais then. Complete
- 1. J)eacripticm of Teat including lteaults: - - - - - - - - - - - - - -
. .. . ..... *----...- ..... ,..._.__ "- -.:..~;---~---~*--~----- ---------- --~-- .
I e- -e
' 2. Method of Analyaia:
( J Static AD.alyais [ ] Equivalent Static Analya1a [x] Dynamic Analysis (X] Response Spectrum [ ] Time-History
- 3. Model Type (each direction): Multi-Degree of Freedom-Lumped Mass
- 4. Computer Codes: CANBM, MDLDF, STRESS S. Damping: ~/a Critical
- 6. Support Considerations: Bolted to concrete floor - bolt loads considered in calculations.
- 7. Critical Structural Elements:
Governing Seismic Tn tal Stres:
A. Identification Location Res~onse Combination Stress Stress Allovab See Attached Table II J. Effect Upon Functional Max. Deflection Location erabilitv Dynamic deflections much less than bearing clearances - No effect upon operability
(
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- - .. 1111 TABIE I T ABIE OF FREQUENCIES.
Ca.le.
Pu.mp Operating Speed 19.75 Hertz Page Pump Column 'Transverse 22.75 73.99 228 1148 15 Vertical 58.1 19 Linesha.ft Transverse 61.2 25 Vertical 106 24 Sha.ft Tube Transverse 29.6 27 Discharge Head a.nd Motor Transverse 47.8 720 17:35 6 Motor Transverse 177 4
("
MATERIAIS AND srRESSES Allow. (J) Cale. ( ) Margin (1) Cale.
location Material Stress Stress 2
- Page Head - Motor Assembly Motor Mounting Bolts A J6 14,.500 956 14.2 8 Baee of Head SA516 Gr. 70 17,500 166) 9 *.5 29 Head Mounting Bblts* SAJ25 20,200 7J.54 . 1.75 29 Discharge Hozzle Flange SA516 Gr. 70 17,500 12,652 .JS JO Flange Bolts N. F. 26,290 JO Sole Plate A )6 14,.500 2820 4.14 J)
Anchor Bolts N. F. 7094 32 Pump and Column Aeeembly Flange (Sta. 4) SB148 CDA 9.54 18,900 S4JJ 2.48 2)
. Flange Bolts SB164 Gr. 400 ,54,000 (4) 1,5,69J 2.45 2J Column Pipe SB 169 CDA .614 18,000 .517J 2.48 2J Discharge Case Flange SB14J-2A 8500 614J .JS 2J Line shaft K500 Monel 21,000(.5) 1),728 .53 26 Shaft Tube SB14J-2A 8500. 121 69.2 27 lotest 1* U---gi* 1 d r1 ed Allowable Stress - 1 ncu.* n s e n as Calculated Stress
- 2. Calculated Stress is at DBE and includes operating, nozmle and seismic loads.
), Allowable Stress is at OBE unless noted.
H
- 4. Allowable Strees at Il3E H
,5. Based on )<>'IC of Y.S. per ANSI B58.1. As this is not a pressure boundry, margin is based on operational criteria only.
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