ML20125B996
| ML20125B996 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/29/1977 |
| From: | Snaider R Office of Nuclear Reactor Regulation |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9212100242 | |
| Download: ML20125B996 (33) | |
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I No. 50 63 DEC 2 9 W N FOR:
D. K. Davis, Acting Chief. ORW2. 00R I
FROM:
i R. P. Snaider, Pmject Manager. ORM2. 00R g
SUBJECT:
SUMMRY'tirm.u mu WIIH NORTRDtN STATES POWER COMPANY REGARDING THE FALL 1977 MONTICELLO FEEDWATER N0ZZLE l
AND CONTROL R0D DRIVE RETURN LINE N0ZZLE MODIFICATIONS On Thursday. December 15, 1977, representatives of the Northern States Power Company (NSP) staff, the General Electric Company (GE) staff, and representatives of other ?nterested utilities, met with the NRC staff to I
discuss the recently comp (leted feedwater nozzle (FWN) and control rod drive return line nozzle CRDRLN) inspections and modifications performed at the Monticello Nuclear Generating Plant. A list of attendees and the slides used during the presentation are enclosed.
The Monticello facility was the first of the Boiling Water Reactors (BWRs) to undergo FWN clad removal by the W clad removal tool, Previously, clad had been removed from the FWNs at Oyster Creek and Nine Mile Point.
l utilizinq equipment of a' different. manufacturer. The NRC staff, after review of these prior successful evolutions,. was interested in the results of the Monticello work, particularly(and has already been used at Brown be used at other BWRs in the future FerryUnitNo.1),
l GE presented detailed infonnation concerning the clad removal machine and its installation and use. - A very candid discussion dealt! with the mechan-ical - and personnel - related probhas that occurred during machining of the first nozzle and which resulted in extension of the schedule. The anticipated resolutions to these problems were discussed.
NSP presented a discussion of the "as-found" conditions (original inter-ference fit stil1 ~ maintained aftar two years; no dye-penetrant (PT) crack indications on FWNs) and noted that had external Ultrasonic Testing (UT). been relied upon to initially indicate flaws, NSP would have been i
forced to enfD the vessel for inspection, only to find that no cracks existed. Th cause of the UT indications evidently was the edges of the j
blended sur W as remaining from previous grindouts.
NSP also discussed the "as-left" condition. Although the original
[
intention was to provide tw lands for future installation of the latest GE design therraal sleeve and sparger, nozzle safe end eccentricity and i
9212100242 771229 Am O 2
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3
1r i
I' D. K. Devis,
DEC 2 91977 subsequent concern for maintaining safe end wall thicknesses resulted in the machining of only one land. The newly-installed thermal sleeves, of an interim design. Incorporate a single piston ring seal in the safe and and were installed with a 13 mil (.013" diametre1 interference fit. MSP noted that the SE strees analysis assume)d that the piston ring seal was 1
non-existent and that leakage occurred. Thus this analysis was overly-conservative and will be revised. MSP also stated that they do not intend to inspect Monticello FWNs from the vessel interior for at least t
four years.
The CRDRLH was discussed in detail. Although this nozzle had what was thought to be an effective thermal sleeve (concentric sleeve and flow shroud welded at three points to the vessel well) inspection revealed that cracking had occurred.
NSP subsequently removed all crack indi-cations (cracking was also found in the nozzle safe-end), cut the control rod drive return line and re-routed the line to the discharge of the Reactor Water Cleanup System (RWCU) and capped the CRDRLN. The return line to the RWCU system is valved out. -The NRC staff stated that this subject is still considered an open review issue.
MSP presented information related to scheduling of the nozzle work. They also discussed the means by which a substantial reduction in radiation exposure over that during the 1975 inspection and repair had been accom-p11shed.
Of the 380 man-7m recorded by NSP, approximately 60 man-rem were attributed to the CRDRLN work, for which little shielding could be installed.
A substantial amount was also attributed to the UT inspection of core spray piping.
The dose results show that the Monticello decon-tamination and shielding efforts paid off well in dose reduction. The NRC staff believes this to be an excellent example of a program designed to reduce personnel exposure to levels as low as reasonably achievable.
s R.
. Snaider, Pro.iect Manager Operating Reactor Branch #2 Division of Operating Reactors i
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NRC FORM 318 (9-76) NRCM 0240 W u. s, movsann nr paintino orrecte s ete - eas.ea4 4
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4 MEETING
SUMMARY
DISTRIBUTION Docket NRC PDR Local PDR ORB #2 Reading NRR Reading B. C. Rusche E. G. Case V. Stello K. R. Goller D. Eisenhut T. J. Carter A. Schwencer G. Lear R. Reid W. Butler B. Grimes R. Baer L. Shao Project Manager - R. Snaider Attorney, OELD -
OI&E (3)
R. Diggs NRC Participants (Major)
R. Fraley, ACRS (16)
T. B. Abernathy, DTIE J. B. Buchanan Licensee - Northern States Power Co.
D. Gridley
- k. E. Schaffstall Hugh McLean C. A. Dalke R. B. Hamilton Bob Baker Bill Tucker J. R. Boyda William Texter Thomas M. Cizanskas Paul Baughman G. Neils Byron Day R. C. Johnson R. W. Klecker G. C. Cwalina C. D. Sellers T. O. Murphy W. J. Collins P. N. Randall W. S. Hazelton 1
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NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C 20006 t
December 29, 1977 Docket No. 50-263 MEMORANDUM FOR:
D. K. Davis, Acting Chief, ORB #2, 00R FROM:
R. P. Snaider, Project Manager, ORB #2, D0R
SUBJECT:
SUMMARY
OF MEETING WITH NORTHERN STATES POWER COMPANY REGARDING THE FALL 1977 MONTICELLO FEEDWATER N0ZZLE AND CONTROL R0D DRIVE RETURN LINE N0ZZLE MODIFICATIONS On Thursday, December 15, 1977, representatives of the Northern States i
Power Company (NSP) staff, the General Electric Company (GE) staff, and representatives of other interested utilities, met with the NRC staff to discuss the recently completed feedwater nozzle (FWN) and control rod.
drive return line nozzle (CRDRLN) inspections and modifications performed at the Monticello Nuclear Generating Plant.
A list of a'ttendees and the slides used during the presentation are enclosed.
The Monticello facility was the first of the Boiling Water Reactors (BWRs)'
to undergo FWN clad removal by the GE clad removal tool. Previously, clad had been removed from the FWNs at Oyster Creek and Nine Mile Point, utilizing equipment of a different manufacturer. The NRC staff, after review of these prior successful evolutions, was interested in the results since the GE equipment will probably of the Monticello work, particularly(and has already been used at Brown's be used at other BWRs in the future Ferry Unit No. 1).
GE presented detailed information concerning the clad removal machine and its installation and use.
A very candid discussion dealt 'with the mechan-ical - and personnel - related problems that occurred during machining of the first nozzle and which resulted in extension of the schedule. The anticipated resolutions to these problems were discussed.
NSP presented a discussion of-the "as-found" conditions (original inter-ference fit still maintained after two years; no dye-penetrant (PT) i crack indications on FWNs) and noted that had external Ultrasonic Testing (UT) been relied upon to initially indicate flaws, NSP would have been forced to enter the vessel for inspection,'only to find that no cracks existed. The cause of the UT indications. evidently was the edges of the blended surfaces remaining from previous grindouts.
NSP.also discussed the "as-left" condition.
Although the original intention was to provide two lands for future-installation of the latest GE design thermal sleeve and sparger, nozzle safe end.ec::entricity and
i
=
i
~
D. K. Davis
-E-December 29, 1977 subsequent concern for maintaining safe end wall thicknesses resulted in the machining of only one land.
The newly-installed thermal sleeves, of an interim design, incorporate a single piston ring seal in the safe end and were installed with a 13 m11 -(.013") diametral interference fit. NSP 4
noted that the GE stress analysis assumed that the piston ring seal was non-existent and that leakage occurred. Thus this analysis was overly-conservative and will be revised. NSP also stated that they do not 4
intend to inspect Monticello FWNs from the vessel interior for at least four years.
+
The CRDRLN was discussed in detail. Although this nozzle had what was thought to be an effective thermal sleeve (concentric sleeve and flow shroud welded at three points to the vessel wall), inspection revealed i -
that cracking had occurred. NSP subsequently removed all crack _indi-i cations (cracking was-also -found in the nozzle safe-end), cut the control-1 rod drive. return line and re-routed the line to the discharge of_ the i
Reactor Water Cleanup System (RWCU) and capped-the CRDRLN. The return line to the _RWCU system is valved out. The NRC staff _ stated that this subject is still considered an open review issue.
NSP presented information related to scheduling of the nozzle work.. They also discussed the means by which a substantial reduction in radiation l
exposure over that during the 1975 inspection and repair had been accom-p11shed. Of the 380 man-rem recorded by NSP, approximately-60 man-rem l
were attributed to the CRDRLN work, for which little shielding could be j
installed. A substantial amount was also attributed to the UT inspection of core spray piping.
The dose results show that the Monticello decon-tamination and shielding efforts paid off well in dose reduction. The
[
NRC staff believes this to be an excellent example of a program designed j
to reduce personnel exposure to levels as-low as reasonably achievable.
l
'Y L
R. P. Snaider, Project Manager l
Operating Reactor Branch #2 Division of Operating Reactors I
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ATTENDANCE LIST 12/15/77 NAME ORGANIZATION Dick Gridley GE - Safety & Licensing R. E. Schaffstall GE - Safety & Licensing 4
Hugh McLean GE C. A. Dalke GE R.11. Hamilton GE 2
Bob Baker Fitzpatrick Nuclear Station Bill Tucker Carolina Power & Light J. R.Boyda Philadelphia Electric Co.
William Texter Philadelphia Electric Co.
1 Thomas M. Cizanskas Yankee Atomic Paul Baughman Yankee Atomic 1
G. Neils NSP l
Byron Day NSP Dick Snaider NRC/ DOR / ORB-2 R. E. Johnson NRC/ DOR /EB R. W. Klecker NRC/ DOR /EB G. C. Cwalina NRC/ DOR / EEB C. D. Sellers NRC/MTEB/ DSS T. O. Murphy NRC/DSE/RAB W. J. Collins NRC/IE P. N. Randall NRC/SD/ DOR W. S. Hazelton NRC/ DOR /EB
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RED SPEED ROUGi ALIGielT 6,50 11,50 FitE ALIGPOIT 6,75 9.75 BORE OJT 5,75 10,50 5 RPM
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4 PROBLEMS CORRECTIONS MACHINE INTERFERENCE W/ SHIELDING STUDY IN ADVANCE AND ELIMINATE TOOLING DESIGN AND MANUFACTURE DRAWING APPROVAL AND QC INSPECTION ROUGH AllGNMENT T00 ROUGH MAKE A QC HOLD POINT FINE AllGNMENT SEPARATE BAR, COMMUTATOR AND SLIP RINGS TRAINING MANUAL, QUAllFICATION F.0 STER, TV WORKER PRODUCTIVITY EXPLAIN EXPECTI. 1UNS, DISCIPLINE COMMUNICATIONS REQUIRE A GOOD SYSTEM AX1AL DIMENSION INDICATION IMPROVED TRAV-A-DIAL, BETTER BACKUP QC PLAN DESIGN FOR AN OPERATING PLANT CHIPS IN MOVING PARTS KEEP PARTS COVERED REPEATABLE ERRORS USE CHECKLISTS TO REDUCE FAST TRAVEL T00 SLOW TEST AND USE NEW GEARB0X ACCESS TO WORK CUTOUTS IN MACHINE STRUCTU2E SURFACES DIFFICULT TO PT USE HONE AS FINAL MACHINING STEP i
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d f1SP EQUESTED TO ADDRESS llE FOLLN1f6 ITEFS
- 1. TIE RDE OF TIE UTILITY ltiCLUDif0 m REQUIREEl#S, CHIP MBERif6 NO DISPOSAL, SYS191 SElllP REQUIRBERS (AIR, WATER, U(DRAULICS, ETC,)
- 2. RADIAT101 PROTECT 10tl CGER0L EASUES NID OCCUPAT10tRL EXPOSURES, 3
EVAllRT1010F TliE t071LE SPARGER N1D TIEPML SLEEVE TO EXTEta Tif 24 I M li GE STRESS # MLYSIS,
- 4. DESCRIPT10fl 0F lllE CRD ETURfl Life fl0ZZLE mDlFICATION, TliE IfEPECTION PROGRNt ItEPECTION ESULTS NO SYSlD1 TESTit6, l
RESPONSE TO U Hi.1 A, 0,A,
- 1. ASSURE COPLINICE WITH FEDERAL EGULAT10tG (10CF"') APPENDIX B) BY:
A.
PROCESSil1G TlE mnlFICATIONS ACCORDil0 TO DESIRI CRYlff DIRECTIVES, i
B.
IflSPECTIfE ALL PilASES OF THE ESIRi OwirE Il6TALLAT10f1 TO ASSURE C0FPLIN4CE WITH PROCEDURE REQllREWIUS,
- 2. ASSURE C0fPLINICE WITH STATEEGULATIONS (ASW CODE) BY llMElf6 l
THE REQUIRBERS OF fM 4000, SECTION 111, ASW B&PV CODE, CE, l&SE WAS C0tHRACTEDFOR TlilS SERVICE, l
B, OllP MTHERif1G AND DISPOSAL
- 1. PROCESSED AS SOLID RANASTE, 2
STORED IN BARRELS WAITIllG FOR DELIVERY TO BURIAL SIE, C, SYSTD1 SETUP REQUIREWNTS 1, WORK PIMPPM AND SHIELDING A,
f1SP PREPARED DESIRI SPECIFICAT10f1 8.
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LOCAL Sil0P CONTRACTED FOR DESIGN NO FABRICATION
2 3, tWiIDER A,
I6PPROViiE 1, OPERAT10 m L SUPPORT (A SB110R LICB1 SED OPERATOR WAS O'1 TE REREllf0 FLOOR AT ALL TlWS) 2, TE0filCAL SUPPORT
- 3. CRAFT SUPPORT (l%0llNit6, WELDif6) 4, IADOR - PIPEFITTERS, BOILERI%KERS, CEtERAL LAPAR B,
ff WAS C0fffPACTED TO SUPPLY 1
DIECT SUPERVIS10f1
- 2. CRM OPERATORS
- 3. NDE & OC PERSONtEL
- 4. CLAD RBUVAL PA0 life (CRM) CRM REQUIRD) 480V POER SilPPLY, SOURCE OF DBilti WATER N1D Cft1 PRESSED AIR II, RESPONSE T0 ITEM 4 A.
RETIR1 LIE FDDIFICATION (SEE FIGURE 1)
- 3. J01ED TO RWCU RETUP11 Life OlITSIDE OF PRif%RY C0!ffAltfBff 4
CRD RETURN LINE PBDVED AND PRIPARY CONTAlfPETT PBURATION CAPPFD
- 5. RETURN TO RWCU ISOLATED DURifF f10PFAL OPERATinti B,
SYSTBi TESTitlG
- 1. CONSISTED OF TE FOLL0dif0 CHECKS:
A, liiSERT Af1D WITHDPAWAL SPEED B.
DRIVE PISTON DIFFER 9fflAL PRESSUPE DURING IDTal SETTLE FDTION
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IfSERT AND WITilDRAWAL SETTLE TIME E,
SCRNi ACClIULATOR OlARGiflG E ADER PRFSSURE
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A, f0ff%L If6ERT NO WITHDRAWAL 0PERATION f0T AFFECTED
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- c. CRD PlW KRF0fV% FEE f0T httuw
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f0ZZLE BLEND RADIUS #10 BORE INSPECTED BY-LIQUID PEfETRANT -
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170P-2000 AT EfRRANCE TO N0ZZE BORE N10 FOUR l!01 CAT 10fS ON IOZZE FACE 3
f%X1tui GRif00lfT OCCURRED. AT If01 CAT 10N ON [0ZZE FACE, PBETRATED 0,110" lift 0-BASE WTAL, Tm GRINT0 lfts PBETRATED BASE ETAL,' SEE FIGURE TWD, l
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Nozzle Bore VESSEL SIDE e
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U ri DErl tilt IONS :
0 1 7/8 1"
1" 0 = Aziliiuth Position X = Distance f rom Reference Circ c
o to Grisulaut Edge 100 2"
1h" 1h" 110" L = lerigth of firintiout W = Circumf erential !lidth of Grind-110 2h" 2h" 1h" D = filIsth of Penetration into fase 11etal 180 8"
34" h"
245 1
1 3/4' 1"
.080"
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LA
.10/2_7/_77 Initial Date
j i.
NSP OBJECTIVES 4
LONG TERM (DESIGN LIFE) i MAINTAIN N0ZZLE INTEGRITY 4
INTERMEDIATE TERM (5 YEARS)
MAINTAIN DEMONSTRABLE !l0ZZLE INTEGRITY MINIM 1ZE AGGREGATE DOWNTIME MittlMlZE OVERALL EXPOSURES LIMIT RECURRENCE OF IN-VESSEL WORK SHORT TERM (77 REFUELlllG OUTAGE)
FIRM PLAN OF ACTION i
PLAN CONSISTENT WITH LONG & lilTERMEDIATE TERM OBJECTIVES REDUCE EXPOSURES VS.1975 EXPERIE!!CE CONSIDER CRD RETURil-p
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4 DECISION INFLUENCE FACTORS SERVICE INCREMENT ? YEARS - 13 CYCLES LIMITED DATA OH "REV 4 MACHitlED FIT" EXTERNAL UT WITH EXI5TitlG SURFACE PARTIAL INTERNAL PT lilSPECT10tl SPARGER REMOVAL - FULL SURFACE INSPECTION DISADVANTAGE OF INSPECTION OilLY ADVANTAGE OF CLAD REMOVAL INTERIM VS, FINAL SLEEVE DESIG!l MACHINE CAPABILITY - AVAILABILITY SUMMER 1977 DECISION
r DECISION - 1977 OUTAGE PLAN i
REMOVE CLADDlHG 1
l DIMEllS10tl FOR FlflAL SPARGER I
USE INTERIM SPARGER ADDIT 10llAL PLAll DECIS10NS FULL SURFACE INSPECTl0tl AS - FOU!1D AS - FOUND UT CONTlHGENCY AS - BUILT SAFE /END INSPECTI0tl FULL SURFACE lilSPECTION AS - t1ACHINED ESTABLISH UT BASELINE AS - MACHitlED PRE-A!!D POST JOB STRESS ANALYSIS IMPROVED DECON AND SillELDitlG COMPLETE CRD N0ZZLE WORK
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O FW !10ZZLE CLAD REl10 VAL & SPARGER JOB PRE - SHUTDOWil SCHEDULE VS. ACTUAL ACTIVITY SCHEDULE ACTUAL DIEE SET UP 6,7 5,8
-0,9 REMOVE CLAD 14,0 23.2
+14.2 IllSTALL SPARGERS 4.5 2,3 1.7 TAKE DOWN TO RX ASSEMBLY 3.5 0.5
-3.0 TOTAL 23.7 37.3
+S.6 TOTAL OUTAGE 51,9 60,6
+3,7 1.
DRY TRAllSFER VS REFLOOD SAVED 3.0.
2.
OUTAGE DURATION FROM 50% PWR DWH TO 507 PWR UP.
1977 OUTAGE PLAN RESULTS AS - FOUND SURFACE INSPECTION AS - MACHINED SURFACE INSPECTION AS - MACHINED UT BASELINE ESTABLISHED SINGLE SAFE END LAND AS - BUILT SLEEVE INTERFEREllCE COMPLETED CRD N0ZZLE WORK IN - VESSEL PlPING INSPECTION DEMONSTRATED DECON & SHIELDING i
e e
I V
l PREF 1ACHINiliG C0l1DIT10fl 110 DETAILED FATIGUE STRESS At1ALYSIS WO FIELD DATA FROM SEllSITIVE PT AllD i1ACHlHED TO FIT REV 4 SLEEVE 1RREGUALR SURFACE GE0 METRY B1 - iiETAL SURFACE U!1 CERTAINTY OF UT lilSPECT10tl i
i JOB CONTROL COMPARIS0ll 19Z5 19ZZ 4
OVERALL DURATION 27 37 i
llWOLVED PERSONilEL 523 400 4
l TOTAL EXPOSURE 473 330
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GEliERAL RATE 0.7 - 1.0
.25
.4 i
fl0ZZLE RATE 2.0 - 2.5
.8 - 1.3 l
HOTE:
1975 WAS FW (107_ZLE WORK ONLY VESSEL WALL DEC0!1 ll1PR. DECON BLANKETS 1"
PLATE CORE SPRAY PRE-FLUSH PRE-FLUSH SURFACE DEC0i1 BLAllKETS 2" CURB PLATE l
SPARGERS BLAi4KETS 1"
PLATE f
SURFACE DECON T
i
t e
1 PROGHOSIS - FUTURE PLAlls i
l SHORT RAl1GE - llEXT REFUELING CONSIDER EXTERllAL MONITORll1G j
ACTUAL SERVICE VS, DESIG'1 ASSUMPT10tlS i
REVISED STRESS ANALYSIS i
INTERMEDIATE RANGE - 5 YEARS FillAL SPARGER EXPERIEllCE i
SAFE END VS, SLEEVE CHAllGES i
EXTERNAL INSPECT 10!ls INTERiiAL lilSPECT10ils CODE VS, 0WNER RESPONSIBILITY
JOB CONTROL COMPARISOU 1911 192Z OVERALL DURATION 27 37 INVOLVED PERSONilEL 528 400 TOTAL EXPOSURE 473 330 GEiiERAL RATE 0.7 - 1.0
.25
.4 N0ZZLE RATE 2.0 - 2.5
.0 - 1.3 4
Il0TE:
1975 WAS FW N0ZZLE WORK ONLY VESSEL WALL DECON ll1PR. DECON BLANKETS 1"
PLATE CORE SPRAY PRE-FLUSH PRE-FLUSil SURFACE DEC0il l
BLANKETS 2" CURB PLATE l
SPARGERS BLAllKETS 1"
PLATE SURFACE DECON l
PERS0fillEL liEASURES 1975 PROTECTIVE CLOTHl!1G DOUBLE COVERALLS, FULL RAlli SulT
- i FULL - FACE AND SUPPLIED AIR FOR ALL lli - VESSEL WORK.
1977 PROTECTIVE CLOTilll1G DOUBLE COVERALLS, FULL - FACE 8 FILTER 1
BUBBLE SulT & SUPPLIED AIR FOR CLEAllif1G AND GRINDil1G.
NO RESPIRATORY PROTECTION FOR GENERAL lli - VESSEL WORK FOR 3RD 8 11TH (10ZZLES i
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