ML20003H194
ML20003H194 | |
Person / Time | |
---|---|
Site: | LaSalle ![]() |
Issue date: | 04/24/1981 |
From: | SARGENT & LUNDY, INC. |
To: | |
Shared Package | |
ML20003H190 | List: |
References | |
029929, 29929, NUDOCS 8105050305 | |
Download: ML20003H194 (235) | |
Text
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C A~D CD3 ..N T C L U N D Y s INTER-OFFICE MEMORANDUM Frcra JJJ2mappan - 30 x6773 Date April 24. 1421 Dept /D.i. Mechanica1 Mngineeri ng hchanic-n g m. w m. 4266 /4267 /6n9 3-00 File k. RMn-024924 Page N . 1 ~n F 1 Gient CECO h T.a S a l l e t'n n n y
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Subject __ _ Equipment Ou-lification - Poe:t Audi t NRC Doct'=antati nn (Vol.6) To: ~ D. C. Haan - 21 (1/1) J. B. Gouvas - 31 (1/6) CC: EBB /AEM/JS - 30 - M. M. Hassaballa - 30 - " EMD File - 30 Attached is the updated progress report on SQRT open items to be transmitted to NRC. The SQRT forms for the completed items since our last submittal dated 3/10/81 are also included. I am sending si:: copies to J. B. Gouvas for distribution to CECO and
'( NRC.
If you have any questions, please call me. .
. . A -
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SARGENT & LUNDY
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LA SALLE COUflTY NUCLEAR STATION - UNIT-1 , COMONWEALTH EDISON C0iiPAtlY
~
SAFETY-RELATED EQUIPMENT QUALIFICATI0fl POST NRC AUDIT DOCUMENTATION 8 - BY l _ _ - . t . ENGINEERING MECHANICS DIVISION SARGEtlT & LUllDY ENGINEERS 4-24-81 I d e
- EliD FILE /!029929 i
nQ SARGENT & LUNDY C\ ENGINEERS CHIC AGO
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LASALLE COUNTY NUCLEAR STATION - UNIT 1 EQUIPMENT QUALIFICATION POST NRC AUDIT DOCUMEhTATION TABLE OF CONTEhTS Updated List of Open Items. O . . . . . . . . Tab.A SQRT Forms for Recently Completed Items .. Tab,B 9 5 e i I O f i
SARGENT O LUNDY i EN GIN EERO cmeAso . O)
. List Of Open Items A. BOP Equipment
- 1. 6.9 Kv Switchgear
- 2. 4.1 Kv Switchgear
- 3. Primary Contairment Hydrogen and Oxygen Monitoring Panels
- 4. 250 V.D.C. Dist.. Equipment B. NSSS Equipment
- 1. Pressure Switch
- 2. Level Indicating Sw! ':ches
- 3. Vaccum Switches
- 4. Square Root Converter
- 5. Flow Summer
- 6. Transducer Power Supply
- 7. Hydraulic Control Unit
- 8. Solenoid Valve
{}- w 9. 2" Globe Valve
- 10. Valve Preamplifier
- 11. WRM-MSV Startup Intermediate Range Monitor
- 12. PWR Neut Monitoring Instrw=ent
- 13. Indicating & Trip Unit
- 14. Ing. Rad. Monitor
- 15. Sensor and Converter
- 16. Flow Switch
- 17. Pressure Switch
- 18. Temperature Element ~
- 19. Time Indicating Switch
- 20. Flow Transmitter
- 21. RCIC Turbine
. .22. Time Delay Relay
- 23. Contractor 'GE' Model CR105/205
- 24. Switch
- 25. CDF Relay
- 26. LJCV Relay
- 27. CEA Relay
- 28. HEA Relay O
O ASALLE COUNTx,&2 Q V Pag
'roject # 4266-10/4267-10 NSSS EQUIPMENT Q:fALIFICATION Rev. 3 _
LIST OF OPEN ITEMS .- . Date 4-247981 A EQUIPMENT DATA QtfALIFICATION/ ItE:: ARKS ITEM REQUALIFICATION No NUMBER NAME LOCATIn" STATUS Analysis completed Main Steam Supply R e-Documentation completed. Completed,
- l. 321-F013 6X10 Relief Valve ' CROSBY' ,x SQRT Forms completed.
Model # llB65-DF ,
# 22A6441 B21-F022 Main. Steam Isolation . I'tegion Ana}y' sis completed.
2 & 26" Globe Valve 'Rockwell' PC-5 Documentation completed. B21-F028 1612 JMNTY SQRT Forms completed. Completed.
#'732E 150K i Mounted on Existing Test Report not OPEN.
- 3. 164C5359 Pressure Switch 'Barksdalo' Local Pand. adequate Retesting in Reactor scheduled.
i Model# BIT-M128S Building - I T 4 159C4383 Level Ind. Trans. Switch
'lTT Barton' Model # 760'
- 5. 159C4445 Level Ind. Switch "Yarway' Model # 4418C --
j -- Vacuum Switch 'Barksdale' " 6 163C1855 " -- Model # D1T-ill8SS -- -- l 145C3046 ,
- ,k l j f ll 4
LASALLE COUN1 )&2 Project # 4266-10/4267-10 O NSSS EQ IPMENT QUALIFICATION r/lz RcI.~ 3 LIST OF OPEN ITEMS Da '.e 4-24-1981, EQUIPMENT DATA QUALIF'ICATION/ ItEMARKS ITEM REQUALIFICATION No NUMBER NAME LOCATION STATUS g 7 B33-K606 A/D Square Root Converter # 136B3051 Hounted on Existing Test Report . OPEN A Panel Retesting scheduled. B33-K608 A/D Part of Flow Unit # 791E392 ill3-P608 not adequate , Aux. Bldg. El.768'0" . w B33-K607 Flow' Summer 8 AAB # 136B3088 Port of Flow Unit -
# 791E392 -- -- --
Transducer Power Supply '
# 136B3058
- 9. B33-K610 Part of Flow Unit '
# 791E392 i -- -- --
i i
! Region ' Additional Analysi's in -
f 10. Cll-D001 Ilydraulic Control Unit l RB-8 Progress OPEN El. 740' * ' ( h L 11. Cll-F009 Solanoid Valve 'ASCO' Region Existing Test Report OPEN l Model # IIT 832322 ; RB-5 not adequate Retesting scheduled.
! # 21A9317AC '
q . h
- 12. Cll-Foll 2" Globe Valve, ,
# 21Al?50 P002 -- 'llansne l Dahl' with NEMCO l
Limit Switch SL-3C-Il2 .
, ACF/WKM Actuator # So2 -
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l g
'P2 5 '.ASALLE COUNT &2 '
Rev, 3
'roject # 4266-10/4267-10 NSSS EQUIPMENT QUALIFICATION __
4-24-1981, LIST OF OPEN ITP.MS Date QUALIFICATION / RynARg3 EQUIPMENT DATA REQUALIFICATION No NUMBER NAME LOCATION STATUS Itegion Requalification completed. Documentation completed. Completed. Valve, Guide Tube PC-1
- 13. C51-J004 SQltT Form completed.
'GE' # 136111302G002 # 175A9755 Voltage Prenmplifier . On Local New testing to be done OPEN 'GE' # 163C1263AA Panels
- 14. C51-KOO2 A/ll ll22-P030, Retosting Model # 828E309AA '
scheduled 31, 32 & e 33 . I . CR-1 WRM-MSV Startup . Intermediate Range Monitor on Pancis "-
- 15. C51-K601 A/II --
'GE' # 368X102AA Ill3-P635 Ill3 -P636 .
x I e i C51-K605 PWR Range Neut. CR - 1 "
- 16. ' --
[ Monitoring Instrument On Panel . h A/II, J/N, - li13-P608 R/Z lixisting Test Report not
- 17. 129B2802 Indicator & Trip Unit 'GE' CR-1 " "9"" --
Ill3-P635 ' l
- Ill3-P636 I,og. Rad. Monitor 'CE' 1 l ,, ,, , -
# 23HX660G007 ,,
18 D18-K610 A/D . M'odel # 807E228 . j -
- a
SALLECOUNrh2 . Pagh4 roject # 4266-10/4267-10 NSSS EQUIPMENT QUAI;7ICATION Rev. 3 LIST OF OPEN 1TEMS Date 4-24-1981 EQUIPMENT DATA QUALIFICATION / REMARKS ITEM ; REQUALIFICATION No NUMBER NAME LOCATION j STATUS Local. Existing Test Report t OPEN
- 19. 194X9276016 Sensor &' Converter 'GE' Mounted adequate Retesting scheduled Region RB-2 El.790'
- w Reactor Analysis completed.
- 20. E12-C002 A/C RilR Pump / Motor . .
Bldg. Documentation complated. Comple ted.
# 21A9243CL Elb73'4" SQRT Forms completed, t ~
- 21. 145C3008 Flow Switch Mounted Existing Test Report not' OPEN ITT 'Barton' On Local adequate Retesting scheduled Model # 289A ,
Panels
- 22. 159C4606 Pressure Switch "
" " ~ 'Barksdale' -- -- - -- . Reactor Analysis completed
- 23. E22-C001 IIPCS i amp & Motor Bldg. Documentation completed.
'Ingersol Rand' E1.694'0" SQRT Forms completed.- , Completed . # 21A9243CK i
E22-S004 , Aux. Bldg. ' Review completed. . 24 SWCR Elec. Metal Encl'sure o El.687' ] Documentation completed Completed.
. SQRT Forms completed.
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__-_____________-___________y_________________________________________- SALLE COUNT 62 Pag oject # 4266-10/4267-10 NSSS EQUIPMENT QUALIFICATION Rev. 3 LIST OF OPEN ITEMS Date 4-24-1981 EQUIPMENT DATA QUALIFICATION / ILEMARKS ITEM -- REQUALIFICATION No NUMBER NAME LOCATION STATUS En;. Gen. For llPCS Sys. Aux. Bldg. Completed.
- 25. E22-S001 # 21A1872AB E1.768' Addit.lonal Analysis done. Completed.
Documentation completed. SQRT Forms completed, l_ .
~~
Locally Additional testing is .0 PEN 26 145C3224 Temp. Element mounted on planned Retesting
'PYCO' Walls . scheduled. # 102-9039-11-00102 Exiating Test Report uot
- OPEN~
- 27. 145C3043 Time Ind. Switch Mounted on adequate Retecting
' ENGLE SIGNAL' Local
- scheduled.
# lips '
i Pancis -
}
163C8338 Flow Transmitter Local .
- 28. ' S&K Inst.' mounted on Additional testing in planned OPEN
# 20-9651-8551 Pipe Retesting scheduled.
I W i . Flow Transmitter Mounted on
- 29. 163C8339 S&K Ins t. ' , local --
Il 91X-16-4-20 Panel - , il22-PO73 t l h itcactor l New Test Report Received.
- 30. E51-C002 RCIC Turbine .,
# 21A9201 AV 8* - l Review Under Progress OPEN Terry Model # GS-2 El 673' l .
s.
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I l 4 l O \SALLE COUNT L i&2 fL Png - Joj ec t # 4266-10/4267-10 NSSS EQUIPMENT QUALIFICATION Rev. 3 LIST OF OPEN ITEMS Date 4-24-1981 EQUIPMENT DATA - QUALIFICATION / It10!ARl'S ITEM REQUALIFICATION-No NUM11ER NAME LOCATION STATUS F21-E003 Refueling Platform Equipment Refueling Analysis completed. Completed. 31.
# 762E897G001 Floor Documentation completed.
843' SQRT Forms completed. l -
. 1[ocal Analysis completed.
- 32. 145C3227 Flow Element mounted Documentation completed.
Vic. Simms/ Daniel SQRT Forms complet,ed. Completed. t' Time Delay ' Relay.'CE' On Main Retesting scheduled. OPEN
- 33. 145C3035 Model # CR2820 Control Retesting scheduled.
Panels -
- 34. , 145C3209 Contractor 'GE' " "
Model CR 105/205 .
- 35. 145C3230 Switch ' Cutler llammer' "
Model # 10250T -- -- p
- 36. 163C1166 Test results obtainpd from GE Test procedure adequate.
CDP Relay -- l Requested Test Report from GE ,OPEN
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_ ,U S L MOCI l QI _ EL S t S S N E M A A N y y T a y A .l a l a D e l R e e T R R N V . E C A A . M E E 0 P J I C H 1 I
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ASALLE COUNTL j 2 O O U Pags roj ec t # 4266-10/4267-10 LOP EQUIPMENT QUALIFICATION Rev. 3 LIST OF OPEN ITEMS Date 4-24-1981, . EQUIPMENT DATA QUALIFICATION / REMARKS ITEM REQUALIFICATION No NUMBER NAME LOCATION STATUS E51-D300 E12-D301 A/C Suppression Pool Suction Strainers Reactor Comple ted
- 1. E21-D302 Cont. Documentation completed Completed E22-D302 E1.735'0" SQRT Ferms completed
~ Aux. Bldg. AP02E 6.9 KV Switchgear El.710'6" a) Basic Switchgear 2 APOSE ITT Imperial Corporation' Reactor Qualification completed Open AP09E El.786'6"& b) Some device qua,lification AP01E 820'6" pending T Aux. Bldg. 3 APO4E 4.16 KV Switchgear El.710'6"A AP06E ' ITT Imperial Corporatien' 731'6" -- Open 4 Several IAV overcurrent Relay 'GE' On 480 V New test completed. Model Il 121AC60B13A Subs ta tions Documentation completed. Comple ted Aux. Bldg. SQRT Forms. completed. ,
; El . 710 ' & 731 TRS yet to be received but we witnesced the test.
IAC overcurrent Relay ' CE'
- 5. Several Model # 121AV69AIA l -- --
6 Several Potential Transfouuer 'GE' - Model JVP-1 -- -- i
O /~'i . gE V LASALLC COUNi M &2 . Pcge Project # 4266-10/4267-10 DOP EQUIPMENT QUALIFICATION Rsv. 3 LIST OF OPEN ITEMS Dato 4-24-198L . EQUIPMENT DATA QUALIFICATION / REMARKS ITEM RE']UALIFICATION No NUMBER NAME LOCATION STATUS On 480 V New test completed. 7 Several JAll-O C.T. Substations Documcota tion completed. Completed
'GE' Aux.Hldg. SQRT Forms completed.
837 X 62 El.710' 4 TRS yet to be received but we 731 witnessed the test. New Test completed.
- 8. Several Circuit Ilreaker Documentation completed.
'GE' KA - 2A-50 --
Completed SQllT Forms completed. Electronic Operator
-i
- 9. Several Circuit lire ake r
'GE' KA-2A-25 Electronic & Mechanical > -- - -
Completed Operator i 250V.D.C. Dist. Equipment Reactor New test scheduled for *
- 10. DC06E ' SYSTEMS CONTROL CORPollATION' Ill dg. 5-7-81 694'6" OPEN I
f g* y,,g y, l'r fana ry Con t . Vent. Deleted from List as nut Supply Fan , Safety Itclated Closed VP02Cn JOY MFC.CO' -- Iteac t or Test lieport for Ilydrogen Pl.763 Pri. Cont. llydrogen and Oxygen Bldg. m1yn'r received. Waitig for
- 12. PI,77J monitoring panels g y ,0" the panel test report. OPEN I
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j 1 4 I-SQRT Forms For Recently Completed Items
- 1. Main Steam Supply Relief Valve - B21-F013 ~ -
- 2. Main Steam Isolation Valve - B21-F022 & B21-F028
- 3. Valve, Guide Tube C51-J004 .
- 4. RHR Pump / Motor #21A9243CL, E12-C002
- 5. HPCS Pump & Motor E22-C001
^
- 6. Switchgear Electrical Metal Enclosure E22-S004 O 7. Suppression Pool Suction Strainer E51-D300 l
- 8. IAV Overcurrent Relay 'GE' Model #121AC60B13A 4 9. IAV Overcurrent Relay 'GE' Model 1121AV69AIA l 10. Potential Transformer 'GE' Model Model #JVP-1
- 11. JAH - Overcurrent Transformer 'GE' #837 x 62
- 12. Circuit Breaker 'GE' KA-2A-50 Electric Operator
- 13. Circuit Breaker 'GE' KA-2A-25 Electrical & Mechanical Operator
- 14. Air Cleaner / Filter (Part of E22-S001)
- 15. Exhaust Silencer - E22-D308 (Part of E22-S001)
- 16. HPCS Diesel G'nerator e Control Panel (Part of E22-S001)
- 17. Refueling Platform Equipment - F21-E003 0 .
l
I
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i LA SALLE NUCLEAR STATIONS' g UNIT 18 2 NSSS EQUIPMENT QUALIFICATION
SUMMARY
EQUIPMENT NAME : Main Steam Safety Palief Valves EQUIPMENT NO: 1,2B21-F013A/H, J/N, P, R, S, U, V LOCATION: Primary Cbntairment EQUIPMENT CLASSIFICATION: @ ACTIVE ] PASSIVE QUALIFICATION METHOD: j Test i CUALIFICATION DOCUMENT
REFERENCES:
1
; 1. Summary of accelecations and nozzle loads from G.E. piping analysis Inter-Memorandum of acceptability of S&L piping analysis 2.
f
- 3. List of References
[
- 4. Specification 22A6441
- 5. Project Sheet, G.E. VPF#921D886F, Sht. No. 1, 2& 3
- 6. Test Report, Wyle Iab. Report #43445-2
- 7. Drawings, Crosby Dwg. #DS-A-63790, Sht. 1, 2& 3 f
- 8. Data Sheet, G.E. Doc. #386HA603
- 9. Analysis Report & Addendums, Crosby Comp. Report No. 3012 (GE VPF#3097-67-2) (or EMD #002533)
Ig LOAD COMBINATIONS CONSIDERED IN QUALIFICATION:
- 1. Normal Operating Loads + OBE + SRVASY-TQ + SRVALL-TO ENVELOP j 2. Normal Opera ting Loads + SSE + COLEVY-2+ b ASY-TO + SRVALL-TO ENVELOP
- 3. Normal Operating Loads + SSE+ Chugging + SRVASY-TQ+ ALL-T ENVELOP
- 4. Normal Operating Loads + SSE + AP l 5. Normal Operating Leads + SSE + COLEVY-1 I
h y OUALIFICATION: l ([(p Date g22M/ 4/ PREPARED BY: Date SARGEilTa LUT10Y j REVIEt:ED BY: i AF ?RC'/ED Y: Date *~2.2Elo c ! g
l. 4 g V QUALIFICATION
SUMMARY
Seismic Qualification Method:
- 1. Resonance Search Conducted in each of the three principal axes with a low level (approximately 0.2g) sine sweep from 1 to 40
~
Hz at a sweep rate of one octave per minute. ,
- 2. Specimen subjected to 30 s :s ., d duration. biaxial phase incoherentt random input consisting of frequency band widths spaced one-thirdt octave apart over the frequency range ~l to 40 Hz.
- 3. The ampiitude of input was independently adjusted in each direction until TRS enveloped the given RRS.
- 4. During the entire testing, inlet and outlet flanges were subjected to 400000 and 300000 inch-pound moments respectively.
- 5. Five OBE tests and one SSE test performed in each biaxial plane.
f) 6. Extended load tests were conducted similar to above tests with the following modification. a) Inlet and outlet flanges were subjected to 800000 and 600000 inch-pound moments respectively, b) SSE test durations are 15 sec. each.
- 7. Valve was tested for operability during the entire seismic l
testing. 1 i 1 SRV Requalification Method: Loads resulting from the analysis of the piping using the hydro-dynamic laod combinations will be limited to the laods to which the valves are qualified. l l dBt l Ref: EMD File No. SARGEUThl0HDY b
-- z _ _. __ .~.,~,-.g
Qualification St : arf of Ecuirrent f') I. Plant tisre: LaSalle Cesunty - 1&2 g a
- 1. Utility: Commonwealth Edison Co. M
- 2. NSSS: General Ele m ie. M X
- 3. A-E Sargent & Lundv l
II. Ca:ponent tire Main Steam Safety Relief Valves ll
- 1. bbdel NL=ber 6xRx10 HP-BP Quantity: 23
- 2. Verdor General Electric ch /m+.- m'. c e Gace Co.
,i ,
i t
- 3. If the ccrponent is a cabinet or panel, nare and rodel ?b. of the devices incitried: -
[ t.
- 4. Physical Description a. Appearance Relief Valve
,f
- b. Dinensions Inlet - 6", Outlet 10" I
)
i i
! c. Weight 2800 lbs.
l-o) ( 5. Iccation: Building: Primarv Containmont E I
~
Elevation; On Main Stean Pininc_ syster _ i I,;
- 6. Field > bunting Conditions [ ] Bolt (!b. , Size )
l [ ] Weld (Length ) h j iX} Pine tbunted j l
- 7. Natural Frequencies in Each Direction: j i,
hl: 20, 2?.5 h2: 22.5 V: none below 40 Hzljl l
' p l 8. a. Functional
Description:
Provideautomaticdepressuril t zation of the reactor vessel and relief pressure discharce to the sucaression cool via a closed ! I discharge pipino path i b. Is the equipnt required forI hbt Standby [ } Cold
! Shutdown IM MG i ; 9. Pertinent Peference Design Specifications: _ I G.E. Spec. E22A6441 V d Feference: D O File ?b. SARGEllTi . ~a,~LUi!DY n n.a hIf '- - _ _ - - ._ mm._ _ , _, , , _ __ . __,,_,__., _ ; ,,g
III. Is Equignent Available for Inspection in the Plant: [X] Yes [ ] No . f') Ca ments: v . IV. Equignent Qualification Method: Test: X Analysis: Canbination of Test and Analysis: Test by: Wyle~ Lab.Recort e43445-2. dated 1/12/77 (name of Ccrpany or laboratory & Feport !b.) ? i r V. Vibration Input: I
- 1. Ioads considered 1.[ ] Seismic only 2.[ lHydrodynamic only 3.[] Explosive only ;
4.[ ] Other (Specify) 5.[X](bcbination of 1 & 2 ; l 1 j
- 2. Requiral Response Spectra (attach the graphs):
l See attached Tables s
- 3. Required Acceleration in Each Direction: See attached Tables {
i V= O a > c hl = h2 = VI. If Qualification by Test, then Cmplete: , 8 1. [ } Single Frequency [X] Multi-Frequency l l
- 2. [ ] Single Axis [X] Multi-Axis s
- 3. Frequency Range: 1 to 40 Hz j g
i
- 4. TRS enveloping RRS using Multi-Frequency Test [3] Yes (Attach TRS grapbs j See attached Tables [ ] ?b
- 5. g-level Test at hl = h2 = V=
. 6. laboratory bbunting: Specially designed modular fixture to apply nozzle loading
- 1. [ ] Bolt (?b. , Size ) [ ] Weld (Inngth )[ ]
W
] ?b [ ] ?bt Applicable I 7. Functional op3rability verified: [X] Yes 6
( 8. Other tests perforTned (such as fragility test, including results) gs Resonance Search test. l L. ] SARGEijT " LUNDY Peference: DD File ?b. _ :ENO:NEEpsJ b l e
.._,1 ._ = -- - Mw1T : . r . ,_ :_=---*=rymm W -)-r _ ---_--.-+- _-- 7==y vw~m *,3 w xxs r v- 1- --_-*'"*K ~ r 2 g
n VII. If Onlificatica b/ k.31ysis or by the Orbiratica cf Test arxi kalvsis,t.M i V Qxplete: N/A
. 1. Description of Test ixltziing Results:
- 2. ttthod of kalysis:
[ ] Static Arulysis [ }Egaivalent Static kalysis [ ]Dyra-ic $ A:ulysis l [ ]T1:ae-Fa.storf [ ] Pes;cnse Spectr:
- 3. Ptxiel Pipe: [ ] 3D l ] 2D [ llD 5
A [ ] Finite Ele: Tnt [ ] M [ ]Cicsed Fcr= Solution,Y
- 4. [ } Corputer Codes: 1 FreqJency Fange and !b. cf rn% considered: 6
[ ] Hand Calculaticas
- 5. Ca. pina:
- 6. Sugort Ccnsideraticas in the incxiel: 4 -
O 3
- 2. Cri 1cet strmeturei z1emnts: Co ern1ng Seismic ecce1 stress I@ntification location Fes;rnse 07.biratien Stress Stress Allcu'llej 1
t A. I I I r I Effect U;cn Ft::rticral l l B. P'ax. Deflection location Cn2rability f 1. I 1 1 1 I i t O ' < i 1 Forereme: en rite in. -s- ! SARGENT LUNDY a, . E %QiN g g sa a. 4 i
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- } REQUIRED RES?C
- iSE SPECTEUM FOR 'mE t-QUAI.IFICATION "'EST -
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- s. QUALIFICATIC:i TEST 4 .
E b e t .
I Pr.ge m. 49 I Report re. 41445-2 i FULL SCALE S*-iOCK SPECTRUM (g Peak) s . s ~ 1.0 O to 0 ~ 100 B 1000 O r - i DAMPING 2 %l
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y *, , .___. H i
!-+
e + - ,- +--t ;; - D
; ; i-+ H ' ;iH
- g. 6 _.-.-_._'_..____;_-_m_._..m.,- __
+-
_....-_.___,mm.-_._ i ! 2-l l t ia o
-+
_2 _ _.._.. = = :::: _
-t__a t : z_..___2_-_ --- = = --
_=
, _ r_g , .
__=__ 8h
- 1.__.t 62: e >
3__.___.
-t a ..
f-
;. t % ,.
{- p) ; - i; : . Ei-i:; .. _ _ . _ _ , >
; 1 t_ -; ^ i . . + t p
s _. , _ -
.. _., i ^
g 8 ._ _ _...
. .;.; ; m . . _._ _ - - . _. . .4 =.=.5._-. _ _.== y_ r_ .- _ . : : : _ _ . __ m_ _. = _. _ - .
m -,-- eg _ .__; __ - .i, =_=r_ _ . =_.: =_ _- :1 ._.
% s> ___ t _-+- t-r- = -
_.1 - 3.____. _____ _ __ _ . _ ._._._- .
. _. _.2:_:. r -__ -----_-- _. -1 . . ;___. - ._p, ~;
i
.byu ,
y_t_ __g
; 4__ .t. : , ---*- 1- :- , , , , . ,i ,v + ---H r . =
I 2 3 4 5 6 7 8 9 to 2 3 I 4 5 6 7 e 5 :S 2 3 4 5 6 7 9
, 1 10 100 1;;
Frequency (Hz) ,
~
gyg5 dc"G /tMe r-
- t.OCATION NO. ICA TEST RUN NO. I / fl
l SARGENTO LUNDY ENGINEERS CH 6CAGO O !
^ \
Summary: Accelerations (g) Allowables (OBE/SSE) Actual (Faulted) from Ref. (A) Ref. (B) Ref. (C) Horizontal' OBE/SSE Pipe Lines (Longitudinal) 4.8/5.2 Line A Line B Line C Line D (Lateral) - 4.5/5.2 or (Resultant) 3 6.6/7.3 2.8 2.9 2.6 2.7 Vertical 2 3.2/4.4 2.5 2.2 1.6 3.2 1
References:
(A) Qualification Report (GE VPF #3097-67-2,i.e., Ref. #10) l (B) Test Report (Wyle Lab. Report #43445-2,i.e., Ref. #7) l (C) Diping Analysis (GE Report, Table 16, See page 2/5) l U
f. i SARGENT O LUNDY ENGINEERS CHICAGO { Equipmeut No. Inlet Pipelino Outlet Pipeline Reducing Flange B21-F013N. 1MS0'4AN8 1MSO4BN12 C307LS (Yes)- B21-F013L 1MSO4AL8 1MSO4BL12 B21-F013R IMSO4AR8 1MSO4BR12 B21-F013E IMS04AE8 1MSO4BE12 B21-F013C 1MSO4AC8 1MSO4BCl2 B21-F013U 1MSO4AU8 lMSO4BU12 B21-F013G 1MSO4AG8 1MSb4BG12-B21-F013H 'lMS04AH8 1MSO4BH12 B21-F013A iMS'04AA8 1MSO4BAl2 B21-F013V , IMSO4AV8 1MSO4BV12 B21-F013P 1MSO4AP8 1MSO4BP12
^
B21-F013J 1MSO4AJ8 1MSO4BJ12 B21-F013B 1MSO4AB8 1MSO4BB12 B21-F013M IMSO4AM8 1MSO4BM12 B21-F013S IMSO4AS8 1MSO4BS12 B21-F013K 1MSO4AK8 1MSO4BK12
- B21-F013F 1MSO4AF8 1MS04AF12 . B21-F013D IMS01AD8 1MSO4BD12 . . . . _ _ _ . _ _ - _ . . 1 r
G k o 5 o
...--.._.-m ie
CARGENT O LUNDY ENOINEERS CHIC A33 O LOADS COMBINATIONS Nozzle Loads from Ref. # (A) pg. 5 and pg. 19 Allowable Nozzle Inlet Moment = 800,000 in-lbs m (From Test Report) Outlet Moment = 600,000 in-lbs Nozzle Loads from Ref. # (B) for SRV Inlet / Outlet Actual Nozzle Inlet Moment = See Table (I) on pg. 8/9 Ioads (Fron GE piping analysis) Outlet Moment = See Table (II) on page 10/11 O 94 0
CARGENT Q LUNDY ~ EN GIN E E RO CHICA2O INUT Real Nozzle Loads from Ref. # '(C): TABLE (I) Valve Service Fg F B C A B "C R l No. Level (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) (in-lb) B21-F13V Node =043 D t s,7 13945 13922 277812 405225 305159 578,367 l B21-F13P Node =053 D 13736 13540 15101 174034 361214 563180 591,328 B21-F013J Node =063 D 11394 10284 10711 103643 317959 332636 471,685 B21-F013B Node =073 D 13900 10462 13544 281070 317967 312969 527,307 B21-F013M Node =043 D 9424 15811 9808 184201 386511 286755 515,314 B21-F013S Node =048 D 13162 13184 10212 158435 265598 329223 451,699 B21-F013K Node =053 D 10897 8641 7555 103559 194994 222736 313,621 B21-F013F Node =058 D 10857 13242 9098 165623 201923 266100 372,845 i B21-F013D Node =063 D 11103 12546 1233.8 169473 290317 219112 401,267 l B21-F013N ' Node =043 D 12012 15509 11849 181538 495736 433673 683,215 B21-F013L Node =048 D 7364 11092 11883 168334 329556 267129 456,401 B21-F013R l Node =053 D 10895 12240 11123 143726 277568 330085 454,596 B21-F013E Node =058 D 11747 12295 10695 180198 267072 267356 418,790 l udl-F013C i Node =063 D 9699 7901 10145 77076 314086 209235 383,188
t
~
CARCENTO LUNDY I GNOINEERS I cmcaso t I !
- l Real Nozzle Loads from Ref. # (C) : TABLE - (I) -
(Continued) Valve F Service Fg B C A b C k No. Level (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) (in-lb) B21-F013U Node =043 D 11703 10/68 9728 173654 222496 342012 443,433 2 B21-F013G . Node =053 D 11468 10339 8597 150376 270693 342281 461,567 l B21-F013H Node =063 D 12776 9992 8853 158646 229880 354938 451,657 B21-F013A Node =073 D 10959 11762 13098 167935 226223 404423 552,092 O All M R listed above are less than the allowable moment, ! the inlet flange is qualified at Service Level'C & D i . o I 1 l i j O
CARGENT Q LUNDY
- ENGINEERG CMICA39 ObTIIT Real Nozzle Loads from Ref. # (C): TABLE (II) 6 Valve Service F F "
B C A B C R No. Level (lb) (lb) (lb) (in-lb) (in-lb) (in-lb) (in-lb) B21-F013V Node =300 D 3679 3562 4615 95903 377462 250763 463,203 B21-F013P Node =200 D 3972 7200 2298 183083 155122 461648 520,289 B21-F013J Node =400 D 6371 4915 905 38396 90406 346851 360,544 B21-F013B Node =500 D 8684 5212 3778 49070 292444 380450 453794 B21-F013M Node =100 D 2492 4151 2549 244894 152665 192699 347,005 B21-F013K Node =200 D 2351 6662 2265 67746 92782 263714 287,651 B21-F013S D 3480 7397 4236 124282 100686 270709 314,431 g[de=300 B21-F013F Node =400 D 1454 6689 1255 41533 69991 179821 291,417 . B21-F013D Node =500 D 922 4697 2777 93721 137450 224696 279,579 B21-F013N Node =100 D 2228 6769 4632 345836 154369 198407 427,548 B21-F013R Node =200 D 3416 9447 2784 114386 139553 234414 295,819 B21-F013L Node =300 D 1848 6707 2255 86330 120987 334202 365,774 B21-F013E Node =400 D 3991 ,7125 29S3 97192 151797 279692 332,741 B21-F013C Node =500 D 10970 4276 2204 41098 69844 201529 217,212 B21-F013U Node =100 D 3470 3351 2884 102556 140114 334233 376,672 "21-F013G 3134 3796 2292 89102 124125 386407 415,519 _,1de=200 D B21-F013H Node =300 D 3837 5474 1819 71128 150616 389931 424,017 B21-F013A Node =400 D 3195 9192 1846 74435 156798 402662 438,478
t CARGENT O LUNDY
- i E N GIN E E QQ g CHICAGO i i
s Summary of Pipino Lines: (From P&I Diagram of LaSalle Station) Qualification of Inlet / Outlet Flanges: (I) Inlet ( A) / Outlet (B) Nozzle Load Allowables at Service < Level C & D (A) Inlet Nczzle Load Allowables Inlet flange studs: Material = SA 193 Gr. B7 Size = l-3/8" - 8UN-3A . Stress Area = 1.2319 in (Mark's Handbook, page 8-13) No. of Studs = 12 i Diameter of Bolting Circle = 12-1/2 (Forged flange 1500 lb.B16.5) Total Stud Stress r eca = 12 x 1.2319 = 14.7828 in 2 Per NC-3658.3, for flan,u bolting material which has an Sm value at 100*F, not less than 20.0 ksi may be analyzed
'( ) as following:
Mfd < (ll,250A b - (x/16)D f Pfd)C (Sy/36) for Service Load C& D where S = Yield Stress of flange material at design temperature (SA105 Gr B) (585'F, Sh.#13 Specification) = 26.6 @ 600*F per Appendix j Table 1-2.1) C = Diameter of bolt circle = 12.5 in l A3 = Stress area = 14.7828 in D f = Outside diameter of raised face.= 8.56in (See Ref. attached) 1 P fd= Pressure concurrent with Mfd = 1375 psi Therefore, M fd 1 11250 (14.7828)-(w/16) (8.56) (1375) , (12.5) (26.6/36) = 1,353,312 in-lbs . l
= Bending or Torsional Moment including
() dynamic loads.
-- . _ _ . . , . _ , . - .,m_ , .._ , . . . . . , . , - , , , , , . - . . . .. _. ..--,._m , ,r.- - - _ .
~
CARGENTO LUNDY I ENGINEERO l CHICAcm i l> (~) _(B) Outlet Nozzle Loads Allowable: Outlet flange studs: Material = SA 193uGr. B7 Size = l-8UNC-2A Stress Area = 0.606 in No. of Studs = 16 Diameter of Bolting Circle = 15-1/4 in 2 Total Stud Stress Area = 16 x 0.606 = 9.696 in Same procedure as the inlet flange analysis. M fd i ll,250Ab* ('! } f P fd ( Y! } # Service Load C&D where S = 29.1 ksi (Appendix, Table I-2.1) @ 500*F. y (Specification SH.UO 14) C = 15.25 in Ab = 9.696 in Df = 12.4 in (12 inch to 10 inch reducing flange) O Pfd= 625 psi (Specification Sht. No. 14) Therefore, M fd i 11250 (9.696)
= (w/16) (12.4) (625)
(15.25) (29.1/36) = 1,112,036 in-lbs. To analyze the flange under Service Level A & B, the procedure of NC-3658-3 can be applied: (II) Inlet (A)/ Outlet (B) No.'.zle Ioad Allowables at Service Level A & B. (A) Fcr inlet flange at Service Level A & B M fd 6250 (26.6/36) (12.5) (14.7828)
= 853,347 in-lbs = Allowable torsional or bending moment Compare the actual nozzle loads of Service Level D which are tabulated in Table (I) to the allowable given above for Service Level A & B. All acturial resultant moments are less than above allowable. Therefore, the inlet flange
(') meets the requirement per NC-3658.
- . .. ~. . - - . ._ . . ~ '
I CARGENTQ LUNDY I t
- ENGINEERS I CHICAGO
, (B) For outlet flange at Service Level A & B M
fd ( ' ' ! ( * ' ( ' '
= 747,021 in-lbs ,
l All loads of Service Level D are less than the Service Level A & B allowable given above, the i outlet flange is qualified. 1
Conclusion:
I The GE piping analysis nozzle loads are acceptable. - l 1 l 4 s
- O r
1 l ! 2 4 O
,,,.,-...._....,,,,,_.._.,..._,..._.__,_..,,~,._.,_,,m.._..,..-4._.,..__..,..._,_,..-._,,m. . , . _ , _ _ _ . , , . . . - - _ , y - _ _ . - - - - _ , ,.
LA SALLE NUCLEAR STATIONS' i ' UNIT 18 2 NSSS EQUIPMENT QUALIFICATION
SUMMARY
EQUIPMENT NAME : Main Steam' Isolation valves EQUIPMENT NO: B21-F022A/D, B21-F028A/D LOCATION: Containment and Reactor Building EQUIPMENT CLASSIFICATION: @ ACTIVE O PASSIVE QUALIFICATION METHOD: Analysis Report and test for operator QUALIFICATION DOCUMEf1T
REFERENCES:
- 1. Analysis Report
- 2. References, see attached.
3. 4. (f.-
. s.
i 6. 7. 8. f 9. ID . 1 LOAD COMBINATIONS CONSIDERED IN QUALIFICATION:
- 1. Normal Operating Loads + OBE + SRVASY-TQ + ALL-T ENVELOP SRV
- 2. Normal Operating Loads + SSE + COLEVY-2+ ASY2 TO+ ALL-TO, ENVELOP !
~
l Normal Operating Loads + SSE+ Chugging + SRVASY-TQ+
- 3. ALL-T ENVELOP
- 4. Normal Operating Loads + SSE + AP
- 5. Normal Operating Loads + SSE + COLEVY-1 QUALIFICATION:
PREPARED BY: gh Date knk/ , REVIEUED BY: Date SfdGETMUNDY $ l
>morumansu d 4 - .c u.o j l
l, li
- \
(~h,
\s' QUALIFICATION
SUMMARY
1 l Seismic Oualification Method:
- 1. A Static Analysis has been done using high g values.
- 2. Air Cylinder bolting, yoke tube / bonnet bolting, bonnet bolting and limit switch bolting have been checked for their functional integrities during seismic events.
- 3. Take tubes, mounting flange and nozzle crotch section are analyzed for their adequacy.
- 4. Natural frequencies of upper structure are found in order to determine the flexibility of valves.
- 5. A safety factor, 1.5, is used to adjust results from static analysis for a flexible equipment.
- 6. The valve upper structure was analyzed and found to be qualified for a maximum load of 6.67g in each direction, applied at the C.G. of the upper structure.
- 7. The actuator qualification is based on a comparison to a similar 24 in. Rockwell Internation actuator assembly. A Comparison Sheet is attached. The 24 in. actuator was cualified (3 by 'a Test (G.E. test report NECE-24122-2, May 1978) . The
\# actuator is found to be adequate, ;
I ! I SR7 Qualification Method l Qualified to the new laadings taking into account hydrodynamic effects. I l I i i 9: ! Ref: EMD File No. puh-0 27$73 ! i SARGEilit LUi!DY 1 j wo.m..J
-- _ . =__3 _
i Osalification St=rarv cf Ecui: rent
/ \ \"/ LaSalle unit 1& 2 p,w .
T. Plant !a e: -
- 1. Utility: CECO IHR
- 2. 1;SSS: G.E. SG X
- 3. A-E: S&L i
l'.ain Steam Isolation Valves ,' II. Camonent th e e
- 1. 3bdel feber 26" Figure 1612 MICIcuantity: 8 l E
- 2. Vendor Rockwell International ;
I
- 3. If the w e ant is a cabinet c pa.-el, na e a-d reaal b. cf ;
the devices ir:cluded: ----- A P
- 4. Physical Description a. Ap;:erance Stop Valve j l I
- b. Dirensicns 26" long x 136.5" tall I
' I,
[
- c. Weicht Dry (16900 lbs) Wet (17900 lbs)
V 5. Imaticn: Buildir.g: Ccntainment & Reactor Building 742 ft, 746 ft. ) Elevation: : d
- 6. Field Stunting Conditions [ ] Eclt (!b. , Sina } i iX} Weld (Ir gth )
(X } #E5T StCI*U
- 7. 1:atural FreqJencies in Each Direction: l.
i hl. 25.71 h2: --- V: --- 1 i
.4
- 8. a. Functicnal
Description:
Steps the =ain steam frca running cut in case of E ercencv - - I".,l j
,0
- b. Is the egai; rent regaired forf libt Sta.cil } Cold -
g Shuti r. j f}Both j 4
- 9. Pertinent Faference D2 sign Specifications: *i
.f t G.E. Sanc_ *21?G7 7 ,
n li (m) n v , y Faference: on File 26. wt>-e21r23 SARGENT tLUNDY H ENG NCI A3_ .4
- c. ca .- n,
.,__n. - ,
M *-- - . , - - _px - - - _ _ ___ - ,. - _- ~ ,
4 V s; [y] Yes []lb i Ill. Is Ecuitrent Available for Ins ction in the Plant: g Ctrrents: (v) IV. Equirrent Onlification Method: Test: Analysis: . Ccrbination of 'Ibst a-d Malysis: y Test ard/cr Analysis bf Analysis bv Ssr e n an?o:?1 ' (na.e of Ccrpany or Iaboratory & Papert !b.) Test of Actuator dcne by Gereral Electric
- v a
f L 1. Ioads considered 1.[ ] Seis-ic only 2.[ ] Hydrodynaric enly 3.[] Explosive only ( l 4.[ ] Other (Specify) 5.!M Cxciraticn of 1&2 _ 11 I i
- 2. Pequired Pasponse Swctra (attach the graphs):
l i b High g values used for Static Analysis u
- 3. Pcquired Icceleration in Each Direction: Frtra Pipng Iralysis Ecrizcntal = 6.03 g p:),
a V= 4.7 y ( q - i 4 VI. If Omlificatica by Test, then Ccrnlete: (Fcr gerator) ] 1
- 1. [ ] Single Frcquency [yj R11ti-Frequercy )
f t' [ ] Multi-Axis (X) Dual Axis If I 2. [ ] Single ;otis G i Prequercy Par 97: 2-50 Hz
- 3. t, l'
- 4. TPS enveloping PRS using Milti-Frequency TestlX] Yes (Attach TES grad.s0
)
I ] !b f'l hl = h2 = V= ,
- 5. g-level Test at ,
See Attached Dr wire j-
- 6. Iaboratorr .* bunting:
f i
- 1. I 1 Bolt ( b. , Size ) [ ] Weld (Icngth )[ ] y 3
9 d I;
}; , 7. nmctioral operability verified: [:1 Yes [ ] !b [ ] !bt Iqplicable D
1 Other tests perfor ed (such as fragility test, including results) } j
- 8. ld u
g p Rw.anm c,nr i c4 m nm' 7 Biaxial Milti-fr m - j. 'd 'j L Valve actuator cualified for PBS. -d 1 8ANOEIIIh[UilDY hj j Pcference: CO File !b.FMD-CA ff*2) -a p.o:N a z a sL !i c--eas: 8: i , _--m m- _.-. m r.m ~ m s.- -. ,.- _ _,m , w m - --- ~ .
~
VII. If 0.nlificaticn by kalysis or by the Caciration of Test aM Malvsis,the, es O Canle*w:
- 1. Description of Test iminhng Pesults: N/A
- 2. Methcd of kalysis:
[ ] Static Malysis [x] Equivalent Static kalysis { ]&pa-lc . [ ] Fesprse Spectn= I ]Ti::n-History
; 3. Ptdel Type: [ ] 3D [ ] 2D [ ]lD
[ ] Finite Elerent[ XJBeam [ ] Closed Forn Solution 1 1
- 4. [ X] Corputer Cbdes: 097130660 0-60Hz, 3 modes Frequency Fange aM !b. of : Ides ccasidered: ,7
[ X] Hand Calculations h
- 5. Da. ping: N/A j
e
- 6. Supf ort Ccnsideraticns in the Inodel: Fivua S. 6 ef 5 /9" tel+_<- +c Mrm:.
- 7. Critical Structural Elemnts: C terning c Total S s
) i A. Identification Iocatica Pesmnse Cabiration Stress S*Jcss A11cv61e! ,
105,000
- i Energency 5,425 Operator bolting Energency 21,405 55,000h Yoke tubes " 17,899 60,000 l
'l Limit. switch bolting " 7,215 33,000 F Upper rounting flange " 45,000 69,400 Yoke-bonnet bolts " 22,319 34,950 Body-flange " 24,240 26,250 Nozzle Area Effect U:rn M.=icral Ocerability ,
B. Fax. Doflection Incation . l - l Upper counting flange Allowable = 0.820in3, 0.6475 in (20" valve) i l t ! l i ( i
,e3 4 -
3 t u peferexe; co File :6. Gmo-ogf2J SARGEHT LUNDY ! l _3_ - E NG.Na tsna $ l c z -- y f ,,e m y ,j y ,, y a -x- m_m- , x- c. , ; m_ , -. -my _. _.___p,,.,m_ _ n - --
(') v
References:
- 1) Computer Output for Valve Upper Structure
- 2) Piping Analysis Results by General Electric
- 3) Status Report for MSIV from General Electric
- 4) Data Sheet, G. E. Doc. #385HA757, dated 5/24/1977
- 5) Rockwell International, Report #RAL-2006, Rev. 1, dated 5/24/73 (Or GE VPF #3090-220-2) dated 11/16/1975
- 6) Rockwell International, Report #RAL-1002, Rev. 2, [
dated 8/14/1973 (Or GE VPF #3090-222-3) dated 5/15/1974
- 7) Specification, G.E. Doc. #21A9257, dated 11/10/1969
- 8) Comparison of 24 inch and 26 inch valves, dated 6/20/1980
- 9) G.E. Test Report for 24 inch valve, dated May 1978
- 10) Rockwell Dwg. #PD-419504, Rev. J, Sh. 2 of 7, dated 11/16/1971 (Or GE.VPF #2793-22-8, dated 1/8/1973) .
L
- 11) G.E. VPF #2793-21-8, datec 4/12/1973
- 12) Sheffer Corporation Cylinder SA-A022 (m
(_) 13) Namco Limit Switch (Catalog)
- 14) Rockwell-Edward Balanced Disk Stop Valve, page 10/19
- 15) Rockwell Manufacturing Company Dwg. #PD-422884, Rev. E, Sh. 1 of 10 (Or G.E. VPF #3090-127-5) [
- 16) Rockwell Manufacturing Company Dwg. #PD-422884, Pev. G, l Sh. 1 of 10 (Or GE VPF #3090-125-9) l 17) Rockwell Manufacturing Company Dwg. #PD-422884, Rev. H, Sh. 3 of 10 (Or GE VPF #3090-126-8)
Rockwell Manufacinring Company Dwg. #PD-422884, Rev. A, T 18) l Sh. 6 of 10 (Or GE VPF #3090-159-2) , t.
- 19) Rockwell Manufacturing Company Dwg. #PD-422884, Rev. A, y Sh. 7 of 10 (Or GE VPF #3090-160-2) i 1'
- 20) Rockwell Manufacturing Company Dwg. #PD-422884, Rev. A, Sh. 8 of 10 (Or GE VPF #3090-161-2) f
- 21) Rockwell Manufacturing Company Dwg. #PD-422884, Rev. A, i f
Sh. 10 of 10 (Or GE VPF #3090-200-2)
- 22) GE Dwg. #732E150 j,
- 23) GE Dwg. #732E150K, Sh. 1, Rev. 4 -
[' 1 1 4
~ -
- t O Refereace==
- 24) Rockwell Manufacturing Company Dwg. (SKC-100345, dated 11/30/1972 .
- 25) Rockwell Manufacturing Company Dwg. (SKD-100367, dated 4/10/1973
- 26) Rockwell Manufacturing Company Dwg. (SKE-100368, dated 4/13/1973 i
- 27) Rockwell Manufacturing Company Dwg. ISKE-100369, dated 4/13/1973 h
- 28) Edward Valves Inc. & Rockwell Manufacturing Company Dwg. 40-182992, (Or GE VPF #3090-207-1) i i
l i 1 1 i
-O . i j
L
m.-,
# h I'y'8{
e 1 .i jN P [o ea sf.:hJ)4 0N j ?v'8Sf ea.daCD CWTC'*.'~Q "Clw? d!'"~tt u***!? oli u n Lieto C.D 4. es.Li D C'~.VT"7 * pa d daad l'u15W..=ad'
'TO: -R.Mudy/C. U1pindo -
DATE: Jun. 20, 1980 pq e M/C 391 M/C 143
' RECEIVED O, f1EOUIR ED it r SI'ONSE rn09: K Kumar H/C 753 dlk,,,,.; JUtl 2 51980 ATE:
- q,qm - .
R.W. HARDY f08: Ac s ton O SUBJECT *. 1.aSalle SQRT REVIEW MEETINC DECtr.lON O INFORMATION @j - From a static deflection test on a 24 inch MSIV (VPF !!3090-75-5), it was deternined that the valve would perform its function (opening or cinninn) with a stem defIcction of 0 634 inch. Awrnian defl< . t ion pre.g. ort lin:a1 t o tha t of 24 inch valve for a 26 inch valve, naximu:r deflect ion shall be 0.655 inch calculated as follbw2: a 4r a,24 _i_nch Valve For a 26 inch valve j b 24 = 0.634 in. 26 = . tl n - I 24 = 51.6 in. X. 26 }= 53.31 , O 24 =b 26 b 24 26 I WHERE d - Deficction 0.634 = 26 - Length of the Yoke Rods 51.h 53.31 - h 26 = 0.655 Inch Load necessary to produce this deflection: b max._ , (W ) (O dE i - 12EI . 0.655 = W (53.31)3 j (12)(27.9 x 100)(74.64) i ' t . Wr 108,037 lbs. # * ' C~ ' N , Convertin',1 this Ioad in terms of g's we get: F = W (C - 1.414) W = Weight of topworks 108037 = 2600 (G 1
- 1.414)
- git; - n ? k
?
C = 39.9 (V3 1
-CO:TrINUED-CC: BO Bohn, CB Johnson, P. Th6mpson
- p. " -
/
f.
. /, - "2 . ,a . - (ht the LaSalle !!ain Steam Isolation Valves,' the hu.!v-hnnnet - bolts are k 11mit tn;; (mn> Imam bolt capahtit ty in 15.24 g's) and producinn naximum nonent of 2,021,373 in-lbu on the cover. This maximum nrvent will be compared with the calculated moment generated by pipin;; ati.ilvnis (pip!np, analynto expected to be completed by 8045) to ausnre that valve is not overloaded for any casc.
1.aSalle !!ain Steam Isolation Valve is supplied by Rockwell. It has a Shef fer net natrir. Rockwell's 24 inch and 26 inch topwori,s denir.ns ' . ' nre sicillar. The body, bonnet, yoke Act,s, and the actuator are very much the same as can be seen in the attached drawfii;;s and dimensional coaparisons. The dtnenstenni similarity ind' the calculate'd results b.ised on the st at Ic bend test (VpF #3090-75-5) as well as Oualification Report No. NEDE-24122-2 assure valve operability when compared to expect.:! dyn.nic loading,s. j 9
/m ! . e ~~. . , ,-w . we em e e eme . t 1
i . t . .
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b 1.A SALLE NUCLEAR STATIONS' UNIT 18 2 4 ) f1SSS EQUIPMEtiT QUALIFICATI0ti SUR%RY j EQUIPMEtiT f4AME : Tip Guide Tube Valve Assembly l L EQUIPMENT tJ0: C51-J004 LOCATION: Piping System PC-1 (ITIPDR) l EQUIPMENT CLASSIFICAT10ft: Q ACTIVE O PASSIVE l i OUALIFICATION METHOD: Test f 1 E QUALIFICATION DOCUMENT
REFERENCES:
i ,
- 1. Adequacy Evaluation i I 2. GE Design Review Report # 235A1670 dated 9-14-72 l 5
l l 3. GE Seismic Test Result # 225A6371 dated 6-16-70
- 4. GE-VPF 856D393 dated 6-13-72 l j 5. PPD 136B1302 l
'j 6. ]
! k 7. ] l 8. r s 9. l 10 . h LOAD COMBINATIONS CONSIDERED lti QUALIFICATION: - t
- ormal Operating Loads + OBE + SRV
- 1. ASY-TQ ALL-TO, ENVELOP
- 2. Normal Operating Loads + SSE + COLEVY-2+ ASY-TO ALL-TO ENVELOP' h
- 3. Normal Operating Loads + SSE+ Chugging + SRV SY-TQ + SRVALL-TO -
ENVELOP,
- 4. Normal Operating Loads + SSE + AP l ll i '
j 5. Normal Operating Loads + SSE + COLEVY-1 i tj f QUALIFICATION: PREPARED BY: . b n et y ctu Date f -/9-8/ s REVIEUCD BY: It' f ' Date 4 ~/5 Y ggg g.gy acc sis 4i g:gey i_ uPmDnf_ff.w40~._ --_ _
O) w OUALIFICATION
SUMMARY
Qualification Method:
- 1. 7 minute resonance sweep test 5-30 Hz range with input of
.5g in vertical and 1.5g horizontal directions.
- 2. Resonance Search continued up to 1000 Hz with .5g input '
I
- 3. Single axis dwell test at 30Hz for 2 minutes with 'g' levels increasing from Sg to log in all three axes.
p 4.10 sec dwell tes t at log at 30 Hz in all the three axes. I %) I i l l i l i 1
! l . I e ; 1l .I i
f I II i Ref: EMD File No. ggp -O 2790 6 gggggg ggyn,gy, L _, _ ,______. _,____ _,.,s: = ru m ec cm b)
;;;;23
4 1 - - - - - - - - - - - - - - . . . _ . _ . Otnlification Strrarf of Fhairr ent (m
)
T. Plant !!are: LASALLE CWhTI 1&2 h
- 1. Utility: CECO g
- 2. GE
!sSS: Brea S&L
- 3. n-E:
II. Cceponent !!a e Tip Guide Tube Valve Assembly C51-JCO4 Y a
- 1. Model !A oek 136B1302
- a On..tity: --
l
- 2. Vendor GE
- 3. If the ccrpomnt is a cahiret er parel, ra:e ard rcdel !b. of y the devices incitrhi:
j[ I
- 4. Physical Description a. I g a rarx:e see 6.g. attached d
- b. Dirensiccs --
4 t.
.. n
- c. 'rieight
- i
- 5. Ircation: Building: In PC-1 piping syste=
Elevation;
- 6. Field .5tunting Conditions [X) Ult (!b. 4 , Size )
[ } Weld (Iancth ) ; Pipe roented ' I 1 )L For Valve Asser.bly:[
!i ne up to 10C0 Hz
- 7. !!atural Frequencies in Each Direction: g l
For Valve Support: Ecrizontal = t> . o nz. .eruca 2 du r.2a L hl: 5.8 Hz h2: V: l' a 8. a. Functicral
Description:
I Provides isolation of primary containment from Reactor Bldg. through Tip Guide Tube under )1
! normal and abnormal condi* ions.
Is the egal; rent req.:nul rcrT'Jiiat Sta.v27/I }Colc.
- b. ,
5: rut h n j [X]sath 4 1 j 1
- 9. Pertinent Peference D2 sign S;xcificaticcs:
s GE136B1302 1 1
,t $ .c 1
3
.4 - - _.3 I Peference: ESD File !b. DiD-029906 SARGEliTt LUNDY llf; .t ---~~'~~~~ " " - ^
r . i n_ m x- _m---- -
-c. c~.a
- m. m n .w.
%}
L.
i _______e ____-r __m -um _ . - _ _ -.m -
-_- 1 n- - , i 1 i i
t' L III. Is Equiprent Available for Inspection in the Plant: ~ [X] Yes [ ] lb [ ( ) : v p
~
I
, \
IV. Equirrent Onlification bbthod: 'Ibst: X ; i Analysis: Orbination of Test and Analysis: Test and/or Analysi,s by Ogden Lab. Report # 70865 dated 6-8-72 ; (nam of capany or Laboratory & Feport b.) .] 1
- v. Vibration Input:
- 1. Ioads considered 1.[ ] Seismic only 2.[ ] Hydrodyna:nic only 3.[] Explosive i onl 4.[ ] Other (Specify) 5.[ ] Orbination of { & 2 . E t
- 2. Pequired Pesponse Spectra (attach the gra;fis): See Attached. 8 h;
Prot: Pesponse Spectrum Curves e.I i
- 3. Pequired Icceleration in Each Direction: El G '
hl = .95 c h2 = _qs y V=
. 7 ,.
[{
.Il o
VI. If Onlification by Test, then Caplete: ' 7 [ -1. [Xl Single Prequency [ ] hiJlti-Preque:ry )
- 2. [X] Single Axis [ ] tiliti-Axis
- 3. Frequency Par.,.?: 1 - 1000 Hz l I l
- 4. TPS enveloping RPS using Filiti-Prequency Test { ] Yes (Attach TPS grap.h
[ ] tb ]j
- 5. g-level Test at hl = log h2 = log y= log .;,
il P
- 6. Iaboratcry > bunting: See figure attached
- 1. I IBolt (ib . , Size ) [ ] Weld (Iength )[ ]
l, ( 7. Functioral operability verified: [X] Yes [ ] tb [ ] !bt 14plicable t
- 8. Other tests performed (such as fragility test, incitxling results)
Firing test done. jl N Peference: DD File !b. Om-0 29 90 6 , SARGEfJT t LUTfDY h, I .~2~..=Ja J} C * ' C a c., - f{ u-+ ,xx w ,- . m~m= _, .
.,.=.x_,-- m a ,_g.v m mrc m-mgn
I
\ 'm VII. If Qualification by Analysis or by the Ucrbination of Test and A:ulysis,thc , , 2 U
Corplete: NA
- 1. Description of Test including Results:
- 2. bethod of Analysis: .
l I [ ] Static Analysis [ ] Equivalent Static Analysis [ JDyname s-1 Analysis [ ] Fesponse Spectru:' [ ] Time-History h i
- 3. bbdel Type: [ ] 3D [ ] 2D [ ]1D i
[ ] Finite Elemnt[ ] Beam [ ] Closed Form Solutioni i [
] 4. [ ] Conputer Codes: ' l i
Frequency Fange and !b. of ntx!es considered: i i [ ] Hand Calculations ; s l 5. Danping: . . . . . . . . - - . . - . - - . _
,3 E
- 6. Su;4crt Considerations in the nulel: ,
Oj >. A. Criticei stm>cterei stem nts: C ,ernin, Seismic rote 1 Stress Identification location Pesm.se Qx.bination Stress Stress Allcwblei. 4
.i l i i ll I:
I i ! i l l l l Effect U;rn Functic:ul;
; Cmrability
\ B. Pax. Deflection Iccation [ i l i a
. +
l 1 : 1 I e
! i i :
a 4 l 3 1 I' l j i a (v3t4 . e.
> Y l
Peterence: 90 File :b. gap - o 2 9fes _,,_ ; SARGEUT - LUllDY (j'!l [ :a,. mea m.a g Kw.r:sr --.+ __.er.--.m = - , a __ _ y_m.,wfm3 ;.3 m ,g.
CUS.tT COMMONUEALTH' EDISON COMPANY i K.OZ3~T LA SRJS COtRTTY - 13 2 JG3NO, $ NMO __ Q @J]t' R I'*/' M-*} g g1Q V] D~~S GM BY 'T t/W.-- DXE < I2 /S O
- - '3M h7- Ci .'ZC'GD C'i9%d,- T.C_D,UENz4 S.' *IET 10 CF_2.7 p ' .3i (J !.lgtf )
ass. na. o ' 1 1 p eaa t.:2.x mmau l 45
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. 20.0 ~~
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-15.0 ~
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- ~
3.0 - 3.0 2.0 - - - - - 2.0 v Y. t,s __ _. __._ . . _ _ . _ _ _ _.
/ 1.5 \ _
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0.8 [-- 0.8 g \ [-- , 0.6
/ N / 0.6 % }h .G / / Nr- ' --
4' t M a,g __ ._. _ ._ . _ . _ . . . _ . - - 0.4 i, f 0.3 o,3 {_ _. ._ ._ . ._ _ . _ _ . _ _ ___ . _ _ .. __ 0.2-[- .. i [ 0.2 n , j r, j__._ __ . . _ _ __. ___ 0.15
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i bl .C05 .02 .04 .06 .1 .2 ' " ' ". 3 4 r:rs. sr. REACTOR DUILDING-ELEVATION : 740' 2% Damping Horizontal Envelop of a) SSE + CO I,EVY- 1 b) SSE + COIEVY-2 + E""UI P (SRvE + SRvASY c) SSE + rMnG. A Envelop of (SRV.cr + S RV e t-) ,,
- t.
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