Text

Requests Assistance in Review of Info Provided by Util Re Facility Restart
	ML20090B458
Person / Time
Site:	Ginna
Issue date:	04/05/1982
From:	Lainas G; Office of Nuclear Reactor Regulation
To:	Grimes B, Knight J, Thompson H; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation
Shared Package
ML082380335	List: ML20090B377; ML20090B412; ML20090B428; ML20090B436; ML20090B439; ML20090B458; ML20090B472; ML20090B481; ML20090B485; ML20090B490; ML20090B493; ML20090B501; ML20090B505; ML20090B507; ML20090B511; ML20090B514; ML20090B519; ML20090B525; ML20090B528; ML20090B531; ML20090B534; ML20090B545; ML20090B659; ML20090B672; ML20090B676; ML20090D196; ML20090E676; ML20090E683; ML20090E686; ML20090G527; ML20090G531; ML20090G578; ML20090H603; ML20090H617; ML20090J352; ML20090J369; ML20090J521; ML20090J804; ML20090J811; ML20090J855; ML20090J859; ML20090J918; ML20090K082; ML20091B798;
References
	FOIA-91-106 NUDOCS 8204220150
	Download: ML20090B458 (81)
	v • d • e

{{#Wiki_filter:M OCh o. p.,.., d - e a sq h j APR 0 5 1982 ~ s7 MElf]PW4DUM FOR: Brian X. Grires. Director Division of Erergency Freparedness Hugh i.. Thonoson, Acting Director Division of Humn factors Safety Jeres P. Anight, Assistant Director for Components & Stractures Engineering Division of Engiutring / William V. Johnston, As31stant Director for Materials & Qualificatlan 4 Division of Engineering 3-Themis P. Speis, Assistant Director for Reactor Safety Division of Systems Integration FROM: G.C. Lainas, Assistant Directer t for Safety Assessmnt ( Division of Licensing JUBJECT: REVIEW OF INFORMATION PRIOR TO GlHNA RESTART 'q L We will need your assistance in review of infor5 nation provided by Rochester Gas & Electric Corporation with regard to the restart of the R.E. Ginna Nuclear PcNer Plant. Enclosure (1) is an outline of the Ginna Restart SER. We have indicated the areas you are requested to review and provide input for. Enclostire (2) is a 2.206 petition that has beers submitted by the Sierra Club. We have agreed to address items 1,2,3,4,5,6,9, 13,14,15, and 16 in our Restart SER and to raview the remaining itens as to tneir pertinence to the Restart of the Ginna Plant. Our initial review of the remaining itens (7 - 8,10,11, and 12) are attached as Enclesure(3). We would like your input on tue remaining items of the 2.206 petition to be included with the rest of your SER submittal since we must address all of the issues prior to restart. ~- ,. /,. M 'Q;LdIdAGE Y ,/, '\\ n f a + c ~~ --.__ omet > su m uth ..l. omre ) ,ncronu m o>anuncuore OFFICIAL RECORD COPY uw m , _ m, 1

f 9 Multiple Addressees APR 0 5 19tf2 The licensee't submittal should b+. ccrnpieted by April 16, 1982, Your input is rtx1 vested to be submitted tc the Project Manager, Jim Lyons (X24362), by April 23, 1982, to support the licensee's plannrj return to parer, Ray 1,19e2. If the licensee's schedule should slip, the Project Manager will keep you inforest of their projected startup date, k'ork performed during the re 11. Surnary and Cen:1usions ,#W l. 111. Steam Generator Analysis DL/3RAB Lead - Supoort From MTEB CMEB, MEB A. Previous History of S.S. Performance 1. ECT Adequacy Inspection Techniques & Results MTES l e 2. Types of Degradation Experienced MTEB 3. Plugging History ORBd5 5 4 Sleeving Efforts ORBS 5 1 8. Cause of Failure 1. Ruptured Tube MTEB -f, 2. Other Damaged Tubes MTEB 3. Source of Foreign Material RI ,( 4. QA Aspects RI I C. Cain vi DahrageT4.c kj e. t' u - (dbs in' MTEB/CMEB I 2 s 1. S.G. Tubes /. ; '.3 :P e 2. Reactor Coolant System, g q _j f D. Inspection Results j T. - L MTES 1. Primary Side 2. Secondary Side E. Metallurgical Results MTEB f ( l. RG&E/Wes tinghouse 'x 2. NRR Independent Analysis 3 F. Repairs and Mod [fications MTES/CMEB/MES G. Future Inscections and Actions 1. Secondary Side Video Inspections MidB 2. Loose Parts Monitor CPS 3. Cociant Activity L.C.O. ogg,5 f e,Ag 7

~~. Review Primary to 5econdary Tech Specs Leakage Limit ORBr5/ RAS~~
_________-__m_
\\ 2 IV. Pressurizer Power Operated Relief Valve Performance DL/0RS#5/MEB A. System Descriptien B. Failure Mechanism C. Modification and Repair V. Steam Generator Safety Valve Performance MEB A. Description B. Use and Failure C. Inspection Results VI. Adequacy of Accident Response A. Emergency Procedures DSI/RSB Lead - support f ro.n PT RS B. Instr rentation to follcr.v the course of an accident DHFS C. Emergency Preparedness EPLB VII. Conclusions and Reco m.endations DL/0PBr5 4 =v.
/
~~\\,~~
BJ-2AF April 23,1982 1 MEMORANDUM FDR: R. J. Mattson, Director e g Division of Systems Integration s 4 q R. H. Vollmer. Director w s Division of Engineering 4 4_ c, S. H. Hanauer. Director H e T Division of Safety Technology (d. Gr - 1; \\ h}l H. L. Thompson, Acting Director ( ' g y,N, ' Division of Htnan Factors Safety B. K. Grines. Director Division of Emergency Preparedness FROM: Darrell G. Eisenhut Director Division of Licensing
~~SUBJECT:~~
INPUT 1"0R GTHNA RESTART SER A memo dated April 5,1982 from G. C. Lainas set out a program for the review of information prior to the restart of Ginna. The restart SER outline proposed in that memo has been modifled based on our latest understanding of the event and is enclosed here as Enclosure 1. Since the release of the April 5,1982 memo, the NRC Task Force that was investigating the steam generator tube rupture incident at Ginna has documented its findings in NUREG-0909. These findings were pre-sented to the Cornissioners on April 15, 1982. Enclosure 2 is a list of the Task Force findings. Enclosure 3 represents questions that the Comissioners raised during the April 15, 1982 briefing. is a list of questions from Comissioner Ahearne regarding NUREG-0909 and the questions raised by the Comissioners need to be addressed in your SER inputs. We call to your particular attention several issues l flowing from the Comission meeting that must be addressed prior to restart: l a. whether 15-minutes for identifying a SGTR accident is acceptable l (RSB), i b.- the need for anindependent staff computer code analysis of the thernal gradients that the RV experienced (RSB), and whether the itcensee has adequate capability (hardware and l c. ( operator training) to recognize a large SGTR event in a timely manner (RSB). B205060626'820423St~ O r
~~,r 4xm. '~~
) \\ l! '1- , p g J r oF FICE ) ..a.. sunsauch ous> anc Fonu m om Nacu mso - OFFICIA t RECORD COPY uso w im - m 4
~( g 2 April 23,1982 Copts: of NUREOO909 and Rochester 8as & Electric's evaluation of the incident are av611able and have been distributed. The RG4E submittal covers everything exedpt the steen generator inspection, evaluation, and repair program which is due to be submitted April 23. 1982 and will be hand-carried to appropriate division representatives. One copy of the transcript of ths Commission briefing is being provided to each Division Director's office by separate cover, in order to ensure that this major effort is completed in a timely manner, we have estimated the following schedule: Licensee subnittals - recatved TR input to DL - May 7,1982 Draft SER to TR Managment for review - May 14, 1902 Issue SER - May 19, 1982 We will need your SER input by c.o.b. May 7.1982. A meeting has beEn scheduled for April 23,1982 at 10:00 a.m. in Roce 542A with Gus Lainas and your Assistant Directors to discuss this and related matters. Originc1 signed by Dat rell G. Eisenhut Ofrector Division of Licensing
~~Enclosures:~~
As stated cc w/ enclosures: DISTRIBUTION H. Denton Central Files F. Congel E. Case. G. Lainas W. Gammill E. Christenbury T. Speis L. Hulman M. Young L. Rubenstein D. Beckham W. Johnston V. Moore J. P. Fnight D. Ziemann R. Houston K. Kniel F. Schroeder T. Ippolito R. Bosnak D. Crutchfiele W. Hazelton J. Lyons V. Benaroya ORB #5 file B. Sheron R. Rosa ' W. Butler
~~0. Parr M. Srinivasan~~
~~? C. Berlinger~~
~~SEE FREVIOUS TISSUE FOR CONCURRENCE n~~
~~e DL.~~
5 DL: ORB #5*
DL: ORAB? DM ^D/SA DL A., one. y (,GL'a,, na s,,,,,,.E.b... ..sQ?pM,,,,A..... .u-o.Jh,.s:cc DCru tch,fi e,1 d TIppol 1,t,o__,, DE-4 ,,,,t ..# d./C... om> enonumpoe scuc2*o OFFiClAL RECORD COPY usam m u y 9 m---
o t 7 2-A cup, of the transicipt of the Cornission briefing is available in the pro. ject manager's office, Room 309. We will need your SER input by April 30, 1982. A meeting has been scheduled for Ap*1123,1982 at 10:00 a.m. In Roots 542A with Gus Lainas and your Assistant Directors to discuss this and related matters. Darrell G. Eisenhut. Director Division of Licensing
~~Enclosures:~~
~~As stated cc w/ enclosures: G Laina s T. Speis L. Rubenstein W. Johnston J. P. Knight R. Ibuston F. Schroeder R. Bosnak W. tb zel ton V. Bitnaroya B. Sheron F. Rosa W Bu tler~~
~~0. Parr~~
^ M. Srinivasan C. Berlinger F. Congel W. Gammill L. Rilman D. Beckham V. Moore D. Ziemann K. Kniel T. Ippoli to D. Crutchfi21d J. Lyons A A OR 5L. C-O RP. At f DL 0:DL .QJ473, g, omce) cuauut )..lyP.D A.:.d n.. DCru.-hdeld Glg/i,r,urs, _ DE i s er.hu t M,%. _, 9/,3(/82 9/./82 . gggu.,.. ,,, j om> 4 /Al./.82,, _., .9/Br e2.., MC FORM M 00 % NRCM Cm OFFICIAL R ECORD COPY usm mi-u
OUTLINE OF.GINNA RESTART SER
~~1.0 INTRODUCTION~~
DL/ ORB 45 EPLB 2.0 NOTI,FICATIONS L/ORAB' 3.0 SEQUENC_E OF EVENTS 3.1 Fummary 3.2 Cooldown t 3.3 Draindown 4.0 OPERATO,R RESPONSE RSB/PTRB/HFEB/0LI 4.1 Procedures 4.2 Evaluation 4.3 Conclusio'ns 1 5.0 EOUIPMENT.PERTORMANCE 5.1 B Steam' Generator Tut $e Failure _ Analyses DL/0RAB tea.d sup. MTEB.~ CMEB, MEB 5.2 'Pressuriser Power. Operated Relief Valves RSB/MEB/ASB 5.3 Pressurizer PORV ' Block Valve Perfomance MEB/RSB 5.4 B Hain Steam System HEB/RSB 5.5 Letdown Isolation RSB/CSB/ASB '5.6 Effluent Monitoring -Sys' tem ETSB 5.7 Sump A Level Indicator ICSB 4 5.8 Safety Injection Pump' ,'.C PSD ~ 6.0 ANALYSIS RSB 6.1 Comparison o.f Plant Response with Previous Analysis RSB 6.2 Steam Void Fomation 6.3 Calculation of Leak $. ate 6.4 Thermal Trans,ient on Reactor Coolant System GIB/RSB/MTEB 6.5 Hydrogen Transfer ,CMEB 4 6.6 Fuel Performance ' CPB. 6.7 SteamGeneratorOverhill MEB/RSB 6.8 Pressuri=er Power Operated Relief Valve R9B/MEB/ASB 6.9 Plant Water Inveitory DL'/0RAB s ~ ~ ~ ' m. mw. Y @ #M '
7,0 RADIOLOGICAL ABSESSMENT 'AEB/.RAB ~ '7.1. Reactor Coolant System and Steam Ger.erator' 'i 7'2 Radiological Releases 7.3 !!eteorologica7 Data 7.4 Sur,vey Teams 7.5 Samp'11ng (Air, Snow, Water) 7.6 TLD Measurements 7.7 Estimated Of fsite Dases 7.8 Additional Radiological Information' 7.9 Recommendations-8.0 C5nclusions and Reconmendations DL/ALL GROUPS' e Note: The first branch listed has lead responsibility for the item. l q 4 1 l l l 1 l l O ( i e l a. s W g D 8 4 -e, v.*=,..p+
m.. LM,LudUnt, 6 ,t; NUREG-0309 ISSUES TO BE ADDRESSED Findings _ Responsible Group Subject Area ' one l.4.1 1 N (Facility 2 RSB Procedure / Guidelines Response) 3 None 4 RSB RCP Trip ~ 5 RSB RCS Depressurizations. 6 RSB/ NEB /ASB PORY use and failure 7 ICSB Failure to record SG valve openings 8 GIB/RSB/MTEB Thennal Shock 9 RSB RCP - Restart ~ 10 RSB/CSB/ASB PRT use and failure 11 RSB/MEB S/G SV use/ behavior 12 ICS8/RSB/DHFS Use ef non-safety equipment 13 ICSB/RSB Post accident monitoring 1.4.2 1 RSB/PTPS Operator Actions (general) (Humun 2< RSB/PTRB Procedure Problems /use Factors 3 RSB/PTRS S/G isolation in 15 min. Considera-4 RSB/DTRB _ Trip of RCP's tions) S RSB/PTPS Steam bubble not addressed in Procedures "6 RSB/PTRB . No subcooling in S! termination criteria 7 RSB/PTRB ~ Operator response to steam bubble No procedure foe failed S/G SV or RV 8 RSB/PTRB 9 RSB/PTRS Use of Aux. FW to cool S/G 10 RSB/PTRB Isolation of S/G RV 11 RSC/PTRB - Auto switch over to RWST and SI Reset 12 RSB/PTRS Failure to terminate letdown relief 13 RSB/PTRS Subcooling meter problems
14 RSB/PTRB PORY and Block Valve controls 15 RSB/PTRB Location of PORY control and RCS pressure / meter 16 RSB/PTRB/HFEB/0LB Indicator lights burned out 17 RSB/PTRB/liFEB/0LB Tenninology problems on control panels and in procedures 1.4.3 AEB/RAB Radiological consequences relative (Radiological to design basis Consequences) 1.4.4 1
DEP/IE/EPLB Licensee's Emergency Plan (Institu-2 DEP/IE/EPLB No alternate evacuation site tional 3 DEP/IE/EPLB State and county decided not to use Response) Prompt Notification System 4 DEP/IE/EPLB State was not notified of RV steam bubble 5 None SRI effective 6 DEP/IE/ EPLB Lack of Region I and HQ coordination 7 DEP/IE/EPLB HPN adequate, ENS marginal 8 DEP/IE/EPLB HQ failed to make some notifications, Note: The first branch listed has lead responsibility for the item,
(- 2 1 Finding . Responsible Group, g ee.t Are,_a, . 1.4.$ 1 ACB/P/3 Error in S/G gas analysis i (Post-2 RSB Slight boron dilution after event Event 3 M11B foreign objects in S/G's . Activities 4 MTZB - - Tube rupture ballooning /frettit,g 1 a t ( ? ( f l-s l l r l' a 4 l-U. i l' i l + Note:. The first branch listed has lead resporaioility for the item, 4 9 l. I t v we r, a t, + r .e rm, 4.,,,- ,,m..-..,~,. ,,__,,--,.s.,,,-.,,.,,-......,_,.<,...,,,,,.,_,..-., ,,,--,_.s,_,... ,..,,m., ,,..,~.,.,-,,,r.... ,..r... ,w
... -. -. _~ -.-... - [NCLD5URE 3 SEk $UBJECTs t Transcript Responsible Reference Bragh i Luby ct Area N_b. P_ age _$_ u 1 24 & 25 1s 15 minutes to conclude which RB S/G had tube ruptore adequato f[- Ways to improve istimate of ~R$8, HFEB 2 38 J l RCS leak rate during transient - rather-than inferred readings 3 46 & 47 Analyses to give better under-GIB/RSB, ORAB. MTEB standing of what may have happened to the reactor vessel. Including evaluation of the rate of temperture drop fnr various parts of the vessel for restart review. - i 4 50-Acceptability of auxiliary AEB/RAB building ventilation system intake in en area close to the steam generator safety and relief valves 5_ 66 $lgnificance of the fact that MTEB plugged tubes in periphery are + always in 4 wedge area. 6 75 Inspection methods to check S/G MTED tube.integr-Ity due to corrosion process ~ 7 79 Acceptability of deviation from RSS/PRTB the procedures. 8 83 Before restart a definite view on MTEB the cause of failure. e i t Note: Tha first branch listed has lead resp,onsthility for the ltem. [ e p 4 )- 1
I I 1, Page 1-3,.last, paragraph,(endi,ng a,t the top of page i l-4): Th0 condensate system was contaminated becuuac of the faulted B-generator dumping stead to the condenhor earlier in the event. Since the secondary sides were tied together The adbsequent atr.osph6r$c dulahing of' A-fenei.atd4 steam '-y,,j3d in the condensate. systems,the A-toon was also' contaminated imounts to intentions 1" release to the= atmospherev e;Was~itt h'ecessary? Were coolant activities checked prior to this b (Md dec!.sion to assyre,that np.excessiyg radioactiv$ty would be M% ' tim ! releaBed toitpe-atm9 sphere by thisi agblos?C;;- s '.r.; s in.. a ::.' s. v.r: t. n s i s p r e h r.bi y *. t whi n 15 ,7!33*Pagsti-8,'5lsi6f arspraphi{66dl6g6ad Ehe (8pS6f pig 67 2 p 409):" The report;5taEei thai ~thitfub6 sallithickdess;sait less thad 50 of nominal at the center of the rupture. In response to my questiqn during the briefing, the staff, respence was.that the;i95%*thickn66siloss ess:due;to; wast.U;d gh l - If; correct, this-has,6wo'spr16us7 implications.. 61nco this? [V particular tube 2uas-inspdctedlin" August, 1981,Jone conidb .N conclude from this,that either the inopoetion techniqub was not captble of.d6tectihg a substantial wall thickness loss,. dr :the wear rate sas (extremely high (75% in 'iive. months). ;; .Ib-addition, based on this'one ev6nt, a thickness loss of M $$%'is;h6cissary to cause tube burst. Therefore, are the present bases of the inspection program and,the tube plugging criteria p. J \\ adequ4te to assufe; tube integrity?---' - "-- p\\p ' b('b) 3. Significant. Finding gn page 1-111., Whether the reactor vessel had been s6bjected to theimil shock and whether civ i i _ damage !was ' sustain 6d shguld be p6rsded 'in-the restart +rev, low, ' the' referenced statskist appears to have been with little basis. 1 4. What was the cause of the process computer malfunction i'Id*(3 for 16 minbtes? Is the process computer qualified to the same standard as other class 1E equipment in the control room?' P 5. Item 13 of Subsection 1.4.5 on The stnam generator do'wncomerLfic'w r'esistance' page 1-23: b plate modification was ef I idh a generic item reconnended by Westir.ghouse in 1975. The staff gLjf should develop a list of the plants that have made this h modification, and examine the opera *ing experience of peripheral I)~@yd c 9 tubes (includ!.ng numbers of tubes plugged or shown degradation indications). Also the staff chould examine whether the p, P, j, f secondary sides of the steam generators of these plants have ever been inspected. 4 e d E 8 4 n L 9 3 ..w ,m. _.,-...m., ,.-r, ,w+ ,m.3-., ..>n .-m..
i l 3 I 6.. In relation to 0. 5, what in the staf f'u assessment 6n h the effectiveness of a loose part raonitoring system for thn i detection of any foreign objects and tube fretting incids j steam generators? 4 l 7. The descriptions'of the B-steam generator water level @'#gg in the first few minutes of the accident (Pages 3-3 and 3-7) nre confusing and appear inconsistent with Figure 3-2.d What u was the staff's estimate of the rate of waterdevel fluctuatioP** in the D-generator in the first five minutes?WWas'the confusion attributable to the instrument problems, or the i level actually fluctuated so fast. [ifji A statement on page 3-9 states that it took 15.sinutus 8 l 34 to positively identify the existence of the problem in the 9 p. B-generator. dis thignormal in terms of plant design or 9 y argilable equipment? Jiow long, would it take far o b&W plant .) in a similar situation?- l 9. In Table 3.8 on page 3-44, the peak leak rates for the-pgAr$ t Surry 2 and the Prairie Island 1 tube rupture accidents are 'different than those in IUJREG-0651 (80 and 390 gpm, respectively). ~ flh 10. Page 4-16, Subsection 4.2.2(1) indicates that the d simulater responded in a similar mannor to the course of og i p.E this event, but at a siower rat,p_ (emphasis added),(/hs the simulator not adequate?if/Are changes needed in the simulator i L -for future operator training? tO 11. SItbsection 4.2.2 (6)'. on page 4-17 appears to indicate. {i ,, 5 that-there are ambiguities in the procedures, which allowed y tha operators to interpret as they saw fit. Stal'f should clarify. 12. Subsection 4.::.2 (10) on page 4-17 indicaten that the ~ 7.6y b[ plant staff did not think they deviated from the applicable procedures. Yat the task force finding says that they did, but were prudent to deviate. Without passing judgement as to who is right and who is wrong, it is obvious that there is something wrong with the procedures.. This question on 4 the procedures should be further pursued in the.restatt review.- T h e 1 e 6d*4'* Nemma N e
4= sew w su-18 n.g-w w gge=ren**r***
?
~~g g.t perenumwk rw - tw eerw-+ y-aw*zwd'w ygree se W g(~~
~~u-+M+1gemur~~
~~W e w-eg*ww rwatum.rque WM,Wpamuwm^ w user-My3-r~~
.._-gzq untee tw F e _ - 9 tem W w =d 9D4d % +r yyh*- 's-WT gM b-uhn e w ' ++t-Ten D'g-g-r=eog W m
_~ j o 3 l 1.$.. .In soveral place's the report references equipment failures. Will the Task Force or the restert ef fort examine I those? For example, I Page 1.10, No. 7 - main aream system valvo positio'n 3'c C2/ i recorders failing to indicate the openings of safety valvo and PORV's. l Page 1-17, No. 13: Requiring a mental' conversion Igd 6g6, which is simple in low stress situationn to probably not wiso.. Does the staff for restart intend to adorous this? Note that, it rc.lics on the computer which at a later stage did broah down. difference in switch operation or whether the sprinij-loaded (ld gi Page 1-18, No. 14: No obvious way to identify the switch had to be hold until the valvo closed or oper.ed fully. L [Sgl0 Page 1-18, No. 15: the centrol room operator is required to rely on son. cone. tico to describe the renults of' o ening the PORV Icading to a two-Ferson bump and wait type 9; t r / i 1.0 }(M gr t* of operation. page 1-18, No. l6: Humerous indicator lights burned out. (1
~~14.~~
Page 1-16, No. los Does the staff intend to address f., . whether the scenario in the second sentence would have led ^ to a_more serious event? 4 0 f 9 4 e i 4 { l 4 6 l 9 jae' e s*- es& map e +w unw wes
~~ie gr epieem, meang>suo i~~
~~,,. gay weee <r 4 ,m+oi-- r g am*Th+- y ,,,s+y---+mu'*e--~~
~~'i,-~~
~~t v wm-e- -y--awe.- s'Wem-9+e wEMg m ew-3 W 4*%**t9e'"'v W'd--ew 9 wt#m 9-*FI- %Td~~
~~9 T T'7T'f a-MMM*"~~
f a. gfy -2)$- i April 23,1982 !*EMDRA ClN FOR: R. J. Mattson, Director M * /4' Division of Systems intogration s i e j $Ap{Y R. H. Yo11mer, Director d. pj .h Division of Engineering m S. H. Hanauer Director >J (y 7 n Division of Safety Technology . {c fg g j $) H. L. Thompson, Acting Director / Division of Human Factors Safety ej B. K. Grines, 91 rector Division of Emergency preparedness FR(H: Darrell G. Eisenhut. Director Division of Licensing StBJECT: INPUT MR GihMA RE$ TART SER A memo dated April 5,1982 frue G. C. Lainas set out a program for the review of infomation prior to the restart of Ginna. The restart SER outline proposed in that memo has been modiff ad based on our latest understanding of the event and is enclosed here ss Enclosure 1 Since the release of the April 5,198? memo, the NRC Task l'orce that was investigating the steam generator tube rupture incident at Ginna has documented its findings in NUREG-0909. These findings were pre-sented to the Comissioners on April 15, 1982. is a list of the Task Force findings. Enclosure 3 represents questions that tha Commissioners raised during the April 15, 1982 briefing. Enclosure 4 is a itst of questions from Comissioner Ahearne regarding NtlREG-0909 and the questions ratsad by the Coussissioners need to be addressed in your SER inputs. We call to your particular ettention several issues flowing from the Comission n<eeting that must be addressed prfor to restarts e a. whether 15 minutes for identifying a SGTR accident is acceptable (R$8), b. the netd for &Mnkpendent staff computer code analysis of the thermal grsdients that the RV experienced (RSU), and c. whether the licensee has adequete capability (har6 tare and operator training) to recognize a large SGTR event in a timely manner (RSB). ~8M50606Nr emNga 74 = Nb, Q}3 fise n A G G G44 4 0 6' m- 'I^ 2N+ i ijh. '0* OFHCE) sumawe > oan > me soau m oc eomacu mo OFFICIAL RECORD COPY owo n.i-m
~.. _ _ _.. _ _ _ _..__ _ _ _. ~ _. _ _ V A ~ e.
~~4 2~~
April 23,1982 Copies of NIAES-0909 and nochester ta 1 Electric's evaluation of the incideait are avellable and havt been distributed. The RQ&E submittal covers everything except the itsam generator inspection, evaluation, and repair program which is due to be submitted April 23. 1982 and will be hanMarried to apprcpriate division representatives. one copy of the transcript of the Ctmuission briefing is being provided to each Division Director's office by separate cover. In order to ensure that this major effort is completed in a timely manner, we have estin'sted the folhwing senedule: Licensee submittels - recetved TR inrut to D(. - May 7. 1982 Craft SER to TR flanagement for review - May 14. 1982 !ssue SER - hay 19, 1982 We will need your SER taput by c.o.h. May 7,1982. A meeting has besn scheduled for April 23,1982 at 10:00 a.m. in Room 542A with Gus Lainas and your Assistant-Directors to discuss this and related matters. Original signed by [ Darrell G. Eisenhut. Director l. Division of Licensing ~
~~Enclosures:~~
As stated cc w/ enclosures: DISTRin0 TION H. Denton-Central Files F. Congel E. Case G. Lainas W. Gammill E. Christent,ury T. Spels L. Hulman 4 M. Young l.. Rubenstein D. Beckham W. Johnston V. Moore it. P. Knight 0.'Ziemann R. Houston K. Kniel 4 F. Schroeder T. Ippolita R. Bosaak D. Crutchfic.lc W. Harelton J. Lyons V. Benaroya ORB #5 file B. Sheron R Rosa 'W. Butler -O. Parr M. Srinivasan 4 1 C. Berlinger
~~SEE PREY:0'JS TISSllE FVR CONCUkREt:CE~~
^ r DLh R DL b ) #5 OL: ORB #5* . 0L : ORAB* O IO/SA OFHC4) ...e $.t'... na s......}.ahk.... ..Jia ..s :s.c DCrus.h.f.ie.!o T l e.e.9.!.i.t.9..... ...q.y1m..... b.... c t .!l n}AL. 9 y:.......... ivRC FORM 3f 9 (M ikM NRCM 0740 OFFICI At, P ECOR D C 3PY terco. mil ' m,4.; -. _- _... .,...m. m_...,_. ...,..,.-.,....-_..m.._.._.,..--_.._._m._..__.,.-_._=.--.-__~-
l i Q -[.' 2 A copy of' the transicipt of the Ceminission briefing it available in the project sansver's office, Room 309. We will need your ST.R input by April 30, 1982. A meeting hss 1,een scheduled for April 23.1982 at 10:00 a.m. in koom 542A with Gus Lainas and your Assistant Directors to discess this and relatH matters. Darrell G. Eisentvt. Director Divition of L' censing
~~Enclosures:~~
~~As stated cc w/ enclosures: G. La i na s T. Spels L. Rvberstein W. Johnston J. 5 Knight P.. Ibu ston F. Schroeder R. Bosnak W. thzelton V. Benaroya B. Sheron F. Rosa W. Butler~~
0. Parr ii. Srinivasan C. Bcrlinger F. Congel W. Gaamill L. ItIman D. Beckham V. Moore D. Ziemann K. Kniel T. Ippolito

0. Crutchfield J. Lyo_ns n
..h 077500 ) su~m >.M9.nrudn.., pg.w...h.t$.. eld..ct.e nh... ..D.I;.i s e Mw t.. au ce' t..# _y > 413/1.k2.... 4/.102.... 4!:qg2,, 4/. p 2 4gffu.,.. o . c wne ronu s e oo x:> nacu ow, OFFICIAL RECORD COPY u m.o. e w
GUTLINE Or GINNA RQTART SER
~~1.0 INTRODUCTION~~
DL/ ORB,d5 g EPLB '2.0 NOTIFICATIONS. M/0 RAD' 3.0 SE00 enc 3 or EVENTS 3.1 Summary 'I 3.2 Cocidown 3.3 Draindown 4.0 0FZRATOR RESPONSg l:58/PTRB/HTEB/0LQ 4.1 Procedures 4.0 Evaluation 4.3 Conclusio'ns 5.0 ECUIPMENT. PERroRFANCE 51 B Steam' Generator Tub'e rallure Analyees -DL/0RAB Lea.d sup: ^ MTEBi ChEB, MEB 5.2 Presst.riter Power Operated Relief Valves RSB/MEB/ASB 5.3 Pressurizer PORV ' Block Valve Performsnee MEB/RSR 5.4 B Hain Steam System HEB/RSB 5.5 Letdown Isolation RSB/CSB/ASB - 5.6 Etfluent Monitoring -Sys't'em ['I SB 5.7 Sump A Level Indicator ICSB 5.8 Safety Injection ' Pump' IC PSB ~ 6.0 ANALYSIS RSb 6.1 Comparison of Plant Response with Previous c Analysis 6.2 Sten.m Void Formation 6.3 Calculation of Leak $ ate 6.4 Thermal Transient on Reactor Coolant System GIB/RSB/MTEB 6.5 Hydrogen Transfer ,CMEB 6.6 Fuel Performance - CPB-SteamGeneratoroverhill, MEB/RSB 6.7 ^ 6.8 Pressurimer Power Operated Re13ef Valvo RSB/MEP/ASU 6.9 Plant Water Inven' tory DL/0RAB ~ a-
'AEB/RAB ','7.0 RADIOLOGICAL ASSESSHENT + - o 7.1 Reactor Coolant Cystem and Steam Generato,r' .i* 72 Radiological Releases 7.3 Heteorological Data 7.4 Survey Teams 7.5 samp' ling (Air, snow, Watur) 76 TLD Measurements 77 E tittated offsite Doscs 7.8 Additional Radiologien1 Information' 7.9 Recommendations-O.0 C5nclusions and Recor$nendations DL/ALL GROUPS ~ A Note: The first branch lis'ted has lead responsibility for the item. ~ .4 4, + 1 e n 4 0 0 A e ~* 6 I k J.
~~LM,LU3OKt, '~~
l .m i NUREG-0909 ISSUES TO BE ADDRESSED Findings Responsible Group Subject Area 1.4.1 1 None i (Facility 2 RSB Procedure /Guldelines Response) 3 None 4 RSB RCP Trip ~ 5 RSB RCS Depressurizations. 6 RSB/HEB/ASB PORY use and failure 7 ICSB Failure to record SG valve openings C GIB/RSB/MTEB Thermal Shock 9 RSB RCP - Restart 10 RSB/CSB/ASB PRT use and failure 11 RSB/MEB S/G SV use/ behavior 12 ICSB/RSB Use of non-safety equipment 13 ICSB/RSB/DHFS Post accident monitoring l.4.2 1 RSB/PTPS OperatcrActions(general) (human 2+ RSB/PTRB Procedure Problems /use Factors 3 RSB/PTP3 S/G isolation in 15 min. Considera-4 RSB/PTRB _ Trip of RCP's tions) 5 RSB/PTRB Steam bubble not addressed in Procedures a -_ "6 RSB/PTPS No subcooling in 51 termination criteria 7 RSB/PTRB f6 procedure for failed S/G S'l or RV 8 RSB/PTP3-Operator response to steam bubble 9 RSB/PTRB Use of Aux. FW to cool S/G 10 RSB/PTPS . a. Isolation of S/G RV 11 RSB/PTRB ~ Auto switch over to RWST and SI Reset 12 RSB/PTP3 Failure to tenninate letdown relief 13 RSB/PTPS._ Subcooling meter problems' 14 RSB/PTRS PORY and Block Valve controls 15 RSB/PTPS location of PORY control and RCS pressure / meter 16 RSB/PTRB/HFEB/0LB Indicator lights burned out 17 RSB/PTRB/ FIFED /0LB Tenninology problems on control panels and in procedures 1.4.3 AEB/ RAS Radiological consequences relative (Radiological to design basis Consequences) 1.4.4 1 DEP/IE/EPLB Licensee's Emergency Plan (Institu-2 DEP/IE/fPLB No alternate evacuation site
~~tional 3~~
DEP/IE/EPLE State and county decided not to use Response) Prompt Notification System 4 DEP/IE/EPLB State was not notified of RV steam bubble 5 None SRI effective 6 DEP/lf/ EPLB Lack of Region I and HQ coordination 7 DEP/IE/EPLB HPN adequate, ENS marginal 8 DEP/IE/EPLB HQ failed to make some notifications, Note: lhe first branch listed has lead responsibility for the item, y s-3,-.y._,.ren.,-,,,,,.,-,,-,--,,.-..,v., my, -,,,,,ow..c.-,,_,,,-, ,.,., ~., _.,.,. .,,,,..,,,,y .,,,cy-- yn m,,-
_m ? (m, 7 ..~ 2-Findings _ Resp 1nsible Group kbJgtArea, j . l.4.5 1 AEB/ RAS Error'in S/G gas analysis (Post-2 RSB Slight boron dilution after event Event. 3 HIEB Foreign objects in S/G's
~~Activities 4~~
MTZB ' Tube rupture ballooning / fretting ~.. + e 4 I k e-es 4 4 Note: The first branch listed has lead responsibility for the item. l l + 4 ,.m-,-- 1,--..cy--m-r ,,-,-,w-5.~,,-,. -,_, w --v,,- ,,-c-y.. m,. -,,,.m.., e -,.. -,..E,-c... .,,,,,.m..-r-ws -,rv -i..--,,. -. - -...- - -. - -,'r,-
n ENCLOSURE 3 e i SER SUBJECTS d Transcript Reference Responsible No._ Pages Sub.iect Area Branch 1 24 & 25 is 15 minutes to conclude which RSB ~ 5/G had tube rupture adequate . t~ Ways to improve ' estimate of' 'RSB, HFEB 2 . 38 ^2 - RCS leak rate during transient - rather then-inferred readings 3 46 & 47 Analyses to give better under-GIB/RSB. OPAB. HTEB standing of what may have happened to the rasctor vessel. Including evaluation of the rate of temperture drop for various parts of the vessel for restart review. 4 50 laceptability of auxiliary AEB/RAB building ventilation system intake in en area close to the Steam gentrator safety and relief valves 5_ 66 Significance of the fact that HTEB plugged tubes in periphery are always in a wndge area. 6 75 Inspection metteds to check $/G MTEB -tube. integrity tJe to corrosion process 7 79 Acceptability of deviation from RSB/PRTB the procedures. 8 83 Before restart a definite view on MTEB the cause of failure. I 4 l l Note: The first branch listed has lead resp,c9sibility for the item. d l s., .e 4m- -c. r.,- .c yer --m,%w ,w- ,-v.<, -c e-----w,*af-=
m 1,, Page 1-3,.last, paragraph,,(endi,s.1 at tht? top of page 1-4): The condensate system was contaminated because of the faulted B-generator dumping steam to the dondenser earlier in the event. Since the secondary sides were tied together 8 in the condensate.nys. tem,,.the A-loop was also' contaminated The enbsequent atmospheric dumping of'A-fenegat5( stens i L,JPd5A smounts to intentional release to the atmosphere <s;Was itt, necessary?* Were coolant activities checked prior to this .L-fdh6 ould be decision to assyrp that np excessiye radioactiv$ty;w'J4 ~31?Si u.P :n is 3.rt.p e in...p' ::r.'s. v_:n.9.Efo6?F ; U - releaBed to'the-&tmps here by this-a r s i s J.rf.: E b i y.'. n X!82 rag &L1-8',t31sitfafairaphilesdisgmaEEhei6p*6fpsjs? f L 4;9} : 'The rep'ortastaEes that thstEub4;ss110thicksssa-whit ~ less-thad 50 of nominal at the center of the rupture. In response to my question during the briefing,'s:he staff,sr.;* gg ' t response was that the-495%"thickn6shaloss wa due tp'we N fl if; correct, this -has two dir16us7 implications. Since thina particular tube 2was-inspsctedlin" August, 1981,Jone could 41.5 conclude from this,that either the inspection technique was not capable of.d6tectihg a substanf.lal-wall thichsess loss,. or'the we(r rate sas(extremely high (75% in~five, months).;; ..In-addition, based oh-this'one ev6nt, a thickness loss of? 4 95t'is!h6chisary'tc cause tube burst. Therefore, are the present bases of the inspoQtion progrmn and the tube plugging criteria s 8~ adequ4.te,to-assure tubh integrity? ;2; -- 4-as\\p d 3. Significant, Finding gn pagU 1-113, Whether the reactor (" vessel had been s6bjected to theimsi; shock and whether ady J. damage 'was sustained shguld be pursued in"the restartirov,iew. The^ referenced statsh6st appears to have been with little basis., 4. What was the cause of the process computer malfunction i 2c9 6 for 16 minutes? In the process computer qualified to the same standard as other class 1E equipment in the control room?' 5. Item 63 of Subsection,,1.4.5 on,page 1 23: The steam. . g' generator downc'omer' flow resistance plate modification was D;thg M a generic item recommended by Westinghouse in 1975._ The staff L;/ h should develop a list of the plants that have made this 9 modification, and examine the operating experience of peripheral I)p ' tubes-(including numbers of tubes plugged or shown degradation indications). Also the staff should examine whether the I secondary sides of the steam generators of these plants have 9 ever been inspected. 4 e p h l l e sp eo. -.e e, 4-we emsw=e' W agmasweeeuwmese.p meseius.. _. g gay e =ep p enge e r I 54 r
^ r 3 6.. In relation to Q. 5, what !.s the staff's assessment 6n 'Oh the effectiveness of a loose part monitoring system for the CJ detection of any foreign objects and tube fretting'inside steam generators?. 7. The descriptions of the B-steam generator water level @'#gA6 ~ -in the first few minutes of the accident (Pages 3-3 and 3-7) f.k b are confusing and appear inconsistent with Figure 3-2.d Whatevel fluctuatio was the staff's estimate of the rate of water in the B-generator in the first five minutes?* Was'the confusion att ributable to the instrument problems, or the level actually fluctuated so fast? [d } B-generator.E Is thig normal in' terms of pla g 8,. A stntement on page 3-9 states that it took 15 minutes Ch to positively identify the existence of the problem in the 9j 9 p. . available equipment? HowLlong would it take for a B&W plant p N in a similar situation? A p/14r$ 9. In Table 3.8 on page 3-44, the peak leak rates for the-Surry 2 and the Prairie Island 1 tube rupture accidents are 'different than those in NUREG-0651 (80 and 390 gpm, respectively). I"N 10.- Page 4-16, Subsection 4.2.2 (1) indicates that the L M simulator responded in a similar manner to the course of o4 p.f this event, but at a slower rate (emphanis added).dhs the simulator not adequate?(p/Are changes needed in the simulator for future operator training? y5N [ .11. Subsection 4.2.2 (6)E on page 4-17 appears to indicate. that there are ambiguities in the procedures, which allowed the operators to interpret as they saw fit. Staff should I clarify. 12. Subsection 4.2.2(10) on page 4-17 indicates that the MyP[ plant staff did not think they deviated from the applicable I procedures. Yet the task force finding says that they did, but were prudent to deviate. Without passing judgement cs l l to who is right and who is wrong, it is obvious that there is something wrong with the procedures. This question on the procedures should be further pursued in the. restart' review. 6 4 l l l
~ 3 ' 13:.' In several places the report references equipment failures. Will the Task Force or the restart effort examine these? For example, Page 1-10, No. 7 - main steam nystem valvc position rC6 b recorders failing to indicate the openings of safety valve and PORV's. j Page 1-i7, No. 13: Re. quiring a montaY conversion I. gy,} Fg which is simple in low stress situations is probably not wise.- Does the staff for restart intend to address this? Note that it relies on the cor.puter whica at a Inter stage did break down. @66 pT9-Page 1.18, No. 14 : No obvious way to identify the . difference in switch operation or whether the sprini;-loaded j switch had to be held until the valve closed or opened fully. Yg,) Page 1-18, No. 15: the control room oporator ir, required to rely on someone else to describe the results of' . opening the PORV leading to a two-person bump and wait type .p: g c6 f of operation. f.@jeA}g v Page 1-18, No. 16: Numerous indicator lights burned out. G f)6 14. Page 1-16, No. 10: Does the staff intend to address whether the scenario in the second sentonce would have 1e'd i ~ to a more cerious event? 4 e 9 [ + 4 e l w e 4 l l _.--e... -. - - %. e + i mw ow,w % - w - e, %.seem. _ 7 y gm --wer-.,-wm.,,4-.,p -., yew.w-,.,,--,--y-w <.-e---,.--, e,, v y-,r----vvv r y *,r et +-r + ~ eww w we ,=e+,'~e, we -w-v+y - -,. m e - w - vve - w v ev' M *-e'-v e-e - w w -r e + we-w-w we
i e 1,. C s:w.s n a.sL i w -. 4 i i i l i i GINflA STATION STEAM GENERATOR EVALUATICli NBC MEETI!1G APRIL 30, 1982 i. 7, } I F 4 i h e e f 'N l. \\ i i I -f' .,$ f
i . c',, GINNA STATION STEAM CENERATOR EVALUATION NRC MEETING APR I L_3_0, 1982 U9.h23. o IllTRODUCTION R. C. Meeredy o INSPECTION RESULTS A. E. Curtic o FAILURE ANALYSIS PROGRAM L. F. Ermold o .B-STEAM GENERATOR REPAIRS J. C, Noon o TECIDlICAL BASIS FOR REPAIRS L. F. Ermold o SU!OtARY J. C. Ilutton 0 ~ i
[ o 4 4 ) GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 OBJECTIVES o DETERMINE TIIE FULL EXTENT OF DEFECTS o DETERMINE THE TUBE FAILURE MECHANISM (S) , M 'Pk; o RESTORE TILE STEAM GENERATOR TO A CONDITICN MIICH U'? /- IS SAFE TO OPERATE MIILt MAINTAINING RADI ATION T / EXPOSURES AS LOW AS REASONABLY AcilIEVABLE / 2 o OBTAIN NBC CONCURRENCE FOR RETURN TO POWER b e E ? t t e I 4 ...s,,,,;,
1 t. 5 s 1 4
~~j i~~
GINNA STATION i STEAM GENERATOR EVALUATION NRC MEETING 1 APRIL 30, 1902 1 i \\ { PURPOSE OF MEETING 1 i j-o TO REVIEW STEAM GENERATOR EVALUATION REPORT DATED APRIL 26, 1982-4 4 N o SUMMARIZE RESULTS OF TUBE FAILURE ANALYSIS PROGRAM i i I o 'PRESENT CONCLUSIONS AS TO REASONS FOR JANUARY 25, 1982 TUBE RUPTURE i 4j' o IDENTIFY ANY ADDITIONAL INFORMATION REQUIRED FOR TIMELY COMPLETION OF SER e Y l I t i. I C i I i h e b i 0 l s b l -. ( l. .. _. '., _.. -...,.., _ -.,,.... _... _. _... ~,...--_,_,_-_.__._........._._..-.....-..,__._....._ns,;,n.-v,,.. _ _ - _ + + 8
i l GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30,. 1982 i NSARB/NRC REVIEWS o CONCURRENCE WITH PROGRAM CONCEPTS NSARB - 2/26 NRC - 3/1 o APPROVAL OF REMOVAL OF METALLURGICAL SAMPLES NSARB - 2/26 NRC - 3/1 o APPROVAL OF REPAIR PROGRAM NSARB - 3/16 ~ NRC - 3/23 o APPROVAL OF RETURN TO POWER NSARD - 5/10 S/19 NRC f h 4 i ~'- t e ye,,-vw wg-, ,eer-2-<:n. ,,y-cr,m.mw...,,%,..w .w-a,.w w m, w w., w,,,w w m r, w w ere, e rg wwr. p,1,.ip .,.-w -w n w ww,,4 r g m ett~ w f- %,m i-cy m+ry.mm.g. ---g ,+ w--n tw g,g-e,rvp+y r-
_ _ _... _ _ _ _ _ ~ -. _. _ _. _ _ _ _ _ _. _. _ _. _ _ _. - - m__- e i .i i i GIN!!A STATION 4 STEAM GENERATOR EVALUATION NRC MEETING APHIL 30, Iq82, r i STEAM,_ GENERATOR CONFIGURATION AND OPERATING llISTORY o CONFIGURATION f o OPERATING !!ISTORY .r I o CllEMISTRY i l o PLUGGING s-< r o SECONDARY SIDE MODIFICATIONS ~ f i l 6 1 e d 0 P i ._.,_'F4 m 4 y z.,..
Ili(llll.lll!ltll. ii 'i. S = )* T N _ mtg Ewb. sI. _ 6 2 r E d,fr.u. ,j 'c W t A M t R c g:., j / M 4 A 0 il B kj A G I 2*ij W PNGI .1rpt. W btt tyyde/ f ej i RREN r I C .l 7 W_
~~e tE ICNN r/~~
i .1 l-M. ti 6 I1 A isg1j/. L l t f 8 A S L EA ft r nE xi Y r i MR mud;wn;:.1i! i j.t tpi 2iI r b 3EAS .3j U u G atgigcg 4d:gl,d j3, j t f 1, 0ETT / E M + y i TOA M< AH -r sE e r i E e,, i 6 T IRT 7 1p-T* i 4 r 1N I b* A i q-t4 l 1 fr. E yi..Mg. f J. 7 9GEO 7 1 .a)!1 ~ R a ~ t
~~2t Y~~
W. 5 8 VN 4i' Ny+l!h[a.j UD, r l+ 1 i R1. j 7 2 A !i <s W 5 L M1T s L 1 f 7 _ -m.MeIUf~,+g. Ce4f+.mn1c+id1w u f., T n u i NE) 2 : : 7 U i c3 7 A di 1 fiq4r.oQ.; 4a-M G i!' 21! M O ii 4+M t ftp 0 U T s s 'f B E li + p} i I
~~t[nd m_T[Jy.mg.e2l3 ll s~~
~~T' 9LI vhItUmnwtr. ruH t4rq. . 1[4 w[t 3 3 E 4 N l, R A at ii 5 r i r j i l'! 4 R p%t lf 4 E 1il 2 i il:l 5 t t~~
~~rp+~~
~~_ymj.Jl4b1gm - u;H'+H t -j 4 6 u i + t. ~! A 1t! g,.i+1p;+1 nf +W{1 .-4' ';I' 0 It ]1i + t+: ps P m!ti.hr:pg_.rt ,g 4 j1! 7 j+t M o L = E .t!eiMtitnp.hplj~~
~~8. I-rT EA iu..~~
~~$Ii 5 J 4a 14=!! !t e: B R t t. 5 5 4"! I z L 4 a4-HQp~~
~~tl 5~~
j
~~rr 4i t~~
~~il 5 3 NI P -lnt-I 4p!h+ g. tge i 1i +- Sy4 '+. + !p,=b1 5 4 O HJ t + if.- 3i i1i1tc.jl; ' 4 t 1T 3 0il 4 RN i J. g v s L YU t i I 1 wH ir r. 4 e ttYe 4+tiec l 7 a~~
~~ggh, o! <~~
E A d 4yu 4^t. i 4 m G AR + .i2htwWnjggg<4 3 r 2 k 5 RY 1 >t J diu.P. rtd.)f-ri i c( E pt mdo;;qpg4p?aattN 4 e f + 4 -s tit + lipj1 5 r I A1 + 3ii + .ir:.,) .Iii re I 4 N 9 - fit + MIo. Wtkmf. -iy, f a L D7 4i k3. !- i j 3 -[ 3 t + +2mi 1 4-n ^4 E E6 rtpg;o n1 i + t 3 .S 3 r 9 o M T F b. tti. .t ii 4 - -pr Mhp+,m4r"*+ l 7 ,3 rt. +lo tf.+j i: 7 ) E t +i 5 C +pr -
~~e. s 3~~
~~igt E9 5 T ~i1 M. +r ~ n!.rIQf~~
igQe<**

:
3 S -d p3n 4 5 r h1Ie ti + n 3 tiU41eTm I t. ct+ 3 i +m2b.tf;:i+" I 0 2 + : 1 Iel 5 8 j1i i t ~. Mw. o+t J t ir;,:1ip fe@+ti ? 9 apMf i1 t dr; t. i s, 2 y; _ _diT - - t j+r++m t i iN &wt1 3 f 7 7 t 6,i: dIi 2 p + _1m}r4pt7 Gt
~~g $.~~
~~t' t 2 5 y I t nWAr ihi i !rY il9 2 -p t41 U r h: 3 r,t ^t hj.1A%ywr'ltf tj llI 2 2 aNi;t !:i 2' t ; 1 W iD."f 1d] Q11i 1 r 1 ' diiI+t3 4ii 9 w$f;JT5G jbh,r4 rih;+:iil' S t i wh i 1 1 4. i 7 7g i~~
l
~~_;wW ~ 1~~
i

i 6
1
~~4. g t2i n.;i r~~
~~4 ,l 1 5 t2 p h++u, 1ii 1 l~~
~~g}47gyfu 4~~
~~M.;M :p1i2:xtigmy+, L.N rN. . M4-t 1 d; ~6i f +:t1ill 1 3 l t I 4; 2ii 1 t NO _.p, ltI* at L ll3[l O gM j '.g ,.+1 - t+; t,r ! ! 9 i!1 h~~
~~++; "~~
~~8 fM:$.g.4++m;p.g9wt 31 Z~~
~~Lj m+ t_ 7 t": Il 6 2 g Z + mtm vjWt -rte 'I 4 .;4e + + / L 5 ll3l!f:l . ). E rt. 4tn.j,1t:m w e, U E e - d. H t~~
~~tmT z MIl tl~~
- 7'r. il 3 E t, at S u iuy B C rH r MDr ,i; 2 S ,y he *, e - EE C I; t R O A L 1 K, 2R U O E M o A m_ N f HB1 S 1 ~ _ 0 2 4 e i9? 2 2 2 33 3 e 3 4 4 0 ~ 0 2 4 e $ 24 6 2 4 d9n8 i,r22 5 y 33 3 3 3 444 357 3 35 79r 1 35 l l)liI llll:{illjlljiiiifl 1 l1 I ll
s j = / S a T r E f 2 M p 9 A ~ T T L'jO /hF;M.j1i, l W l 4 .t L M A t t.r A C N_ ? f, ; ' i B PNCI W_ 2" 'tmv.pJ'g((l 4i2 RREN W ICNN e 2 H f i W 3 A I E@ is. I+ ;- h B L EA f Y N +'I /f t +m 'i @p y MR 3EAS 4 t f S U D 2 fgf/,#w 6 fl/] f i 7 ,0ETT m, li I M G '1%. i' Tfd f TOA B E'i; R 9 1 I RT t sH - E }t ,.w,f e }r E 1 1 1N I t i tJ[ i I tP,. / a' i. R A tg 2 bi 7 7 9GEO i +& 5 8 VN r i 4 7 2 A R i C tfin 1 Eg t. W-6 9 t+j } p;. bI* 5 L 4 t t t A 1 a. N E Il 2 7 U fy4p' g
ii
~~$4" 7l' A t _I UD - {y. L p !l e L t wt t' T !4. rfi f jMG a Eis9!l B E il,a M O 'i r I~~
~~+44 A~~
~~a. ,. l l . 4 uK~~
~~i!.~~
~ 14%r; l*, @ ' R 4 tl a N E A ilnll M+++'4 ~E i !i t t d, +t I iiR sH !i i t R,jl4t8 5 EiT t_ Net jl i +ii; t f Fiili '4 _[W , f'!T i 4E 2 L i,j_.I !MLMao p l! A i; i. r 4 i 4! p t 4 if.d! + tf t 1 M kh,
~~it t+H11iI Hi11H f!i1 vh~~~
~~i -1t T i 1 -1i I j T P e. T4 i E 7 1 If i L_ 5i! 5 BR~~
~~j d~~
~~i t. 5 i ~ .t i - dl' 5 - I E[ ~~ =~~
~~4 P~~
~~HP h'+.~ T, Y i s'i l i c TE i+,hTr +y ++ t i+ 5 3 c i 2 5 6 OH 4- - i.iiWi i f il I~~
+
~~tf H n 4 RM T TiF.:,1id d' i i !I il 9 s P-l LYA 4 t + rf 4 e E Y E T s' ,t ie f+ M Q 4t -t T; iD 7 a 4i1FHi ~ + i '.e 4 m GA t I r&tMQ .1} +t~~
[
~~4 4 f R1 i1 4 5 c !i t E9 . t ( m t11tj!H t~~
~~v,_m i1 mi~~
' a 3 t EE I A7 tt ' 4 5 + rMi H. 1 t-l! 14 N 6 t+.et i4 ',z t 1 T _ T e cl - + +11HI!! r r1 a LD +i.H!%! I M i 3 7 ) 1 i 3 e '4 l1J i t 2 3 TF _r r +eI11W l t4 I .il + 'tJ E + r %^ yt t C 7 3 i T"+t '1 4i!tf t r-1 5 T tr
~~g b~~
~~!h4i~~
~~3 S~~
t 4;t 'gl TH jI 3 1 tt; 1 i 'w4.;t I 1 7 3 1~ Mt ! r il t 1 i4..t f*4iT n t4;. t.- ?_ " i t. 2 I!5; p"{4tiTt 9 W11 tMiTit,_ 2 r4FiIu!t: W4 7 il lllb'l rL;t !i! t+ 2 4yt ',t y - Nh I 5 tO'iM?MiH'!o i t 1 " M 2 2 J.,M'[g i 2it t 3 h '1p l 7 2 2 t i M i 8 tiHLHl:+- j C t dN l 1 9 tr 4r# T 15 1 13 i 4 1 7 n7mM 6 1 t-f;Md:. 1 it
~~p t +4 r~~
h'1 +ld ' b + .i-1i 3 .I 5 5 L : 4 Hip 4d++4. ,t 3 4 t;UI L 3 4 +: ^ J : 2 1 I ,i % N .Q" ++4H4r-4 Fit !l 1 w $tH $Hb,+' wi"h$. 1 1 O __(* 0' ft - ti4pi 4 t ? 9 i WN. lMFgM@: r ;.. i 8 Z + NfT rM> M[$%. M 4 7 +- + ;m. r 6 Z l L t + .iHEH. m7,ot + NV 5 i- - !]tp I j ih t. 4 E t t 3 +4 ' ',M D h i, 2 S f! h BG i I e=, t e EE C t R O A L 2 R 2R U O _ E M o W A s N f S S 1 0 ~ d 0 $' 6' e' 2 1 2 2 2 2 3 3_ 4 3 a 4 0 2 4 e 8 0c 4 0 4 on83 5 ', 9 8, 2 ",;, 22333 3 4 i 3 79i3 91 t,
i
~~m n( e W.oA4.. ,s M l 7a ~3 ,W o 1.,. p I J C i s+h+w.1+g-+'. .<.M.w. w. %-:, N b. ey w p g L -4 o z a.O.,~~
~~rv 4,y*4- <4 ; b, p u.Ls. m:. s p.~~
~~s i , + + ,.:;I Wn.*. $ h4-.4'h.s: *.M+.k.9, LAW,\\.-- -~~
~~h..~~
~~3 HO~U w 44" 4 I~~
* * + -
~~^ 1 w 4 ~ 'p ge d.4 -,.7,,++W-4h f-~~ *g F t > g .a,.tr... ' ',%mt 3 g-e w m s. m s +4,,e i c O., v d A. p 1, z g; : g o(~~
g. g

d...
~~s ? -t4--,gg -h;t1 e -+-*t i;1 N-== -st t oy a 4 7o+t gm' l y a m.yq~~
~~A q m 1~~
... : u-- g+ - Y OD. a s ew' .4 a (,, g -{ q + , g. p.++4.I. 4 -, u 4 L-bt. <.i, t.ed (4% - -
== g, =J @Q O y =H, 9.,i., m.+.4+ O Jf .e rp .a = 3<
~~p p- (b m e-,.p; p.I.~~
,j a-.~,. t J g y j ..j->.<-, g.-h v y- . + ~ y m9 =m ~ w 3 j ,c: ...po , m. % >;9 p-pp p.g - - - Wm 4 ..4 o %.. w,. o p i e+. 3 .H , % +1;;i M ..,.v.- f ?. + , -.3 3,. gg ,1 a p.o p 4 H t,I . 4; , M t.t. o.4, y,* :,p . m +-~ + w f) J,- b i +.4 y, .h +p,, 4% p4 e- 4 ~ p M++, -c.s.4.,,,,- 44.. -,+ . ; 44+ g o. ~ 4 g,.y \\ 'D p.
~~7. -~~
g. -yw . ~. +~ ; y4 -b b a w.4.M4 4 q. 4T -1 -4 m.v.,pa p e .A w.,yd,.w. -..Am_-- I _ g h.u,.. ,1) -.A4 4 4.w1 4 t l 4_ .m.:. gb +..p. m. -- ~> 4... : $p. I.y- .4 A %e- .m + e 44 T._44 .-,.}-. 4.~ 4.h, 4+.. /%. 4,444-4 h pm.t.-.. .4co.-4.p4-,$ p ' f p.- ..- ;p %+pp. --..- g = =.- .,a e - , m.o.+. r g g 4 4.g, p- ,.++.+.o.<, q.1, ,4,,,<m. ~ .o. e -44<4++ 4 LF 4.,4'4 h J g ~ o + g 3 n L,4
~~6,+ A.~~
g-h. tu %f ,s l Qn4+,44 I 1 N.+.. 4+4,4 4. - +. ) 4,. -,J. I .g.L - L4 j ~ o+~ 4-t- -M, q-a z =,m g 4-. . + 4-- j j s.% o ._g p- ... f .,.7, - m.q. .o-5 om ).,, -4 4 s e_. f& 44,us is..,+m+.-,..-- [ . I '. 7 n gmy s 2 gi.e. 1*U .A 9--,.c.i.-,+- ,<...,. 4 .m, ,m g) p 4, 1 j-,@. _.. _... l o. -. { ,4 m.~ H. ty ,4-e m d .m. 4 ..-...p m.-. Q-4 4
~~y. ;.~~
- _,4 .a l x: 1 g!j 9 . A.a p.q o> .o.L.A o ii W; ' --- mp, .+ ,, [c p. ,.4J 4 p g g 3, .e. _,.e4.b.. k, qe 3, +:L. p-~t-i ir ,e -e a >q d [_ h.._Mj i11 C4 ,44d ,I: M 44d.4.f R..Ii ~" -gaat,q._. e 3 Z -4 i q*4.... 4 .-4 44..+..q.<.4n_.._..., ..,e.4 4t_. w, _- %.sa. m p,. j g g EC a I 3 3 m l p4 -+u o + 87) e 4 4.,,,.'.n.--l - - y y..~ 9 ,, m .+ ,,7 ..o.p.. r..~ ~ g,-4.... q -. ,p. y , -.,i 4.4 +,4.e{ 4' [ a e l
~~D j~~
4
~~44.g~~
.i$.4 L-4+, ,- 9 ~- ~..i r 4 ,4 s w -,.%,4+ T,.o...p.4 ; 4 .,p h.4 - q -_- 4 .o.- u .o ..,-..o o ~a 4..19 -..,.4..4 -.h4.a ,_. at4,, -,. +, 4., 3 4 + 6 %J-g M4b.-+:. 7, 4,.4.+..~,,, i4. . g-. +,a,4. s .w r y g+ .. o g ~,4q. - ;'..g8., i; t, - --- - - ]* 4 = +; 4.rr ,4..-,,.H.. g',. I 4 N 9r_,.-- +~, 7. m%.. 3 7, y n, a s,,. .+,, m H- _4. H+
~~9..~~
~~.~ 4 g g,+. -.: m.t.++.,p;.:. -+ - ,4,g. g 9 y. g~~
i

: ;4+
~~t 4-4-4,44.,- 4 p.4 r 5+ ,- -.f W 44~~
~~8.- +9. y+,4 9 t-+ +,~~
1 p.,+, +, 6 4 o N. N m.p..4,m.- 4 + 4- &on m y-g 9 +4; 4, ~-,.+t-N,%++t 4.,..,. q. ~ y T+- nb 4; . -++>.a+e++ o .i- ~ g - 3,.u.+4.+++ m+.4 4++ .4pp$3.. 4 w+-. id .+4 - +. 9f 5-q g -., m.9.q p. ' ', <- ;,d..w;. ~ ge,o..o.s.,. .o y f, 2 4 g 4 e. 4dd44, 9 9 4.f., .i,--~- +. 4 [gg4-4 e,3 pg s 'b w...w + g +.. ;7; 3yy. s 4 e+.+. y,b - +.; ,p 44., 4 i.4-H.o Q W y +-**+p+ p.+4.~.+.+.,..p.p - T* % I F. - +* 4+s.J. +4 4#++
~~1..y ' N.M.ly j~~
t
~~t. t~~
~~- f i^ =.,,. 7 t++"* j W: g ++ .t.47Pt-*-*i j j y + f-- 4 t-9. +++N :. t..Ti-. e, i a ~+ o C.-) 4. u e+ v..-+ l - % ~.s. o o <.4~~
+
+4 M- -d W'4 " ',+4 4 ~4 m t'-r4-4't +- +-+ 4 Md'4M". 'Wi -t'~. i N -+ H-- 4 '" '"- 4* 4 N T &'~- a- -m . - 4,4p.,4-.pg.g(d% . + %, b + }! _-m r~ 3 y;py4-~y +. ~ pe, e +y 4-3 4 -H : p . w -- til +. g v< e, m..+.r Q w m..y m4_ _- ~ ..c m 4+ w44 u H, yn% wa y C +. th Y. $ Ir ( -. #,.a o.+ a.. ,..WO. ?? mm I') O et m> t~ l-w 'O M3 C O I* C 0 s .z
~~m n~~
~~M e l o~~
~~~' l" o i~~
~~i N h O *D { { N N N W u bs he b g A m u. N m m (= = N o N y m w o y3 WV'J @"QgqQNNNNNWWuuwAAA Os @ NW-u&yo g9~~

~~L----~~

4
~~i lli~~
+ S 9 T pg",yff,. Il. 7 E f. [, 9 A M Hibrptpftiy /.< ' 8 B PNGI t [N 5 S M I i A ,o 8 8 l" A G y 7 N. W. 3q,rg 4ihnj/,p(g / j S S hREN J t 1CNN 4 i J W S A oj N E p, M S L EA Y 4; gg / I MR j 3EA'T 1 S 1, U D / 7 N Hi 0ET P d 4i M G k 7 _p2;_t' i TOA 9 l Mf f;dH: B E 4 7 RT
~~MFEp.j;,f I~~
~~B T E 1N I i 1 7 7 9GEO j.lo RA. j L 5 8 VN f t,, g3 R 7 i $,1 4 7 2 A l i 44;a W-5 L E. Mti'. 7 - }; .Mp>~1p fs h1}a NEl 2 7 L A rt p"ny 'llt l UD Ik:! A' 1 i o u T~~
t
~~[2;:+T L_ p ;H m. n. MG*1i s. t 1 j 2_ %f t I B L B E 1lf fng r ~J 7 O 'j~~
I*

~~Ie,/ + p E i 4 N 9ng IiT _ ia p Qj A - ' afi 5 l ' R 4 4 ..l. g4 ,pH L RiljiI L' _ d +p m j b +Ti r i~~
~~eglt,~~
~~' 4E 2 i Y1pH ktq li A *i l A'iI 4+i4 t hmq4Q_n ~ d,l M 4+vr & <pl t: r. E 1j: 2 p75t -l. 5 P 4t 7 l n E 1j4t ad 5 BR . :y t~~
~~5 5~~
~~'4; 4 it!+ - I 4 5 f g - g1 ~~ hga V HP i 5 3 OHJ g:.yIl j; 1 ~ 2 5 ~ 6 1 E TEA / ' sdII 4 RN~~
~~thl 9~~
~~S e 4 LYU =: R l A 7 a t - ~~ +' 4 P 4 e E A ~ g,, 2 4 L 4 m GAR 9 RY ~ q^Tg l 4 5 C y 4 f 1 r 4 e ( E a M y rf1y;; L"dI-s~~
~~i 5~~
n ?A1 i+I4 ^ C 2 e l 4 N 9 g$ 7 l 5 r b y-LD7 1 ij7 a l 4 3 t EE8 - si =j1ll_ x -!rt ir. l, l 3 9 o TF I. N.l 3 r a rv" l 3 5 T E 7 ) +F E C 1lil E p 3; h3 1 [ p: 3 A }f ~ K 9 3 S g;+' 1, + E R l 3 3 ~
r
~ - DT;1wgh y 7 3 7r 5 j 6l 2 y*;'1ji; ~ 1jfi+ 1!i f e 9 7 Ta 8 2 .j C 2 7 $.y 1 i .L 2 1 2 5 T 4 2 l 4 r t_ m tSy N 2 3 2 x 2 Wu' 4 {:41 e . {I4_ A:. q; 6 1 2 1 C 1 ]^ ' h i 9 I ,3, S 1 w '1j t4 1 7 I 5 1 pg!'1; gg>g-T.4,h..
~~om t~~
~~4 1 'j 9t t 3 2 1 O - @j "ng l 1 p 'i f r t N i gl 1 O 1 gy _ i MHip;g.j1.p. yrhpmi:!UE 4 9 { 8 e w Z H: j 7 Z ti i 6 NW 5 L a E g'i4di 3 g, l~~
!

!MD 2
~~S s B G i I h =) EE C ee t R O A L 4 R 2R U O ~ E M o A f W N i S S 1 0 2~~
~~9 8 0 6~~
1 f 2 2 2 2 2 3 33 3 4 p. 0 2 4 s a0 246 0 ,. g,,, s 7' i 2 2 2 y 5 h 5 7 9 4 i '53 f 5 333 444 9 35 t t,
a i
}i
'1 i )i i;{. I1 jij1 O S 4 T f f E (f M A 3Ng.+%nI ,l / o 9 M M i ~S . I.i. 4jlMf-l 2* 3 RREN S e A G l .I M PNGI A o "t N tJJ1 l i CNN %iW1li4{.M 5.JIei6 7 I II 9 S W-2 m L EA J e r / ;, M A MR i .lr i S t i 3EAS J Y ,U N !Tt Ir nQ i4f,? E !i tai f ly S a 0ETT 'i U D. / r TOA I t / ip 1i M G .I 7 ?. t ll IRT .IT i4t. -!,g n1 9 if' 1N I B E. yvNg./ 7 9GEO 1 H E .I I I a .t n +V RA.!, ..it. / 1.7 8 VN ~ H;i n f v,; - 2 A + r i .r. 1 r R. II ~+ !8 L l i; ;i{i:1 f 1 / n t- ';t NE 2 7 A h A-!1 W 6 E-l1 .i U 1! 7 o z1j; 4 ' BEi ?$W. ii : 7 T 1? I UD t rIhj7 ' bl-o 9 I +A [r{i11lf t ? MG J O ~ tp t [y.i i,
~~-i1, i,;~~
~~i 17 N - Ng !01i!i Ii?,yM, ,,all r 111 .9 J~~
~~W, 4j~~
~~1t I~~
~~t !l 1 E +N141 p +I;W-Wrt; ?r 9 R A i 5 'j i! i t t R d !i. t.. t -I11} -!,i +4,, ' 4E 1 u + I1i 1! y}p1l!1i!i t+r+!, +t iii~~
~~I a~~
l A 1np t n 1ri1 1t!!. +W. (/T fl i o s II 'p l5' 1 r i F g.i!11h! i !i -i!1 i-i!!. i l! P t 5 Ii. i B3 Ml 4 1 !1 i I 1l ,-;i!1 i1i i, i4i T 5 s HP 1r, Cl> 5 D OH I , I 7 +I1 y 5 3 C TEA a7 2 5 + 1 E RP 1. ++; I1 t ,0 4 LYR ji 9 S E I p-?I e!i i7t!+ M f 4 t 4 e GAL ir h 7 a R ~ i 4 m 1l ,-l1 'tt E1 Ii t!. ~ +
~~tt'~~
~~( h @g;I1 4 5 C IA9 i 1 j, t " " 4+~!t, i -T Ii ' + Itt i i! 4 4 e iti; If r 4 5 n N 7 kf-If, t 1 i~~
~~l i1 t~~
~~i! 2 e LD8 = t c34r-dl 4 4 r ri+ t I a EE 4i' .i~~
~~?e 1i t;Qi!i~~
~~>r"b!';;I.i TF 3 t 4". i. 1;Ii> 3 9 o E ) 3 r .ty M C j !,Ii1g t !li 1 7 b1I i1t" t T f 3 S !l f M g y: t -W !1!ii,T.!I,II, i:T ? I 5 5 4 T" 1' 4 t['/ 1 + I z 3 I[;M',ih s i.t t' ; 't~ c 2 -I 4+ f~~
i
~~{li~~
f~
1 ij! 7 9 7, @.i 2 7 ~ -i!Mwg,I N i g!i lq 2 . y. )g1Iit,$t+r ~ t + f1 t 2 I.I'r tj h 5 it. ,I 1! yi'1I t t, . ltg. ;g: 11t r = i A 2 +t ii I i 2 3 ir - '1Ti4-m+II;i ctfM,- Ji I 9 b:i i* -ti T ~ 2 T 2 2' 1 1!4tO ' a71 Iib C 1
~~t T~~
~~sN I t E ?tA$ +; 1 7 I -Hpf' 11 9>Jt 6 ~ +i I I 1I 4 tv p;Li 1i -jI.-i: tI +;. 41 5 1 !g Ft + Ii4 1 ,y' 1tsUid. i t- 'l 2 I L ~ 1 3 O.- .hy~~
~~y"r]i,.[ttQ'd.~~
~~- +t i Ilt-! ~ i i N r ~ ! iiy, l 9 O '&E '"- MgM4ttNjf*+qwiQ.M.,ityMiM t !t l 6 It S S/- Z "~ 7 i i i itt b-Z l tT 't; 5 .. t4,. .c !i NW' Mm!' r,U E L b 4 E y I,f.rJf*f7t 'f 4 m It; 2~~
~~i i,~~
S 3 ' i7 iy ti' t ,M D ' h p4 !t 1 i BG' e s e ed t - E E C R O A L 5 R 23 U O o E M f i A V N 1 S S 0 1 4 g t 2 +'. sg(g0 o l 2 J(6' 2 3 s{ ,, 4 4 2 4 6 o 2 4 5 7 9 g s2 J' 7 o g722 3.i333 444 I I ,I 35
~~3579! 35~~
,b.- r !ii > i '
4 4i, ll,!i4 4j; !4 + ; if l: i 4 S I r" T $j. Aq. d4i-E 2 9 A g. / M 4 S M d p+ r. ! W hit +;&s(: gi@w, / i l;o 8 f i A / 2 9 n G t 1 l r 5l a 8 fUGI N-Y lHi W,- @. -.y R e L EA ij 7 .a RREN ii ~ t= 1 f a M 5 ICNN A / g g f _7
~~j 1 t pj~~
/. g: i MR i N E c:e I 8 d+i oDr 2 n 3 E A.S kH uGuq3;:. _ms.4a / ij\\ 'p& 0ETT i 7 i TOA 9 Njn aE ey R A ;+,g,*i RT I S T p 3 i f n 1N I E l %I! l 7 9GEO ilp! l Nln R 5 8 VN - qm{, i M 7 ieE :ya4_j1. 1 2 A l il iil W I 5 h 7 L i ( I NE 2 7 U iip,mgg i Au - hl N I I U D 1lt 0 I. i t i 'g t l 7 NI[.. A iW[g+, 1-A: f 1t !1 H ,j i M G 1ij 9 T t l HI t I-t 1 }Nel.1vMlli 4Et1i 1 I { BE1 7 O f +, - i : 1 t 7y j E , g
f

11!

~
~~A t1 4 5 d1/. R ts ,f tl }g..j1iu+ 1; 4 4 1 i e1i f1 nim., R l-. ji N 'H 1 4 t= ry t$1l eiw?i 7 l l 1 a ra A;;';h t "r U, &w;gi[sp pf}lq 5 P _,8 M+ j t~~
~~p4im0 thFt,l~~
~~{ 3 M + l E 4; o N ltih S 7 l l i E r L 5 }g . s 'i n i 5 5 BR . i g~~
N
~~- I iwji 1 1 5 3 c t l l 9 5~~
~~j i;~~
~~a t IIil HPt A+ !Po l j; pi~~
~~hll, i;y OHr 2~~
5 6 f V 4 r tee -';1i 4 f 'i 9 r RR u LYU 4 .~ I 4 v MIi N111p1;njt E A 7 = 'l) p i 4 = CAR jt i L @di: gFt ,;i; ~fx t_ ii;i 4il 5 RY c 4 4 e ( E l. +i jgl1 f a 1 r. IA1 ? e 41 sMpi gli d N 9 A r ll s 4._p - +i;m
i
~~.i. m.~~
~~x g a LD7 p. ij: 3 t EE9 lt 3 9 o t! TF~~
~~t. l8!~~
t3 i 3 7 ) 1i ii h 3 r E N -i!+,; 3 C dli A ",7 d 3 S I-5 T d I!1+2 - f t r-p. _ =pi tng# %;, fo 2 1I i41 3 3 f tl E j a,. ) h1i I _k1 -,4n I'+ %4 7 F> t t f 9 i 2 i i - N. 43 faLw M F 4 UI! Z 7 2 W I! 4;4 5 g 2 7
~~l w~~
~~3 k8l l47 2 2 g%j r 3'i! 1 i j 1 ll1 !1i 4 1 9 .j4}p l 5 1 g 1 7 + q;l j;:et7g [~~
~~+ 2 6~~
1 t I i, 1 1l 5 8 lH E: +. !ii 9yHiNa ":!4 wi 4 1 M i1t 1 3 i P4 < 2 i r 4 I l NO.f#li4 O vi tg, ff g:.T3 -Hnv. 1fPj iQpe 9 b m 8 N~ Z 1 .!dj 7 b_!l4;jjq: ' TnTr 6 Z i j 1 i. NW ;j !i, 4 5 ii L t hg: g ht5j-h1:9+. i UE t 3 1 E f t. f. l MD j 2 j f S i i li ri i BG h e E E C i e R O t A L 6 R 2R U O - E M A o d W N f S S 1 0 0 i2 2 a, 2 2 3 3 3 3 j 4 a i 3 4 6 8 1 2 4o g0 2 3 a ', 4 6 a 2 a 3379,3's g222 57912 2 3 3 ~f,3 i 444 3 9: 33
e r.o g L, M S M M.h--~C - __'9'*3 __. 3
~~G d~~
~~$2 mm.. -. -th-M.g. - ~ C w: nS cp -Hg-yg N p g re zi , :tw 6 e mza- '9 g.4_ w %w .> i.,. A '. x~~
~~m. x m ~*9 q~~
~~n:, ce Q~. 3 i g 7"_, '$'.._j t--t-~ t R--- -' N~~
~
~~oa- >s g s g C-' a p > M %r 2m 1 1 x n%,,,, @ .Xg Z"2 C o,. p,., \\ w m,u g. i i omH p ,gO _p._,_ i-j o > I~~
-+
~~CD m ( ) g+. AN a a .a s. -- g s -NH .-q x~--.--- .f--~~
~~4Z a~~
~~.-74m 1, , /4 .. -- m.y r, ynt..m.n e -t e o m, o i "f M, v.y s, c a M f.t g~~
~~J Yti,t-. c) m -~~
~~1 y 5 -i G v i 1 -4+ gq. 1 c . m* N . 41 90., 7..9,$.g,.. 1 -..2m _...i C. l~~
~~g. +,--o 4-.-~~
~~I .*7--, -n.+ +. ] j'1y$$f___\\ -- co.-- y y .r -s.. 4 + * + - H '" K o {- g ._ \\ 4-+l+-~.~~
~~t. 4,~~
~~- c) m N-- j 1 - te.,_ 1 ~ o . -+t--r; i i~~
+i
~~.,i>.. i m ~ ~ + + t--.+4-+4,-*f 1 ri~~
~~) > -~~
~~y. e. 1 7 ',i .c 4---* ig-1 g e I >1 l l y -~4 ,.y.!_"4 ;, 4.f ,-.-.-) _ _,,,,,, A m [ 4 k.._y>.i.4 i.. t t** r,.T}'-+~~
~~A++e+3 C~~
~~N I!I W H~t;'- j~~
1~
~~r-lI +4-t++- +.*i i. ^,i i i~~
i
~~+:++-* b M f.~ ~ (.# p.,%-------- < t > ' ?-+-+~~
~~i., 44 c~~~
~~1 1 l . +. - 1 4--.--~~
~~o..~~
~~m ~ C~~
~~~ '~~
~~T**~*~~~
~~-..++ 44-.+ "~~TM1 1 b m -i~~
~~i i.~~
~~i i ttTm: 7P "~+" .i ; i : b, 1 I 2 e,, CD A. 1 i - Pc i 11, t Ii1 1 t- .ir r 't*'tTN[o "" Pt" r [^ j b 1 3 -er r -+ p i 1~~
O'*
94
~~--*"'*"'y~~
~~'O y~~
~~Pg Q j r 3~~
~~i ^ ift .Ii T!I [ i tttf-" t- .I~~
~~.0 C~~
~~2 o am 3 ) ~e . 1 T I !?' i pp.[. - TH+$~b 14 % '~.'. J" {' h3 4-...4 .4;iI !j i t- "h 3~~
~~3 M O W~~
2
~~g M~~
~~?f-x b s m3 g a yn.:rH h r i i i rt m ti a.J M CT) b"*r - itT1 it""-~ t'.- 4. w a. x~~
~~r rr r1 y~~
~~A 3 O>M qi i i : t-+ ? ~. - +t++-r i ;; f _,i i t. ;i ,r - F __.: 1 i itg- -- I, g i j ;i .+1.;q h g;---* e,,,~~
3
~~,my i e-+4 44.,.i.,._...-.4--*t,.t i- , 1 i -.. -..,i -. ii 1.- y .* t-*Ttt-"-*+"-+t-1~~
~~1. : i~~
~~- -* tw~~
)
~~,, > g b h'* w_ -h**h" y. k_ i s."-f w ,b l Q.j~~
~~.h.- 4'.-.4. _.__r.-4,~~
~~~ 5' "a i ; T* i ( pea 1 4 p g J.. t-t-4 w-if+ t---t +- -+ n --- - g .a, dmo g p. , p _.._--r-o . 1 y 1 u f-y Q l {~~
g
~~,). ' ' .L .y ~ i w f. 2 4 _x.;- - +-- .w o,~~
~~v.,~~
~~a w u-e m~~
~~.y 1~~
~~s r;- 1 -, o w ,p., 4.-,,,,,. m _ ve~~
!t
~~,I E, I I I !. ; ji i ~IJJ N ' q' g .III I! .I 1 1! t I I 'I. _s l ft i -+ t+--++T** +fTH --tm, l [ , -- :t y -*-9 .ii h'*h*+-~~
~~1 h~~
~~I ' i 1 1 o, - F,..; 7 i+t-ret i i! r y 4 r y i r-4tt. i1 T-l I 7 f~~
~~i i,..~~
~~i r 1 1 i g.-,j ,- ': 4 e >+ f e ', - f j +.t- -' j 6' d, f ..h.4 l . - +., '.'e -p[, 44 N h N d.~~
~~1 i~~
~~r"* 4 - >l*t.;_. 4,,$*-",* 4+r z v m hh' l - [ h .~ It'[.g+J o _m w.s :;*,eL w.g,! v.e /a_.t-G~~
~~y. =~~
~~- n,. ,!l t +3 r 9, -.M kid o[,- ! k i O.***+tt'4ff} } i ~ r~~
~~ir;~~
.*^ 4 .d., w 1 3 . l r. 'i!4 ae O {l i, j i l h-..!..Hd4-t,23]9-t:hi'f+-,'Ef,4-. +4+-I - o I
==- J +. ) ~ .Z 2 t O i - r i, +.;.+ - t -,. p _o .,1,.. N [1 iPt i : iir i-'**T **4 - cg3 dt' /- b- - [-,Q t t
~~t l-~~
~~? r - + M- -s N V. i : > (~~

~~t m~~

,i v*d-M- ~..e (.g. y f-.. p- , f_ . t -t-p- - {g_tm 7-.,..._. 49 __. 3 m -4: rra ..r. c o Ty. e j .t. r7 - ooc +rt,~jda. ~r- -w -rvy q. - _ -+ --y vv6., - ta ~ j-#- 1 (D O i =. 7 ( l m m m OQ O ft m> r a I N3 C O l >m a$ R I' m m f 3l 3 N N N N Nu uv v v s N A e c) 5 3 g 'O T N A O D O N & O CD o N> s l l "h N bbQt h h E, o N w u e jJ, k,)$,o yw F -u
w l + %f hg,f {/ S 3 T lI 1i
j i i 9 E

y. y 3l.
7 M A 1 ' fyf{ ylg l -l w M l A 7;:h;f~-. +. / 'j p, PNGI B i A G l il N. }t IIg1 ii 7 h-l1 a RREN W l e + 4t. . Pc JI/l, g i ' g 5 ICNN A t Wc + in 8 L EA r Y HIpE _2FI N E / l, u 4 jlJ 5 MR e 3EAS U D i fj r ,0ETT -/ 1' l MG 1 t r l c TOA r BEMf+dp p; p- .j i 2 i il di 7 1 IRT (g s 1 1N I "$tp E RHb i i ' 7 9GEO i l' s? l' 5 8 VN i RA s i, l i !i {r tp R:f 1 a 7 rMt f MC Ml ll il 2 A W. 5' E;f L tth 1pii. !_Hk+h NE u 7 t A, + !il ji t i F U t t 7 UD A I l c e MG !l h.'i i,9 T L! ~- g.i l e L I 4j:, r 4 h 4 L }, J ! a BE .gi,1 iI Il 7 O iy t 1 E R A ll w1 - 1d s .h 5 EH1! L h +td:dnl Dfp. M i 4 4 r C _~ mi,4 R 1 l 4E. a + 4 b +tpH +i t A u) '8 - L s t +byPl1t -r ta u 4 1 Y s o i p /. e i 1 i pg LI i s 5 ER P 7 E !1%byi Q '. h+*.1d - ? p4 ~,LQy%p_p&t [: 4+ 7 5 !1 J e 4 5 E !i - I 1
~~r 4 4.w. -i Ai8 P~~
~~HP s. 3 G OH 5 6 tr .i A1* 8 E TEA ~ j 49 S RP 1 ~ f$'l~~
~~f e~~
~~4 r LYR t fih,gy g k-l a E I t 7 a ImRg ! OAL m i4i t Il 4 t P N t A 5 R _. i p L v l 6 r N 8 a C z j E1 M e ( rpNiL n I A9~~
~~g r:g 4Jm~~
-l; n u ir W [ 4 e +p I pprp,t.p:dDFsI!M s-a LD0 f ! yn 8 e 3 sme t s 9 c EE f_ E 1p{ TF l n 3 r ntgFxI#1iNa1Mf}TgI4b.y-g g T e l E 7 ) t ilj r 3 C 1 2 5 T 3 f S g r h }.E$!i rg wgp -l, u t! 4 t tp4: 4:$ i@ I:il 3 t w 1 iQ t hp:i*c;p@1qh,iiMtg dj I 2 t tf: : 4 7 i 7 9 8 2 i N: Pp. '_ 5 .f.3 tc: ud ti 7 1;p - c. iI tt 4 u. + 2 h - }:i r r 2 2 t.hF 2 3 4 2 1} mhiiid}*gi r -l 2 i E j9i 2 2 +r t 1 ig(r + g1 1 7 3 c 9 ikM"f; 16 ff tpt_ '1 1 1ff +l "_ '4 elI { j3 g i y+ 1 j 6 1 g[M!t 4 1 5 ri 4 i djgy k" g d4+4 il 8 1 3
~~= +t 2~~
pp 4 t ( N 1 O- . iA- +1j1:rM0I$NG o 1l ~: 9 Ff Z i, %U Egw4p 'i 3 I 'l 7 }t 6 Z ic t NW 5 i i L t ihu, k LCEq hI 4 s l E n A iLf dmo n94r ill 2 t1 +, . \\ S \\ B G i h k EE C i e ~- R O e t A L _2 R U 8 ,p E M 9 o A y e N f g S 1 0 4633 6 8 1 1 2 1 22 2 33 3 3 4 4 02 2 4 6 8 4 6 0 24
7
.g5?8222";233' l 3 444 35 '3 9 35
4 e b [J ~%.~ -.Iys m s,,;:N. J p.3 m ~A. wws w,, g.H'4' -+. freer.-. %

~~=-a~~

~~+- 4 'a w n'a.j p.6..oc $44;, g p. p R 4"~ -' q =~~ ,,ay 2 l 9 *. 4. '.9 E I - W,g Ji,--- .a,4 4't+-+**d 9H +.+.+ _-h: -s eg pxmz~~
~~7 l~~
~~W 44,. ,..,+4-@g'- N-3 ., o Z z., r p,~~
~~4. ; ~~~
~~N-y g 4.L. a 24 4 - <g~~
~~.m.~~
~~i sw.x 2,~~
~~m ",'" o.,-Mh L f U +g._-. L.yd .a _4, +4 I o t v+rt- }.b.er+bA-- gx k WM , C om44 l-p a e -t r i.f dO> i : x a J l4+ UM n) M - W - * +tkM - N~~
~~j gh~~
~~) 2h i U m, m..t..t, a m#+"a_c$+th$mth; \\ b1 1 -a .a eamo pi c r-c.--Wm i~~
~~.: =~~
~~e m ,h, g' c .o l A,. 4, m.m x !o- ~ 4., J~~~ V V ~' - - ? i 1 4 > T$,I _i,l4,., t.r+*$ ^ ! :... ^QT"'*iN ,m- ~ ~ c H+- M,-t.+s-\\- .:r,! ~~~
~~4.r C o,_~~
~~o.__ e a a -+- I. - + ;. 1 [2f.$.M W*@W-(i cu m. - g[:- $ \\ 5O [ M i. ,_ pf u!.Q~., J.! .I +$ " r +"H.orkH' i~~
t
-+i.-, ei-4 -4 o -* t1-4- -~ m > e a-1 t iH C.u_ i -r" g :4 .-t.--. .-,4 i i et' 4- -t-t*Y.t -t.+4 J .*~1 - o 'U * - O n ' !'b,-7.-o-. 4,. -,p-. y.- .t-i"i i 44 ,...a_,,. p 7 .+. + t .d g + 4.<.++4 y -- 4. n - e >i. 4- ~*. f'i *+ + p; g p- 'f p i "*",t,;g"'+T i i I. -.+w++j N "5, r[ -p*4 FF4 m4 f,.y..m+<.# --i Q +"~ 3, _ w .a,b 1 u, 1 1 . i ? +Tt4itit- -a m I ~ly- -h, 3-* t h,14-4+--+- + T l 1 O y a,c .,--f <LQ +M1 4.F4py4.44y4 f :+.-,.+,_n,$"w_r.b' 444 1 t ~*-*-t 3.- g 1aw,- r **.+ 4- - -- M g,., e +g. T + + + - - ~ , i +-- "9 r -t- +tv-- ~ w w a 't+ 4 t,4+v4}.t.t.+h+ F4 - 9l :.Q tt - y.'+r~tt i i it: ii rt u e c 0- ' ~ ' ~{.++ t+k4--- &4 - +H ' t.p3,. -r+! ;4, q+v; : M ki M > t t -
~~+4++ j--+.-+o-~~tt--g-., -~~
~~w r.r i. .t s f o aJ m, rv,x m I b 4 t .~.4.y! ! i7 -t.k --4~- yf- <m 3 1 t : ,1~~
y
-t. - +- 4 ' T,ygj> i. _~~""~~~y ( {,74-t,} F-.- m .4 Tt p - j Q ',b p . x.r~~r r *- i: -a i !,r4.yls..y- .. n x u e n 74 j U li 41-4 'H i . J-j.-,.17't*"Tf I r+ f4ih-- "" ' M ** ,u$rt " i 4 ii i -- -{"7~'M ere.u,, ra~ '* *T f, + - I j E#$ ,4 pJ--J r++:t p4 . p+_D. : +4 '- ' 1 4 l d.%.4 x _.4-. F 44 - *Q" ;,i !?t 4 +-++ 4. 4- +-+ > 1 5 u a v' mm 6 h -t t-4e+ - - +. " Cm. l r u 4 o ..p: r. -..i +r i q ry 4 ~ !
~~t. tt, -~~
~~. *p--.f.~+ t-r-tt "+- +-4tP ~'r'+:t - -,i 7 u j j u -Y~~
~~M 1~~
a44.H. : t-- i e v M t. Tt~'"N,i 44 r 4,., ! -,$n-i 1 r Q i x-o m 1 g g ..,.+ 4.... LJ.,1 3 -+ 4 +,- e s. .r a, m t e- 'f. '.,k, ~.8 N{1*i, T. *T iI N 'W f v, ,w .-??T.iE..*. ' 44 + A *-*+! } j ! k h !.. t-'44 r 1 11 s / ti r b? +P-tie - f *tT*" ~ , tt' **- *,.,.,h. '*e' O p*- t.1 ed %.t. *4 + t-+tt -* +t t .tt.,.". +.. t r-2 N A444Yy4-+444-t!: j ^ 4y'Tit
~~f. ri--~~
~~i N M 4 j 'bt h.?t.4444f,.ta -, a.L_"M . w*" .. + *T ~f g.+M ~ ~ ~ " t' ]'.. p*.f'-. 'o . 'u 4 +t y g ! :, 'di" *kt" 4 "*~+' l i6 'T'T M h 9 i N it Tt"ylfgf p + M.,_-',+eg/~}41< _CD~~
~~e. 444 "4~~
~~.p. -H ii -,.f4.f.! ' ; ~ !-j W-- 44 "r -t ,.1 eg. t i= r g -- ;- ,.,i m ., d4+M; ,,., e., 1 o 4 ~. 4 i g t+o-.-74+ [ t+-*"*-tr*-{,..,...-. I"* N +.J~~
~~;.4.e444,-+., - Tt. t.-t j j ;i ' ; j 4 4 9-T]., 4;. M'~*+O4e-4 +~~
~~---d m '-'S' ~6-r i j,. **m-- +-. 1.ltob-t-f+; te94+ +-M f, i o.,..Q-l a..e,4.. Lp+.. j Lt - yyebt,,-.,, -4~~
!F
~~+ ~+ - -t:- 71 7i u - s' , i - L.p,4-.+4-j i t-A i+t- .g,74, 7-*++tt.9-. - + * --vae-F t t -'. ! 44. 44.4' y +444.V'$'@P%. ' *+.~~
~~'.' :;.t~~
~~t. ~~~
~~T N~~
1
-.t t,7.4 I 9 7 l heAy.1 I,: i 1 i 1 .l 1 44 4-4 P.- o f < -b/+ t-4+ Po (~) O'~ W$t-- .a=- r @=t-cn -id 7-t 'i +~.I.di ' i h ' tr.Mm.1th N .yrf-tt - *nW'--t ,-r. 4 r-N y m, m 44,.+.44. m ocd, g p>! j, t**- ~ +4 lE - +k --t 4-- +,.-.: w m . t - r:*- t 3 F .-..~ .i-u 4-+4-.-- ; Y'9t+-*-*te f..- l i --.c m "-~+- m w.- 7 i "tg O-N h fhy[.. # 'j l kD O gy-m m ga er r c 'O m :D C m g O./,
O
>Z m W l (f) .a I ~ s m w- -A o cuo ~ L & cQ N A O W O N n o N - - ~ ~ ~ ~ ~w v u. w v s u a g I i t 1 i i u @ *Q @ ** u V *d D -eNNN N N u f.,pd Od W Oe Ahb e ya @ '4 @ ~Qg 9 A -~ wq
3 -3 0 f 4 k a H d. m, m W., f.M: it
~~rsW.:~~
~~3 [p .p. i e-J* d .:C -N--- +t r 'T - ~i'-*??rM h a---9 3,, ?%u.4.v,.c<~~
~~+~6%'* p%s O~~
~~gi .p .; =, ...-N 8 ozos yggg~~
C
~~-t l at*tt i,i--2 y.- ' s-11 1 [..- 3 4 t. ~ 0.-, ~ ^9 7 c,, <D. po--~ -. kl 2 F m *ai'4 "7 3p f"" M> S ,4 -'-# LT.-_ 3 umBM ..p m Q.-< b-.C O:~~
~~t +-*. t---..~~
~~e MW -- - p]-- -- omHH~~
~~y'If'hm+;w$~~
~~O ."-%'*pb.s g?....F-\\-- ji -N~~
~~s. @ $~~
~~H .o i c-4 -m r+.t-t-4M _ m a s H + H. 3 > +i i i I ' l l } }. +rrt N u-OOCO 1 1 ~ +tTTtW@h"W 'i-d 1 t+ 1 a> s= t--" 3 -- - X~~
~~d N~~
~~.1-~~'O i ; ^i i rt-~~
~~l'~'~~
M t"t ri i -i "T-i i i r T f*fi-T \\ iJ V (" >.'44.hp4 [ j 4-4444-,4.' \\ [ c l .,Ar-2m -co-I + : *+, ; m. 1 '~t i . rM+t t*'- 4 d...;- o e 'T 'KO -~~J d -+t-t +.*r Ptt *-~ \\ S t, 4, ; --+,t;H4-~Y-~H ' ?9- + +P' 4 t c3 m e. O r <,+'*t 'T, 1 ii i' r i p 4fh I 44-t-< 444 ' *I . 4L4 4 Ml \\
~~3. - --~~
~~E b ~ j ++t"+4-r+ O t i+- -+4tt t+ i ~ 3 i 'i'3 W Pla d+ \\ .m _f Q ..p. --.y q.4.v i 1 .m T, -,-a. 4 - t.+. LI.+,.4. 9 ;7t,-m -1 - e rv $ w :.w.a g 4- -w4 -+! '~~
~~, 2 h~~
~~? f+ !bd-2-~~
~~S o-+,.~~
q. l' i. [, $+ + -44 2 -+ f~+[+ : j y. {* -x' J t m s, 'T NT l! " t>wa i f *-t7 jj 44 q g i p++'rTtt+t i i 'T--t i i ; tit * + b r a* 3 44- -H+ ap-F 7AI'+--+i T 1. h,o g> -..H-L-H4 M (' T!.I p{ o 1. m .1
e.
~~O,, 2: w w a p,- - +t-- t i i 1D. -.1_ l 7!I l 'I i. 2 f; ^' i i:; +;: .-4 - +e* f Ry ie a m> i,t ii i a. T ? ra >< m 7..p_.i [*i.. -. j ?. J I i I ,[ hy.+4 J'l jj Jd M 9 - m--- 1_,- o t~~
~~ii i,~~
~~F-d414.h ! , r1 y; e g g yN i ! } L.4 7-.d4., --fj!l! I 5' Mm 3 i4 1 i 1+tF1r +1t+ : tti j - - + - %r g, L 4 } } so.j 4N~..I i ; 4.g4 Y ,,e u, g~~
~~g. M g w~~
1, 44,.f. 4-,+,! l-3 e j ygy j .p.., .m.r,.. . ;,.y,~.g4+e I - 4 4.a - /j + i,- g +... 4 ;; m+ y< p4..:t 7l -..t+a -+ 4-+4- - .; 1 i - / -- u m -+- ,1 .1 +- i! i. - x 3; t- ~~ 1 i: 1 -t~' itT N w N .MN 1 "4 t. O .ti 1 ~T.; -r - ' i 1 ~. 3 f e u t?*tt; i i1 _i i ' " * ~ n "'*- "-~ J b3 H r } .,, 4,.- i. I : hf'"~~'" ' - * - + ^ T 1 ,.1 ,1 i . ! A.. I. ,f L3 M 4 .44. 1 .u -Q .N h.- -tf "T"'" . u_. l-'
~~u i 1~~
~~- c !".+44+++++-t+p+-4N U)!!;,I % +T;N!i h" 6 3~~
?
t r 44-+ +44 '13,,? f l y.i r i ; i. : ?+T ~tN y [I I-41\\ p N p* [ [, +.+ } Y T&++i iii . 4 k g 444-.i"4a_4.44-,l;d. -T'n : M.- u ,i i ii 7.t~ l ' '" T*+ 4-y..C' ;h., A., r f f.!I N-N -,-t.' v; ', ++: a e-,-+4w.N. 4,. w: i. H+ i: l m o + ' *w++Nw+; w..,
.+
~~.L. t u- -i.--->.4p,-i-.bj < -},.**4*y p. 4 +4-- +y7 +r i.i m.rM.~~
~~E -L -.~~
~~T m q 1 - ' i i i.i > r 1 rtri + - - * +- (h, ? .,= r r 2 u s '4w y+4. :q= r+bT+;j ' h. { - -Yf. y-k*"' A[ 4-+/t' e-E~~
~~t i~~
~~e-. t n:,: +++. t .:, Yh,1 u~~
+-
~~+++ th j if I y m' f f i h'*'i'"7' a.;_,. 7 i A'". 74.d.i i;; O p I ~ ' ' i~~
~~dCi-O" -~~
~~1 e i N t++, - g-i~~
~~s. r~~
~~-,--tt 4s*T **Tv j r- . -++7tr+TT-*t, 1 m v~~
=
~~m l N tr-T+---- m --- N +r: e c n W-t-N + -f' H,-t $4t~~
~~h?.*d.W ? ?- -7+-+~~~
~~l I 07 t?+1 t~~
~~t M"*- 71jtr u'-~~
~~+, c' m' +++t - 'M T..a.-,0,ch.-.F1-A tt (T) i -a .,+~~
+

.p:%p+ i 3 u
~~l +; y I t.i~~
~~.#-. 'pf~~
+-- e F-t- +t.-.~ o it N l (n l l 4 Jm ,+ +-. 'l cO I( l r0 m m O l m o j x> rt r' t w 7) ND C o O j m g 2' a 1 l .Z l1 l lllf W m W 1 i i i O b' O CO G Q f g I N N NN N w V s,.u w wb y b @O'w m a; o N y e cp O N a N i n j
== @ @ N 4 ; g Q -'- Q N N N NNuuuuuAgg y 4 O N@ u&N4 um I
~_. .. -... _ _ _. - _. - _ -. ~.. -.. - I GINNA STATION STEAM CENERATOR EVALUATION NRC MEETING APRIL 30, 1982 p~. , ~ ~Q a s A" STEAM GENERATOR INSPECTION RESULTS Tr p '\\, M j d ' M -' ~~~ o EDDY CURRENT E TION ,ne% +\\, .. - ~
~
~~^% g g. R.},,,(',_.3 ,; e y & 4 i o PROFILOMETRY EXAMINATION \\ to ( M'Mi (Mi~~
~~dJe~~
~ [4 4.v cv 's ~ t ro Ms-., L' s ~# o FIBER OPTICS INSPECTION L' '* 3 o TELEVISION VIDEO INSPECTION ~ o FOREIGN OBJECTS ~ 4 s J 4 y r s y,-
d ~ ~ . _,. np q ~.5 7 C 'L f /F#' GINNA STATION D gf 24 ~ /- stEAN GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 CATEGORIZATION OF DEFECTS I NO. 6 R40C70 NO. 4 NO. 2 CATEGORY WEDGE AREA AREA WEDGE AREA WEDGE AREA p~. 1. Structurally R8C92 ~~ R42C55tU R43C59 R44C55M Degraded R10C93 ' IC4TC53 R43C60 R44C56 i I R11C91 243C54M R43C61 R44C57 R12C91 R43C55M R44C52 R44C58 R14C90 R43C56M R44C53M R45C53 R15C90 R43C57 R44C54 R45C54 R43C58 2. Video R9C91 R38071 R45C51 OD Indication R13C90 R38C72 R16C99 R39C68 R17C89 R39C69 l R39C70 l l 3. Eddy Current R15C89 R35C75* R45C46 312C2 I R40C67 R45C47M R28Cl2* Signal R40C68 R45C48 R30C15 R41C66 R45C49 R31C15 R45C50 R32C15 R32C16 R33C15 4. Preventatively [ R41C55 R42C54 Plugged R42C56 TOTALS 11 9 28 7 plugged for cold leg, support plate intersection, M Metallurgical Samples O.D. indications R45CS2 pulled April 1978
___..... _ _ _. ~. _.. - _ _ t j GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING. APRIL 30, 1982 METALLUROICAL EXAMINATION AND FAILURE ANALYSIS, t o SITE PHOTOGRAPHY t o WESTINGHO~USE/BATTELLE COLUMBUS LABORATORIES - o. MODEL FOR WEAR ORIENTATION COMPARISONS o PHOTOGRAPHY AT 90' INCREMENTS o RADIOGRAPHY AT 45' IliCREMENTS ~ o-DblENSIONING i ~ o OPTICAL METALLOGRAPHY OF TRANSVERSE SECTIONS o SCANNING ELECTRON MICROSCOPE FRACTOCRAPHY o KNOOP MICROHARD! FESS DETERMINATION o ELECTRODE DISCHARGE SPECTROSCOPY - CHEMICAL COMPOSITION o PHYSICAL PROPERTY DETERMINATIONS h i my 2 q_.- ,g f
~~m. -~~
m. .=.,,.,.;- - m -..r- .w., v., m .,w.,, ,r,-, vg..- y.-- y-. - ~,---c-3,-vm-,m w w,. 7-3-.
l l 1 GINNA STATION STEAM GENERATOR EVALUATICN NRC MEETING APRIL 30, ly82 METALLURGICAL EXAMINATION AND FAILURE ANALYSIS CONCLUSIONS o MICROSTRUCTURES WERE NORMAL o MECHANICAL PROPERTIES WERE NORMAL o NO EVIDENCE OF CORROSION OF ANY TUBE o INITIAL MLTALLURGICAL SAMPLES DISPLAYED WEAR ZONFS OF O.D. WALL REDUCTION WITH CIRCUMFERENTIAL STRIATIONS o 38 OF THE 40 WEAR ZONES SHOWED KNOOP MICROilARDNESS VALUES INDICATIVE OF COLD WORK FROM THE WEAR FROCESS o THE " BURST" R42 CSS OCCl?RRED WHERE THE WEAR ZONE HAD REDUCED THE WALL THICKNESS TO < 0.008 INCHES FOR APPROXIMATELY 4 INCHES IN LENGTH o THE " BURST" R42 CSS FRACTURE FACE WAS PURE SHEAR (DIMPLED RUPTURE), THE NORMAL FRACTURE MODE FOR TENSILE OVERLOAD o COLLAPSED AREAS OF PERIPHERY TUBES SHOWED EXTENSIVE COLD WORK 8-10 MILS IN DEPTH i o AREAS OF ShWER AND AXIAL BREAKAGE SHOWED FATIGUE STRIATIONS o THE DEFECT 24" ABOVE TUBE SHEET ON R45 C47 WAS CAUSED BY RUBBING FROM SEVERED TUBE R45 C54 WHICH WAS WEDGED BETWEEN WRAPPER AND OUTER ROW OF TUBES
GINNA STATION STEAM GENERATOR EVALVATION NRC MEETING APRIL 30. 1982 4 l P0STULATED FAILURE MECHANISM 0 INITIAL PLUGGING Y C< N^O( 0 COLLAPSE ( l-inpCW j "C[f / C WGSLk ) Q Urwe',.M G 4 e-O SEVERANCE gj,g p{., vxL,-j C&YC ^2't O
~~WEAP, C oWN"^i CY -~~
rca= jo, + [' ,Wu hvK n q. O
. _.._._, _. _.m._ _. 4 GINNA STATION STEAM-GENERATOR EVALUATION NRC MEETING n APRIL ~- 30; ~1982 [- c Mechanical Lead t Active Tube f-i 1 P a. Tute Plugged e 1P

~~g Collapse I-l 1r~~

~~\\ 0 Vibration i-i I~~
{
iP 1r i Shredding Sever ( i~f: i 4 p. p Wear Wear 4 j. Plugged Tube i Active Tube i-l it k 4 4 a - Plugging Burst }' { o .' - ( jU J i Postulated Failure Mechanism Sequence i i,- 1 ~ ... ~., a,
STEAM RA V LUATION JJLY 7 Al> L3 1 82 4 ACCESS hcl.E SHELL g \\ \\ R45 C54 LEAKER f ~ WRAPPER WEDGE, f fg ) i l = i,4 1 %, g 3f(3=i(f)_45 bi 44 ?- t 43
~~--_a g~~
gcit A peeeseg Ps ikk k . Y Rk k k ^2 COLUMN 62 61 60 59 58 57 56 55 54 53 52 51 50 49 48 47 46 45 Shaet 1 of 8
l STEAM RA R LUATION bAIUA 9 ARL 1 82 ACCESS HOLE ~ \\, SHELL \\ y 1 R44 C54 LEAKER, WEDGE, 1, i WRAPPER 7 \\ / I g ,;s = = * #~ l \\. - i- - ) ,}._ _ (.h j s 44 e j + f + i .___ 4 3 42 L j e COLUMN 62 61 t30 59 58 57 56 55 54 53 52 51 50 49 48 47 46 45 Sheet 2 of 8
GINNA STATION 11 0. 4 WEDGE AREA STEAM GENERATOR EVALUATION _ APRIL 1978 NRC MEETING APRIL 30, 1982 ACCESS HOLE t ~ ~ g SHELL \\\\ ^ \\v WEDGE kk f WRAPPER ,z \\ -h i I l
~~=="~~
l l> 3 * \\ t \\ I f_o_ ep/ ,'y I [ }- ..- 4 4 3 p p ~ r s . _t .. Y__43 t a . I_ f; . _(_ _' g h 0*^4 i l 1 COLUMN 62 61 60 59 58 57 56 55 54 53 52 Si 50 49 43 47 46 45 Sheet 3 of 8
a GINNA STATION Wo. 4 WEDGE AREA STEAM GENERATOR EVALUATION FEBRUARY 1979 ATR L 1 82 ACCES3 HOLE f \\/ / SHELL j \\ \\ \\ WRAPPER 1, WEDGE f 1 1 z Row l
~'
~~I A0~~
W
~* ~~ i R~ \\ 44 'Al l '] \\ 43 [ -_\\ 2 I it $9of ? -e COLUMN 62 61 60 59 58 57 56 55 54 53 52 51 49 48 4 46 45 Sheet 4 of 8 l
GIlfriA STATION NO. 4 WEDGE AREA STEAM GENERATOR EVALUATION DECEMBER 1979 NRC MEETING APRIL 30, 1982 ACCESS HOLE f a 1, SHELL R43 C54 LEAKER WRAPPER WEDGE j i 1 i ,,r * $ l I/ l l 1 \\ r l i i COLUMN 62 61 60 59 58 57 56 55 5-4 53 52 51 50 49 48 47 46 45 ~ Sheet 5 of 8
GINNA STATION NO. 4 WEDGE AREA STEAM GENERATOR EVALUATION APRIL 1980 NRC MEETING APRIL 30, 1982 ACCESS HOLE ,/ SHELL \\ \\ \\ WEDGEm i WRAPPER 1 1 ~ 1 l ,ys. M ~ l j \\ 3 i [;T.
~~5 s~~
_1 l_ .i 44 I 43 y-(- i. 42 J I j j -4g 8 ( ~ i F s 'j 'sj 40 l l l COLUMN 62 61 60 59 58 57 56 55 54 53 52 51 50 49 48 47 46 45 Sheet 6 of 8
~ ~ ~ GINNA STATION NO. 4 WEDGE AREA STEAM GENERATOR EVALUATION APRIL 1981__ NRC MEETING APRIL 30, 1982 [ l ACCESS NOLE ~ \\/ / SHELL \\ WRAPPER WEDGE t 1, p \\ \\ l l g s::: \\ now t 44 l -;--...j I -43 ~ + jt jfMi4 53h3(. l f I ll l i COLUMN 62 61 60 59 58 57 56 55 54 53 52 51 50 49 48 47 4G 45 Sheet 7 of 8
'I l \\) \\jl. 1l !l ~ 2 0 4 4 4 ,5 y 4 a j 6 e 8 u 4 R s EP j 8 t P 7 e A 4 e R n W y ; j s 8 [ 4 d 9 i* y 4 j [ u,0 e 5 j j 1 i l 5 ~ ,, 3 2 ? ( 5 E ~ A2 L E8 O 3 R9 H ~ 5 A1 A S s i E S 4 G5 E D2 I' 5 E i C s C WY A \\} 7 r[- - X .5 R 5 4A t U .N OA ,\\ 6 NJ 1 5 ^ \\ s \\ 7 5 \\~ 8 4 5 _s 9 5 N O 0 I T 6 AU j L 2 1 NA 8 E 6 g OVG9 G I EN1 D T I 1, TOE 0 V , O2 E ART 6 STE3 AM AR L N NECI M NNRR U ~ IENP L ~._ '- GG A O M C AE T S lIi
. - ~ _. '4 GINNA STATION STEAM GENERATOR EVALVATION NRC MEETING APRIL 30. 1982 t ANALYSIS AND TESTING PROGRAMS l DESIGN PARAMETERS THERMAL HYDRAULIC EVALUATION FLOW INDUCED VIBRATION LATERAL IMPACT LOADS AXIAL LOADS 7 COLLAPSE FATIGUE WEAR / BURST COLLAPSE TESTING FATIGUE TESTING MODEL TESTING CONCLUSIONS + w.--..
1 GINNA STATION . STEAM CENERATOR EVALUATION NRC MEETING APRIL 30,'1982 DESIGN PARAMETERS N0__. LOAD STEADY-STATE That cold T,y 547 F T = = = f P 2250 PSIA = p 1020 PSIA P = 3 100% FULL-POWER 0 T 603.8 F T 547.7 F = = hot cold 516.3 F 572.5 F T T = = av stm 2250 PSIA P 777 PSIA P = = p s 0 414.7 F RECIRC R'ATIO T 4.73 = = pg 8 4
GINNA STATION STEAM GENERATOR EVALUATION 1 NRC MEETING APRIL 30, 198? WRAPPER OUTER PERIPHERY TtRE, Bh5'0.D.x ht tnical O.75* SUPPORTBLOCK[ WEDGE y SUPPORT PLATE
~~. r n~~
58.5" - 60,88" = !E3 51.81" I' STUB BARREL /SHELL E y dO W A 14.00' ~ 1t u '22.00" TUBE SHEET v l Tubing Mill Annealed Inconel 600 7/8" 0.0. X.050 Wall 2% Max. Ovality R.T. Yield 40 - 65 ksi 6 S - 26.0 ksi at 10 Cycles a Tube Pitch 1.234" I
GINNA STAT 10N STEAM GENERA 10R EVALUATION NRC MEETING APRIL 30, 1982 THERMAL HYD__RAULIC EVALUATION . - PURPOSE DETERMINE FLUlD VELOCITIES FOR USE IN EVALUATING FLUID-INDUCED LOADS METHODS CHARM ANALYSIS WECAN ANALYSIS 5*0 .fd ~" N 56.5" tot 6 5.T
~~.;y FirstSupporth~~
~~/yot ggd ,47 yN,.;'g I,*,[*,. M hrouch wrapper 2,14 ft/sec Plate~~
f;
,c, 'v Opening j',.,,,p,, y/i 9 '. 51.81" h(E },f;;, y Chara Analysis Plane / %2's -*/- Y % /,. 'ji sn d ~, f.;?:. a" r 2.38 ft/4 V ' M k Tuoe sheet 20", Through Vrapper 0% ing \\ gwrq?] Tubes Pluggeo t .r~ L y l V = 30 WECAN Hydraulic Analysts l l
1 ~ ua ? g
~~e. ;~~
2 3* o 4 a e 5 .. (..' ,I,I,I,i I i,4, s.W - a 3g n 3 [ ,,yy;y4 ............. g.....,, ..... E... ......V..... * * * * * *. n. .y. .......~.......,...... l ,.............q..,...........s c ." -A-....................s . ~% e e s'! .-~ ~~.- ~ ~ ~ ~ ~ ~ - - - - - n,. ... i. U f m ~~~ .. s. -.a---- ....i.. m u p m .... i s s i i.... = .y-- s ..-...., is s yr-TT H .s.. rssssu ......... \\ \\ \\ \\ % % i } ss .........g....... un _ i i i ; i,t p Rf} n o t t 1 = gg 3 a M n. a
~~=c e4 c~~
~~3 w o m, z-tu- -o n. 1 >. w O .i <wn~~
mz

w a

z u -
~~.w w w J C Z Ch.< r< n w V. _................ g". ~,i,l,i,i l I i 2 _ rr:~~
~~vc :~~
s m ygg s ........a...... f ff j g g g N oy, g g ',, ........y ....... e....... 5 s = s g -~~ h..---................. 5 .................s . s.... i l s; y . -- _q s h -.-~~~------------,,,. s; } u _ __ s s -~~ ~ yA s s.. cj ! --/.- s i i i. sss) t t : E ^ a.. ss\\\\ti 1 7 A\\\\\\\\li J / __ _ liIL'I1l e ' 1 t.. M A l e
GINNA STATION STEAM GEt:ERATOR EVALUATION NRC t1EETING APRIL 30, 1982 my m v j / -7 9 1st 1%P 1:34 f 6 s 4 2 y g / ll \\) ll iii ,,i i I ial i / l / isi -i i ( il l i I l l-l - I I g ll s. l i iI l -i ( l i I k !/ " A" ll HUT Sid R D $tt( $1ALTff Ot!Yttarra or g nA vitu non pter4t0
a GINNA STATION ~ STEAM CENERATOR EVALUATION NkC MEETING - ~ APRIL 30,19R2 FLOW - INDUCED VIBRATION P_URPOSE_ DETERMINE THE STABILITY CHARACTERISTICS AND MAGNITUDES OF FLOW-INDUCED VIBPATION DISPLACEMENTS AND/OR LOADS FOR HOT LEG TULES BETWEEN THE TUBESHEET AND FIRST SUPPORT PLATE. d E E. ~ t 8 GROSS FLulo EFFECTS - DYNAMIC BEHAVIOR OF TUBES WITH VARIOUS CROSS-SECTIONS SUBJECTED TO CROSSFLOW. 8 LOCAL FLUID EFFECTS - ESTIMATE MAGNITUDES OF DYNAMIC LOADS ACTING ON A TEAR IN STEAM GENERATOR TUBING. e p e I 4
GINNA ST/, TION STEAM GENERATOR EVALUAT80N i NRC MEETING APR!t. 30, 1982 f r-. .8 3 14 0.D. 05 In R A k u ~ U ntAA O! Ct3! M + In ftLDCTTT= rPS ss.o-2 t' i / i s' /- x v n.s - I' stemn rtmo caces ruw eso:: '"~ nas m0cm ^~ 14.0- [d r s.o-i s. 3 e o I I 1 I f f I ~ ' RA$!C AWT3Js fCCtt EIDMITt? TUBE FUNDAMENTAL FREQUENCIES FOR THE VARIOUS CASES ANALYZED Cross Section Fixed-Fixed i Fixed Pinned P0 l P=0 , P. -1000 1bs Cylinder 58.7 HZ 40.3 HZ 38.5 HZ Flat 43.9 HZ 31.6 HZ 27.9 HZ 10 Ovalized 58.3 HZ 40.0 HZ Kidney 58.2 HZ 39.9 HZ
I t ,y: efI f r1' t '. ; [ .l l! u ii f! 1i:i l!l ? > i.*,i' i f!* i ^ 2rs D ti 0 As
~~e. s. 8 9~~
.M. s 3 t fM I sm93 A - t 5P F D 5I W EAWI e F s 1 T 0 7 0 1 .5 FY m OT 9 I 1 OC - W IO TL S / PRE-I T D A m M TW R E V i 2 9 1T$ t T 1 1L se C r L I r .h C 1 e 1 t a 4 1 O eS0 v Y T S a cE L A 5I ar 5 t t TOT m W SR1 D a a5 r r t 0 ! C0 s u t F 1 g C W 1F2 r t e R T8C 5 7 Ama f 7 L 9 5 f 5 Ei& DR '8 0 BT0C8 n f O m 9W9 C C 1 OOO
F9
~~?nap m N u O o 0 g . '4 I a T r u E m L A a E " l U F T .L D ko A E t I 9 -e uV 2 4" F i 6 4 8'. 4 2~~
~~l..E 8~~
~~' G9 2 4 1 1 nRN1 iOI gS. ACE E E+h E .TT .AE0 RE3 I.'~~
~~a. E M N~~
~~L aECI I uGRR TM NP D H A 0 M A A Q E E e. 9 3 t 0 7 e8 6 7 Sf A - F s4 55 D T t sf tf S si o o tF t I 1_ c e 7T 0 T~~
~~0. /~~
s CT 5 0 1 5 I t OC f IO TL-0 s AW R 1 t T i D T TN m A Y R f I i I C IL 0 O LFsr T I C a L D' L 1 u 1 f n 4 2 ? Y E 85 1 85f F n t E T0T 2 S aT I / W S2I. 9 S eA E B n CD 0 I L C n-O l n1 K F IF o. 5 P C ( T0C 9 5 S f. Ama-1 5 L T 0 id I 8 3 NTt D ( s t 3
~~ICa, m~~
~~Uos r C f OOQA R F' s L~~
~~J-9 f~~
s e T c 0 i me t c. ~4 .D .E .M ..~ .D w* N U 0 e 4' 0 4 t 2 I-2 0 1 s *
~~h c dR i~~
i' t' .%fe j 3 i1
w. U M k.d I ** e u o o,a. a . o. D s ~ D P* 3 o .GB J o & w a -e aE 4 o. u r, Q 3 w p a., w - a - a . o. E o ~ n. p u u .u O en R = o a,. s.d es a a ts. p w A. ta. u. e a = - O w w w . o -., a m. m. o w o w u a* o
~~o. o. m~~
~~= .z u oo-o . o. o = s o p o o at" = 5 A 004 o ^ z> N o O. D. 6, q q QW CC "ezm O ~ s n u t gow WHW e sn < u2 C 51tu~~
~~30nalidwy swy iv3s ac w to at w g Ez J~~
~~ZWOm yy ~0MK $8 e z o. E a. .= s w =c o a = ~~~
~~s i~~
~~W $.id p M ,0- ~ ea w a m E J w u w s' 4 Ew u E o w.n w = u .r o. o x. o. 4 e= N p g w a W a.s x .o. u a n a, '.n a n., .n =l =- s i u w e.n~~
~~o a 6.~~
~~40 =a w . w o w s-w M so m W m 6 o,, e e .a o W W 5. .e o o g d d , a. n .u = ~ a .a e o r o i -OO4 o. o o. b. o. a. o. e N .O. N $11u - 104111def Sus sv3d / (1 .a~~
~~.y n..... -,.s.,~~
~~i GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING april 30. 1982 o Liri ( \\~~
~~r f~~
~~./ #' H ~ N!$ tit of p/,A~~
~~!,P utt.tgter/t)bestll.O vf~~
,1,se ut for t.luistig vf tu. t, ter it) e ist (4 0 wim**uim u* s ve ran. c ter,,3 g r,,3,,, (i.u VQRTEX-SHEDDlH3 INDUCED LOADS ON PROTRUSIONT FOR A FLul.D. VELOCITY OF 10.0 FT/SEC Lift Toratie Lif t a for Drag Drag _ HID g (inches) (Ibs) (in.Ibs) F reauency;que (HI) (Ibs) Frecuency(Hz) 1.0 0.1 .28(10-2) .35(10-4) 240 .28(10-3) 480 It0 0.20 .11(10-1) .28 (10-3) 120 .11 ( 'L-2) 240 1.0 0.30 .25 (10-1) .95 (1 7 ) 80 .25(10-2) 160 3 1.0 0.40 .45 (10-1) .22(10-2) 60 .45(10-2) 120 1.0 0.50 .70 (10-1) .44(10-2) 48 ,70(10-2) 96 5.0 0.50 .14(10-1) .38 (10-3) 240 .14(10-2) 480 5.0 1.00 .56 (10-1) .14(10-2) 120 .56(10;2) 240 5.0 1.50 0.13 .47 (10-2) 80 .13 (1C51) 160 5.0 2.00 0.22 .11(10-1) 60 .22(10-1) 120 5.0 2.50 0.35 .22 (10-1) 48 .35(10-1) 96 1 ~~~
61ntin 3 AstuN STEAM GENERATOR E44tUATf0N 09C QEETING APRIL 30, 1982 i t 4 r FOREIGN OSECT INDUCED LON6 i i 4 Madel 1* Model 2* Xo (0) Peak Load Peak Load Case (Inches) Uss (f t/ set) Ua (ftisec) -(1bs)--- -(1bs)-- j 1 -5 2.3 0 26 107 i 2 0 .69 .69 .15 .28 l 3 0 .345 .69 .39 1.40 i i i
~~Model 1: K5G - 3717 lb/ inches 2 MSG "'.03767 lb - set / inches Model 2:~~
Md 19439 !blinches Ksr .01068 lb - sec2/ inches i c I l i t 5 j 'p l1
GINNA STA?!0N STEAri GENERATOR EVALUATION NRC MEETING APRit 30, 1982 ANALYSJS AND TEST!NG PROGRAMS TUBE LOADINGS 9 LATERAL IMPACT LOADS 8 FLOW-INDUCED VIBRATIONS 6 AXIAL LOADS EXTERNAL PRESSURE THERMAL GROWTH MISMATCHES TUBE SHEET ROTATION AND MISALIGNMENT TUBE DEGRADATION / FAILURE MECHANISMS 0 EOLLAPSE 9 FATIGUE ~ 8 WEAR A BURST LABORATORY TESTING e COLLAPSE 4 FATIGUE 4 FLOW MODEL 1
GINNA STATION STEAM GENERATO9 EVALVATION NRC MEETING APRIL 30, 1982 e AXIAL LOADS ON PLUGGED TUBES S 0 t@,CX MAX. LOAD,_LB. I SECONDARY PRE 3SURE II NO-LOAD SS, P= 1005 PSIG 604 FULL-LOAD SS, " = 762 PSIG
~~A58, e~~
TUBE-70-SHELL INTERACTION I2) HOT STANDBY: TUBE-547 F, SHELL-476 F 1940. PLANT LOADING: TUBE-517 F, SHELL-547 F 825. 0 PLANT UNLO, DING: TUBE-547 F. SHELL-497 F -1375. FULL POWER SS: TUBE-517 F. SHELL-497 F 550. 9 PLUGGED -TO-AC ' '.V E TU8E IN TER AC T ION ( 2) FULL POWER SS: T a517 F. T =565 F 1410. 0 p A NOTES: (1) TUDE FREE TO MOVE AXIALLY AT TSP (2) TUBE AXIALLY RESTRAINED AT TSP 1 rv, ,w-= -v r - -,v-., -r i- ,cr= i- ,w, v -,wi-vu-,,-,yr-y-a ,-w
GINNA STATION STEAM GENERATOR EVALUATION NRC HEETING APRIL 30, 1982 _,.m
~~.~===,_.,g======_~~
~~w-r --- a,. _. ;.:..~~
~~+- .:.=w._=3-r g=.s =2=~~
~~2===;== r= ;===v=k~~
~~-- r r . w -- 3=i======F.=~:=.=gy 3=; _3_- _;1=1 =3 =.~~
=,
y g===}=x=_:,._===t =.=-+- "_-s=::= :=== = .._--. p.,..._.. _. _].. --- :- 1 -: :: ;===s= =-::=.. ;.==*.c =E=._.:: =,. -1 ~ -+ .- = '"~'*:=. f~ -. E - - _ _=;.... :=-._ .=_,t.._c = =: c.,.. __=.,==...=m.. .=.= y= ===$==4E==_.=u = - =_. _=_ m _. .=Eg a_...-- _. _ __.._
,=
~~w _ t...-_=. g= a- _-.G._:ek: .._ 6_=.y,;=_ l_.._.W_. _ =_.:.g=_ L=_. .. =. ~ =. =_E=~ = =_ = .a _ t=. = =i=- g ;,_=- =. "'7M==n= =rth_'.*'._. _ + 2'--""'~ C'~~
~~39 =2==t ~ -~~
4 =-+=_,{=.=r----
== a.0301n. WALL.=t=)-_ z =-
~~L._ =3~~
+ - - 5 -_ 1= L._ -~ .. = =_=-. =_ t=.p. m.==$====_==.1; ='.R= =222.'.~t_.y y m,_.. __- - =- = -
== w. r. u r =. s %---~' ' -.,.q=__= - = _ =r a g =,.. L.=..=T=a. '.;===t :=. ~~L - :d.s. 2.=__,r=:=.. }==r= =. =_er=a== =p:.g=l=+==n=.=._=. _ !.======; m -. x r _.=.;2~===..=-m 7. . - _.,. g_-=_ 7 =- ~a:-=~*==m., p = = p_.___.. = - - - - = :==":y"1 ".z__=g =1 m- = =' =* ' ^=_ 5 ..w _ _z= =,=== e - = =",p==ad=- _sr:
~~~~=y_a_.~~
".. f =._,. _:~=- n. _=._ _. ._.._._.E ~'I_EE.="-_ _. _ ..w.=_y, =.
== STRESS = E v . - = _ .y,-~_..-.-., e,..___= , _ _ = = (KSI) =3=%r= _ _ w=,..---=4,:.:p. r== =g- , _ _= _.,. _,_=j...i,g7, _- z, =...x= =_=.5,==:j. _=:==t.,=_=.Q. = -=_=. =m_.. =_. _
==.- .m = =.=.u ,.+ g _J=_ w v s r._ n-o. =. 4 _ = r+
t
. =. - = -.,=m==. = =..==.=Q=.{.=. -~ .==, = r.: . wx
==
~~. =~~
~~m _ q = =_~ =_~ ~. - - t r,= ; a: =_= =%.~~
=c
=
~~.- --ehsa=_.g==.m1=.~~
~~, i+,y =raf4:-- 1 3a=e=a--g -t=~~
~~.==.- 3_.-~~
~~..=_.=_= rmp- = t==:== u= p....a: c = =:_ J vg.. ,,..._ - &... -77_.. . v -, _.. _..---=. 7. =.-=_g' ;. _,=_ -,a=;;,yr a - = 3=. 3 a=_. _ g..~~
~~w....~~
~~>===_t : -==t. r _ _, _-...,.-=d_-__=.,_=u;:=.d==m=p-r=m=.. 4 g '~....._ _i ..__4_,_._.. _ ' __ 4+.w"'~_.*=.T. ?. ~=:O.P.ui - _-- +_--a. + r s MiU-*;L : \\ ~= _;.y~'g- " _b =1~~
~~="t= -%~~
~~. p---~~
~~- _--= nt.g[=:.,rg~~
" % =T%, ,,;., ;, f._._.E_=. =_=M=.W.f_~. '.'2 '=j=__.4, ~~3==d=J-'-~ l ;. ))g*,, } : .' =.f=2?.!.9(- )t==.:. 2 _. _. _..,.g...,. __...-:. -.._ +:-4-+-.-v... , _,: :.5:,=2_ _. a-- _;,,,-.=_. r. c 3,. "- 3.=_.g=.=~.1?:* *1=c.-:p= g ... = _.. ..__t _ ;_._.__7t"'*- s .. c. s _.. _ l g ,_::r--- .._;_... 2=_ a mm.= 2__ - - - -..4 - *-- - w ..m=u c.w =
~~=.y, _ .~~
~~-*0= L; =**J '**.~~
~~_. = =~~
~~.g _.,_- g_="x."" C$'.=._.3==.t _... g =."x W=lt ! -_4. :=t- - ' - - g = _ _ 7 _._:---~ = n . A._. . s. . -.=_j==.==4m =. _~ =-~~
-m* g*
N. h.N Y,. t..tA_11_ -=,. 4_s_-------__1.4,_.,____,=..g_,:. g:.=t4g.,b. ath, ,7 g 4, 4 w._ __ _m.__ e -... . r., _ %-.g.=. _= = =u.. . =, p ..-4, --? N 0. _. t_._. '* *.".: _~4-. 4., L 4 = =*:. ; r*!.** Trag-* ,..~_~___4 _..,Q= .,y. Aam.en -._44948 gmf __r .g_... 0 .1 .2 .3 4 .5 AXIAL DISTANCE FROM LOAD (IN) HOOP STRESS IN OUTER FIBER DUE TO 5 POUND RADIAL LOAD l '.=-M __.__.______m.__.______._m,_,.
GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 I
~~SUMMARY~~
OF C01. LAPSE ANALYS15 FOR A NOMINAL 0.050 INCH WALL TUBE WITH 2% OVALITY l AND 58 KS! Y! ELD STRENGTH, A LATFRAL LOAD OF 75 LB. 15 REQUIRED FOR INCIPIENT YlELDING. AXIAL LOAD OF 1000 lb. TENSION REDUCES THE INclP!ENT YlELD LOAD BY APPROV1MATELY 10.0 LB. i HOWEVER THE STRE,5 FIELO e t? 1.0CALIIED. TO PRECIPITATE COLLAP5t 't si % Uti!ED l HAT: 1. THE LOAD BE SIGNIFICAhlLY HIGHER IN ORDCR TO OBTAIN A THROUGH-WA.L PLASTIC ZONE (HINGE)
~~AND, 2.~~
THE LOAD MUST ACT AT DIFFERENT TUBE LOCATIONS, IN ORDER TO PLASTICALLY DEFORM AN AREA 2 TO 3 TVEE DIAMETER 5 LONG AXIALLY. a
GINNA STATION STEAM GENERATOR EVALUA?!0N NRC PECTING APRIL 30,19B2 SUMERY OF PLUGGED TUBE FATIGUE ANALYSIS (DESIGN Mlft. WALL =0.045 INCH, NOMIN,At OVAllTY=2%) STRUCiURALLY STABLE TUBES PRINCIPAL LOADING: THERMAL MECHANICAL DUTY CYCLES (LOW CYCLE FAT 1GUE) CASE LATERAL LOAD IMPACT IUSAGEFACTOR(U).
1. NOMIN11LY PLUGGED NONE 0.036

2. HOMINALLY PLUGGED WITH NOTCH NOTCH (SCFa4.0) 0.676 STRUCTURALLY DEGRADED TUBES (LOCALLY COLLAPSED)
~~PRINCIPAL LOADifiG: FLOW-INDUCED YlBRATIONS (CROSS-FLOW TUBBULDICE), (HIGHCYCLEFATIGUE) LATERAL LOAD LB. POSTULATED FAILURE ~ CASE (CONTINUOUSLY ACTING) (pl.0) TIME. DAYS~~
~~3. FIXED-PIANED TUBE SPAN 0.~~
~~NO FAILURE LOCALLY COLLAPSED OVER 10. 30. 2.0 INCH LENGTH NEAR 25, 2.5 TUBE SHEET 50. 0.7~~
~~SUMMARY~~
STRUCTURALLY STABLE TUBES HAVE ACCEPTABl.E FATIGUE MARGINS STRUCTURALLY ^ DEGRADED TUBE, WHEN C0fiTINUOUSLY ACTED V00N dY A LATERAL LOAD, CAN Fall IN HIGH CYCLE FATIGUE DUE TO FLUID INTF.RAC110N. t 1
_=.. GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30,1982 WEAR CORRELATION L e JASIC INCONEL ON INCONEL SPECIFIC WEAR COEFF. RANGE = 2 58 to 854 IN /lb. WEAR VOLUME BASED ON RUB AREA = 8.0" LONG X 0.1" WIDE X 0.0434" DEEP CONTACT FORCE BASED ON DRAG FORCE ON SEVERED TUBE = 3.0 LBS. RUB VELOCITY a 5 in/ set USING ARCHARD THEORY ~ RUB FREQUENCY = 50 HZ AND MEAN RUB AMPLITUDE = 0.050 INCH ESTIMATED TIME RANGE FOR TUBE BURST, 59 DAYS ~ TO 1.27 YEARS e CONCLUSIONS FOR THE CASE OF A SEVERED TUBE (AT TUBE SHEET) RUBBING ON A NEIGHBORING TUBE, CALCULATED FAILURE TIME PERIODS REASONABLY ENVELOP THE OBSERVED WEAR RANGE WEAR BY UNSEVERED TUBE NOT POSSIBLE SINCE FLOW-1NDUCED V!BRATION AMPLITUDES ARE STALL AND WILL NOT RESULT IN TUBE CONTACT
GINNA STATION $7EAM GENERATOR EVALVATION NRC MEETING APRIL 30, 1982 ju_RST CORRCLAT1ON 8 MINIMUM TUBE WALL AT BURST ASME CODE NB - 3324.1 P,
S

09*7 KSI u
9 P = 780 PSI n 2250 PSI P a g 0.0066 INCH t = 8. MEASUREMENT 0F (MINIMUM) WALL OF BURST TUDE (R42 CSS) t = 0.008 INCH 6
v 4...m s i n i, v i a STEAM GF.NERATOR EVALUATION y i;RC MEETING + APRIL 30. 1902 t O*h 460ic ts 6 i [ Ain pal E E D Nt/v lTY P BOTH twos) 1 cap BC84W l LND CAP 2556(0[// Y//.n/b
~~-J 6%CivW j~~
~~d -{ ' ~ ~ pxllYid, m~. . 4., sype ~ M s L g :: w e, we== ~ Ag E tI R.O DlA.TVer~~
~~O" A ING&~~
Iij 4} O YP. bO7H EWDs) J LWAGt.LO6. '2.0 D A TEE i . L %g' - q,e bl 4 ~~ /+ 6000 PSl i D W Ai k R s ,'j OY NAMic t.tAL OR Mb ' il -- IM PACT $1 0 D ..- ETA ND OF F b i - LoAo ctLL nh ns 1 I l .3 --- w Y DC4 AULIC CY L14C18A li I I t' l' l i 1 l l -wvDA AULtc CfLtNCtfA l M C%>NTIN G FtRTURE, _E.J ud E i l 1 l l i, i l l l I l l h SCHEMATIC-TUBE COLLAP5E TEST l l l l l..,...,. _.. -...... =.. _. _ _ _. _, _.... _ _.. _.. _. - _,.. r-e,
......n.n.... STEAM GENERATOR EVALUATION NRC HEETING APRIL 30, 1982 LATERAL LOAD BENCH TEST-STAT!_C, C IMPACT R00 - TIP.125" x 1.00', 900 W TAPER Clamp Cic:op ~ 5 \\/ r-TUBE, 0. 0.=. 87 2 " !. D.r. 7 6 6 " ..y.. ..y.. O V A L I T Y 0 " */, Block Block a i i < i i i i i i < i i i i r i t ir7 t 2400 - a 2200 - 2000 - 0.0. MAX. 0.D. MIN. IS00 - 1600-1400 - J3 1200-ci .g a 1000 - 800-600-f 400< 200' .872" O i .400 500 .600.700.800.900 1.00 1.10 1.20 DIAMETER. IN. _ ~~ :,
. _.._. _ ~. GINNA STATION STEAM GENERATOR EVALUATION NRC NEETLNG APRIL 30 982 LATERALLOADBENCHTEST-STATIC, CHISEL IMPACTOR g g TUBE V-BLOCK 6" V-BLOCK -r s. a OVALITY (%) LOAD (LBS) ~~ SHARP CHISEL BLUNT CHISEL 0_ 0 0 550 1.1 0.2 700 2.1 0.8 850-3.9 1.9 1000 6.0 3.7 8 Chisel Facq: Sharp = 0.030" x 1.0" Blunt = 0.125" x 1.0" i l l
GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30.1982 DYNAMIC COLLAPSE TESTING 1 l _1 " f " 0 EXTERNAL PRESSURE <1000 PSI 0 LATERAL LOAD = 600 LBS g ]- # 0 1MPACTING SEQUENCE: a. IMPACT AT EVERY 1/4" ALONG impacted Area r 0-DEGREE PLANE FROM ONE END OF AREA TO THE OTHER. THEN OFFSET 1/8" AND BACKTRACK. 0
b. REPEAT STEP "a" ON THE + 20 PLANE 0

c. REPEAT STEP "b" ON THE -20 PLANE.
M SHARP CHISEL (1.00"x0.030"fBLUNT CHISEL (1.00"x0.125") . SEQUENCE DD MAX /00M1?{' 10 MIN OVALITY (%) (INCH) (INCH) ITY(%) ODMAX/00Mih ID MIN NO. (INCH) .I (INCH) INITIAL '0 884 0.873 /0.861 0.755 2.6% /0.873 0.766 0% 1 ~~' O.724 0.734 2 0.699 0.695 3 0.680 0.664 4 0.660 0.647 0.928 0.923 FINAL /0.73- /0.766 23.5% 18.5% NO COLLAPSE. DEVELOPED CRACK TEST IN PROGRESS DURING SUBSEQUENT IMPACTS 4 P INCREASED TO 1500 PSI
~~0VAll2ED IN AVISE~~
\\ l
-I e e H O e uJ W st LAJ W W "O D J e "L.. m .J J U J H w w O >= e-a st. et W O
~~C W~~
~~W J Z LA. w m uJ D O aC H O cx E 2 6 =C 2 e% J to @ W c WO O4 O O O O WW mW r. m r= m t.) H e4 >m X X X X x WW Z N Ch M = CC H aC O W~~
~~M E~~
~~P f6 w O W s. O DM EM W' W Z cr uJ U J. .a W e .a = x e a w ~g Cg O WM CO O O O O O (2 sc H J.J C O O O >= 0 CL O O O O 1* ut aCs W e r= c= m v O e W C3 O W M Hu w w~~
s

ax cc O Cu O
O O O i CL o. W W H W wE D CL M M C M MM w M HO w +-e O T3 W W -W a:C w W W> 4 8 s t H. s I J a* O O O Ow O OJ O w w W w w W at U M M M % M ME >=e e.* +=e U w e.e W W W W >= W W &= OZ 2*; O O W W I O Q. CL -5 5 W CL M A e e-c >c i O. at c d (3 a >O 1: OX 2: C s WW -O O - O WO W w W.J H J Ht
~~_J z~~~
~~J Q O~~
~~C A~~
st .O a .J z Jz Js e-a s WN LA. N WN Mm 24 N s 4.-
GINNA STA1!ON STEAM GENERATOR EVALUATION NRC MEETING. APRIL 30, 1982 MODEL, TEST, L t O_BJECTIVES NATURE AND EXTENT FOREIGN ODJECT MOBILITY i MAGNITUDE FOREIGN OBJECT IMPACT 1.0 ADS STABILITY CHARACTERISTICS OF OEGRADED TUDES NATURE AND EXTENT OF TUBE-TO-TUBE INTERACTION W l s- = s ~- 'I 4s .c y v. ,v-v--, ,-v- -y y .yr-w=m.,3-~,,-#,+ -m m,e =v n,v- +-w.< ,+.---,r-- ..,e e.~--,-, ---m..m,e-m - - ~ ---- - - - - -
m s, ~%, A. - - * +. 4 - 9 e e 8 ' E"'E !!"$l"^"*" hf l%?f - Ql8 v j N t s. LAng ^ w 9 <v' ~ s /. , weap,ER "ow <, Psyg
YE
~~& a no.o.y g ~ w ~~ now,, ,uru Col.4g b $ 0L, ' L'50l 1Ysr"YfL'ere, op g O ot.,, e-Col. HUG wgg .v.~~
~~iftlNo, y~~
f l Y) / o i ,Ng ee a
1 GINNA STATION STEAM GENERATOR EVALUATION NRC HEETING APRIL 30, 1982 .:: w _ ..m. _._..... --.r < w T .. [p (0 I J l 1 l ~[~'g,g I i !2 Support i I s i t Plate e A.8 p-r s j
my
~~.l s s n ~ ~ s Perforatel F.zit Plat 4t a i) ,l ( L $64 66" ,l 2 w. 5;. 81" 44,38 6 "',,, Tub t.{~~
~~32. 3B"~~
~~-~ y k )~~
~~14.00"~~
\\ I- \\ s 6_ dea 9-31 -) Y t Section View of Flow Test Model h ,u,.. ~ (. l t <e ,.r
4 GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRll 30, 1982 \\ MODEL TES_,1 r CONCLUSIONS OBJECT MOTION RANDOM IN NATURE AND OCCURRED FOR ALL ORIENTATIONS AND POSITIONS r ? MAXIMUM FOREIGN OB' JECT IMPACT FORCES -ACCELEROMETER DATA 120 - 180.LBS. t FORCE TRAhSDUCERS 200 - 350 LDS, ~ TUBES WITH UNDEGRADED AND LOCALLY DEGRADED CROSS SECTIONS WERE STABLE SEVERED TUBE TENDED TO-NESTLE BETWEEN NEICHBORING TUBES AND INTERMITTENT IMPACTS WERE OBSERVED = l: I i - i. j o i 4 as _s. .%4 g p ,.e- ,_.w.. ,.m.,, .,.-u,.,
GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 CONCLUSIONS COLLAPSE -SIGNIFICANT LEVELS OF COLD WORK FOUND ON COLLAPSED TUBING SURFACE -LARGE FOREIGN OBJECT REMOVED FROM STEAM GENERATOR CAPABLE OF PROVIDING 100 - 350 LBS. IMPACT LOADS -LATERAL IMPACT LOADS IN THE RANGE OF SO - 75 LBS. WILL IN COMBINATION WITH A 1000 PSI-EXTERNAL PRESSURE CAUSE INCIP!ENT YlELDING
~~FATIGUE,~~
-STRUCTURALLY DEGRADED TUBE--CAN-Fall DUE-TO--HIGH CYCLE FATIGUE-WHEN SUBJECTED TO CONTINUING LATERAL IMPACT LOADS -STRUCTURALLY-DEGRADED TUBE WILL NOT FAIL DUE TO FLUID INDUCED VIBRATION -NOMINAL PLUGGED TUBE WITH A NOTCH OR STRESS RISER WILL NOT Fall IN' FAT!GUE -FATIGUE TY_PE STRIATIONS FOUND AT FAILED TUBING SURFACES -TU6E WEAR PATTERNS COMPATIBLE WITH ONE. TUBE RUBBING AGAINST ANOTHER -SUFFICIENT WEAR CAN OCCUR TO CAUSE BURSTING OF-A TUBE -EDDY CURRENT DATA SUBSEQUENT TO FEBRUARY 1979 C0f,45! STENT W11H PROPAGATION OF DEGRADAT!?N BY WEAR PROCESS BURST -LABORATORY EXAMINATION INDICATED A PURELY DUCTILE FAILURE R42 CSS -CALCULATED AND OBSERVED BURST THICKNESS ARE CONSISTENT
GI!4NA STATION STEAM GEllERATOR EVALUATION NRC MEETIllG AlR,IL 30, 1982 REPAIR PROGRAM o ACCESG HOLES o TUBE REMOVAL o TUDE PULL o LOOSE PARTS o MECHANICAL PLUG REMOVAL o INSPECTIONS AND TESTS o RADIATION EXPOSURE e I

~~__.__.m.-__.~~

4 GItalA STATION STEAM GEllERATOR EVALUATIOli liRC MEETI!1G APRIL 30, 1992 ACCESS HOLE LO_,CA_TIoti AN N ULu $ ._ y. f r D I we_ocas S U P PO RT PL ATE. g- -- r s j TustS OHELL -_.Y/RAPPCE cTub SAEP.EL Tubf CHtt.T ) A C f. E. O S H O L E 'L ,~ ' <L l b 8
rt l0 ? 0 ? I I I o -- 0 4J ~ ~ g h--'ih?ll g -4 f h k (h-4 I t-1 t-y 5 x y y ? Ili d E E O -/ gQ3p gg g 090 _U .3 3 J\\ I sl l ~I ~ ~ \\ ~, E G .e g -i o N i e y e S N.'.- e w w S gy N e ~- t c j a a o s p i
~~,,,\\\\ -~~
.f. g g g y w a n', fs 't. @ E a @ C W s L s 8: g =s ~ a s, Sge r s ', o -a= 3,.. e gN h $j N t m m ,$' ' y. k U l smee ( I a0 GD== g g o d 5 i u g M J t
1 ~ GINNA STATION STEA!1 GENERATOR EVALUATION NRC MEETING APRIL _30, 1982 ACCESS Il0LE COVER _4 g,,,. b Q . g,. E u.,em 4' y se bol.T p Covt.t P L,e.q E, fT Il /f~//,A T7, erun s a ceL. k f ,c w~ ,. x s N 6 N s xx xx 4 i w
GIH!!A STATIO!!
/
~~WRAPPER STEAM GENERATOR EVALUATIO!! NRC MEETING f i M'RIL 30, 1982 ,/- ,/ ' NO. 6 WEDGE AREA ~~ SHELL ,s g - o q; (,(- ik ,jeo o Ni -i ' lg ' i l' -le-;~~
~~ACCESS j~~
HOLE - + ,, 7 O !r 16-A, a_ f I s N,' N. - ~ ~ ~. 'N N w y y + r. 1 YJ J u i l ff' 1}. a ~ J WEDGE-e 'l/,// x ' nlO l jN i s .g: I e l 8 t l .7 _ _ 6 4 -- f 3-l i l I I i ii 52 ' 91 90 9 88 .7 6 5 COLtNN ' '
i l GIhHA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 i i g. i RADI ATION__EXPOSI)RE o PREPARATION 40 Man rem o PRE 4 REPAIR INSPECTIONS 80 o ACCESS HOLES 30 1 __o- --TUBE--REMOVAL 35 o TUBE PULL 50 o LOOSE PARTS REMOVAL 40 _= ~ o MECHANICAL PLUG REMOVAL 20 { o - POST-REPAIR INSPECTIONS 25 o CLOSEOUT 15 TOTAL 335 Man rem I h e RGE-11
~~"w y3 e~~
,..y ,- +, - r,.- -,.. ~,,..r. y.-.,,...,,,c~.,., .-..-,--m., ,v,.,--,..--m----,,,.....-...-.-,-,w-+---->-.--<
~-. GINNA STATION STEAM GENERATOR EVALVATION NRC HEETING APRIL 30, 1932 1 .TJCHNICAt. BASIS REP AIR PROGRAM 4 ACCESS PORTS 8 THERHAL/ HYDRAULIC EVALUATION 8 STRUCTURAL EVALUATION P ,, FATIGUE COLLAPSE GE0HETRIC STABILITY ~ ~ e' ? k
n.-..._-- e GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 r m g [ ,4 s 'w j i 1 1 I i I l l I 4 r%.m u w :
~~/ we vtm i~~
~~o \\ I f / 4 .g\\ = ...s. w .--.--4 ~ r -B ut.tw wt u.uiu Met~~
t.
T 5 I / \\ J / i / ./ .~ l l . Location of Access Ports l l I e.
~..,.. ~~ '. ' - G!NNA STAT!ON STEAM GENERATOR EVALUATION l NRC MEETING APRIL 30. 1982 i STRESS SUMMRY FOR 3 INCH DIAETER ACCESS PORT I Ratio of Maximum Stress to Allowable Stress Belt Cover Shell Lead Condition. 0.63(1) 0.29(3) (6) l Design 1.01(5) l Normal and Abnorma) 0.65(1) <1.0 O.98(2) i 0.65(1) 0.29(3). ,(6) i Test 0.62(2) 0.85(4) 0.00 0.16 Fatigue usage Factor Bolt Replacement Interval 8 years - s. 4 Notes (1) Average Service Stress i (2) Maxime Service Stress ~ Primary Mea 6rane Plus Sending (3) (4)- Fatigue usage factor based on srecified replacement interval ~ A simplified elastic - p)estic (5) Acceptable per Code. analysis was invoked for the fatigue eva Primary stress limits are satisfied by Code rules for (6) i opening not requiring reinforcement. o o e Y 4 A ^ l 3 se s M ee av v v- -ver7 T-
~~r*4=-~~
~~'s-e tve~~
~~r w v-g e-pv+,,-v+w~~
~~.w-e-.w w e ww--+, -+p4 v%1,9 r-r-m 1+ m-~~

w-

~~w g~~

-=w,-W
.~ ...x - G,l9A STATION-STEAM GENERATOR EVALUATf0N NRC MEETING APRIL 30,1981' i THERMAL HYORAULIC EVALUATION _ 4 ED l PURPOSE DETERMINE FLUID VELOCITIES FOR USE IN 4 LOADS ~ .ME_T H 00 S_ CHARM ANALYSIS l .WECAN ANALYSIS } ..s- .aqs ~~ J. 5" N af t.t! ~w l .,i'I< l 4 i. /, L '. 2,14 f t/s'C I @M I Ys'? ^ A n m an wrapper l First Supportir 'j @nW- -- Hate J'. A.,v - sv t,. t~ 1 l l~ 51.81*' (Addj Chore Analysts Plan
~~d l.~~
'f;i;? f * ', 'A Q N .i, / I'M' " Tube Sheet 2.38 ft/s V 2% Througn tireP9" Tutes P1899'd Opening .3 t' J t --y I L 3o aca previte Analyste ~ l, l~ l i .y,
GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30,1982 BETWEEN-TUBE CROSSFLOW VELOC1 TIES IN AND HEAR THE TUBES REMOVED REGION ~ Crossflow Velocity Cressflow Velocity Crossflow Velocity (1 block of 2 nlocks of Location -(nsminal) tubes removed) _, ; If es removed) - Perimeter Cell 8.2 ft/sec 9.13 ftisec S.i. ic/sec (Face A) Perimeter Cell 8.2 f t/sec 9.13 f t/sec 9.13 ft/sec (FaceC) L_ Perimeter Cell 9.01 f t/sec 10.12 f t/sec 10.33 ft/sec (Face B) One Cell in 8.54 ft/sec 9.48 ft/sec 10.95 ft/sec from Perimeter (FaceB) Two Cells in 8.21 ft/sec 9.16 ft/sec 10.46 ft/sec from Perimeter (Face B) Ug n I \\ v U C N UC B N C C / 9 Node 11 ) A l \\ Ug MAXIMUM TUBE GAP VELOCITIES i WITH AND WITHOUT TUBE REHGVAL Case. Maxirmm Geo Velocity; f t/sec Nonical-9.01 One block of tubes removed 10.12 Two block of tubes removed 10.95 _______________-____-__________________._________L_.
GINNA STATION STIAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 I ~ _SUt*t1ARY OF TUR3ULENCE ANAtJSES - FIXED-FIXED BOUNDARIES - CROSS-FLOW VELOCITY, 10.0 FT/SEC - DAMPING RATIO, 0.01 CROSS SECTION OF VIBRATION AMPLITUDES, FILS= DIST0kTED 2,0NE TURBULENCE CYLINDER (NOMINAL) 0.01 10 PERCENT,,0,V ALITY 0.83 XIONEY 0.83 N e 1
1 GINNA STATION STEAM GEhERATOR EVALUATION NRC MEETING APRIL 30, 1982 FATIGUE THEkMAL/ MECHANICAL LOADS NOMINAL CLUGGED TUBE .036 US AGE ( l.0 NOMINAL PLUGGED TUBE .676 'JS AGE 41.0 WITH NOTCH OR STRESS R I S E 'l ,HYDRAUL.iC LOADS STABILITY 10.12 FT/SEC < 14 FT/SEC CROSS FLOW TORDULENCE 111.24 KSI<l3 KS1 AT 10 .(10 TT/SEC, NOTCH, F-P) s e e h e 6
=mv GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 COLLAPSE l y_ I 6 NQ ~ S O 3d g O +4 E Es e, h S o "t O woutcTLD i .o MrmlwDumN t O WWlwDlthCN g , wmiwo uwcm " IrlfrNIMDimCN e a e e e im RAXIMW DECitADAfl0N,9 een ~ COLLAPSE PRESSURE OF UNIFORMLY THINNED TUBING 8 TESTING RESULTS -COLLAPSE STRENGTH NOMINAL TUBE 5000 PSI -80% UNIFORM THINNING FOR COLLAP5E AT 1020 PSI t FOR A GIVEN % WALL DEGRADATION COLLAPSE, PRESSURE FOR LOCALIZED THINNING WILL BE GREATER THAN FOR UNIFORM i THINNING 6 TUBES IN STEAM SENERATOR HAVE PASSED A PROOF COLLAPSE TEST i h,.
i_ [..... _ GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30. 1982 GEOMETRIC STABIt.,1,TY PRESSURE ~ THERNAL LATERAL TUBE DEFLECTION s BROKEN HOT LEG OF m HJBE GUIDED BY UPPER PLATES {' $ TSP THE = 0.75 INCH 9 1 _ d,, TUSE SEVERED JU57 51.B8 INCH BELOW THE FIRST PLATE i n --- 33 1 Schemetic of a Partial Tube i O c. I m ^ - - - - - - - - - - - - ~ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _
i e I e GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1.982
~~SUMMARY~~
o CAUSE OF TUBE RUPTURE o WORK IN PROGRESS o LOOSE PARTS MONITORING SYSTEM o ADEQUACY OF REPAIRS o INTERMEDIATE OUTAGE ~ 'l umm I 4 e a _________m_ ,]
i J,' GINNA STATION STEAM GENERATOR EVALUATION I ~~ NRC V2ETING APRIL 30, 1982 POSTULATED FAILURE MECHANISM SEQUENCE Mechanical Load Active Tube v Tube Plugged s v D Collapse r-Y p Vibration q ~ r v v Shredding Sever Wear Wear Plugged Tube Active Tube Plugging Burst g h-r*4 v.1 y., a a-Wv w v m. e
9 GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1902 LOOSE PARTS MONITOR SENSOR LOCATIONS .~ / HOT LEG i } 'N. I x/ -l / 9/ / ~ ~~ =, 1 ] \\,/ ( y m ut t. 4 _w" O I k ( h
t.
~~'d I / -.a q -. \\ 4 ai ~J f ( ~ u f-s t= L..._.) Y hj - - - - ---}}~~

ML20090B458

Contents

Text

SUBJECT:

Enclosures:

Enclosures:

1.0 INTRODUCTION

Enclosures:

Enclosures:

1.0 INTRODUCTION

.~===,_.,g======_

w-r --- a,. _. ;.:..

2===;== r= ;===v=k

L._ =3

~~=y_a_.

t

=c

.- --ehsa=_.g==.m1=.

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML20090B458

Text

SUBJECT:

Enclosures:

Enclosures:

1.0 INTRODUCTION

Enclosures:

Enclosures:

1.0 INTRODUCTION

.~===,_.,g======_

w-r --- a,. _. ;.:..

2===;== r= ;===v=k

L._ =3

~~=y_a_.

t

=c

.- --ehsa=_.g==.m1=.

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search