ML20080H041
| ML20080H041 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/24/1983 |
| From: | Cook F, Perry R, Toland R CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20080H032 | List: |
| References | |
| NUDOCS 8309200442 | |
| Download: ML20080H041 (200) | |
Text
{{#Wiki_filter:_ 5 Attachment to UC-34198 l e RSSPONSE TO NRC (BROOKHAVEN NATIONAL LABORATORY) REOUEST FOR ADDITIONAL INFORMATION MARK I CONTAINMENT LONG TERM PROGRAM PLANT UNIOUE ANALYSIS REPORT STRUCTURAL EVALUATION FOR BRUNSWICK STEAM ELECTRIC PLAITI
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UNITS 1 & 2 Prepared By: .
..lG Tol nd Date
/ '7 R. F. Per r/a/o Da t'e d e }ry n zs-as F. A. Cook Date 9 46 %
K. L. Bar e/z4/8 Date OA Revieu: pn F Z YlP.E
/Datd f J. Freeman Approved By:
"L.' R.' Slott
/2 h0 /./-{
Date N.. ' 8309200442 830915 PDR ADOCK 05000324 P PDR
INDEX Responses To Brookhaven-National Laboratory Item Total Sheets Listing of Questions 4 RAI-la 1
-RAI-lb and Attachment 3 RAI-2a 3 RAI-2b 6 RAI-2c 9 RAI-3 and Attachment 8 RAI-4 ,
4 RAI-5 and Attachment (47 pagee + 1 drawing) 51 RAI-6 and Attachment (2 pages) 5 RAI-7 1 RAI-8a 16 RAI-8b 20 RAI-8c 1 RAI-8d 1 RAI-9 1 RAI-10A 1 PAI-10B 1 RAI-ll and Attachment (11-1, 2 pgs.; 11-2, 15 pgs.; 40 11-3,13 pgs. and 11-4, 3 pgs . ) RAI-13a and Attachment (24 pages) 25 RAI-13b and Attachment (1 page) 3 RAI-14 1
e MARK I CONTAINMENT LONG TERM PROGRAM PLANT UNIOUE ANALYSIS REPORT LOADS EVALUATION REOUEST FOR ADDITIONAL INFORMATION (BROOKHAVEN NATIONAL LABORATORY) FOR BRUNSWICK UNITS 1 & 2
.RAI la PUAR Section 1.5 Justify the assumption that the unit S/RV forces and moments are approximately the same as the unit pre-chugging load.
RAI lb PUAR Section 1.5 Provide a comparison of the longitudinal distributions for both the unit S/RV and pre-chugging loads and discuss any available conservatisms which may offset the differences between the two distributions. RAI 2a PUAP Section 2.2.1.2, AC Section 2.7 Describe the alternate procedure used to calculate the pool swell impact and drag loads for structures located above the initial pool surface and below the maximum pool swell height. RAI 2b PUAR Section 2.2.1.2, AC Section 2.7 Provide all pertinent documehtation on the method used to develop the load definition for Brunswick from the Monticello test results and indicate why these pool swell profiles are a conservative representation for the Brunswick geometry. RAI 2c PUAR Section 2.2.1.2, AC Section 2.7 5f In addition, justify the use of the first set of pool swell profiles which were obtained in the Bruinswick test using a wingless deflector in regions where no deflector exists. RAI 3 PUAR Section 2.2.1.3, AC Section 2.8 The OSTS plant-specific movies were utilized in the calculation of the froth impingement loads, as allowed by the AC, on the RHR test lines, RHR containment cooling line'and the monorail. Which OSTF tests were used. Describe how a conserva-tive load specification was achieved and what uncertainty limits were applied as discussed in the AC. Discuss in detail the
c , 1 RAI 3 (Continued) method used to determine the froth source velocity. Were i Region II froth loads considered as part of the PUA?
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RAI 4 PUAR Section 2.2.2, AC Section 2.13.8 i The AC required that each licensee demonstrate that previously , submitted pool temperature analyses are sufficient or provide ' plant-specific pool temperature response analyses to asssure that S/RV discharge transients will not exceed the pool temperature limits specified in the AC as supplemented by 4 NUREG-0783. Provide sufficient information to satisfy the above requirement concerning the pool temperature elevation including the maximum bulk pool temperature and maximum local pool temperature obtained for each SRV discharge transient considered. In addition, explain in detail and justify how the local-to-bulk pool temperature differences was determined. RAI 5 PUAR. Section 2.2.2, AC Section 2.13.8.3 The AC stipulates that the Suppression Pool Temperature Monitoring System (SPTMS) is required to ensure that the suppression pool 4 is within the allowable temperature limits set forth in the Plant Technical Specifications. Provide sufficient information to demonstrate that the Brunswick SPTMS design is in accordance with the requirements of AC Section 2.13.8.3. RAI 6 PUAR Section 2.2. 2, AC Section 2.13.7 During the disecssion concerning the SRV load cases which are applicable to Brunswick, various load cases were eliminted by stating that these load cases were bounded by others, e.g.
- case A1.2 (SBA) bounds A1.2 (IBA), thus only A1.2 (SBA) was analyzed. Justify these statenents by providing the results of the computer analysis _ which were performed or the reasons
~
why various cases bound others. RAI 7 PUAR Section 2.2.2, AC Section 2.13.7
.. The AC required that an asymmetric SRV discharge load case be
,{7-
. considered for both first and subsequent actuations with the
,. degree of asymmetric discharge for each event combination j being determined from a plant-specific primary system analysis designed to maximize the asymmetric condition. No mention of an asymmetric SRV discharge load case is made in the PUAR load care discussion. Provide sufficient information to satisfy the AC requirements concerning this matter. l l l RAI 8a PUAR Section 3. 3. 2. 3, AC Section 2.10.1 l The equations presented in the PUAR for interpolating the vent header deflector forces at various Z/L's are not consistent with the AC. These equations utilized the longitudinal. multiplier distribution from NEDO-24612 and thus do not incorporate l l .. -- .. - - . - - . - - - . - - . - _ _.. - - - .-. -
RAI 8a (Continued) I the AC specification that the three-dimensional load variation shall be based on the EPRI " main vent orifice" tests. Describe in detail how the vent deflector forces were calculated at the various Z/L's. RAI 8b PUAR Section 3. 3.2. 3, AC Section 2.10.1 Specify as part of your response which longitudinal multipliers "and set of equations were used in the interpolation process. RAI Sc PUAR Section 3. 3.2. 3, AC Section 2.10.1 In addition, specify what the Z/L is for the typical pool swell impact and drag load given in Figure 3. 3.2. 3-1 of the PUAR. , RAI 8d PUAR Tables 3. 9. 2.1-1 and 3. 9. 2.1-2 Indicate service levels for bolts and welds listed in Tables 3. 9. 2.1-1 and 3. 9. 2.1-2 of PUAR. RAI 9 PUAR Section 3.3.2.5, AC Section 2.12.2 Describe what analyses were done to satisfy the AC requirement for multiple downcomer chugging synchronization. Indicate what exceedance probability was used to assess the statistical directional dependence and what the corresponding fo ce per downcomer was. RAI 10a PUAR Section 1. 3.4, AC Section 2.13 Provide more detailed information concerning the T quencher utilized in the Brunswick plants. RAI 10b PUAR Section 1. 3.4, AC Section 2.13 Specify any differences such as hole spacing, hole diameter, etc. between the Brunswick T-quencher and the T quencher tested at Monticello. RAI 11 PUAR Section 2. 2.1.8, AC Section 2.14.8 Provide the details of a post chug submerged structure load calculation for a given segment of a vent header support" column. Include numerical values of source strength and DLF as a function of frequency. In addition, provide the acceleration volume, drag coefficient, interference effect multiplier and pertinent geometric parameters, and configuration used in the calculation. RAI 12 DELETED
F. RAI 13a Provide the impact /dr'd load transients used in the analysis of the main vent, vent header, vacuum breaker and downcomers. RAI 13b In addition, provide the position of the maximum pool swell height and its relation to the main vent. RAI 14 Provide the loads that were used in the Torus attached piping. 9 { RAl la - PUAR ction 1.5
~
Justify the assumption that the unit S/RV forces and moments are approximately the same as the unit pre-chugging load. - 1 RESPONSE y W The unit pre-chugging load is higher than the unit S/RV load used in the analysis, except at the longitudinal angles between 0 and 100 However, asymmetric loads on the torus will produce shear forces FNT and FST in addition to forces and moments SF , FT , FNS MS , and MT . FNT and FST are maximum when there is a sharp change in the applied loads, in this case between 0 and 400 in the longitudinal 3 direction. The shear forces then decrease in the longitudinal direction. Maximum shear forces are obtained when the unit S/RV load analysis is _ used for the pre-chugging load. Although the forces along the longi-tudinal direction from the unit S/RV and unit pre-chugging loads are not the same, the maximum shear forces from the unit S/RV loads is approximately the same or even higher than shear' forces from the unit pre-ch'ugging loads. The maximum forces and moments TF , FS, FNS, Ms and MT are controlled either by the symmetric distribution of pre-chugging load or occur at the same locations as F NT and F ST between 0 and 200 . In addition, the maximum pre-chugging load, including the effect of fluid-structure interaction, is approximately 2.26 psi at the dead bottom center of the torus which can be considered negligible when compared to other loads due to LOCA conditions (max. of 44 psi). Therefore, the unit S/RV load was used in lieu of unit pre-chugging load to reduce computer cost. I
^
n a. RAI lb - PUAR Section 1.5 Provide a comparison of the longitudinal distributions for both the unit S/RV and pre-chugging loads and discuss any available conservatisms which may offset the differences between the two distributions.
RESPONSE
Calculation sheet 50 of 187, Attachment RAI lb, shows the longitudinal distribution of the: a) unit S/RV load. b) unit S/RV load used in the analysis. c) unit pre-chugging asymmetric load. d) uniform pre-chugging symmetric load. i s'
f:- t CALCUIJLTION SET NO. 9527-040-E-SC-TS-3 SHEET 50 0F 187 (ONE PAGE) CAROLINA POkT.R & LIGHT COMPANY . BRUNSk'ICK STEAM ELECTRIC PLANT 7-UNITS 1 & 2 O l l l
'/. ATTACHMENT RAI lb-l G l
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u RAI 2a - PUAR Section 2.2.1.2. AC Section 2.7 Describe the alternate procedure used to calculate the pool swell impact and drag loads for structures located above the initial pool surface and below the maximum pool swell height.
RESPONSE
The alternate procedure provided by the NRC was used to calculate the pool swell impact and drag loads for structures located above the initial pool surface and below the maximum pool swell height. Structures are classified as either cylindrical, exposed flat surfaces or gratings and different calculation methods apply. The longitudinal displacement and velocity distributions were based on the " main vent" EPRI pool swell tests as shown in Figures
- 4. 3.4-2 and 4. 3.4-4 of the LDR. Described below is the NRC alter-nate procedure used in the entire load specification:
a) Cvlindrical Structures
- 1. The maximum pressure of impact Pg ,x was determined by P,,x = 7.0 x 1/2 ( 2) where Poax = the maximum pressure averaged over the projected area (psi) f=thedensityofwater(62.4lbm/ft3) v = the impact velocity (ft/sec) g = 32. 3 f t-lbm/lbf-sec 2 e
- 2. The hydrodynamic mass per unit area for impact loading was ob-tained from Fig. 6-8 of NEDE-13426-P. A margin of +35% was added to account for data scatter.
RESPONSE (Continued)
- 3. The impulse of impact per unit area was determined by:
Ip =b( V ) T 144ge where Ip= the impulse per unit area (psi-sec) MH /A = hydrodynamic mass from 2 above
- 4. The pulse duration was determined from the following equation:
t = 2I p/Prax
- 5. The pressure due to drag following impact was determined by:
2 P P V max D"2D_ '144ge where Pd = the average drag pressure acting on the projected area of the target (psi) Cp = the drag coefficient as defined by Fig. 2.7-2 of the Acceptance Criteria. Vmax = the maximum vertical velocity attained by the pool (ft/sec) l b. Flat-Surface Structures l 1. The pulse duration (Y ) was defined as a function of the impact velocity: T = 0.0016w for V < 7 ft/see t = 0.0llw for V ) 7 ft/see V i where w = the width of the flat surface (ft)
- 2. The pressure due to drag following impact was determined by:
l: P g=CD PV2 ,,x 144 ge 2
RESPONSE- (Continued)
- b. Flat-Surface Structures (Continued)
- 3. From Fig. 6-8 of NEDE-13426-P, M H /A was obtained. A margin of
+35% was added to account for data scatter.
- 4. The impulse of impact pur unit area was determined by:
l=MH v T 144ge
- 5. The maximum pressure (Paax) was calculated from the impulse per unit area and the drag pressure as follows:
21p +p P,,x = D
- c. Gratings The force on the grating was calculated as follows:
D=AP x A grating ( max) 2 40 where AP = pressure differential (lbf/in )2 from Fig. 2.7-4 in the Acceptance Criteria To account for the dynamic nature of the initial loading, the load was increased by a multiplier given by: FSE/D = 1 + [1 + (0.0064 vff] 12/ for wf <2000 in/see where FSE = Static equivalent load w = width of grating bars, inches f = natural frequency of lowest mode, Hz D = Static drag load l This procedure was used to develop the Brunswick load definition for all internal structures except the vent header, downcomers, and vent header deflectors.
RAI 2b - PUAR Section 2.2.1.2, AC Section 2.7 Provide all pertinent documentation on the method used to develop the load definition for Brunswick from the Monticello test results and indicate why these pool swell profiles are a conservative representation for the Brunswick geometry.
RESPONSE
Figures 1 and 2, Attachment RAI 2b-1, were the pertinent documents utilized to develop the load definition for Brunswick from the Monticello test results. The use of the Brunswick pool swell profiles is conservative and is justified by the General Electric Company's
" MARK I SSE Ouestion Response", Attachment RAI 2b-1. GE's justification did not include the effects of modified downcomer submergence which is 1 ft, shorter than the original submergence on which the QSTF test and load specification were based.
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g' 1 ,- e !. GDTRAL ELECTRIC COMPANY . I MARK I SSE QUESTION RESPONSE l QIFRON 262.1 { (Total 2 Pages)
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s I I CAROLINA POWER & LIGET COMPANT BRUNS *'ICK STEAM ELECTRIC PLAhi n*ITS 1 & 2 Attachment RAI 2b-1 e ee e e-* e e** -ee a e e ,e .
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i G.E. COMPANY PROPRIETARY SHEET 1 0F 4 . MARK I SSE QUESTION RESPONSE : i - QUESTION # 7s? 1 DATE October 31. 1990 , t t REQUESTOR United Encineers TASK # 9.g 1
' - DRFf T23-226 RESPONSIBLE ENGINEER TASK MANAGER Apurba Mukherjee k. a tehe EWA# EAF79 - 04 .SUPPS APPROVALS:
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I G.E. Wade Manager i Mark I Containment Design QUESTION: . In Reference 1, we requested that Gf provide a load definition for . Brunswick for. pool swell impact and drag forces for a deflector ! configuration ~ that was modified from what was used in our plant unique . quarter scale tests. In Ref.erence 2. GE provided new load definitions for the ring header and deflector. In a telephone conversation (S. Hucik, GE to H. Painter, UE&C, 5-14-80), GE stated that to calculate pool swell loads on other structures, the pool swell displacement and velocity distributions,as originally provided in the PULD should still be used. We understand that conservatism exists in this load definition. Please provide a quantitative statement of the conservatism ~ and provide justificatton for it. G.E. RESPONSE: The following information is provided as an addendu= to the previous response to EDT Question 252.1 dated 10-22-80 . Pool swell velocity and displacement profiles were requested for Brunswick for a deflector configuration different from the one that , was used in the QSTF tests. Monticello is the most similar plant with a T-deflector._ Teets 17 and 18 were chosen to represent Brunswick velocity and displacement
~ profiles and that will give conservative loads for the following reasons:
I. . This answer to a Mark I Owner /AE question on the Load Definition Report (LDR),
. Application Guide (AG) or Plant Unique Load Definition (PULD) is provided for clar-ification. This answer is not to be construed as modifying any of the design loads which have been formally issued in the LDR or PULD.
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. . . G.E. COMPANY PROPRIE30t2 ,, i SEEET - OF 4 l MARK I SSE QQ:.m u CN RESPONSE (CONTINUATION SEEET)
- QUESTION i 262.1 REY. 1 Sensitivity test shows that higher p by 27.60% will result in higher pool velocity and higher displacement profiles. Also the header at a higher level will allow the pool to swell higher. -
Conclusion:
By using Monticello (tests 17 and 18) pool swell velocity and displacement profiles for Brunswick will be conservative. BRUNSWICK (NEW) M)NTICELLO
~
DERECTOR WIDTU . Header diameter 0.52 0.51 Submergence (ft) ,4.3' 3.58'
#(PSI /SEC.) 56.7 72.5 p(psid) 0 0 R/0 5.17 5.17 Water / Deflector Gap (in) 3.75 5.85 1 Water /HeaderGap(in) 33.7 . 41.8 4
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r RAI 2c - PUAR Section 2.2.1.2, AC Section 2.7 In addition, justify the use of the first set of pool swell profiles which were obtained in the Brunswick tes,t using a wingless deflector in regions where no deflector exists.
RESPONSE
Two sets of pool swell profiles were used in the load calculation. The first set is a result of Brunswick quarter scale test with wingless deflector. The second set is the load definition for Brunswick devel-oped by the General Electric Company based on the Monticello test. When calculating pool swell loads, the first set of curves were used - for structures located in the region without the deflector while the second set of curves were used for structures located in the region with the winged deflector. Figure 3, Attachment RAI 2c-1 shows the re-gions in which dif ferent pool swell profiles were applied. Both Brunswick and Monticello pool profiles were derived from OSTF tests with deflectors. The former was specifically tested for the Brunswick plants. There is no test data available for pool swell without deflee-tor. For regions where no deflector exists, Brunswick pool profiles were used since they are closer to the actual plant geometry than those based on the Monticello test. The use of the Brunswick pool suell pro-files is conservative and is justified by the General Electric Company's MARK 1 SSE Ouestion Response", Attachment RAI 2c-2. l i e
' . . s G .
t PARTIAL PLAN .- I
,- i DWG. 9527-T-1322 .
(Total one sheet) .
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CAROLINA PO*ER & LIGET CodPANY BRUNS'n*ICK STEAM ELECTRIC PLANT i UNITS 1 & 2 i l -g*, l l l l i l r Attach: nan: RAI 2e -1 I - I* l. i e t 9@ wm W + r - w-e ---.-mymw. - ---. , - w - ,------
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GEKERAL " TrTRIC COMPANY MARK I SSE OtwSTION RESPONSE g. ;
* . e SHIEIS 1 to 3 FIGURES 114.1-1 FIGURES 114.1-2 <.
(TOTAL 5 SEEETS)
. CAROLINA PO'w'ER & LIGHT COMPAhi
" 3 RUNS *='ICK STEAM ELECTRIC PLANT i .
s-UNITS 1 & 2 l l I I I . I- . i i
- ATTAC1DIENT RAI 2C-2
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n - j h: c.I. ::MFANY FRDFK: AKT IIII: 1 sd j s 4 . l MAJJ 5t! C'*II :ON RIf?0NEI I g:ss as # 114.1 sx:I August 17. 1979 . l L.- I* age:ts7pm CP&L ;Asg #9.1.1 , .
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*1:37 = s:2:.I EK n XIIR Eary W. Lawson gay i T13-233 .
i. kIniEd4-6F.b/.0 As: m u:rm Acu-ba Mukherjee M. Nu O
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l a r*Ut $ T. S \ L M & $*7'79 ' -- I j V5 Tashjian, T':n. e L. 5J Start. Manager c.E. WADI, mar.sgar Mark I/II contain- Mark I/II contLin- Eark 1 Cs:-=*- - : Desist f, :;
. ernt Engineering ment ingineering (- !.
G:Is= x: Carolina Power & Light Company is urrently planning to install the ven:
- f. . '
header cefle::ct in only *the non-vent bay. Our 1/4 s: ale tests were =en-suned m' h the vent oefiener, and thus our plant unigue load definitien 1. : for pool swell is with the vent defle:ur. This letter is is request that !
' O General Ile nri: provice a load definition for ecol swell withour. a defle= tor ; '
- s. for our uss in tht! analysis cf the vent-bay. This subje:t has been discussed *
[. previously between United Engineers and C:ns u:ters (Mr. H.E. Painter) and General 31en ri: (Mr. 5.W. 5=ith). s l F.is? DIGI: l' . ins effe::s =f n : having a vent hea:er cefle: tor (vs. having a deflector) cn ne Tent header ir:an transients is well d::umented. The pur; se of a [n vent header efle::=r is u =iti; ate ven nea:er i=::: / drat loads du-ing i pool swell. The Mark I C:::tzinmer.: P-a; ram Plant unique Duarter 5:aie tests I were evaluated to establish the effe:*, cf n:t having a vent headtr de#1e:::t . U
- n ven; header i=:a:: lot:s. Tnis evaluation led to the definition of vent [
header ir.ca:: 1 cads f=r plants that have *.estad with a defle:.or and do n:t wish :: ins.all defle:::rs in the vent bays. The-der. ails of the vent henjer inna:: load definition for use in the analysis of the vent-bay (without .a ,
. defiener) is provided in res ense to """-" W ' The attached ; ,
Figure 114.1-1 is plar.: unipue and replates Figure 103.1-3 of the response E to Question 103.1. This figure np-esents the plant uni:ve location of the' ( ic=an p-esse-e transients on the vent header to be used on conjunction with insi generi: pre: dure enlined in ne' response to Question 103.1. . b The sensitivities =f ther p::1 swell loads (e.g., :r.:s vertical loads. l-l l : us airspa:e : essure loads, and urus subme ged p essu a loads) and .I l- peel swell displace.aen.s and vele:ities u the absen:e of a ven header 4 defien:r in a < vent bay have been evaluated using the quartet scale generi: { , This a=.svt: se a Mark :. Owner /A2 questi== ss the I. mad <d* *-* en Erper: CLD1), - A;rplicati:= Cuide (A*) s 71.s= U=igue 1. sad .4d1:1.1== (? . e) is yryvidst is: alar- j .
. idiza ias. :1.is a=.svs: 1.s 3.s: to bc ==natrust as ast.iffing a=y sf the desig= 1 ands . t vt.ith have bee. ds mal , issued 1.= the 13R c ?OD. .
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E.E. :DNPANY PROPRIETARY , j, .g . U. M RK 1 SSI OUISTION RESPONSE f (CDNTINUATIDH SHEIT) , [ ggg5720N t 114.1
. i i sensitivity tests (NEDE 23545-7) and the quarter scale plant unique tests . . :
(NEDE 2194a-P and NIDE 24615-P). These evaluatiers lead to the following -
'i i netonnended margins to be applied to the existing plant unique pool swell # f
* - a
~
loads oefined in the PULD's if a u ffity wishes not to 4.ista11 a defle: tor in the vent bays while the plant unique quarter scale tests were performed with a . eeflector. . .
- 1) Torus vertical loads f
a) Download - he margins, in ' addition to those recuired'by the NRO, , , , are ne:essary because presen:e or absence of a deflector does not ..
, j~
influenze the torus download. 1 b) Uploads - The NR imoesed margins on uploads are adecuate and contain sufficient u.argin for uncertainty due te presence of . ! - nefiens-s in the CSTF plant unicue tests. Therefore, no addi- . f tional margins, cther than : nose impased by the NRC, are re=ennended. .
- 2) Terus suome ped pressu.e- No margins in addition to these reguired by the NR* are re :mrnended.
7 3
- 3) Torus airsca:e pressure - H: ma ; ins in addition to thes: :::;ui d by l
'- :ne NR* are re := mended, j s
~
t 5) 1= san and dra; on stru:ures above .he pool surface .- The load oefinition I i p-c:edure f=r calculatin; imsa:t and dra; on structursa located above the pool su-fa:e :::umented in -ne Mark I LDR (NEDO 21881, Se:: ion 4.3.4) l l utili:es plant unicue cos1 swell dis:1a:emen and velocity profiles obtained i ! fr== :ne : Tant unieve CITF tests. The absen:e of a defiece- in a vent bey alte's Me 30 1 Swell d sDItte"Tr.* En* ve sc:1*v 0-Ofiies net- tne vicin1*yi f
-- - ~
'-. un- Jnere cre, :ne foiiowin; rar; ns an: :nanges are '
Pe== ended $ be a: plied :: iihe plant unitue pool swell displacement and velo:ity p- files: ! a) Ps:1 swell disclacement - Er*-as:la*e the plant uni =ue cosi swell di3- -
;13:n nent e- eties directly a:eva --- y -- -- --- e*nector to 1. values e:ual :: :e-c. A ste::n cew.stratin l .
I ex raposa: ion is presented in Figure 114.1-2. __g this , . reco:rnenses ; b) Pool swell velocity - Peel swell velocities /ie'ah the occ1 cen*erline a-. 4eened by the ;-erence e' a ce: .er: r.W.owever, poci sweit-f veld:ities nen :ne ecoi tee *-** c'v'n av the clant uiiicue cuarte_r i s:sie tests a e --"Se-v o n when a:314ed : D v*"- 28 v5 *' 3 0' % #8 ' *"#P5 !
.ne-::: e, n: rarr.r.s , in a= :3cn = ==se re:ut re: by the NR;, are f
- I l ne:essary.
- l- 7:e1 swell vele:ities a 1c:stiens away frse the peel centerline and net-
- 'ie :: =.ts 5nt es a: ".. z ~iG ;*
~
_M W 8CI* f* * *O '~~UI* AI a. sni:ul: be n:: c :na: :ne NR criteria requires a: ding a 35: margin to the i=sa: icads en stru:*.ures Luove .he p::1 and, therefore, no . , a:ditional margins are re=:rnended.
- l. :
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G.E. C51? ANT PT& TdrTARY - j h-
~s' MRK 1 SSE OUISTION RISPOMSI e
(CDNTINUATION SK i) u ' QUESTION f 114.1
- 6) Froth impingernent loads - The NR: criter:ia on frcth impingement velocities ?
l and froth densities to be used in cal:ulating froth impingement loads are: '
!e sufficiently :enservative to offset a 1y uncertainties due to the absen=a C * .
l '
, of a deflector in.a vent bay. No additional mstgins are re:ounendec. ;
I
- 7) Fool f allback loads - Use th+ *e-e--1 **d-- -:- w *-- % w 1 swell .
displacement profile (ites La above) to obtain the bulk pool swell heign:~ ; use. in :ascusatin; the fallback loads. No additional 1r.argins are . reco=nenced. ,
- 8) Fr:th f allback loads - The froth fallback loads rre n:t affe:ted by the .j absence of a defle: tor in a vent bay. No margins are re:scenended. .
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- - - - Recomended Extrapolation .
Currently defined plant unieve pool swell displace- ' . ment based on presence of a - - Gefle: tor /
- i
- ..* -- Vent
. Henner .
c'
= .
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0 1.0 h: elized Heri:entai Dis an:e fr== Pool Centerline (X/R) - Fige e 114.1 Re::e nenced I rapolation =f Ps:1 Snell Displacement Pr: files *
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Tt r - w e y e - -- ---e 's--,v-w.--ew--*yv=--- - - *-,--v -ey - w *w-*- W -- - - - - e --- --'-+ ---**= -*
RAI 3 - PUAR Section 2.2.1.3, AC Section 2.8 The QSTF plant-specific movies were utilized in the calculation of the froth impingement loads, as allowed by the AC, on the RHR test lines, RER contaimeent cooling line and the monorail. Which QSTF tests were used? Describe how a conservative load specification was achieved and what uncertainty limits were applied as discussed in the AC. Dis-cuss in detail the method used to determine the froth source velocity. Were Region II froth loads considered as part of the PUA?
RESPONSE
Brunswick plant unique QSTF movies were used in the calculation of the froth impingement loads. Described below are the method and procedures used to determine the froth source velocity:
- 1. Three tests were filmed at a rate of 498 frames per second. The films were viewed and individual frames were numbered.
- 2. A Bell & Howell 159216mm projector was set up.
., 3. A frame prior to downcomer discharge was frozen. Figure 1 lists the distances between the downcomers, diameters of the vent header, downcomers and deflector that were measured to determine the se' ale factor between the QSTF and the film. The scale factor for the Brunswick QSTF was taken from Reference 1.
- 4. The position of the projector was noted to detect any accidental movement. ,
- 5. Sheets of tracing paper with the outline of the vent header were taped to the wall. The frame and test numbers were noted.
- 6. Tracings of the pool surface and any froth due to the pool impact-ing the vent header were made on approximately every five frames.
The pool surface and froth were diverted to each side of the vent header after impact. Figure 2 shows the measurements on each
/ < RAI 3 PUAR Section 2.2.1.3, AC Section 2.8 (Continued)
RESPONSE: (Continued)
- 6. (Continued) side used in calculating the froth velocity. After analyzing the tracings, it was found that the maximum froth velocity occurred between frames 65 and 75 in Test 1, between frames 60 and 70 in Test 2 and between frames 50 and 60 in Test 3. Measurements of froth displacement, froth angle and froth width for these frames were then taken on a frame-by-frame basis.
- 7. Due to the small elapsed time between frames, a discrepancy of 0.01 inches in measured displacement will change the calculated velocity 4.6 ft/sec. Because a frame-by-frame result is so sensitive to error, running average values of ten consecutive frames in each test were calculated (Fig. 3). "The maximum calculated velocities (vertical and horizontal) frc= three tests were used in the design. A comparison of frame-by-frame horizontal velocity, running average velocity and the design velocity for Test 1 is shown in Fig. 4 A conservative load specification, based on the procedures discussed above, with uncertainty limits properly accounted for, was achieved in the following manner:
- 1. Maximum horizontal and vertical velocity never took place in the same frame of the film,' however, they were applied to structures simultaneously.
h. 2
RAI 3 - PUAR Section 2.2.1.3, AC Section 2.8 (Continued) RESPONSE: (Continued)
- 2. According to the Acceptance Criteria a separate, lower bound froth source velocity was used to estimate the froth density. This resulted in a froth density greater than that of water and the LDR procedure was used for the calculation of froth density.
- 3. The calculated duration of the froth impingement was shorter than 0.0S0 seconds specified in the LDR. The LDR specified duration was used for the load specification.
Region II froth loads were considered as part of the PUA. The LDR procedure was , employed for the load s'pecification. In the overlap reginn where both Region I and II froth loads must be calculated,
~
it was found that Region I loads always govern.
Reference:
- 1. Mark I Containment Program Quarter Scale Plant Unique Teste, Vol. I, page 2-27, NEDE-21966-P, April 1979.
l s.
. i r
4 CALCULATION SET NO. 9527-E-SC-AP-1-F Figure 1 Dimensions Pg. 314 of 356 . Figure 2 Froth Source Measurements Pg. 319 of 356 l Figure 3 Running Average Calculation Pg. 344 of 356 , Figure 4 Froth Source Velocity (Total 4 pages) CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 & 2 l l l Attachment RAI 3 l L
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( RAI 4 - PUAR tion 2.2.2, AC Section 2.13.8 The AC required that each licensee demonstrate that previously ' submitted pool temperature analyses are sufficient or provide plant-specific pool temperature response analyses to assure that S/RV discharge transients will not exceed the pool temperature limits specified in the AC as supplemented by NUREG-0783. Provide sufficient information to satisfy the above requirement 1 concerning the pool temperature evaluation including the maximum
. bulk pool temperature and maximum local pool temperature obtained for each SRV discharge transient considered.
In addition, explain in detail and justify how the local-to-bulk pool temperature differences were determined.
RESPONSE
Previously submitted pool temperature analyses were documented in " Brunswick Steam Electric Plant Unit 1 and 2 Suppression Pool Temperature Response" (NEDC-24364-P) issued by General Electric in 1981.
- -(
This document has provided process transient analyses of seven (7) postulated events including various SRV and RHR system failures, as outlined in NUREG-0783, Section 5.6. Two (2) GE proprietary computer codes and models were used to perform the analyses. i
- 1. The coupled reactor and suppression pool model uses a thermo-dynamic code to calculate the transient response of the l suppression pool during.long-term events which add heat to the pool. This code perfonas fluid mass and energy balances in the reactor primary system and suppression pool, and calculates the reactor vessel water level, pressure, and long-term response f
1 l 3 of the suppression pool bulk temperature. l
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RAI 4 - PUAR Section 2.2.2, AC Section 2.13.8 (Continued) ( RESPONSE: (Continued) The calculations include the temperatures in the bay (s) of discharge, . downstream of the quencher device, on the bay
, centerline, and at elevations above and below the quencher device.
The local temperature is the average of the temperatures calculated in the vicinity of (above and below) the T quencher in the downstream portion of the bay. The reported local temperatures correspond to the highest temperature calculated in this manner. Updated design data unique to the Brunswick Plant were submitted by licensee and used by CE for adjusting the computer models, setting up the necessary assumptions and inputting the events' initial conditions. Summary of Results:
- 1. The maximum local temperatures in all cases remained below the 2000F limit throughout the transients analyzed.
- 2. The maximum local temperature achieved is 1960F for SBA with one RHR loop available.
- 3. The maximum local-to-bulk temperature difference (43T) equals
$00F, which occurred at the beginning of two (2) events and prior to the RHR suppression pool cooling mode initiation.
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RAl 4 - PUAR Section 2.2.2, AC Section 2.13.8 (Continued) RESPONSE (Continued)
- 1. (Continued) ,
The various modes of operation of all important auxiliary systems, such as the SRV's, MSIV's, ECCS, RHR and Feedwater System are modeled. 1 To simulate a specified reactor cooldown and/or depressurization rate (s), a, predetermined rate of change of temperature may be
- imposed onto the reactor vessel. ,
in addition, the model also simultes system set points (automatic and manual), and specified operator actions.
- 2. The local pool temperature model is used to calculate the water temperature in the vicinity of the quencher during SRV discharge events which add heat to the pool.
Results obtained from the previously described calculations such as the mass and energy added to and/or removed from the pool during each transient -(i.e. RER and SRV flows), are input into this model along with pool geometry, submerged structures geometry and pool initial conditions. The overall local temperature analysis consists of two major coupled components; a momentum balance to solve for the bulk pool velocity, and a two-dimensional energy model which
- s.,
($ superimposes the local recirculation on the bulk velocity to determine the temperature distribution in the pool.
['. RAI 4 - PUAR Section 2.2.2, AC Section 2.13.8 (Continued) RESPONSE: (Continued)
- 3. (Continued)
It should be noted that the corresponding pool bulk temperatures
, were around 1200F in both cases but subsequent pool thermal mixing and cooling, performed by RHR, have decreased the o T to 25-300F in 3 to 5 minutes.
- 4. A T at the time of maximum temperatures (local as well as bulk) are about 150F for cases where two RHR loops are assumed operational and about 300F for cases where only one pet loop is available.
t It may be concluded that RHR induced suppression pool circu-lation leads to good thermal mixing, which effectively lowers water temperatures in the vicinity of discharging T-quencher, thus improving the steau condensing process. s e
+
1 . ,9 p RAI 5 - PUAR Se*ction 2.2.2, AC Section 2.13.8. 3 1: The AC stipulates that the Suppression Pool Temperature Monitoring System (SPTMS) is required to ensure that the suppression pool is within the allowable temperature limits set forth in the Plant Technical Specifications. Provide sufficient information to demon-strate that the Brunswick SPTMS design is in accordance with the requirements of AC Section 2.13.8.3. 3
RESPONSE
CP&L's commitment with regard to installation of the modified . suppression pool water temperature monitoring systems (SPTMS's) is , to have them operational prior to the start of the fuel cycle 6 on Unit 2 and fuel cycle 5 on Unit 1. This translates into December 1984 and July 1934 respectively. I The design status of the above systems is described below: A. The suppression pool water temperature sensor location analysis with regard to the reouirements of NUREG-0661 and 0783 was per-formed by NUTECH Engineering, San Jose, California. The final report with recommendations as to quantity and exact placing of sensors was submitted: See Attachment 5-1. This analysis was based on the Monticello test resulta. B. Subsequent structural mqdifications of the in-torus equipment (service) platforms, walkway =, etc.) prompted a need for minor relocation of I ! the above' sensors, preserving though the elevation and the torus bays where the sensors were previously placed and analysed. Presently NUTECH is finalizing the relocation evaluation. Preliminary results indicate that the new locations will be fensible, which will improve the accessibility and maintainability of the
-, SPTMS's temperature sensors without sacrificing the accuracy of . Q::
measurements.
-. RAI 5 - PUAR Se'etion 2.2.2, AC Section 2.13.8. 3 (Continued)
RESPONSE (Continued) C. The design of the balance of the systems is presently in progress. We are evaluating alternate methods of data processing, communi-cation lines, hardware, sof tware, etc. The necessary changes to the existing temperature monitoring systems are being identified to avoid. duplication of information. The above design is proceeding in compliance with the NUREG-0661 NUREG-0783. The subject systems will possess the following features:
- 1. Two redundant networks of resistance temperature detectors -
thirteen (13) RTD's in each loop - will be located about the perimeter of the vent header at approved locations and See Attachment 5-1. calculated elevations:
- 2. Separate Class 17. circuits will carry the RTD signals out of the torus via fully qualified electrical penetrations.
- 3. The computing device (either micro-processor based or existing computer) will compute the bulk temperature reading and transmit the signal to:
, a. Data logger for the plant monitoring system.
- b. Main control room for indication, recording and alarms, l as required.
- c. Remote shutdown panel to substitute the presently used single point si~gnal, if necessary.
4 Alarm set points will be established in strict compliance with the NRC requirements and necessary modifications to operational l f' e procedures will be made accordingly. l - ?
e {. 1 RAI 5 - FUAR Section 2.2.2, AC Section 2.13.8.3 (Continued) p K , RESPONSE: (Continued) [0 NOTE: (1) Redundancy is to be consistently maintained P t-to provide the necessary reliability of the system. (2) Item 3.c. is still being evaluated. { Raf.: Attachment 5-1 i
" Final Results on temperature sensor locations for the I Brunswick Plant" - 47 pages plus 1 drawing.
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ff))- df.N * . pops + - pg , ""'C M h s'" j f s ._ BM nwA= yJB y Mr. 1. R. Scott 7 United Engineers and Constructors, Inc. pCh_/) 30 South 17th Street [M P. O. Box 8223 Philadelphia, PA 19101 g' gg-p
SUBJECT:
FINAL RESULTS ON TEMPERATURE SENSOR LOCATIONS FOR
HE BRUNSWICK PLANT -
REFERENCES:
- 1) NU"'ECS Proposal N81-038, dated March 12, 1981
- 2) Leuter from L. R. Scott (UEC) to P.-M. DonnellY, UV06072, dated June 23, 1981
(
Dear Mr. Scott:
Per the scope of work identified in Reference 1, please find enclosed Attachment A outlining our recommendations and justifica-tions for sensor placements, Attachment B containing the calculation package supporting our recommendations, and a copy of the final drawing indicating sensor locations. Addressing the concerns itemized in Reference 2: 1
- 1. The RHR line locations and direction of flow are indicated on the attached drawing.
- 2. The reference to temperature monitoring system has been changed to read, "RTD sensors for temperature monitoring system".
- 3. The length of the RTD is unimportant from a thermal mixing viewpoint, as long as the sensitive portion of the RTD is only in contact with water. Therefore, the length will be dictated by the method of attachment and other system require-l ments.
l 4. We are recommending that two sensors be placed at each location to provide redundancy at each location. The use of (. e.
- . . a..
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"- addressed in the enclosed recommendations.
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. 5. All sensors are placed so as to yield an accurate bukt temperature. Currently, Tione .of the . sensor locations are intended to measure local temperature. However, an approp-riate algorithm can be developed to infer the local -
temperatur; et each T-Quencher location. .. In . summary, NUTECH recommends that RTD sensors for the temperature mon'itoring system should be placed at thirteen locations as indicated in the attached drawing. NUTECH is also recommending placement of a redundant RTD at each location to ensurecaccurate measurement of the suppression pool bulk temperature in the event of a sensor. failure
- If you have any questions, please call Pat Donnelly or me.
Yours very truly,
.Erik Matheson T.
S J. 0. MtWford{ Faq$,yer Consultant Thermal-Hydraulics Ingineering Grcup ( ' J
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E. F. M. Donnelly, P.E. P.[ojectEngineer Project Manager i hg t l l l c l C nutech I
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.. ATTACHMENT A '.
FINAL DESIGN RECOMMENDATIONS CONCERNING p. RTD SENSOR LOCATIONS FOR THE , SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM
Reference:
- 1) NUTECH Proposal N81-038 to Provide Engineering Services to United
- Engineers and Constructors, Inc., March 12, 1981.
- 2) Monticello T-Quencher Thermal Mixing Test Final Report, Task No. 7.5.2, General Electric Co., April 1979.
- 3) Safety Evalua, tion Report - Mark I Contr.inment Long-Terin Program, U. S. Nuclear Regulatory Commission, NUREG-0661, July 1980.
- 4) Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following en Accident, U. S. Nuclear Regulatory Commission, Regulatory Guide 1.97, December 1980.
- 5) " Carolina Power and Light Company, Brunswick Steam Electric Plant Unit 2, RTD Sensor Locations - Suppression Pool Installation Draving",
NUTECH Drawing No. UEC-01-200, Rev. O, NUTECH File No~. 155.2301.0200. (,~ This letter report completes the objectives of the Phase I work defined in.NUTECH Proposal NB1-038 (Reference 1). The primary objectives.were to evaluate and make recommendations concerning the present location of - RTD sensors for the suppression pool temperature monitoring system, to make. a recommendation with respect tio bulk versus local temperature measurement, and to recommend sensor locations in accordance with References 3 and 4. The necessity to perform the first two tasks outlined in NUTECH Proposal N81-038 (Reference 1) was eliminated after the conversation with Mr. Vasant Deo on May 18, 1981. In this conversation, Mr. Deo informed NUTECH that the catwalk structure, where the present monitor- - ing system is mounted, will be removed from the wetwell in the future. Therefore, the need to evaluate the existing system was eliminated. The'Monticello thermal mixing test report (Reference 2) was extensively reviewed and evaluated with respect to temperature sensor placement. NUREG-0661 (Reference 3) was also utilized for determination of require-ments for bulk and local temperature measurements. Likewise, Regulatory Guide 1.97 (Reference 4) was the basis for system redundancy requirements. Upon completion of these reviews; it was apparent that there were two options which would meet the system requirements and regulatory guide-lines. These are: (7 1) Place sensors for local temperature determination per Reference 3 L' guidelines and compute the bulk temperature,if desired, from f these measurements..
. :.= _.-
_ - .= l . UEC-01-05
. Final.De3ign Recommendation 3 Attachment A Conc;rning RTD S23or Locations ,
. for the suppression Pool Temperature !
Monitoring System -
- 2) Place sensors for optimum bulk temperature determination and apply -
a local-to-bulk temperature difference for local pool temperature , determination.
- DESIGN RECOMMENDATIONS NUTECH is recommending that the sensors be placed for optimum bulk temperature determination. There should be at least one sensor loca-tion for each discharge device. NUTECH recommends that two additional censor locations be utilized in order to avoid undue conservatism in computing the bulk temperature. A diagram of the thirteen recommended censor locations is presented in Reference 5. The vertical location ;
of the sensors about the torus remains at a constant elevation which is also indicated in Reference 5. This sensor elevation corresponds to the level at which the centroid of the pool water volume is located for cverage operating water' level. . It should be noted that the sensors are placed on the vent header support columns on the Reactor Pressure Vessel (RPV) side of the torus to account for the lesser capacity of that side to condense steam due to the smaller cross-section as viewed from above. It is also recommended that a redundant sensor be placed at each location specified, thus a total of 26 sensors are required for the monitoring system. Both sensors at each location should have the sensitive portion of the device located at the elevation specified. As long as the sensitive portion (, of the sensor is not touching the vent header support column, almost any sensor mounting scheme which provides the proper support is accept - able from a temperature measurement standpoint. A volumetric weighting factor will be assigned to each sensor in the Phase II work described in Reference 1. Finally, a local-to-bulk temperature difference will be determined during the Phase III work described in Reference 1. DESIGN JUSTIFICATIONS . ' There are several reasons why the bulk temperature measurement system is chosen over the local temperature measurement. First, plant opera-tional procedures are written in terms of bulk pool temperature and providing a local measurement would require a rewriting of operational l procedures. Also, if the sensors were placed at a low enough' elevation to measure the local temperature, a non-conservative estimate of the bulk temperature would be obtained. This is due to the fact that the pool flow is stratified, i.e. , the ' cool water tends to be near the bottom, which would result in low values of the local temperature every-
. where except at the discharge quencher.
l The justification for the sensor placement primarily stems from the Monticello tests. These tests demonstrated that the placement of the censors on the vent header support columns on the RPV side of the torus
~
and at the elevation of the pool centroid, along with a volumetric g- average of the temperatures at these locations, will give a very good V prediction of the bulk temperature throughout the transient. i
l __o . UEC-01-05 +
' ~* Final *De31gn RecommendOtieno Attachment A *~
Conc 3rning RTD S2nnor Locations
. far tho SupprC00 ion Pool Temperatur3 Monitoring System i e i-Secondly, installation of the system should be simplified since the [
leads for the present system are routed through the vent header distri- i bution system and the torus liner plate is backed with concrete, i.e., it is easier to mount the sensors on the vent header support columns ' than on the torus walls. Also, since the T-Quenchers are approximately ' symmetric with respect to the torus miter joints and the vent header
- eupport columns are located near the miter joints, these locations give a good indication of the average cell temperature in all bays, including the discharging bay.
It is recommended that there is at least one sensor location in every bay with a discharge. device. This arrangement assures a conservative measurement of the bulk pool temperature since the hottest bay, i.e., the discharging bay, will always be monitored. Redundancy is also recommended in each bay with a discharge device for this same reason. The possibility of a f ailure of the sensor in the bay with the dis-charging device could lead to a nonconservative indication of the bulk pool temperature. Finally, the failure of any sensor would unnecessarily complicate the algorithm for determining the bulk temperature from the censor readings. Without redundancy, the algorithm would have to search for the failed sensor and' determine its proximity to the discharging device and make adequate corrections. This could lead to a fairly large number of permutations that the algcrithm would have to consider. After considering all of these possibilities, NUTECH recommends that 26
- sensors be located in sets of two for bulk temperature measurements I cecording to the diagrams in Reference 5.
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elesd a ion iw -the dis ekacgig tuewebe ba.v { .
. it i.s wecessac3 tc> extcapelde -l ke.
re.spewscs feom sencces a.bove -lbi s I e\ev ution i.w ordec. Yo ob+aiw .s respo*se at. 4 bis elevati ew. Amer d is d5kecanvted -thk the_ lwYec-medicdic e\esqYion is o. good indicc b ' [. of be. overage. Yempecduce iw g bu g is a { M-ndcassac3 -b assigvs vokmcicit cocightiw3 -fa.cdee b eacA. l wh;c.b. cowtaiws dempecaiu.ce s e n s ea s. b.3 l siwe.e Yhese_ (ecat'ow.s a.ce. wot evea'],- c didei bded a. bod Oc s uppressiew pool. ve,(u.metc;c. ft fier- cessiaf n$ agcopridc.
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.-- San Jose, California f Pro M muak E\e & & Pl d r u g n. m i.. w . [_ 3 ,,,r O m h P e e awA L . kt O e eu . e4 - ca. Ow b l E aq ,,cs (wd %dm/64 Lc. a - , n; l n , .._; - -- O : 11% a p, ha .' 3.0 CALCULATroMS i.. { . I kC. CcdCu.\ ims or he. kgo e,o. g es C.CC4*ibR. kW \t i.V\ TO R C. k OW. R f C. b pe c h e m ,A 2.s ogtwea 1, s c+c ,2.0 elevd;on he- [ iw %is ' sec. tion . Th e_ sensor- plu.ement ivt -tke. Scusci c k 7 plad ts &o c o n d e..l iw tL a
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5s Revision O Pace 10 Prepared By/Date D Shiki of 40 Che:ked By/Date $ I/MD
5 11Ut9Ch . s.n3 c.woroa - 5 p,.3.c1 Bewesein S+e<m Eiedete Plad.- n u o m 3 w .o w F %,CW h Phoec amol Li At O-mu o cia i D mt+ J Eo w o - tbhebMLe.
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[ The -bempecabes for Ba.3 b 64 4 L 3 edrapdded from. c%ec kbshow simea { no mon' doc- cx_c l pac.eA so" from & 6 c.e. of -hke. suppressim poo\ w -this. padic A.c [ 6 3. From R y e s. A-14 . 4 A ir of Ref~me i, [ ib is b 4 ud rootcs.T% and T22 et ~ me % 4 t u .4 " { c om -tke 6 se. 4h [ s uppres.sion pcd , ebb, % m ,4ces T17 a4 Tzz a.c e & es s". The.s,. +emeua me.es l' acc. %6AA .5 4mwchs e+ time im Tdde l 3.1.z. T he -Firs-t ' % +.emp,4c=% es are wecged b obhtn e. represedd;ve. b erduc g e et 12 2.9" , a a d , L e-t Le e b= Ace e.e. ser$cA 4. .Lieim g,<Aure_ d cfr. 5 " . l
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Checked By/Date l _m. _. .- _ , _ . . _ . . . . ~ . . , _ . .- ,_ _. _ _ . , , . , - . -,o_ _ - -. - - . -
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! Page 13 Prepared By/Date E@YZYsi of L10 Checked By/Date @ khI !
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Page 15 Prepared By/Date khk2k of @ checked By/Date '_M k [l
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N,Ak-E 3.i.iAVER$E BAY TEMPERATURE.s(*F) [ W-(.wQ Eb C- 8"b 8 8*3 N Ik3 E/F Ba3 b/E
, O 53.3 53.3 53.3 '53.3 s3.3
[ 2 - CE.E G2.Z F3.3 53 3 sg.s
- g. 4 7t5 76.0 57.s- 53.3 ss.o 6 S75 3't.1 GS.F 54.b 55.2.
h 8 91.Z 81 2. 76 7 - G3.8 63 s 950 72.o 72 5 10 93 7 83.2 12 100.7 1Co.O 59.o 78.o S2.3 (~ 14 93.3 1 00.8 95 4 72.8 gf5
~
% 29.3 94 5 97.5- gg.g 8T.s 12 90.0 91.0 99.3 92.0 90.0 92.0 93.0 42.o 20 91.8 91.7
[ 12. 93.7 935 40 3 90.0 90.0 24 94.0 94 5 42 o si.3.. T13
; 24 92.4 94 5 43.0 90.0 90.0
_ 2e 912. 93.o 94.0 903 g8.9 30 11.Z. 92.o 99.0 92.o 90.2 3z 92.0 T2.0 93.2 93.0 91.0 3't 92.0 T2.0 42.0 93.0 72.0 (
~
36 42 5 9Z5 92 5 92 5 4Z5 l Revision O p g, j'7 l Prepared By/Date [ $ M h r/ 39 f,49 Checked By/Date MH 4/3/9/
m.u _ - San Jose, CCifornia 5 Pnhe:t ru" sack S % Eleirte Pd ,, u ,,y y. m ,. w P own.r Carob %ec .wd L6kt C%o..u g ca.nt litted .E'ag wee <= ,J Ntructc,# sc. ,
-T41!(E-3.1.Z. TEMPERATURE.s IlJ BAY b(F)(DiscL93 Quewekec)
E -Ti$vd (mQ T5 Ty T,s Tn To t u 1, 2 123 Ave.. %p. [ -- 10 F33 E3.3 53.3 E3.3 53.3 FI.3 53.3 63 3 53.3 74.0 74.0 31.2 65.0 30.0 EL.o 78,f. 7t.2
- 2. 77.3 71.(o 78.S 38.0 69 5 sg.o 96.o ss.o 353 4 837 U 6 79.3 78.S 90 4 GSs 92.2 98.0 36.s sgo Vs.3, E 74.4- 74.0 91.o 73 S 92 7 1008 T1.0 to.o 88.2 10 91.2 104 97.2 30.8 15.3 104 4 9Eo 45.0 94 1
. 12 98.o 9L3 100 5 77.3 104 5 113 5 104.0 104.s 101.9 r 14 94 5 si.o f2.0 32.9 85.0 g3/o 92.0 %% .O T7.5 l' 16 90.2. 37.8 52.S 85.0 90.o ss.3 90.0 90.0 35.0 13 96.0 93.0 T3.1 81 5 90.7 T.7 94.0 90.0 91.0 20 95.0 %.0 SL.9 't 3.4 94.7 93.0 1S.0 iLE 4%
22 9f.0 %.2 T1.3 94.2 45;o 93.7 97.0 95.0 95 2. 24 94.7 93.g go,y T3.2 9tt.g 92.7 9ts 94.8 T3.7 26 92.0 91.0 90 5 9f.o 92.2. 91.4 42.2 92.2 91.6 2.8 90 3 10.0 TOS 90.5- 92.0 40.9 92.o 92.o 91,0 30 90 0 90.0 92.0 S t.g iz.o Tzo 42.0 42.o 91 5 ' - - - - 32. 91.0 91.0 42.Z qao 92.o 42.7 42.o T2.o 9f.3 34 92.0 92.o 93,Z 92.7 T2.0 93.4 12.o 92.o 92 4
- 34 91.0 92.0 93.b 93.b T2.0 92 1 92.0 92.o 42 5 b Revision O I p, g l Prepared By/Date ($ h g l
checked sy/Date W #/42/ I
T nutech . San Jose, California i
- i. Project Bt uws c.o'ek e m E\e d etc. R etd File No frF.2 3ol.o3a
% , C a ce h o_ Pomec- J LrAt C6pom .
cii.nt Wi+ed Eaem ' J Teatm&eWs, h L
- 7 .
,_ -TasAE 5.1.3.TEMPERftTORE MEA 50Eb 50"FROM BOTTOM OF BY/{ F)
!L T4.bQ be Q B3 8 Bas H Ee E/F &.3 b/E %b
[ -- C E3.3 53.3 53.3 E3.3 53.3 53.3 i r Z. 59.0 GOS 5~3.3 59.0 53.D 74.8 If 75 9 70.6 55 G F4.0 f3 3 82.4
- t. (o SF.2 94.G Git.5- 54.9 53.0 33.6
;- 8 T1.2 907 79 1 G3.3 60.2 .S7.2 1
10 93.0 94.0 75.5- 79.0 72o 94.5 12 47.2 100.s 90.3 71,7 ' 73.1 f 00.3
'e N 92.0 102.0 % 5- SL.O 32..O SE.8 - 16 87.6 93.S 91.G 91.3 86.3 83.2 13 V1.2 40 5 %.7 47.2 93.0 ST.E 20 91.0 91 5 T2.8 97.3 95.9 95.5-( 22 93.0 935 11.2 94.7 95.4 46.?
1 ~ 2A 43.3 94 5 T2.0 41.0 42.0 14.0 24 92.6 44.3 93.2 91.2. 89.8 91.3 l 23 91M 43.4 94.1 T2.0 90.0 90.9 30 4f.0 42.5 43 5 92.5 90.7 91.0 32 91.2. 92.4 TZ.7 94.0 91.9 91.5-39 91.4 927 92.f 94.0 92.1 iz o 30 q2.0 43.0 TZ.1 94.0 TZ. 5' 42.0 ( Revision O l Page I9 Prepared By/Date [M h/ of LIQ Cne:ked By/Date %ff W9/ I
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- San Jose, California . .h Project Musta tc. S = Elecisc. P%t rii,u,tenz2oi. 2.c i m(LL. Aec M Lt,tt h w ;
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y-c.: l h, ' TABLE 3.i.4 r . i' ~ TIME-AVERAGED DEVIATI.Ob3 0F TEMPERATURE @ 70" FROM TimT r- OF AVERAGE BAY TEMPERATURE ic p b.3 Devidion(*F) C 1.7 8 0.6
~
H 1.0 E/F 1.9 D/e 2.4 D 0.2 C Revisten O p ,, 7,,,9 Prepared By/Date % h2lki 4 ,_ gf qg Checked By'/Date rJ6H h k/
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- 7 flut9Ch .
s.n a e. c.iiforni.
- Prok _ brwnst.jic h ec v-i c. ak File No MF.T.301.03ot
- y. we n sa %e<- A L:BrC%~n
- h cii.nt UAl Eates M Ns%tM L a TSBLd3.15. BULK TEMPERATORE Mb IEVIATIoM51
- ROM BOLK O T0" (
-Tim. (mQ 'bk. e.c C. oa % %. ci,
-- 0 E3.3 0.0 0.0 0.0 0.0 0.0 0.0
- 2. 59.1 - 0.1 1.7 -
5.9 -5.1 -G.1 17.7 0 4 60.0 3.'l 10.6 -10.4 -12.0 -1Z.7 %4
- [ (o 72.2. 13.0 12.4 - 2.7 -17.3 - 19.1 11.4 r s 79.o 10.2 11.7 01 -1s.7 -1s.s . v.2 10 vs.z. 7.3 S.8 0.3 -11.E -13.2 9.3 11 92.0 5.2 2.9 -1.7 -1z.3 -12.9 2.3 14 92.T -0.3 9.2 3.7 -L.s -10.8 -7.0 16 92.3 -
4.2. 1.0 6.3 -1.F -65 'l.6
~
_. 12 92.E - 3.6 -Z.3 9.0 4.4 0.2 -3.3 20 92.3 - 1.2 - 1.3 0.0 45 3.1 2.7 l , . 21 92.3 0. 2. 0.7 -1.E 2.0 ZG 91
- - 24 92.8 05 1.7 -0.8 - 1. 3 -0. 3 1. Z.
15 l 26 9 Z.8 -0. Z ' 0.'t - 1.L -3.0 -15 2g 9E.2 -1.4 6.4 1.5 - 0.S -z.S -1.9 , 30 92.7 -1.s -4.3 0.7 0.0 -z.1 -1.s
- 32 92.s -1 6 . -0.9 -0.3 1.2 -0.9 - 1.3 34 92.7 -1.4 -0.1 -07 1.2 -0.7 -0.3 36 92.T -
as 0.2 -0.7 1.2 -0.3 -c.S
.. Revision () ll l p, gj Prepared By/Date @k2/f8f l e 40 Checked By/Date W 94/P/l l I
~
,,-,--% .,,.,,--.- . .. , ----.-e,-- . - - - - --y -.mym,-------wr ----.---,---.--v-,c- - - - . . - - - - - - - .
2 ~ nutech - San Jose, California
- Pro g b r u n s O i c k b m Eleririe_ N it- n u , as. m i.o u , .!
'O owner Creb bec w kink-I- Omsu !.
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. TABLE 3.1.4 I NUMBEPs 01: BAYS REPRE59JTED BV R EACR MOMITOR ANb RESULTAVT VOLOMETRIC. OEIGH TIOG 1 ACTcR5 B$ Ne. of &y %hth3 Fat -
r- , C 2 0.1250
~~
B 2 0.17.5 0
~
H 7 0.9375 2 0.1750 D/E 2 0.1250 [- D 1 0.oG2.s-j .- j -(' -- Revision - (y l l Pm Ol Prepared By/Date @ f/2fffl l d @ Cne:ked By/Date M MP/ l l l
.,w,-
---_r-,- ,_%_...__ _ _ _ . .-,_r -,,..,._,,,m. -_.___-.._,-,c. _ .----_,,,.,,-,-.-__w , , _ - _ . . _ , _ , - . . _ _ - , . . _ _ , _ . _ . , _ _ _ _ - , . . , _ _
$ 11utech. .
Sar. Jose, California ~ E, e,,, 3r aws u>.tek ' Sb E\. Acte. R.J. rii u, is.z i.o3,c 7^ w CamL P-mml Lt.Mr hmm : r Ciw_Uwt tea L 6een %J 4 % 2t W & # ,.. I nc. #
~
i _ . .I' L' I _ . . . . _ . _ . _ _ . .. _ . . . . . .
- t. i L. ..
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E t.4 TAB i F 3.1.7 i- VOLUME-AVERAGEb DEVIATION FROM BotK @ go"(*F) Tt me (mQ cr Time.(mw') er I.. r O 0.0 20 0.7 E - E. 6 22 0, Z.
; 4 -4.1 24 - 0. 3 1
2 4 - 1. 9 ZG - 0.3 i 8 ~ i. 0 2% -o1 10 - 0.3 30 - 0,3 l it -1,6 31 - o.4
~
14 0,0 34 -0. 5 i L 14 1.3 36 -0. 3 13 1.4 a l l
-- Revision O l p, u I Prepared By/Date @ h/kfi g q9 .. Cnecked By/Date Sti6/Gd/l l
San Jose, California :
~
Project - EMSCIC O:"W- E C- CIC Pa File No M5'I"301-03o0 F %, Caokm h< mJ Lt.ht C6mm : Client EY bA v I%h o NE M ~e - b c- ! p ., , ' . .
~' - - - - ' * ** ' --
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F. , t.
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/
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[.. 270 90* L. +w t l
\ N i
\ +2 L \
{ 180* ( Revision O p,,, g Prepared By/Date Checked By/Date M h/ F of 40 "56tf MMf/
,, ._, _ - _ . - . . w. . ---v.- . - - - - - - - - - . - . --
E nutech . San Jose, California
, Project u"50iCk bY h EIecbl' bb"L Rue MS mew
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e bhTA REbOCTI.otJ FOR CASE OF 00 R)lR CIRCUL&TIotJ
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& resdtet mucca3e.36 hped-e s behs 4 h we. Thecc vetwe s oce bmA
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+empe< h es in & -
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- Cne:ked By/Date '
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- - . . _ _, , . . . _ . . _ . . - , . . . . _ . - . .w_. _ _ _ _ . . . . . . _ , , . - . , . . , _ . - . . - - . _ . - , . . . - - . . , , . - - ~ , ~ . _ ,
r-F nutech - i - San Jose, California Project runsciek 8keam Eleekdc hla"I File No 15S23ei.e soc !
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Revusion D I Page ? [o Prepared By/Date [h ZJfS/ l 1 of 40 Cne:ked By/Date MH MN/l l I ! I
b 11Utech - s n 2.u. c rnorni. E p,oj.ct Bru.asorck 5tm E\e.e* -tc Fa\ riie no is s 220i.o3 m wrNhm Peer M LtAt Gb- ' {, cr at ik&cl E~t - **A b bEM;Le-r~ i..I at -Eke .e(evdios of go" v e.
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Cne:ked By/Date $ M4/8/l l l
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.... =. . =.- - - - . - _ .- -. ....._ ______.. .
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re.sponse_ mAchocs t's f & T *F of tke k\A 'be mprOuv e..
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.-- .< San Jose, California '
l pg sQ k N emw b d ric b Awl File No IFC23of.o noe a w Gom b Poote mA L.:.kt C.~% . [f V_
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il j $$52.1. IVER AGE BAY TEMPER ATURES(T) ! [e -TIO 614 .. Bag - -O - Bs3 'B Bag H Ba3 E/F Bag D/E b --- i0 -
. -sz.o 52.0 sz.o sz.o s c.o
' ~
2 - -6 9.0 { 53.0 Sz.3 5'z.3 ,6'7.1
._. 4 E0. 2. 63.0 s z. 3 5 z.3 7c.15 6 94.0 70.0 F8.4 57. 4 si.o .
- [ . S 98.4 SC.=t u. s- Go.O S4. z. '
10 101.6 9 Z.0 76.0 GS.S E9. 5-12 100.E 9G.0 Sfi.O 7S.7 F't. 4 (
< M 90.0 90.0 93.0 SL.9 92.0
; 16 Es.1 74.57 27.0 90.ct 92.s
~
, 1[ 8 S.9 sS. s- 28. % Es.1 92.9 26, 21.7 27.3 ES.9 77.9 9z.o az %0 V9.1 38.9 TT7 91.9
~
2.4 ti.o S7.3 T'L2. t7,z. 89.5-2.6 si.s T7.2 ES.7 88.7 91.o 2.8 39.2. SS.i TS.4 T S . 't 90.8 l . 50 8't.7 Sf.1 SS.5 .- .. ?t0 90.5
~ '
-- 52 79.E 78 4 St.f -
Et[7 90.2
.. 54 Si.o 97.1 gg,q gg.3 90 6 le(.. 34 f f.7 57. 5~
~
66 4 T9,Z 90.5 Revision O I p Prepared By/Date Checked By/Date [Mh) Mff- 94/g/l ' g l
- - - - - m -- e ,v.,w-wemww--e.-e-,-,-n-we-,--, ,w,---,.-,,-,,-a ,.--r a e ,-aw-w,,--w-ea---..,w., w__,,e, e- _ e-, .,---o,,,m_---w-e~-
,. . San Jose, Cartfornia ;
Projet r'uesl$ic.'r Neam E!eNeic C* File No l'rs 23ol.o3ct ;
%,CL A Pe,0.c- wa AtCb% -
i I
. r.,g LL62 Epete . # Go d ,-ut.%
L. j 7shlE-3.2.2.. TEMPERATURES U BAY D('FXDischo.cgin3 Quencher)
% T T. T. T To
-T(de (min) '
T7 Tu Ave. Temp. E
- !o ~d2.0 sz o st.o 52.o s2.o s2.o s2.o sz.o sz.o i 2 -
s5.2. SEO 78.S 77.T E9.0 St.o %.s' %7 SS.~7 [ 4 103.2 104.1 107 3 92.0 1M.5 10s.1 106.6 104.6 10s.2 6 113.E 114.'i 11 7.0 90.6 1Z1.1 12.2.6 127.2. 1 28.o 117.7 2 12.2.0 122.o 122.o 107.1 1z65 124.0 130.5 130.5 123.1
.. 10 1 Z.1.0 121.'2 1Z4.7 106.0 ft8.6 128.o 134.0 13rD 114a
- 12. 1zo.a. 116.z 56 o 83.o 103.ti St.o 12_to 11 7.s- 10E7 14 1Z2.8 99.S TZ.o 91.1 TG.0 '76.9 123.6 107 3 9%.6 iG 122.7 100.3 7E2 TL.6 sG.o 73.0 12f.1 99.1 965 12 120.0 100.S ' r1.2. TF.S s9.0 74.0 111.r 10b T4,6
. 20 120.7 102.7 6s.2. S% 30.0 70.0 120.0 1oss 99.1 l 2.2 120,7 104,6 67.2 '77.1 75.0 GC.t 119.0 104.s- 42.9 Z4 119.5- 106.3 6 6. t . '78.S 75,0 G7.1 120.0 107.5 93.1 ZG 117.S 10E1 64.G 77.'t 75.~7 66.o tit.o 108,0 915 22 11s.g ios.s- Gc.L 77.7 13.1 65.8 118. 6 10% o 92.6 cc.r 935 30 111.6 104.2 19.4 715 1Gs.o 115.0 106.g 32 li%.0 103.1 6 f.0 ' T1.6 31.9 GS.o jig.t105.i 92.3 34 115.0 1033 64.3 12.S 33.0 G4.S 11 7.o 1015 92 3 36 115.0 103,2. 65.5 S2. 0 TZ.T 44.S 114.9 10E3 9 Z.3
\
, Revision O p, 3 Prepared By/Date fM h/ e 40 Checked Dy/Da*e NM k(//9[ l
. - , - - _,a_
(:; .- .: - g g s'. ; q s. . .,.y- = -.. 1
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b- pp bmskiick. bbw Elebn't. I FiWE5".22 c'3eo o,,,,,,0 ~. 6 N e<- M Lt At C6-u . - g' I eg CAA A Lw.em - o
& J G 1.,b % h.. a_ , ~
i *-e e . !q .e ' . T3RR-5.1.3. TEMPERATORE MEASUREb S6'FRbhM, ej rfo .., H OF BAY (*N)' T/M (mt,0 Bq C hs 8 B<.3 4- B.3 E/F-Ag#E.- hM 3 , sr.o - :st.o -sr$ o sz..o sr.o .s z.o [ 2 71.o sz.o sz.o sz.s -- --42:o - - -l41.g-4 7 Z..t G~l.S Ez.o 531 7z.S : - -i11.1 , 6 109.0 73.0 54.o E3Jz ; 70.2 - 121.9
- c. .
sr.o S 112.4 94.o ss.3 7g.3 1259 10 1 Ut.4 103.9 70.8 72.4 76.3 12.8.4 12 11 5.4 111. z. 27.5 S1.2. %.o 112.5 c 1+ s s.7 90.6 92.6 97.0 94.0 92 5
- 16 94.6 7 g.9 sc.s vr.1 ss.2 s7.o 1% ts.0 si.s 90.s 94.7 42.7 90.5 20 , 90.8 T !.4 94.7 93.s 90.F- i94.7 u
- 22. s. 90.E 9r.3 94.0. ; 91.5 -- -- 17:9 -- , 97. 2.
24- 'S S.'7 914. iz.SL i-41 1 -: 9 7.3 - - 300.1-26 91.4 91.0 12.5 -- --!-91.3 -- . TE,S - 1 99.5 [. 2.8 90.0 94.o 92.o:-- + 92.2 , T1.9 - 99.7 30 9 z.o 9z.o 91 5 ": 92.0 . ., w-+.90/z - . if,2.
- 32. 93.2 92.s- 91.1 j-W.&}y@t--- 97.0 34 9 E.z 91.4 90.8 - 92.4i..' M 14-1 96.1 7
(, 36 91.0 90.1 91.3- j 9t;t -
-j91.Z. 96.G Revision D l _ y Prepared By/Date % M1 .
g Checked By/Date M kh(I l c.~ -.__-_.-...,_.,,,.,__-,__.__._-_,._..___..__,,,,,,.....__,_,._.,_,m,-y,,,., _ _ , _m _ ,,y_.,, _ _ .
=-- . - - . - - . _- _ - _ . ._..___ __ _ _ _ _ __
15 nutech .
- senJo convern
[. Propet ^ 5 W IC- fAm bet Y'ic %* File No fEs.'Zh.03cc 6C~.% Powec- J L;.ht- O , _ . f c :.a. ciMt
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au di d u c. b . % c. I-
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o -l M 4 . _ . . TABLE 3.2. 4
.__.i . .
. . . TIME-AVERAGEb DEVIATIOR OF TEMPERATVRE @ 20" FROM TH AT OF WERAGE BAV TEMPERATURE Ea.3 De.vi.ati.on(*F)
- {
C H.9 B '+. 2. (. .. H 3. s' l t E/F 43 l i i. , D/E 2.9 t. D tt.8 r l Remien o I ease 32. Prepared By/Datt @ h) t56(+ P(t/gll l Checked By/Date ' l f \
San Jose, California
- pg ruw.statek beawm b e r b C b
- File No fM 2_w.o3co :.
~ w Gehn Po- m.l LtLt Co m . i
- -4.qtMA1 Ent- aJ QuLs%e&A.
. *,. - t se V
'll
.hh.[$M.NLk 'T3MPERATURE AND DEVIAT ORS FRd4 pVLX@ 30"(*F)
~
'~ j -TMj%in') -lT @ - - c-e v. o;; d -- % as; I !1 ' Oe - -L Et.0 0.0 0.0 0.0 0.0 0.0 0.0 r
. . .. . _.g . . _.,. l .58.6 12.4 -LG -G.C -5.s -3.4 33.0 4-
-! (,5.3 7.5 Z.5 -13.3 -12.2 7.6 %?
6 - 72.0 32.0 1.0 -18.o -18.S -1.8 49.9 I 8 78 G 33.8 15 4 -z3.G -25.3 -0.3 47.3 10 SS.2 34.Z 18.7 -19A - 12.% -S.9 43.'i tt 89.o zG.4 IZ.a -1.s o.z. -3.0 13.5 14 29.0 -3.3 1.6 3.6 E.0 5.0 3.5 16 29.0 -4,9 -101 -2.2 %.1 q.2 -Z. 0 18 39.0 - 1.0 - 7. 5 1.3 5'.~1 3.9 15
; 20 33.0 1.2 - 1.6 5.7 4.S 2.F E7 12 29.0 1.% 3.3 5.0 2.5 -1,1 7. 2.
24 39.0 -0.3 34 3.s 0.% -1.7 11.1 26 E.o 2.9 2. 0 ~&F Z.3 ~ -0.2 10. 5 2E 29.0 1.0 5.0 3.0 3.2 o.y 10.7
- 50 89.0 3.0 3.0 25 3.0 1.2 %Z :
32 E9.o 4.1 35 Z.S E.4L . o,3 go 1.2 34- 89.0 3.2 ZS 1,8 . 3.41 7.1 i 36 31.o 2.0 1.2 23 3.s . z.2 7.6
'~
Revision O I py, 33 Pre;;ared By/Date Checked By/Date q M hl C Iytf" @ @ l g g _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - ~ . . _ . _ - - _ - - - -
r' li nutech - - San Jose, California - pg _brudk be b b Pkd~ Rie No MSTM MM I w h 6 % .c o A Lt.W c6.~m o - ij h
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[ Z~ TABLE 3.2.(, [' VOLUME-AVERAGEb bEVIATIONS FROM ButK e s"(T$ Time (min) e Time (mtw) e
.. 0 0.0 20 3,8 a - 1.s zz s.s-4- -2.3 2.4 Z.7 L.~
6 -3. z z.6 3.0 s -4,4 22 3. 2. 10 0.3 30 1.T l l c 12 (e5 32 3.1 ll 14 3.1 34 3.S
< 14 - 1.4 36 1.7 12 1. 0 3
5 *^
~
i l b' Revision h l l p,,, 3q Drepared By/Date MM ! of g Checked By/Date $ ' 6 W /71 l
,, .... ,_ m... __- - ... _ - - - -
4
- ~ '
nutech rt. San Jose, California pp .), uwGwkc.k Nec m Eke.ciric. b^ File No IFF.2301.03co LO
- .\im Powe e- M Lt h O~~ - u i i
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- .9
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'~
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= / i 1
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P VEhrT HEADER suPFcRT COLUMNS k ssu me. Am.y opea$ Udec Level = ((-)# +(-)t-7]= (-n'-r" el = 0 '-l' - (- ) 2!-5" = 30"
'~
R = lLf'-(,# j']Lf" i
, From CRC. 5t*d <A R't( 'Td\e ,1 % E d. , g . 1 z.:
_ Ap,,i = R* ces~' (-k) -Q R ._4 2 2.
- The L , h du lu el is gven in Rdueace ~5, okde,
( - t Od( okl1 < C[* mCWSi OM 4ft ("c m kE&49C C. 7. Revision D l p g Prepared By/Date @ hMf7l l d & Cne:ked By/Date @ (5@f/ l l
= . _ _ _ . _ _ .
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RAI 6 - PUAR Section 2.2.2, AC Section 2.13.7 During the discussion concerning the SRV load cases which are applicable to Brunswick, various load cases were eliminated by stating that these load cases were bounded by others, e.g. case A1.2 (SBA) bounds A1.2 (IBA), thus only A1.2 (SBA) was analyzed. Justify these statements by providing the results of the computer analysis which were performed or the reasons
. why various cases bound others.
RESPONSE
A. The actuation of a Safety Relief Valve (SRV) results in tha following loads:
- 1) Thrust loads on the SRV piping and T-Quencher (RVFOR)
- 2) T-Quencher water jet loads (T0 JET)
- 3) Pressure loads on torus shell (QBUBS)
- 4) Drag loads on submerged structures ,(T0FOR)
These loads were calculated by GE's computer codes RVFOR, TQJET, OBUBS and T0FOR, respectively. Table 1, Attachment RAI 6 shows computer analyses performed for various SRV loading cases (marked by X), and reasons why various cases bound others. For A1.2 and A3.2 load cases, both SBA and IBA are required in the load specification. The only input difference used in c.alculating thrust loads for SBA and IBA is the drywell pressure at the time of air purging from drywell to wetwell. For Brunswick, the drywell pressure is 22.6 psig at SBA and 21.6 psig at IBA. This small dif ference in input leads to small variations in the magnitude of the loads. Table 2, Attachment RAI 6 indicates that the loads from SBA are slightly greater than those from IBA, (. it was therefore concluded that A1.2 (SBA) bounds A1.2 (IBA) and A3.2 (SBA) bounds A3.2 (IBA). I
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RAI 6 - PUAE Section 2.2,2, AC Section 2.13.7 (Continued) ; l RESPONSE (Con *.inued ) ! I For cases Al.1 and A1.3 the same initial conditions apply in l RVFOR, but the ASME S/RV flow rate for A1.3 is less than A1.1, i l therefore A1.1 bounds A1.3. 4 l e e p.e - e l l ( l r t f'
4 9 Table 1 Analysis for SRV Load Cases Table 2 RVTOR -S/RVDL Discharge Loads
~
8 e O CAROLINA POkTR &' LIGHT COMPAhT BRUNSWICK SIEAM ELECTRIC PLANT UNITS 1 & 2 g' G A::achment RAI 6
m ~ _~ - - BNL. RAI 6 . O - bv. Table 1 Analysis f or SRV Load Cases
-( .-
sav
- Lead Cases RVTOR TQJET 03UES TQFOR A1.1 I I I I A1.2 I I I I [
A1.3 Use A1.1(2) Use A1.1( ) Use A1.1(1) Use A1.1(1) Use A1.2 Cl) 42.2 Use A1.2 N/A( } I(4) . A3.1 'Use A1.1(1) N/A( ) Use A1.1 C1) Z( ) - s
~
A3.2 Use A1.2(1) N/A( ) Use A1.2 51) I I)
.C3.1 I I I *I ,,
f.. . Notes: ,
- 1. Same initial conditions apply, hence same results can be used. -
- 2. Same initial conditions apply except the ASME S/RV flow rate.
- Ihe flow rate for A1.3 is less tha= thai for L1.1, therefore, i 11.1 tounds 11.3. Il.
- 3. Since the water jets from the arm cf one quencher will not intarac
, with the water jets from any adjacent quencher, only one valve discharge load should be considered (Application Guide 6) , 4 In some cases, instead of computer analysis a multiplier was applied to corresponding single valve loads to bound the multiple f valve loads. ;, m me i - l. i b. i
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( RAI 7 - PUAR Section 2.2.2, AC Section 2.13.7 The AC required that an asymmetric SRV discharge load case be considered for both first and subsequent actuations with the degree of asymmetric discharge for each event combination being determined from a plant-specific primary system analysis design to maximize the asymmetric condition. No mention of an asymmetric SRV discharge load case is made in the PUAR load case discussion. Provide sufficient information to satisfy the AC requirements concerning this matter.
RESPONSE
A. The various combinations of S/RV actuations was considered and the maximum possible effect of all the asymmetric effects are included by calculating the absolute sum of all the
. effects from the eleven S/RV's. See Section 1.5-d of PUAR for details.
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RAI 8a - PUAR Section 3.3.2.3, AC Section 2.10.1 The equations presented in the PUAR for interpolating the vent header deflector forces at various Z/L's are not consistent with the AC. These equations utilized the longitudinal multiplier distribution from NEDO- 24612'and thus do not incorporate the AC specification that the three-dimensional load variation shall be based on the EPRI " main vent orifice" tests. Describe in detail how the vent deflector forces were calculated at the various Z/L's.
RESPONSE
The pool swell deflector loads were calculated in accordance with procedures are described below:
- 1. Figures 1, 2 and 3, Attachment RAI 8a-1, show the load histories presented in the PULD for Z/L locations, 1.0, 0.5 and 0 used ar the calculation bases.
f
- 2. Figure 4, attachment RAI Ca-1, show the load histories for intermediate Z/L stations. These were calculated using the following interpolation equations:
i For 0 < Z/L < 0.5 F (Z/L) = [F (0.5) - F (0)] [K (Z/L)- 0.830] 0.170 +F (0) For 0.5 < Z/L < 1.0 F (Z/L) = [F(1.0) - F (0.5)) [K (Z/L) - 1.0] 0.350 +F (0.5) where K is the acceleration multiplier derived from the i EPRI 1/12 scale movie data (Ref.1) shown in Fig. 3-21 - of NEDO-24612, Attachment RAI 8a-2. The multiplier K, which is a _ function of longitudinal location, was developed in NEDO-24614 to take into account the three-dimensional effects.
. . - -, , , .,m, ,- . ~ . _ ,,,m____,+.--.__,_w%, ,-,,,,m., _ _ . . . , - _. . , _ , . . , , _ _ _ . .,~v.-.m .--.
RESPONSE: (Continued)
- 3. Figure 5, Attachment RAI 8a-1, show the Pool Swell Height versus Impact Time curves at Z/L locations, 0, 0.5 and 1.0. These curves were based on the Pool Surface Displacement Longitudinal Distribution curves shown in Figure 4.3.4.2 of the LDR and the Plant Pool Surface Displacement curves (PULD). Data for inter-mediate Z/L stations were linearly interpolated from the gener-ated curves. This process, similar to that described for FiFure 8-3, Attachment RAI 8a-3, was taken into account for the effect of impact time delay.
- 4. Figure 6, Attachment RAI 8a-1, show the Pool Swell Velocities versus Impact Time Curves at Z/L locations, 0., 0.5 and 1.0.
These curves were based on the Pool Surface Velocity Longitud-inal Distribution curves shown in Figure 4.3.4-4 of the LDR and the Plant Velocity Transient curves (PULD). Data for intermed-iate Z/L stations whre linearly interpolated from the generated curves. This process, similar to that described for Figure 8-4, Attachment RAI 8a-3, was taken into account for the effect of pool swell velocity due to the uneveu spacing of downcomer pairs.
- 5. The initial impact pressure (F) and the duration of the spike (t), for various Z/L stations were calculated using the following equations:
F= 7Vd 2 4
/ 2 t = 0.136d V
- where d = diameter of deflector (ft) V = impact velocity (ft/sec)
= water density (1bm/ft3)
RESPONSE: (Continued)
- 5. (Continued)
The impact pressure was conservatively added. Since the deflector is 3.75 inches above the pool surface, it will, however experience no impact as shown in Figures 1 through 3, Attachment RAI 8a-1.
- 6. Final pool swell deflector loads, Figure 7, Attachment RAI 8a-1, can be obtained by combining the impact and drag loads and con-sidering the effects of time delay, (Reference Figure 2.10-3 of the Acceptance Criteria).
The above procedure complies with the LDR, Revision 2, except crep 2 which is further discussed in the Response of RAI 8b. References _
- 1. Three Dimensional Pool Swell Modelling of a Mark 1 Suppression System, EPRI NP-906, October ,1978.
- 2. . Mark I Containment Program Vent Header Deflector Load Definition, NEDO-21612, april, 1979.
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f Figure 3-21 i Page 3-36 ; 4 (Total 1 Sheet) . u . CARO'INA POL'Dt & LIGET COMPANT 3R"NS~~ICK S?AM T.*!C"RIC PLANT UNITS 1 & 2
/ Attachment RAI Ba-2
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t TERIE DDENSIONAL POOL ShTI.L MODELING , 9 i
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MARI I SUFFRESSION SYSTIM . ; i IFRI NP-906, OCT. 1978 - Pages 8-3 and S-4 . (Total 2 Pages) . . m - r r. (. O CAROLINA PCrJER & LIGET COMPANT BRUKE% TICK S~ RAM ILECTRIC FLANT UNITS 1 & 2
- I I
t h e
- '( Appendix RAI Ba-3 9
e e 9 9
. . . , . . . e-e . ese e-* - w omes-
- _ . _ _ , - , . . - , , . ,9 , , - . , , . - - _ , . , ., _ m , , , , ,.- c__, - , , , . _ - . . . , , - - -
- ,7 ,__ w - - - .~ .. w . .u...,- - - - - . . - -. . . . . . w a
. e ,
a l i . I was aeossaary. T.arly attempts at mamerinal d.!".f aren_iation wara nasatisfactory 3 because the process of differentiation amplified any i=reyslarities in the original
. data. *be 1.treyularities, manifestad as wifgles in an otherwise smooth serva, were associated with film reselstian and projector registratian.
Fayure a-3 aws three of these untreatmo pool swall historias. D e symbal paints ; !
,8 are idaselM=rst asmaal data paists sannered every 2 as. Se sesrumpending walacity l
- historias, nr. aimed by differentiation, are shame la Fiyare 8-4, dLimb AmarW ;
absus the --'*wtism of izzeyularities. Inne adwaree annaequeten af this .
--"*weian was that the peel swell velocity 4m*=e==tian had an unaoseptably 3 1arye asattas. .
e :
~
- to on=ress this shortaaming, a special data reduction sabame was deviseL Firs % 4 the untrasted pool swell histlary was replaced by a thir6-order polyansial fit., thma .
i the d' **erentiation was parfa=umed. Sia scheme was $ns** fied heemase the mass of *
- l .
water ps_ icip. ting in the poet swan =a ao lary that a $e *y motism was sinoly L me . .- -- N - - A 1.as.-squarne-fit zestiw was specially deval= Ped far this purposa. ( lL' [
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.i
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.a . .
4 l*
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**is fi~iag zur=Las put ex=a emphasis on the last 10 data points priar ta impact ,., ,
Dy assigr.isy them a higher weighting far*.o=. In se doing, the de=ived polynomial .! represented r. truer average of these points, thus resulting la a more asserate P ign=t velo =ity. Flyure 8 *5, a suparposition of four pool swail histories of four . repeated tests at s ation 1. shows the sta istical variance la t.be row data. I
- I-Flyure 5-6 shows the **'-6-crear polys.w.ial . fits to t.he raw data of " Figure 5-1 ya- 7 d--*, salse.ed raw data . poi ==s are superimposed. Figure 5-7 shows the l cssresponding pool walacity histaries ch a.ined by d* **eren iatim of these [
i l pecy- '='- if one overlays ripres h3 a=15-6 and Figures S-4 and 8-7, the
- i e
polynomials and their derivatives v:mid represent smooth averages to the raw data. t
.* L 1
A set of graphs was prepared for asch motism p!cture mateir teet A typiaal ast *
- l. '
(Figure 5-8) shows the em--- menianas position (also a ** ' - -.- polyhmi ( , fit) , the --4 -- -'valocity, the pool surface . positions at tae fih 1 stations - - shown i= Flycre B-2, and the poc1 swell velocities. .t i i. r' y. w s-4 1 l
~
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-r-- , ,~, -y, - . - , - - - . , _ - , , - . ...,n. ..,-.,.,-,-..---,,,.,.,,.,,,,n . .~,.n.n.,,,n-n -.,_--.m , , ,,v..-, ,,-.. , ,
I a 1 RAI 8b - PUAR Section 3. 3. 2. 3, AC Section 2.10.1 Specify as part aof your response which longitudinal multipliers and set of equations were used in the interpolation process. l
RESPONSE
The longitudinal multipliers shown in Figure 3-21 of NEDO-24612, Attachment RAI 8a-2, and set of equations given in the response to RAI 8a were used in the interpolation for PUAR. New loads were calculated herein using lcngitudinal multipliers based on EPRI " main vent orifice" test, Attachment RAI 8b-1, and following interpolation equations: For 0 < Z/L < 0.5 F-(Z/L) = F (0) + [K (Z/L)- 0.825]
- 0. 2 35 [F (0.5) - F (0)]
For 0.5 < Z/L < l.0 F (Z/L) = F (0.5) + [K (Z/L) - 1.06] 0.13 [F (1.0) - F (0.5)] The new loads as shown in Figures 8 through 21, Attachment RAI 8b-2, reflect about 1% decrease at the non-vent bay nnd about 1-25% increase at the vent-bay. Structural analysis was performed using the newly calculated load. The impact spike forces which were conservatively added in the original load specification were not included in the new analysis. Comparing the results of the new analysis, (Figure 22, Attachment RAI 8b-2) with original analysis (Figure 23, attachment RAI 8b-2) show that newly calculated pool swell loads result in smaller element forces and smaller reactions at node 310. Structural evaluations based on the originally calculated po'ol swell loads W as presented in the PUAR are conservative. _ _ y - . , . , , .-.9-
. .. ~. s. . .s _m. . . . .: . . .. - - - . - - .. '
4 E i
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t i i I NEDO-21888 e Figure 4.3.bli Page 4.3.bl5 (Total 1 Shaat) :' I CAROLINA PCE*EP. & LICET COMPANY BRUN5k'ICK STT.AM ELECTRIC PLANT UNITS 1 & 2 i i l I Attachment RAI 8b-1
HEDO -21 bel T I 1 1*- ' tJ - u - u - - - 1.19 IG E a 1.06 E sn - 2 I es - E
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t i. 1 i i CALCULATItXt SET NO. t 9527-E-SC-DV-1-F i Shaats 33a thru 46a of 217 Sheet 73a of 217 . Sheet 73. of 217 i i (Total 16 Sheets) j s CAROLINA POWER & LIGHT COMPANT BRUNE'4"ICK ETEAM ELECTRIC PI. ALT . IEITS 1 & 2 - f 1 l f 6 Attachment RAI Sb-2 i
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RAI 8c - PUAR Section 3. 3.2. 3, AC Section 2.1.0.1 1 In addition, specify what the Z/L is for the typical pool swell i impact and drag load given in Figure 3.3.2.3-1 of the PUAR. a
RESPONSE
The Z/L for the typical pool swell impact and drag load given in Figure 3.3.2.3-1 of the PUAR is 0.792 as shown in Figure 11, Attachment RAI 8b-2. b
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RAI 8d - PUAR Tables 3.9. 2.1-1 and 3.9.2.1-2 Indicate service levels for bolts and welds listed in Tables
- 3. 9. 2.1-1 and 3. 9. 2.1-2 of PUAR. -
l
RESPONSE
The structural acceptance criteria used to evaluate the acceptability of the existing Mark I containment systems or to provide tha basis for any modifications required to withstand LDR defined loads, are
. generally through the Summer 1977 Addenda to Section III, Division I, ASME Boiler and Pressure Vessel Code. The analysis showed that
. load combination No. 18, which consists of dead load, earthquake, LOCA thermal and LOCA pool swell loads, is the governing load case.
Service Level D is spec 4fied for this load case. However, the bolts were conservatively designed by tha allowables of Service Level A. As for the welda, the 1977 ASME Code lists only one set of allowables and is silent about its applicable service levels. As such, no service level was indicated for the welds in the PUAR. O 6 w.,. . v ,-.- _.. - - _ . , , , , .-
RAl 9 - PUAR Section 3.3.2.5, AC Section 2.12.2 Describe what analyses were done to satisfy the AC requirement for multiple downcomer chugging synchronization. Indicate what exceedance probability was used to assess the statistical directional dependence and what the corresponding force per downcomer was.
RESPONSE
Two worst case load conditions were analyzed, 96 and 8 downcomers chugging synchronization. Quasistatic loads, including dynsmic load factors, were applied to the 180 beam model of the vent system. The mitered joints were reviewed per ASME Boiler and Pressure vessel Code, 1981, Code Case N-319, " Alternate Procedure for Evaluation of Stresses in Butt Welding Elbows in Class 1 Piping Section III, Division 1". Stress indices (C 22 = 9.0 for in plane bending, C23 " 11. 4 f r ut- f P ane l bending and torsion) and maximum stress intensities were computed. The latter were within the code allowable s. i The exceedance probability used to assess statistical directional dependence was 10" per LOCA. The corresponding plant uniqu'e force for Brunswick was 6.6 Kips per downcomer for the 8 downcomers for the 96 downcomers synchronization, depending upon direction.
~
RAl 10a - PUAR section 1.3.4, AC section 2.13 Provide more detailed information concernin'g the T-quencher utilized in the Brunswick plants.
RESPONSE
The T-quencher utilized in the Brunswick Plant were compared to those used at Monticello and found to be identical, except that the Brunswick T-quencher does not have end cap holes".
References:
Brunswick: F.P. 9527-66038 (GE Dwg. No. 794E828) Monticello: Tee-Quencher Stress Analysis Report 22a6010 Fig. 4.2 9 k lC
RAI 10b - PUAR section 1.3.4, AC section 2.13 Specify any dif ferences such as hole spacing, hole diameter, etc. between the Brunswick T-quencher and the T-quencher tested at Monticello.
RESPONSE
There are no differences,, the hole size and spacing of the two designs are identical, except es noted i'n "'a".
References:
Brunswick: F.P. 9527-66038 (G.E. Dwg. No. 794E828) Monticello: Tee Quencher Stress Analysis Report 22A6010 Fig. 4.2
RAI 11 - PUAR Section 2.2.1.8, AC Section 2.14.8 Provide the details of a post-chug submerged structure load calculation for a given segment of a vent header support column. Include numerical values of source strength and DLF as a function of frequency. In addition, provide the acceleration volume, drag coefficient, interference effect multiplier and pertinent geometric parameters and configuration used in the calculation. RESPONEE The post-chug load was calculated based on Application Guide 2
, (Ref. 1). A rectangular s?.ll model which includes 18 down-comers and the vent header columns was made. The submerged length of column A is 11.02 ft. which was divided into 20 sections. The length of each section is 0.551 ft. which is less than its diameter of 0.552 ft. as required by Application Guide 2. Inputs for section 1 which is near the water surface are shown below:
The location of the section centers are: XSTR (1) = -2. 267 f t. l l YSTR (1) = -2.609 ft. ZSTR (1) = 173.18 f t.
, Orientations of structure section axes are:
SX (1) = 0.0 SY (1) = 1.0 SZ (1) = 0.0 Structure section acceleration drag volume (VOL) and projected area (AX) were determined as follows: V$L (1) = 277R2 L=2 (0.552) 2 (0.551) = 0.264 ' 2 AX (1) = 2RL = 0.552
- 0.551 = 0.304
() The drag coeficcient (CD) for cylinder in this case is: CD (1) = 3.6 Standard drag is included conservatively without calculating the value for U mT/D. The column is adjacent to the center support of the T-Quencher, the interference effects between neighboring structure were calculated as follows: rl2 = 1.968 < 315 = 4.008 li = (0.552 + 2.12)/2 = 1.336 XI = rl2 - 1 = 0.473 D AI = 0.2 ( D9 ) = 0. 3354 XI Di+D2 DI = 0.2/XI = 0.4228 The multiplier (1 + AI = 1.3354) was used to increase the acceleration drag and the multiplier (1 + DI = 1.4228) was used to increase the standard drag. These multiplies were applied to the acceleration drag volumn (VOL) and the drag coefficient (CD) respectively. The drag force due to the source at 26.5 Hz. was calculated. The amplitude of the source function at frequency 26.5 Hz. is 377.83 f t 3/sec ;2 hence AMP (NB) = 377.83 NB = 1, 2 FRE0 (NB) = 26.5 NB = 1. 2 Only the two downcomer vents nearest to the header column need to be considered in post-chug calculations. The downcomer vents and corresponding phases for calculating maximum loadings are given in Table 1, Attachment RAI 11-1. Using these relationships, maximum loadings in the X, Y and Z directions and the maximum (_. l l l nomeht were computed for a frequency of 26.5 Hz. The post-chug loads for other frequencies (Table 2, Attachment RAI 11-1) were obtained by ratioing the amplitude of the source function with respect to that of 26.5 Hz. A steady state analysis was conducted to determine the dynamic effects for each frequency. The dynamic effects were not output in terms of dynamic load factors (DLF). An absolute summation of the individual responses of all 50 frequencies was then combined with fluid-structure-interaction induced drag loads to form the post-chug design loads. For more information, refer to the attached conf,iguration, calculations (Attachment RAI 11-2) and computer output (Attach-ment RAI 11-3, 4).
Reference:
- 1. Mark I Containment Program, Application Guide 2 NEDE-24555-P.
4 9 a 4 Y 1 y.
~.__._- . . - - - - _ _ . _ - _ _ - - , . , _ . _ _ , - . _ _ _ _ _ , . _ . _ _ _ . . .
I l p s Table 1 The Downcomer Vents and Corresponding Phases Table' 2 Amplitudes at Various Frequences for Post-chug Source Strength V CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 & 2
]
C Attachment RAI 11-1
BNL R A E //-/ p.- TABLE 1 The Downcomer Vents cnd Corresponding Phases ' Loading Condition Quadrants Downcomer Vents Phasing Maximum Loading I/IV 11, 12 180* out of phase in X-Direction II/III Maximum Loading I/II 10, 12 180* out of phase in Z-Direction III/IV Maximum Loading I/II 10, 12 In Phase in Y-Direction II/Ill III/IV I/IV , Maximum Moment I/III 9, 12 , 180* out of phase II/IV , V
23//L /f/137 //- / IABLE 2 , f, '
- Amplitudes at Various Frequencies for j i
Post-Chug Source Strength ! l Frequency (HZ) Amplitude (ft 3/3,e 2) Frequency (HZ) Amplitude (ft 3/sec 2) 0.5 11.98 25.5 313.84 i 1.5 11.98 26.5 377.83 2.5 10. 36 27.5 251.89 3.5 9.87 28.5 163.32 4.5 17.40 29.5 116.66 5.5 17.00 30.5 43.14 6.5 18.88 31.5 21.57 7.5 18.88 32.5 37.91 8.5 18.88 33.5 50.54 9.5 18.88 34.5 42.54 10.5 87.90 35.5 61.87 11.5 76.18 36.5 41.95 12.5 41.01 37.5 20.97 13.5 35.89 38.5 24.47 14.5 6.82 39.5 29. 37 15.5 6.20 40.5 224.90 16.5 3.14 41.5 224.90 17.5 4.18 42.5 224.90 18.5 2.94 43.5 224.90 19.5 16.82 s 224.90 20.5 17.53 45.5 224.90 21.5 30.67 46.5 90 22.5 92.39 47.5 224.90 ( 23.5 92.39 48.5 224.90 24.5 134.50 49.5 224.90
i CALCULATION SET NO. 9527-E-SC-SL-3-F Sheets 62 to 66 of 471 Sheets 61, 62 of 180 Sheets 159,161,163 and 164 of 471 Sheets 167 to 170 of 471 (Total 15 Pages) e s O CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLWT Units'l & 2 1 Attachment RAI 11-2
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