ML20080C425
| ML20080C425 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/11/1983 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| REF-SSINS-6820 IEB-80-11, NUDOCS 8308260039 | |
| Download: ML20080C425 (100) | |
Text
_ __-_____ - -
I GPU Nuclear
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P.O. Box 388 g{
Forked River, New Jersey 08731 3
609-693-6000 Writer's Direct Dial Number:
August 11, 1983 Mr. D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Cotraission Washington, D.C.
20555
Dear Mr. Crutchfield:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Additional Information Regarding Masonry Wall Design (IE Bulletin No. 80-11)
As stated in our July 15, 1983 letter, responses to your request for additional information regarding masonry wall design at Oyster Creek will be provided by two separate submittals. This correspondence addresses items 2, 3, 5, 6, and 9 of your request. Our responses are as follows:
Item No. 2:
Provide sample calculctions of the stresses for a typical stacked bond wall.
Response
Investigation of wall No. 2-2 (Attachment 1) is such a sample.
Item No. 3:
Indicate if walls are subject to impact or tornado loads.
If so, provide sample calculations for impact and tornado analysis.
Response
All concrete block walls are located inside the main st ruc t ure s. No impact or tornado loads, except seismic, have been considered in the analysis.
Item No. 5:
Provide sample calculations illustrating the analysis of a multi-wythe wall.
Response
Only one multi-wythe wall (No. 43) was identified in previous submittals. Due to lack of collar joint, this wall was analyzed as a single-wythe wall of the thickness of one wythe (12 inches).
Item No. 6:
In a meeting between the licensee and NRC staf f on March 31, 1983, it was indicated by the licensee that non-linear techniques, such as energy balance technique and arching actions, are no longer relied upon to qualify masonry walls. The licensee is required to confirm this j
indication. Otherwise, these issues will remain unresolved l
until the establishment of the final staf f position on them.
l 8308260039 830811 Ib[
PDR ADOCK 05000219 G
PDR GPU Nuclear is a part of the General Pubhc Utilities System
};
Mr. D. M. Crutchfield, Chief August 11, 1983 Page 2
Response
During the first stage of calculations, wall Nos. 8,15,19, 20, 21, 22, 23, 24, and 29 had been qualified by operability calculation. Subsequently, additional supports were designed for thece-walla jnd new calculations performed, taking into cont.ideration the new supports to be provided.
All walls are new qualified using linear techniques.
Item No. 9 Indicate the current status of the required modifications and provide detailed drawings of some sample modifications.
Re sponse:
The current status of the required modifications is as follows:
Walls Completed: Wall Nos. 9, 10, 11, 12, 13, 14, 34, 35, 37, 38, 39, 40, 41, 42, and 47 Walls to be completed during the current refueling / maintenance outage prior to restart:
4 Wall Nos. 1, 2, 3, 4, 5, 6, 7, 16, 21, 22, 23, 43, and 46 Walls to be completed af ter restart and/or daring the next refueling outage:
Wall Nos. 8, 15, 17, 18, 19, J
20, and 25 Walls that require further analysis: Wall Nos. 24, 29, 30, 31, 32, and 33 (refer to Attachment 3)
Walls which did not need modifications: Wall Nos. 26, 27, 28, 44, and 45. shows typical modification details for wall Nos. 24, 29, and 30.
Additionally, by letter dated April 15, 1983, to Mr. Eisenhut, we requested deferral of block wall modifications until af ter startup from the current refueling / maintenance outage (Cycle 10) with lastest completion projected for the next refueling outage (Cycle 11). As indicated in Attachment 1 of that letter we agreed to perf.rm a more detailed evaluation of af fected walls.
Attachnent 3 to this lett er provides the results of that evaluation. However, further analysis is required for five walls which are identified in the response _ to Item No. 9 above and in Attachment 3.
The modification l
implementation schedule for those five walls will be provided together with our l
response to the remaining items in your request for additional information by l
the end of Oc tober 1983.
Mr. D. M. Crutchfield, Chief August 11, 1983 Page 3 If you should have any questions, please contact Mr. James Knubel at (201) 299-2264.
Very truly yours, 4 0_
F Pe'ter B. Fiedler Vice President and Director Oyster Creek PBF:jal Attachments i
i i
cc: Dr. Thomas E. Murley
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Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 i
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.~;:t:r Crcsk 2 :1 car Station 13021-323 -106 T.sevalmier. of Ccncrete Masonry Wall NRO II Sulle.in 80 - 11 INVESTIGATION OF WALL NO.
COffrENTS FACES DESCRIFfION jf.Og
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Summaary of Results j tof of 73 2.
Elevation of Wall and location of 73
[to 3.
Attached Loads and Masses 4.
Geometry and Input Data for Frequency Analysis
[tofof[#)
for Uncracked Section, One Way Model
((to(( of [h 5.
Frequency Range and Input Data for Static Analysis for Uncracked Section, One Way Model 6.
Static calculations of tmcrackad Section, One Way Model
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Geometry and Input Data for Frequency Analysis for f/tokof73 Uncracked Section, Two Way Model 8.
Frequency Range and Input Data fo; Static Analysis
((to2[offb for Uncracked Section for Two Way Model Static Calculations of Uncracked Section,[p/ch Way
((co /cf73 9.
Nodel 10.
Geometry and Input Data for frequency analysis 8 to k of 73 for cracked section, one way model M[ toMdof 75 11.
Frequency range and input data for Static Analysis for cracked section,.one way model 12.
Static Calculation for Cracked Section, One Way Model 8 to[3 of 73-13.
Geometry and Input Data for Frequency Analysis for ff to [f,of 7.,,3 Cracked Section, Two Way Model e
14.
Frequency Range and Input Data for Static Analysis
[v3 to hf[3 for Cracked Section, Two Way Model 15.
Static Calculations for cracked Section. Two Way Model
((co7.3 of M to --ed -
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Operability Calculation 7
to -of 17.
18.
Reference Sketches and Supporting Fages Items.
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Thickness:
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Model Width:
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Type of Block: ASDL - C-90
( ) Running Bond Construction Mortar: Typa "M" (X) Stacked Bond l
(X) Reinforced
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( ) Unreinforced Frequency (X) One Way Range - Ez (X) Vertical Span 6.23 To 7 s, (Uncracked
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( ).3-Edge Support
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Acceleration CBE )
CBE )
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@ncracked 0.56 g,
(SSE )
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(Allowable)
Vs (SSE+DL)
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(SSE+DL)
(Allowable) 1 (x) Parallel to Bed Joint, 34.5
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(Allowable) 48.4 vs 27.7
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(Allowable)
Continue for cracked section model analysis Wall No. 2-2 Remarks I
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Frequency Ot) One Way Range - Hz
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(K) 4-Edge Support 12.27 To 15.03
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(03E)
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1.33 g
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(SSE)
(SSE)
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Stresses - psi
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(Allowable)
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(Allowable) f
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(Allowab[e3
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(Allowab[e7 (K) Parallel To Bed Joint 26,108 vs 30,000 f( ** ) :
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(Allowable) 35,080 vs 63,000 (SSE+0L)
(Allowable) l Model 2 of Wall #2 is good for Two-l Remarks Way Model - Cracked Section Wall No. 2-2 l
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13^,22-3EIC-D6 CPU Servica CALC.NO. Oyster Creek Nuclear Station SHEET NO. OF Reevaluatica of Concrete Masonry Wall .. g..gg..g.1116 tit.~ E3 ' ' ' '11 ' ~ DA TE '.b' '- / /I SUBJECT lt/4/l Ff - 4 NO4ff f N/M NI'O'Y c ."~'el',o^a 'E.r[:'" K g,{ o 5h 5yyJ/p)B,$'b'6Lc?GQ, MF//W/ PHTM'd'20'* / 16A O. 94F 7'-DI-WT/ CAL TE~N!/LF !7A'E!:EC FfD NfbAL .TWR pH //p//EdME4' )/fNTA/I dl/ !A Pk': g 19 -3/7.fi W l!g,.9-f3 g I9 -117. 2 l -y q = 5% l lb 1707 l -gy,G i-1+.(H,9 7 !? 176.5 ! -iv.s ' =42.'1 1 i i i I i i l i i e i ..: 0,0 714./-&& ' - 0,0//5& Fg C_ e /-42 t e l
CALC.No $.02.bE-m 1 CPU servies Oy:;ter Creet Nuclear Station SHEET No - .$?ll N ? $$$ $f-lM M A//A!Xf8 'To_",;*e',',',k. I(/M .nesv32nction.cf. concrete Masonry Wall DATE. ho, SUBJECT e nw susysm,6a mox,mwame,eNawzbw '<. GAL 6Wf-f.D( VID.'Al 7Hnti F WRF.'!F.'" FKtM ELsM.~Y.:EZ sN N w & atrerds) Rfhf ?){ S yi.c. f. EM4MS. l x 6 //f. 5 -M./ M/ 7 l
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. -7A7 GPU Service CALC.NO..***' SHEET NO.. F, Oyster Creek Nuclear Station SUBJECT......... 9 eav22.u t!.icn..of. 4oncre.to. Masonry.. Tall.............. DATE.[.[ [.C... @ d WAu"h5?**lN"hk 2 -minc M! f""*" N' - ' " ...............................................................................n.../ o C &F WAY //PDFL,,6/U&'96c, MH&= AM:: :.. fdACcd=D 5??7 6EOMEfff ff AfGDEL. N'/M FJ W - AX-2./ n v (i6177D&/ O n n '23 '24 gS 1./ '22 e _w vi a . ve veo 4-9 a., 3 s, s,e h I/ / f 'lh h '0 G s e ,s ~8 ) [ f $"$ h Az -1.6 7 z- /-46 e A000 0016 l
"* ' l 35 Oyster Creek Nuclear Station SUBJECT... Reevaluation of Concreta..Vasonry.Jin11.. DATE. NE II Bulletin 83 - 11 CcMP. aYlDATE 9F A h/5-b bs-W b. CHK'O. BYICATE.. * {.. !.. f. lI2 ?Pof op 64.h de72ti^!(7 des.&Wif g'^'"'"j grE MfM-c 7o grqDwq. wo.22ffC #M z i 7 't a // b-J-(f i =A00 d= ?d=.9 l'/. f (Poa essrpa A"od) j%-f fi gg = 2 x /z x /a o.+ f&-"A*) X 9 2 =3y,Pfo"/;/ f Whu ., lue7t'k4-=. l-[!2 x T: D Y't t -3 ) x.3 4l.. /z. =/(I2.4'"/.// c f *.f 87 /z = 2. 702 " N (, ,ft.[t%(o}N= r.11y= o.y H /k = kr,-f = l4y i z.7 8. ray x t:.t ! j'f ty 9 9 " '"~/f/* c 2cibcy, = 7 &Zsif rs A= o.)ct-x s x s. D = hi7 afp l ,,a a E'I =.r.4 %qg-p 9 p~/' f' Gkr>~G bz =[i4 zj tR97 E=.( f t2 '% o,ny lp ~ f ] ( w r p= g(t m a i o n w n' n u n m.'.....,. i \\ .c ps ruy,pp,_4,
23a21-322:.ics eu me exc. ~o.. SHEETNO... .OF. Cyster Creek N;: lear Statien susJECT .Reevaluatio3 of Concrete Masonry fall DATE../..'[..:../f [.9... NRO IE Bulletin 0 OM P. BYlD ATE.. 7. :. pg gg cm.o..y,o,1E. 3,. y y.3 $$$8 h/Al 8/$C,~Q f
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GPu semce CALC. NO.. ~ ~ Cyster Creek N;: lear Station SHEET NO. - .0F.. SUBJECT.... 88.e,ga,1,qa,tjen,,cy,,Cep,:r,e,te,, Mas,cnry, Tall.. DATE. . $... 7'. " *"g '7 N2; II I.dletin 80 - 11 ) f./...t..(... C...... /?..A.. W....=. '... . MA. CK.N.!F K. cu.".wo rE :.... . >.4 o. i k Es = 2 s/,0 Vidh - 2sAO x y.'ews =/.m gg,l It- " f) E = //2. 6-f f.f 7-/54 57 AV # t y.= 5./3/2 - 2.//5/d ffa = *2.//f'M N = Siff /# U M'.-foo //2 = f/// If48. 4 N" /06fd / /7Cd 1/4 I 969.= Ze = !./76f I +(/- a/764).&x t Zc = O '7Sf' /67,57 +[/-J./X f} W Tc - 44'. 9 /Nf ' /#nr THinweis $*h (( ~~ ~~ /NfAT MMSiry ppy3__ J.0/ x0. @.- 4 gg-L a276 l 1-60 aooo ooie e l l
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GPU sevic* CALC.NO.19 ~ Cyster Creek Nu: lear Station SHEET NO.. . 0F. SUSJECT.. ......Reaveluation.cf.Concre:2. Masonry fall DATE./[<. . hN. .. ?$! h?k.?...f7A77f.AMA(@X *,.'"l,',o*ll,"f ,\\- L; l e /EfMAf/W~L &# 4/96Q AfMF /W/t, CMO:d=615%~ j ffEdf=~MYR7f5) f#F ///AY/MSFL auf //JSC /4W M X5 GSftfL 94FtDL /$ / 79
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13022 322C-M6 W M ** CALC.NO.... Oyster Cr:et Nu: lear Etation SHEET No. OF neev:1;1:Lon of Concrete 90SJECT. ........g7.I; ;,(ty1hg* g* "b'd ' 7 5i. Mssanry.1L11.... D#*** j' f'..,/;#) M.. h(4ti J 2 - $4fl2..:?A77C.$?M/?cnn'o'w**;&!'?'- COMP. 8YiDATE
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_m k ATTACHMENT 3 A
WALL FAILURE CONSEQUENCE ANALYSIS
1.0 BACKGROUND
In accordance with the requirements of NRC I.E. Bulletin 80-11, all masonry walls at Oyster Creek that are in proximity to or have attachments from safety related piping or equipment such that wall failure could af feet a safety related system have been identified to the Nuclear Regulatory Commission. These walls are being upgraded to meet the more current required seismic standards. Of the masonry walls identified, twenty-five still require modifications. The first and third reports to the NRC (dated July 7, 1980, and November 14, 1980, respectively) identify'these 25 walls which are discussed in this report. 2.0
SUMMARY
Of the twenty-five walls that require modifications, only twelve walls are located such that a failure could impact on the plant's ability to be brought to a cold shutdown. These twelve walls will be modified during this refueling outage. Additionally, another eight walls will be repaired during the following refueling outage. The engineering evaluation that provided the basis to defer these eight walls for this interim operation is provided in EDS Nuclear Report Number 02-0370-1137. The remaining 5 walls will be reanalyzed prior to October 1, 1983 to determine whether their failure can disable the safety system they may impact.
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- l If the analysis demonstrates that safety system operations will not be prevented by wall failure, the walls will be modi fied before startup from the next refueling outage. If the analysis indicates that safety systems will fail due to wall interactions, modifications will be performed this refueling-outage.
3.0 METHODOLOGY OF INVESTICATION The purpose of the EDS study was to determine if the failure of the masonry walls following a seismic event will impact on plant safety. This was accomplished in two phases. First, by identifying the compocents affected by the wall failure. Secondly, an$1yzing the effects of the component f ailures on the respective system and ultimately the impact on plant safety and ability to achieve a safe shutdown condition. The methodology employed to complete this evaluation is sum-marized in this section. 3.1 Identification Phase The first part of the identification phase consisted of an evaluation to determine the direction of failure of the wall and the area of influence created by its failure. The area of influence is defined as the are the wall develops during failure and the ground area impacted. Allowance was made on the ground area to i i include possible sliding or shifting of the wall upon 1 \\ 1 impact. ( All walls are assumed to fail simultaneously following the seismic event. A plant walkdown was then conduc-ted. An itemized list of the components, cable trays, piping, and other equipment was developed for each area of influence. Subsequent to the plant walkdown, the itemized list was reviewed and equipment which had no impact on plant safety and was not required to achieve a safe shutdown condition were eliminated from consideration. 3.2 System Failure Criteria: The failure modes of each component, the ef fect on the system, and compensating provisions (i.e., redundant trains or alternate methods to achieve a protective function) were evaluated. It is possible that a loss of offsite power would occur following a seismic event end is assumed for this evaluation. Also, systems which are not seismically designed such as feedwater, condensate, turbine bypass, etc., are not assumed to be functional following the event. Give these constraints the impact of the system failures on the plant's ability to achieve a safe shutdown condi-tion was then determined. This review accounted for all systems (NSSS and BOP) that are affected by the system malfunctions and failures, as well as those which could be utilized for safe shutdown pathways.
. i No high energy line breaks or NSSS transients were assumed to occur as a result of the seismic event unless a pipe was ef fected by a block wall. In these cases, an evaluation was or will be performed to determine if the s incremental increase in piping loads is enough to cause pipe failure. Single failures and operator errors were not considered. S 4.0 RESULTS The equipment which could af fect plant safety or is utilized i to achieve the plant protective functions required for plant shutdown is af fected by the following wall failures: 1, 2,'3', 4, 5, 6, 7, 16, 21, 22, 23, 42 Walls whose failure does not directly af fect plant shitdown are as follows: 8, IS, 17, 18, 19, 20, 25 In addition, wall 42 was removed above the cable trays. Wall 42 was previously designated as a wall requiring sidition of boundary supports. The removal of the top of th'c wall elimi-nated the. requirement for boundary supports. Walls 24, 29, 30, 31, 32 and 33 will be reanalyzed to determine if'the ESW and containment spray piping can maintain structural integrity after wall failure. s -e s l \\
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5.0 CONCLUSION
Walls 1, 2, 3, 4, 5, 6, 7,16, 21, 22, and 23 will be struc-turally inodified prior to the restart from the current 1983-1984 refueling outage. Walls 24, 29, 30, 31, 32 and 33 will ,' y undergo additional analysis to determine if their failure 5J' would methally cause a failure to a safety related system that e-4 would effect the integrity of the containment spray system. ss If the, analysis determines that the walls have a negative ef fech$n the containment spray piping walls 24, 29, 30, 31, h 32, and 33 wil1 be modified prior to restart. The remaining ~ walls 8, 15, 17, 18, 19, 20, and 25 will be addressed and modified prior to restart froin the following refueling outage. 1 s- _= g e N. q-% 'lkw .7 w s t s s 4, s, j 'A is l h g ] \\' s l> l _gs + u.3 N. s vj ' s N s . s i / v
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