ML19210B831

Summary of 791004 Meeting W/Util in Bethesda,Md Re Hot Leg Temp Indication Anomaly

ML19210B831
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/12/1979
From:	Vissing G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7911120503
Download: ML19210B831 (34)

Text

{{#Wiki_filter:. 'o UNITED STATES ^,% NUCLEAR REGULATORY COMMISSION j wAsmmoros, o. c. :oses f %g ,j October 12, 1979 Docket No. 50-368 LICENSEE: ARXANSAS POWER AND LIGHT COMPANY (AP&L) FACILITY: ARKANSAS NUCLEAR ONE, LIT NO. 2 (ANO-2)

SUMMARY

OF MEETING OF OCTOBER 4,1979 FOR ANO-2 REGARDING THE HOT LEG TEMPERATURE INDICATION ANOMALY purcose of the Meeting This meeting was an information meeting held on October 4,1979, in Bethesda, Maryland, during which AP&L provided information on their activities to date and their plans relating to the analysis, inspection of reacto r vessel internals, and modifications for the hot leg temperature anomaly. A list of attendees is provided in Enclosure 1. An agenda and copies of the illustrations shown during the AP&L presentation are provided in Enclosure 2. Discussion At 50 percent power level, the Resistant Temperature Detectors (RTD's) on the hot legs of the reactor coolant system of ANO-2, which are approximately 15 feet from the vessel and 90* apart on top of each hot leg, have shown a temperature difference of up to 3. This temperature difference switches in a random manner from -3* to +3*. The amount of difference has shown to vary linearly with power level. The maximum power level which the unit has operated is 50'.. At 100% power level it is expected that the tem::erature difference would be 6. With such a temperature difference, the Core Protection Calculator would trip the reactor. On a practical basis, the anomaly wculd prevent the reactor from going above 80% power level. The licensee has analyzed the most probable' mechanisms which could be the cause of the anomaly. They have also made studies on hydraulic models of the system. Their analysis and modeling to date has not shown a firm cause for th anomaly. AP&L plans to shut down ANO-2 for approximately eight weeks to make an inspection of the vessel internals and to add additional RTD's on the hot legs. The inspections will involve removal, insaection, and replacing selected fuel element asse.%11es and other reactor comconents. The nodifications will involve the addition of four RTD's on each hot leg. Each channel feeding into the CPC will have two RTD's 90' apart instead of one. The signals will be added. The CPC will handle the averaging of the two signals for eacn enannel. 503 13 m 1;,4 791u so q ic

9 ANO-2 10/4/79 The licensee's belief was that the modifications could be made under 10 CFR 50.59. However, they have not completed their analysis to support the change. Conclusions ~ We left the question of what would be required for DOR information, review, and/or approval open. / s g } Guy S. Vissing, Project Manager / Operating Reacto~rs Branch #4 Division of Operating Reactors

Enclosures:

1. List of Attendees 2. AP&L Presentation Illustrations cc w/ enclosures: See attached list q e 8 e

MEETING WITH AP&L CONCERNING TEMPERATURE VARIATION IN HOT LEG OF ANO-2 10 A.M. OCTOBER 4, 1979 ATTENDANCE LIST NRC ORNL Ap&L Guy T. Vissing R. C. Kryter Dave Trimble W. D. Johnson Don Rueter H. VanderMolen R. F. Scholl R. W. Reid Margaret Chatterton Garry G. Young COMBUSTION Joseph P. Joyce ENGINEERING Sammy S. Diab Ph.illip F. McKee Fred Sears Bill Morris Fred Sernatinger John Eurdoin__. Peter Kapo Jack GuttmADn O 13i2 136

I. Introduction Rueter II. Cescribe the T.YsmsAncmaly and the ?ctantial Sernatinger Causing Mechan III. Discuss ANO-2 Testing Comcleted Sears IV. Discuss Flcw 'dodel Testing Lawrence Y. Cescribe the "est Probable Mechanism Parrette VI. Review the Safety Considersticns of Serna:1nger Such a Mechanism VII. Planned Inscec:1cn Pecgrim t'ulicolv 7* * *. Of scuss the Corrective 3ction Planned Criffin IX. Dicuss P s: Inscection Program and Seneduies Ccgturn X. Concluding Statement Ruetar j "j] j

REPRCDUCI3LE CBSGYATIONS 0 l. STEADY STATE TDPERATURE "IAS CF APPRCX. 3 F AT 50% PO!iG 2. WEST SIDE HIGH, EAST SIDE LOW 3. tiAGNITUCE PROPORTIONAL To PCWG LEVEL 4 NON-PGIODIC TEPGATURE TRANSIENTS (FLIPS) 5. FREQUENCY OF FLIPS GREATER CN"ALCOP THAN 03 "3" LCCP 5. EXCELLDT CORREUT!0N SET.iED FLIPS ON EAST SIDE AND FLIPS ON ' DEST SIDE 7. NO CORRELATION 3ET. LED FLIPS ON"A"t. COP AND FLIPS CM'"3 "L109 3. TDPERAT.45 FLIPS CCRREUTE '.!IT'i VESSEL.P 3 LIPS ON SAME '40T LIG 9. CCLD LIG TDPERATURE EXHIBIT BLIPS BUT REDUCED BY FACT 90 0F 10 *N d!EE

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ANO-2 HOT LEG ANOMALY ANOMALY DESCRIPTION STEADY STATE DIFFEREITIAL TEMPERAT1JRE BETWEEl THE ' DEST SIDE HOT LEG RTDS AND THOSE OF THE EAST SIDE. TRANSIENT REVERSAL OF THIS DIFFEREITIAL IN A RANDOM, NCN-PREDICTABLE MANNER. 1312 146 e

ANO-2 HOT LEG ANOMALY PRELIMINARY It0/ESTIGATIONS INSTRuiEITATION PERF0EANCE CORE PERFORMAflCE PRESSURlIER LEVEL AND PRESSURE CHARGING AND LETDOWil ~ MODERATOR TEPERATURE SECONDARY SIDE EXCORE NOISE ANALYSIS RC? PERFORMANCE L:M (ACCELEROMETER) 3EHAVICR REACTOR C:CLE SYSTE DI??ERENTIAL ?:.ESSURES 1312 i47

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• EAXAGE FLCW (TYP 4 PLACES)

WEDGE r-PROSE TRAVERSE _3 I 0 ~5 AGE \\h\\Y 4 [ r7 - 9.23S" -4 i e (TYP 4 7, 7,,l,l, La.als GA, //////, 9.37" CESI / n 2,c47~,J ~Q~ 3.682 " l' V ~ SIMULATED ~ 1.520" 6 C3A SHRCUCS - 3 0", 13/4" C1A. 7 j } } 'g j (, j gJ P AARY

7:- vel.CCITY, FT,SEC $3 w a o a w e e 5 C C r?"* 4 6 4 4 P O>\\ l> m 1 / T i >I ( / ( w I N e 5 1 3 >O ocm e M 9 s 1 3 = i 3< O 1 -m ~ P r mO g"* ma O > >c >L c x-e 3e 1 2= o 2 >39 N. ( ,. 5 e a-m4 r= r= 2 m m 1, c: ? r, < < 4= -Z m-OC * ? EN O 1 g

• C L

cc so i SO2 >\\ m. 1 e/ / s, .i x r=.: ) o '9 " lo o v y n3 An m v DLthh

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i l- ~ E l VELCCITY, FT/SEC !,. 3 I, W = e a w e e 5 O 7e N p h b t b a 4 6 Y Q g \\ / M O 't g ~ ~ ~ / T i m 4 I 3e u e 7 I- = = m W M g ~ bE > = [ Q< m 8 O m

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SUMMARY

OF SIGNIFICANT EEFECTS 1. SIMILAR LATERAL ASYMMETRY IN A AND B LOOPS DUE TO LATERAL FLOW STRATIFICATION. ^ ~

2. 'SIMILAR RE/ERSALS OCCUR AT RANDOM INTERVALS IN BOTH LOOPS.

3. RE/ERSAL MEAN FREQUENCY GREATER IN LOOP A. NO TIME CORRELATION BETWEEN OCCURENCES OF RE/ERSALS IN A AND 3. 4. RE/ERSAl.S ARE HIGHLY SYSTEMATIC IN NATURE. 5. LATERAL STRATIFICATION AND RE/ERSALS ARE EI PRODUCED 3Y: A. LEAKAGE FLOW AS SUCH. 3. CHANGES IN CORE POWER DISTRI30 TION. C. SIGNIFICANT CHANGES IN CORE FLOW DISTRIBUTION. 5. THERE IS SOME E/IDENCE THAY RCD MOTIONS (POWER SHIFTS) C.;N AFFECT FRECUENCY OF RE/ERSALS. [$$$}$bkkk 1312 167 e O f

POSTULATED MECHANISM e 1. FLOW ASYMMETRIES OCCURRING Ill THE REGION BETWEEN CORE OUTLET AtlD RTD LOCATIONS IN BOTH LOOPS. 2. FLOW ASYMMETRIES HAVE TWO SIMILAP META-STABLE STATES IN EACH LOOP. 3. IN EACH LOOP ONE OF THESE STATES IS SUBSTANTIALLY MORE STABLE THAN THE OTHER. 4. RANDOM EVENTS " TRIGGER" A DEPARTURE FROM THE MORE STABLE STATE. THESE RANDOM EVENTS ARE NOT C0tTON TO BOTH LOOPS. 5. TIME IN LESS STABLE STATE IS SHORT BUT ALSO RANDOM. G. POSSIBLE FLOW STATES AND RANDOM TRIGGER EVEilTS: A. STREA11 C0ALESCENCE. B. CORE BARREL N0ZZLE - VESSEL N0ZZLE LEAKAGE PATH. 1312 168 e e

(* W e-- M>Z = =C C P- -C W C VD = WW = * >= P-E CC CiJ %V d *M = = 0> cQ WM C= = e-W VV CW QC W >- >= cc = O L) = c C> WL W= = cW LO &W L. 3 CC = Z WD

• ==

= Wv e-- C W t LJ C= W D= >- E J L >= = M WJ =Q C C >=- CC = W

== c=

=. =

L. CW W O e=- L.J Co = = W =E CLJ cn >-- = L C MJ L *) O C::2 JM +W W= =c = O "E" L.J WV a:::" to C:2 =D CW V c= = L.D >== >=

• >=- W J C2 L.J =

C= W >= =C C W M =

• E CC W kJ.J VW

= b-W CM CM => 2: > W CO >= M e e

EVALUAT!CNS C0fl00CTED 1. 5FFECT ON NON-SAFETY SYSTEMS A. REACTOR REGULATI'lG SYSTE'1 (RRS) 3. CCRE OPE?>T!iG LIMIT SUPERVISORY SYSTEM (COLSS) 2. SAFETY SYSTEM PERF0Pf9NCE A. CCRE PROTECT!O.*! CALCULATOR '\\s,i?. i 70 7 W

1 I i i i l a i = mE l l l E i w C >= = eC. ' o M w w= h: l -wE G C 6 e E a C

=

s E e U V U C = = m e e c w O C = C CD C = 0 a w w a c c. sn et m eC. m eC m eC c c k C U C U b b e c. m c. m c. m s. s C

== 0 C C = c C C C C C C W 2 d = .=J C m.l C ed C C C = C C L C-e a sc e e C .= c .= m .= cm .e e.- s y a y a v s v ac ) a .l. p d9 iT d 9 r v y o c N .N 2 dug 1.V., 10H1 d W1 S luH1 GDd 1-

2L1 2IEI e Z W Cn >W W== <W= L.) W= WW Z WC CD to MJ W =J C Lh < E cM c:3 CC C WW c c C Cll = W WW t-3l: C v) C 3 3 = L DCc La H WW W M3 C C CD C Lh L 2

=

M W C = MD W J d W C C C W W AZ La C 3 LO &M W >== C Ln <D V) WW W CO --.! E W E CC G W EW C

=

LC W W W 3l: J C3 C cll2 W L= C J N< N LS O LN OD CC lE: W C >- JJ C) WE clQ CQ C C h 4 - es

Inspection Program Objectives 1. Detar nine that no abnomal condition exists within the reactor that would be the initiating.techanism for the ancmaly. 2. Eliminata as possible causes of the ancmaly potential abner, a' leakage paths and any other mechanism leaving only the hypothesied ficw switching event as the cause of the ancmaly. 3. Verify that the ancmaly has not caused any unusual wear en any internal stPJctures or ComcCnents. D

IN-CORE INSTRUMENTATION SUPPORT PLATE _CEDM N0ZZLE . N' IN CORE INSTRUMENT 9 '~[dYl'?k{bD C - --IN5TRUMENTATi0iv GUIDE TUBE b' N0ZZLE Q4::x.a=:lm?CN. HOLDDG,u,,N uf-i ,e, ;i " / i Mi] / KEY ~ ALIGNMENT RING l ',' m 1~,: 6.,i ' E..V CONTRCL si ELE.' TENT ' % :]i'.}i1 f$ fir;Ffil? ~ 'riA6bd, ~~i I ASSEMBLY UP PER-FULLY 4 p; n' ;;.'i I'h / GUIDE - si WITHDRAWN 5:, pl i:, 3 c STRUCTURE / b, .. a

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---

SHROUD 3

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INSPECTIC:1 DETAILS I, DiliE!! SIC::AL li!SPECTICMS A. HOLCCCN! RII G VERIFY !!riEGRIT/ CF HCLDDC'/01 - - AllD CU,'?!NG FORCE Cl TrE INTERf!ALS 5i." YERTIdAL LCbATIC:-S OF THE VERIFY TIE CC :DITICil CF THE UGS FLANGE M41CH SHCULD FUEL SPRI!!GS BE APPROXIMATELY.9 INCs WITi RESPECT TO THE CSS FLAT!GE C. . VERTICAL LCCATIC t CF THE VERIFY THAT NO 'Ga HAS TAKEi! CS3 FLANGE WIT 4 RESPECT TO FLACE BET.-{EEN THE CSB PJNGE THE R.V. SEATII;G SURFACE

1. 1D THE P.V. LEDGE II. VISUAL I!!SPECTIC::S INDICATCRS OF FRACTURE [DISTCRTIC:b A.

ICIIT..?! R!!!G OR EXCESSIVE ROTATIC*l B[ REACICR VESSEL HEAD INTERFACESIGNAL CF WE/R INDICATII G SURFACES OF TdE ALIG:: MENT KE(S itTICN CF THE R.I. C[ IllTERFACE AREAS OF THE R.V. SIGMS CF WEAR IIGICATI!!G REAC~R HEAD INCLUDII:G THE ALIGi? SIT INTEFNALS ICTIC:t 15Y SLOTS MID THE HCLECC.01 RING EEARING AREA N.' CCRE SERCUD DIRETalOL GAF WITH RESPECT TO THE C33 INDICATICI CF 3Y-PASS LEAYAGE E. TCF OF tie FUEL ASSEGLIES ANY R?:FALCUS CC:CITIC';S

1. 4D PJEL SPRIMOS l 3 } 2

1. o /l 0,

D D D'T j p oo; o o

!!iSFECTIC:! CETAILS (CC'lTINUED) II DICATIC:?S C. WEAR RESULTING F. GUICE LUGS RID GUIDE LUG SLOTS FRC!41'DTIC:: OF 31E USS RELATIVE ~ TO B-lE CSB G. CS3 CUTLET NC" c GAPS BYFASS LEW4iE EFFECTS c H." CEA S'-iRCUCS R!D ATTACHED SIGHS OF DR' AGE INSTRLCEIT TUSES 1. CEA S'5 CUD ECLTS RC LCC' GARS TO D.ETECT FCSSIBILIT/ OF LCOSE SHRCUDS J.' CCRE SHRCUD VERTICR SEM'S IIIDICATIC: S CF 3Y-FASS LEAMGE K; SELECT b)EL ESSE'BLIES GUIDE TUSE IIE/R[ EC!It?d UFFER AND LC!ER E:D FITTING WEAR, GRID CONTACTS R1D X:Ci'ALCUS CCNDITIC::S a.. L _s..upyg;tLA."cg HC'; gnS ;A3 .gif g a y;LOUS CO OITIC:!S 'FLCil SKIRT r 14, REACTOR '!ESSEL 307 0". HEAD ANY A!!C!!ALOUS CC::0ITIO :S ~ A!O REACTOR I: TERT!A,LS LO' DER SUPPORT STRUCURE .'\\ s CORE SUPP03T CARREL F.E'*0'!AL AS INDIC.ATIO::S OF 'dEAP. RESULTI::3 ::.0" CSS DICTATED 3Y A30'!E I::EPECTIC:: MOTIO:l (5::*.":EEF.S, OUT'.ET ;0E '_I ! :TEEF'.CE, AfiD CSG/R'/ FLAi;GE I:iTERFACE) FI iD::i35 00 &,0k/gs E 1312 185

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ANO-2 HOT LEG ANOMALY RESTART TESTING PURPOSES A. VERIFICATION OF PROPER ASSEMBLY B. BASELINE DATA FOR REFERENCE AND COMPARISON C. CONFIRMATION OF EXPECTED AND ASSUMED BEHAVIOR D. VERIFICATION OF EXTRAPOLATED BEHAVIOR E. EVALUAT. ION OF HIGHER POWER OPERATION F. MONITORING OF' PERFORMANCE FOR CHANGES PHASES I. HOT FUNCTIONAL TESTING II. LOW POWER PHYSICS TESTING III. POWER ASCSISION TESTING (s. 800 I'/. RESUMPTIO: OF iiDRMAL POWER ASCEISION 1312 iBB

ANO-2 HOT LEG ANOMALY RESTART TESTING PHASE I - HOT FUNCTIONAL TESTING HEATUP - FLOW VERIFICATION CEA DROP TIMES HZ? BASELINE DATA COLLECTION PHASE II - LOW POWER PHYSICS TESTING CRITICALITY CEA COUPLING VERIFICATION CEA GROUP WORTH - GROUPS 6 & 5 BASELINE EXCORE (UIC) NOISE ANALYSIS b L j I 1312 139

ANO-2 HOT LEG ANOMALY RESTART TESTIN'i PHASE III - POWER ASCENSION TESTING (5. 80%) 30%,ARO 40%,ARO 50%,ARO 50%, 6 & 5 50%,ARO 50%,ARO 707.,ARO 80%. ARO PHASE IV gi1{ ION OF NORMAL POWER ASCENSION fbN $2($1

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