ML20031D833

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Summary of 780524 Meeting W/B&W Re Orifice Rod Assembly Operating Experience.Operational Problems Are Similar to Those Previously Observed W/Poison Rod Assemblies.Agenda & Related Matl Encl
ML20031D833
Person / Time
Issue date: 06/13/1978
From: Houston M
Office of Nuclear Reactor Regulation
To: Ross D
Office of Nuclear Reactor Regulation
Shared Package
ML20031D800 List:
References
FOIA-81-236 NUDOCS 8110140274
Download: ML20031D833 (31)
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Text

{{#Wiki_filter:' (t \\ JUN 1 2 GB ( I MENORNiDUM FOR: D.F. Ross,'J.F, A_s.si.stant_Di. recto.r for _R.eac.t.or Safety, DSS K.Kniel,' Chief,CorePerformanceBranch,gS_ _ [, _, THRU: FROM: M.D. Houston','.R.eactgr Fuels Sect.io.n, CPB, DSS

SUBJECT:

SUM"ARY OF MEETING WITH BABC0CK AND WILCOX ON ORIFICE ROD ASSEMBl.Y OPERATING' EXPERIENCE "'~ ~-~ - ' - ~ ~ ~ ' l The NRC staff met with representatives of Babcock and Wilcox (B&W) and representatives from those utilitief siith B&W plants"on' Wednesday, May 24, 1978, at NRC headquartirs. W difcuGe'd tNe '6pe' rating expei ~' -~~ ~ ~ ~ ience of the orifice rod asse=b1Ter'(ORAs)~ aiid thn're'cehtly"6bs'erved * ~ --"' ~ ~ wear in% ations in the latchin'g insc1(ain5.smi, Th'e* 00elffected plant -" '- ---""- (Davis-Besse 1) proposed to with5ia'waT1 DRArfoF futur'e 'op'eration. Because other B&W plants will 'c~ohtinue'id oper' atewith 0 ras" inserted,-' ~~~ ~ ' - ~ ~ B&W presented ' justification for~thircontinuhd' operation ~. Fut'ure'-~ near-term inspection plans to 'fu'rnisif"c6ntirir.ato'ry data' Tof continued ' ~ ~ ~ ~ - ~ operation with ORAs were discu'ssed7-':A cdpy o~f 'the B&W vu' graphs"hnd ' O. - -" * ~ . a n a t ten da nc e l i s t i s a tt a ched.-'_.. '...~. ~_ ~ ~.'.. '.. ' ' ' ~. ~_'.'.~ ~ ~ ' ~ - ' ~ ~~ (. In early April 1978, abcock and Wilcox and Florida Power Corpo' ration infomed HRC of a problem at Crystalliver' that' Cas cau' sed b'y'the '-' ---' ejection of two burnable poisch rod' ass'emblies (BPPAs)* fro:n the core' ' ' ~~ ~ while operating at full flow. Alth6 ugh the' ~ ejected hardwh~re was' -~ detected by the loose parts monitorihg~ system,'which a1 Towed prompt- ~' " " -' reacto.r shutdown, significant damale' 6ccuri'ed to' the tdb6' ends"in--~~~ ~ the 5t.eara generator, B&W analyfed the probl hi'and det'er :iined it to---- ~ ^ ~ be caused by levitation of the7PRKs'Rith'YoDF' pump operation"and -'---'~ subsequent fretting wear in the' hMddcim Tatching' mech 6nism. 'As'a ~ solution to the BPRA problem, B&W~recosended contin 0ed ' operation of the plants at reduced flow with' three pu.tps. B7.W i's'also developing ~~ ~ ' additional hardware to increas'e the' holdd6wn' force applied' to these' - -' " '" ~-'~ " -~~~ ~ ~ ~ " - ~ ~ ~ ' ~- assemblies. l I Extensive inspections were perfort::ed in B&W plants to assess the wear conditions for the BPRAs. Because'ORAs'are' held in place ~by the same - - latching design but differ in.iiass (15 7b'.s. vs~ 45 '1bs. for BPRAs), the'.-".'.' J l s %110140274 810906 iPDR FOIA SROWNB1-236 PDR ? 4

t. ~ 'D.,F. Ross, Jr. 2. ggy 3 3, y73 .e_.._..._.m. ~- ~. the wear characteristics for these assemblies were also examined. In four reactors, no wear indications Vere' noted'for' up to' three' cycles T " ~ I of operation. However, in Davis'-Besse'1, which ~ had ope' rated only-~ 120 days, significant wear was 'ob'sei'ved with ORAs b~ut 'none"of'the' ~ ~ ~ 7 ' ' ~ assemblies were ejected from their~1ocke6d6Jn' position ~/ ~(These '~ :~ ~ '"': ~ observations were made on Friday ~ May'197 M8,- a'nd ~ discussed by ~"----~ -- ' - " * ~ ' ' " --' ~ ~~" phone with NRC on, Monday, May 22'.) g For Davis-Besse 1 (originally shut down to remove BPRAs), the utility ' ~ ~'~ ~ has decided to remove all ORAs' from~ continued' operatio'n.~The ' increase ' a w in the amount of bypass flow in' th'e guide'tbb~es 'due to' th'isrch~ nge ' as -" - - ~ -- calculated to be 4.7 percent. ~The thednal-hydrhulic~ analysis. for the' D-B1 core with the increased bypass was submitted to NRC during the ~ ~~T' ~ week of May 29. B&W reviewed the operating perfomance of ORAs 'n all of their plants. ~ They presented their analysis of the ~o'c'carrence'fri' D-B1' and the reason' - ~ it is of little concern in other ' ope' rating reacto'rs.' Two' factors were "' - identified with regard to D-B1"that 'contribbted 'to' the wear condition: " 1. The holddown latching tubes in B-B1 were manufactured by a j casting process rather than' grinding or' cutting from bar stock. The properties of the cast stainless ' steel 'were ~ ~ within the materials specificatioh rang'e but were at the' - ~ ~ lower end of the r=nge for yield strength-'and hardness.' ~ ~ (The cast end fittings have been bsed on all B&W reloads ~ ~ 4 so that operating experience has' be'en"obtain'ed in most' ~~ ~ other B&W plants. Wear indications for' 0 ras"were only - ~ noted at D-B1 although latching' devices ~with identical" ~ ~ ~ i- ^ '~ " ~ material properties as 'the cast ~ bnits', als6 conta'ining' "-" ORAs, were inspected at other plants {[ j~,'{~;],', ', 2. D-B1 had operated for an extended time'(35 days) at a ~ ~ '~ reduced-flow condition with two pbnip 'operationi At this r flow, the ORAs, because of their Toter mass', Experienced ~~~ a levitation condition similar' to' the.BPRAs' at four-pump ' " ~~ ~ ' - ~ ~ ~ ' - ' ~ operation, j ",- - i Thus, B&W concluded that the combination of the cast holddown device (softer material) and. the reduced flow at tso-pump operation led to ~ ~ ' i the significant wear bbserved with ORAs at D-Bl. t l i e. P G d'

s. D.F. Ross, Jr. .3.. JLIN 13 573 ?;'.

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. *.r.7.k.. /'.',.,.v. Y. : a, ~' ~ BIW discussed,two-pump opera, tion at other plants. This code of reduced-flow operation oscurs mainly during heatsp~a'nd shutdown conditions! The' ' tt:ne period for this condition ~at'other' plant's ranged from 1 to' 16 days. ~ ~" The fact that other plants hai e'rienced ' fewer days of two-pump ~ opera' ~ ~ ' " ' tion was the basis for B&W t ude that'the ORA problem was' restricted ' to only the Davis-Besse 1 pl:

{,"-'] ',-~],7,~;, [,7, '," " ' ' ~ ~ ~

^ ~ ' ' Near-tem inspection plaas for wear were discussed. The first inspec-tion pill be perfomed at Ocon'e'e-3 in mid 'JuneT 'Ocone'e'-3 has had three- ~ days of two-pump operation and' ha's 28 ORAs 'in cast-latching devices..~ " ~~ Another inspection will be perfo~med at' TiireF Mile' Island-2 in July while - servicing the BPRAs. TMI-2 ha's had 16' days' of twot 40 ORAs in cast-latching devis'.es'.-~~ ~ - '."_ ~..~.'.,". pump operation'an '~ In sumary, B&W discussed'an operational problem observed with orifice rod assemblies (ORAs) in Davis-Bes's'e'1'. 'The" problem" arid the cause have been ~~ analyzed by B&W to be similar 'in'"natu're' to the previously observed problem' -'~ ~ ' ~ with buranble poison rod assembTies-(BPRAs)'.' B&W th'erefore reconnends that reduced flow with two-pump 'oper'ation be~ minimized." B&W feels' that continued operation with ORAs in' other' pla~nts is fustified on the basis ' that these plants have had limited" ope' rationin a two-pump mode. Near " ~ ~ tem inspecticn plans were disuossed 'to' furnish' confirmatory data to ~ ~ ~ support continued operation. ~ '~ ^^' M. Dean Houston ~~ ' Reactor Fuels section i Core Perfomance Branch ~"- ' l Division of Systems Safety ~ ~ '... ~ \\ l

Enclosure:

As stated ~~~~' k CEtiTRAL FILES tiRR RDG FILE' ' CPB RDG FILE De O ? / ' l +

I t. 'JUN 131918 .D. r.. Ross, Jr.. .~ MErTINGSUfNARY i .J. '.1.. -. '....... -. -.. ...". t DISTRIBU. TION: c.......... .s. D. Fieno S. Hanauer' R. Mattson/F. Schroeder -~~ -~ Y. Bicoks . ' " ' / ~ ~ '. ~ ~ -7~"' ~ R. Fraley, ACRS (16)

  • ~ ~~ 7 D~.- Hiu s t6n~~ ~ ~"

. - ' ' ' '. - " ~ J. Knight-'. - i' S~.' Kini- ~ ~ ~ -' ' ' ~ ' ~~~ '~ R. Tedesco ~~~~~ II.~ Powers R. Denise '-' '~~ M'.' Tokar w. T ' '. ' ~ ~ - D. Vassallo - ' '-~ R. Lobel 't" ~ -~ ' T.. ~ T F. Coffman D. Skovholt ' ' ' '. - ~ "~~' B. Eisenhut J.-. ~-~~T.' Rosztoczy. ' ' ' ' ' ' ~ ~ ~ - ' " B. Grimes 1 " " ~ l'.'Phillips ,3~'~~' - ' " ' ~ ~ M. Ernst. ' . T '"W.' Hodges .' ' ' ' " ~ ' '~-'J. 01shinski, DSS. W. Gamill ~~ ~ ~ ~ ~ " - " ~~ ~ R. Vollmer '? - 1".~Engle ~ ' - ' ' 'r ' J-4 Y. Moore.' m-H. Silver R. Bernero ' ' '-'S.' Weiss ' ~" - ~ a - - ~ ' '. ~~~- C. Roberts ' ~-~~ R7 Reid ' ' ' ' ' '~- J. J. Davis ~~" ~~HTI.evin E. English

  • ~T J. Fair

- ' ' ~ ~ " ~ C. Kelber ~ - ~ R~.' Ri gg s -- ' ' ~ ~ ' L.S. Tong '"" ^~ D. Kirkpatrick faE (3) '~ ~ M.* Fai rtil e ~' L. Tripp ^'~~ ~ R. Muller. ACRS J. McGough J. Henning, IE (Reg. III) ~ P. Boehnert ACRS ~~~ ' ~ F." Jape IE (Reg. II) ~~ W. Johnston 7 " - - " ' ~ ' ' ' ' ' ~ ~ ' ' P. CM NRC PDR . ' ~ ~... -. ' ' ~~~ t /CPB DSS DSS /CPB DSS / CPS KKn6el DHouston:jt RMeyer 6/12/78 6/ /78 6/ /78 ? r

i, NRC/ Babcock and Wilcox/ Utilities Meeting on Orifice Rod Assemblies May 24, 1978 i ~ Meeting Attendees NRC Me tropolit an Edison-Co. P. C h e c't, DSS D. Curry L. Phillips, DSS D. McGettrick W. H o d g<m s, DSS J. Hilbish M. Houston, DSS J. Stair J. Olshinski, DSS K. Kniel, DPM L. Engle DPM Toledo Edison Co. 3 H. Sil -4 r, DPM S. Weiss, DOR T. Murray F. Coffman, DOR F. Miller R. Reid, DOR H. Levin, D04 J. Fair, DOR Arkansas Power and Light ' ~ ~ R. Riggs, DOR D. Kirkpatrick, IE D. Mardis J. Menning, I ?, (R e g. III) T. Cogburn F. Jape, IE (Reg. II) D. Sikes R. Muller, ACRS M. Fairtile, DOR Duke Power Babcock and Wilcox K. Canady J. Taylor H. Sneap J. Tulenk-> B. Hao G. Meyer Florida Power Corporation R. DeMars M. Montgomery Q. DuBois T. Scott G. Beatty, Jr. R. Berchin L. Tittle M. Croft R. Borsum E. Kane Sacramento Municipal Utility District D. Raasch GPU Service Corporation R. Rodriguez G. Bond 4: e r O

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. [ D UPPER E \\D FITTING ASSE V BLY T / \\ l 1 !-$op M M F-i z $;dmo W oxo& Z ! 't iLJ _ _f t / $IOMoY(okblT ~ - !-IOkoNopOM-! ~ [, s' p ', s A __ _.;: l l ( \\ _%g j g.__ / 7 N b _1, e a k .i 3 sR R 1 FR F3 l PEAXdV///A'&%f/A \\W % i SECTION Z-Z f 8 e

MATERIAL PROPERTY COMPARIS0N HOLDDOWN LATCH ASSEMBLIE3 YlELD STRENGTH HARDHESS CORE MATERIAL PSI BHN RB_ CR-III BAR 36,000 149 63,000 217 ANO-l BAa 37,000 156 63,000 217 0CONEE-Il BAR 33,500 ~145 77.1 69,000 197 Davis BESSE-l CAST 40,700 ~153 80 48,000 ~170 85 . S.1]D BAR 63,000 207 75,000 217 GENERIC RELOADS CAST ~38,000 ~78 s47,000 ~78-80 L.. lUBJ5CT 3[0 CATALOG NO. 15 1000-3M CENTER. ST. PAUL. f *lN*= A

POSSIBLE WEAR CONTRIBUTORS 1. REDUCED FL0w; I.E. 2 AND 3 PUMP OPERATION 2. MARK-BI4 END FITTING A. CAST HOLDDOWN LATCH B. REDUCED PRESSURE DROP 3. OmER A. PUMP PRESSURE PutSATIONS B. MINOR MANUFACTURING VARIABLES n. ..-4 U BJECT 3@ CATALOG NO. 15 1006 n

TL f ) [j MAY 23, 1978 rn O REACTOR CYCLE NUMBER OF OPERATING DAYS 1, PUMP 2 PUMPS 3 PUMPS 4 PUMPS 4 DAVIS-BESSE-1 1 1 35 41 194

.TMI-1 1

I 2 6 4.5 2 277 3 1.5 1.5 2 305 4 >l >l 27 n TMI-II 1 16 28 2 l ANO-I 1 i 2 >l 3 1 l 3 >l 1.5 2 1 i OCONEz-I 19 5.5 9 i I' OCONEE-II 27 12 13 OCONEE-III 5 3 18 l DI CR-III 1 y,g 24 la RANCHO SECo 1 6 8 6 608 ' un 55 I yp 2 >l - >l 14

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  • OPERATING SINCE MK-B4 Eno FImnG S-

B PR A UNLATCHtNG CONDTioN N F3 9 i Fx s 6 a pP -/ P FOR BALLS TO RETRACT Fx >> A P FOR A =. 4 AP =.4 P r 30' 45* Go* 75* Fx L12 P l.O P .5BP .27P = O e w JB.JF r.T

i OPERATING PLANT COMPARISON NSS 3 4 5 6 7 8 9 11 14 l . PLANT - DUKE I DUKE 2 TMI-1 TMI-2 CR-3 ANO-1 DUKE-3 SMUD' DB-1 i PUMP TYPE W BINGHAM W BINGHAM B-J B-J BINGHAM BINGHAM B-J RATED POWER (MWT) 2568 2568 2535 2772 2452 2568 2568 2772 2772 4 SYSTgFLOW 109 111 109 110 112 109 110 114 113.4 kk0F352000 ~ GPM) 't.gSED(MIN) 106.5 106.5 106.5 105 105 106.5 106.5~ 105 105 y, 1 i j i ,f e e

.w THERMAL-HYDRAULIC DESIGN I I 177 FA PLANTS Ag' MUM (k h YSf b b 5 TOTAL GUIDE TUBE INITIAL BASE - A'_L FA'S CONTAIN ClA's, BPRA's, OR ORA's 6.0 1.7 TYPICAL PRACTICE - gj4 ORA's '3) (h.k) 8 ALL BPRA's/0RA's RE5VED 10,4 6.4 NOTE: REMOVAL OF ONE ORA INCR$ASES CORE BYPASS BY s 0.04% O e O D 0 .l O

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FIGURE 1 FUEL TRMiSFER OC0!;EE I, CYCLE 4 CORE LOADING CANAL DIAGRAM r REY. 1 [ FA ' FD G5 C9 F7 . FG GO CH 1D06 1D48 1D08 G4 GE . FT 0,f1 C17 C56 C48 R0001C GP FY 1D26' 6P 6C 1D51 60 6H 1D21 GL FS OXX CIS OXI' C29 OXX C32 OXX' CS2 OXX ~' G2 FM 13 15 72 .5Q 1D46 5X 1D12 SM 71 1B03 FK FX OXX C49 OXX A04 ,0XX C16 OXX A05 OXX C42 OXX G1 1D45 70 SY 1D27 5F 1D03 5J 1D29 SW SU 1D20 FZ C19 OXX C05 OXX C23 OXX C27 OXX C07 OXX C57 F5 FJ 6Y 65 1D28 1D17 SC 1D59 6K 1D18 1D25 6Q 6L GN F8 C04 OXI A026 OIX C01 OXX' C21 OXX C30 OXX A06 07X C24 61 6S 1D44 67 1D52 FC 1D35l 02I G8 1D30 6A 1D11 SE SR 1D07 6T 'C61 C25 OXX C46 CSS OXX. C22 _0XX C26 OXX G7 1D56-1D09-SB 1D01 1D61 6X 1D05 5Z 1D58 1D02 6U 1D50 1D60 GQ C41 OXX C14 OXX CO2 OXX C12 OXX C38 OXI C10 OXX C50 FE 1D22 50 1D15 6M 66 1D19 5H 1D32 ST 6G 1D14 69 1D42 GB C51 OXX C53 OXX '. C13 OXX C15 OXX C_06 OXX C54'

F9 FP 6R SK 1D16 1D36 55 1D57 62 1D37 1D23 64 6V CJ F3 C44 OXX A07 OXX C03 OXX C47

,0XX C39 CXX A02-OXX C20 GF-1D43 5V 67 1D53 63 1D04 6N 1D24 68 SN 1D13 CG C60 OXX C43 OXX C.58 OXX C59 OXX C28 OXX C40 G3 GK 1B01 6E SD 1D10 6W 1D49 6B SP 1B07 FN FW OXX C36 OXX A08 OXX CO6 OXX A01 OXX C37 OXX L GC, FL ID54 6Z 6D 1D3B SL 6J 1D55 GM FU OXX C45 OXX C35 OXX C34 OXX C11 OXX FF FV FQ 1D41 1D4? 1D31 FR GD FH-C33 C31 C09 OXI l R00009 ~ G6 FE F4 F6 GA l l l l l Z 1 2 3-4 5 6 7 8 9 10 11 12 13 14 15 Fuel 1.D. (lDXX - Batch 4; SX, 6X or 7X - Batch 5; FX or GX - Batch 6 ; Orifice (OXX) or Control Rod ID (CXX - CRA; AXX - APSRA) 1BXI -Batch Source I.D. (R000XX ' Secondary) 86-000E-01 NOTE: NJ00 prefixes Batches 5 and 6 F. A. I.D. 's p.. ? nf 2

t t i t StJffRLOF_HOU.00HH 1ATG! lll."PECUD!$ SITE l{QJUJB_0M UD.m JfilitI'!% OCONEE I 8 0 OCONEE Il 7 25 M0I 20 36 CR Ill 40 66 DAVIS BESSE 9 24 o O ae b d' 3 M .,si,,i.. .. _ _ _ _ _ _ _ _ _,,,. ~ _

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FICURE 1 QUALITATIVE DESCRIPTION OF LATCll TUBE tJFAR IATCH fUBE INSIDE SURFACE r A m \\. A ., '. s... -. G.. - -... v g p . - w..._ -., y s \\ I TYPE I TYPE II TYPE III TYPE IV )(_.,ltOSS M LOCKIllG I g N .. _... a. g _.. BALL - 1 ION ( Y LOCATION WEAR AREA CllARACTERIZATIO!! LA*lCil TUl \\ .\\. = _.. SMALL WEAR AREA ON LOUER CHAMFER ONLY. TYPE I TYPE II k?>.R INTO VERTICAL LAND, BUT LESS Tit;N HALF Tile IIE1 Girl. TYPE III - WEAR INTO VERTICAL LAND, GREATER T11AN HALF Tile IIEIGilT. TYPE IV UEAR IllTO UPPER CllAMFER. apqg BPRA CO. OF 1ATCH PERCENTAGE OF TUBES SilOWING WEAR OF; FLA!fT TU3ES EXAlfINED TYPE I TYPE II TYPE III TYPE IV CR-3 68 7 49 34 10 CGr.=a. -2 25 52 44 4 0 + A2>-1 36 47 53 0 0 D-B-I 24 54 13 20 13 - , 3..- - J 3C 7, .. n i i s. r."

U/W I bl.bbt. 01411 1 LUn!..i L i 'c .L U }' tI n. T..*... : r C A*; A!. . [., x 'l 6 t 11 1 r. 4 -l 1 b: 3 O 1 c ~ ( 1 1 3 1 2 1-V t 3 _.-. w s - l 2 3 _b..._ ..b_.. .. _..... i... _. 2 3 1 1 f P 3 1 1 3 !1 1 1 = - - ~- .t 1 I 2 1 l I4 i f 1 1 ) l l 1 lI i 1 2 3 4 5 6 7 8 9 , 10 11 12 13 l '. F l l l \\

  • l

i SIFMRY OF ORA LATCH TUBE INSPECTIONS T LATCH TUBE CHARACTERISTICS TUBES PLANT BHN YlELD KS1 EXAMINFD REMARKS i \\ OCONEE-1 73.8 7 ORA FOR 2 On 3 CYCLES ~ l0CONEE-1 170 34.8 1 ORA FOR 3 CYCLES l OCONEE-2 170 43.0 7 ORA FOR ONE CYCLE ANO-1 217 63.8 ~ 8 ORA FOR ONE CYCLE ANO-1 156 37.0 12 ORA FOR ONE CYCLE CR-3 149-159 42-36 19 ORA FOR 270 EFPD CR-3 170 43 2 ORA FOR 270 EFPD CR-3 217 63.8 19 ORA FOR 270 EFPD DB-1 153-168 9 ORdrOR85EFPD Tg p l II % g ~. Il % O la.%

.s COUPLl}iG UNI.ATCHi!!G EXPERIENCE l I T PLANT DIFFICULTY MAXIMUM WEAR I I BPRA ORA BPRA ORA i DAVIS-BESSE HIGH HIGH HIGH HIGH 9 1 CR-Ill HIGH NONE HIGH NONE [. I OCONEE-I NONE NONE NONE Oc0 NEE-Il NONE NONE MODERATE NONE OCONEE-Ill NONE NONE A!i0-1 NONE NONE low NONE TMI-I ' NONE NONE RANCHO SEco NONE NONE LJ 3 k ? 4

i l ~ ) f OCONEE I k . NUMBER OF NUMBER OF ORA'S NUMB 5ROFORA'S I TOTAL NUMBER ORA'S IN IN B ASS'Y IN B ASS'Y l i 0RA'S B,n ASS'Y 2kYClFS 3 C CLES l \\ \\ j

CYCLE 1 (g,

0 I. s-I CYCLE 2 62 0 0 l i 4 i ~ CYCLE 3 62 14 0 0 i , CYCLE 1: 62 38 10 ~ 0 I !Ii ll

/ DCONEEII ~ I l NUMBER OF NUMBER OF ORA'S NUMBER OF ORA' TOTAL NUMBER ORA'S IN IN Bq ASS'Y IN Bq ASS'Y ORA'S Bi, ASS'Y 2 CYCLES 3 CYCLES \\ CYCLE 1 4 0 I l j 1 CYCLE 2 63 11 0 j

YCi.E 3 64 28 8

0 A l p ,3 e e

67 C. OCONEE III ~ 7 Q c_ rn Q' NUMBER OF NUMBER OF ORA'S NUMBER OF ORA'! r TOTAL NUMBER ORA'S IN IN B ASS'Y IN Bq ASS'Y q ORA'S By ASS'Y 2 CYCLES 3 CYCLES i CYCLE 1 4 0 \\ s l j bhCLE2 62 10 0 4 CYCLE 3 62 26 2 0 ~ / I 't W .B t

j [ TMI-I T , NUMBER OF NUMBER OF ORA'S. NUMBER OF ORA': j TOTAL NUMBER ORA'S IN IN Bq ASS'Y IN Bq ASS'Y i 0RA'S B ASS'Y i2 CYClFS 3 CYCLES y CYGLE 1 l 4 0 i j 8 CYCLE 2 62 10 0 l CYCLE 3 62 30 2 0 4 CYCLE 4 62 46 18 2 t i i. 1. I

<TMI-li [ l NUMBER OF NUMBER OF ORA'S NUMBER OF ORA' ~ 7 TOTAL NUMBER ORA'S IN IN B ASS'Y IN'Bq ASS'Y q ORA'S By ASS'Y 2 CYCLES 3 CYCLES

i l

CYCLE 1 40 1:0 l l i s. I t i. 1 i 4 1 i I I j 1 t i

TMI-I . NUMBER OF NUMBER OF ORA'S NUMBER OF ORA': i TOTAL NUMBER ORA'S IN IN Bq ASS'Y IN Bq ASS'Y ORA'S B ASS'Y 2 CYCLES 3 CYCLES q \\ ^ CYCLE 1 4 0 ~ . CYCLE 2 62 10 0 ^ CYCLE 3 62 30 2 CYCLE 4 62 46 18 2 e i ; i 4

3 C,' CRYSTAL RIVER CD { C._ i iil i O' NUMBER OF NUMBER OF ORA'S NUMBER OF ORA' d - TOTAL NUMBER ORA'S IN IN B ASS'Y IN B A55'Y - q q i ORA'S Br, ASS'Y _ 2 CYCLES 3 CYCLES s CYCLE 1 40 0 ~ i \\ l 't> e g \\ Bj iE ~ a .b~ ~ = [5

~ - - - - - - - ~ ) SMUD 3I _a. ] . NUMBER OF NUMBER OF ORA'S NUMBER OF ORA' TOTAL NUMBER ORA'S IN IN Bq ASS'Y IN Bq ASS'Y l j 7 ORA'S Bq ASS'Y 2 CYCLES 3 CYCLES i CYCLE 1 4 0 i i \\ CYGLE2l 62 2 0 l' s e 0 4

'g

07 4 C I Q DAVIS BESSE c_ mOI HI NUMBER OF NUMBER OF ORA'S NUMBER OF ORA' l TOTAL NUMBER ORA'S IN IN B ASS'Y t ORA'S By ASS'Y___ 2hYCLES IN Br. ASS'Y 3 CYCLES i I CYCLE 1 48 48 i \\ i a s e e u' 3 l 5 \\.

1 I m ! ) C (~ ANO W c_ m

7 TOTAi. NUMBER RA's NUMBER OF ORA'-

sI B SS ' IN B, ASS Y 4 ORA'S 3 AS_S,Y 2 CY_CLES 3 CYCLES t 4 CYCLE 1 4 0 ^ \\ ~ l i 'tYCLE 2 62' 10 0 l ~ CYCLE 3-66 30 2 0 1 i { p I i W !B 9 i -p

  • b 1

=

O '? 1 PLANT STATUS

SUMMARY

f POWER NEXT PLANT LEVEL STATUS REFUELING 7 OCONEE 1 2568 100% SEPT-0CT OCCNEE 2 2568 100% OCT-NOV ~ OCONEE 3 - 2568 100% JUNE k., I TMI-l ' 2535 100% 1979 4 TMI-2 2772 .IN STARTUP TESTING 1979 CR-3 2t452 SHUTDOWN 1979 DAVIS BESSE 2772 SHUTDOWN 1979 l RANCHO SECO 2772 ~70% LATE 1978 l ANO-1 2568 100% 1979 i S 0 e P

~ t t ~ JUL 2 01978 a Mat 0RANDUM F0R: SIA. Varga, Chief. LWR Branch #4, DPM t K. Knie}, Ch'i.Cf. Core Perfornance Branch, DSS FROM: .r

SUBJECT:

EVALUATION OF TECHNICAL SPECIFICA7 ION CHANGE 14 FOR ~~ ~ ' - - " ' ' - ~ ' ~ - ' ' ~ ' ' THREE MILE ISLAND',' UNIT 2 Enclosed is the evaluatios of' Technical Specification Change No.14 dated July 7,.1978 for TMI-2 ty the"Rea'c~ tor' FdeTs"Se'ctio'n"oT~th'e' Cope 75'rforinan'ce"'-'~ Branch. The Reactor Enysics' S~e'ct'ioh'h'as-no-~ihput.' I5"s65ina'r)Tse~ approve ~ ~ --- the use of the propased holddown-^pe'tain'eFs'ToFBPRAs and mo'difie~d' ORAs. Also, the' applied rod bow equation las"b'e'e'n verlfre'd to"c~onfo6nto' the NRC-approved rod bow equatio'n'.f0r B&W' pTan'ts. ' - ~ ~ ~ ~ ~ - ~ ' - - ' ' ~ - ~. .. - ~ - - ~ Karl Kniel, Chief ~ ' ~ ~ ~ ~ ~ ~ ~ Core Perfomance Branch ~ Division of Systems Safety 7,-~,~,--~~',,',,

Enclosure:

As stated cc: S. Hanauer R. Mattson " - ~ ~ ' - - - ' D. Vassallo ~ ' ~ ----- -- - g, gayg CENTARL FILES H. Silver NRR RDG FILE ' D. Ross CPB RDG FILE' D. Fieno ,/, R. !!ayer ~ ~ ,/ M. Tokar ~ / j, W. Brooks ./ D. Houston l

Contact:

W. Brooks, NRR, 27577 D. Hous ton, NRR, 27603' ~ ~ ~ -~ ~~ ~ ~~ ~- - ' '--- ~~, $h l BSS/CPB DSS /CPB._, , DSS /C,PB DSS /CPB,, DSS /,CPB DHouston:jt W. Brooks Rhayer DFieno KKniel 7/20/78 7/ /78 7/ /78 7/ /78 7/ /78 i i.

p 7 r e EVALUATION OF T. 11 CAL SPECIFICATION CHANGE 14 FOR TMI-2 .2 ACTOR FUELS SECTION f A burnable poison rod assembly (BPRA) was ejected from the core at one of B&W's Mark B plants. B&W analyzed the problem and determined it to be caused by levitation of the BPRAs during four-pump op'eration and subsequent fretting wear in the holddown latching mechanism. After the ~ initial inspection of fuel assemblies at the affected plant, B&W also observed visual indications of wear at other plants in the identical - latching mechanisms of BPRAs, assemblies that held orifice rods (0 ras), and source or modified orifice rod assemblies (MORAs). A retainer device was then designed and tested by B&W to ensure positive holddown of BPRAs, ORAs and MORAs during reactor operation. The design and the test results were reported to NRC in references 1 and 2. We have re-viewed these references and have previously determined (Ref. 3) that the test results and design analyses provfde reasonable assurance that the retainers will provide adequate positive holddown force on the BPRAs, ORAs, and MORAs and that the proposed use of the retainers poses no safety problem. For continued operation of TMI-2, Metropolitan Edison Company proposes to install the retair.er devices on 68 BPRAs and 2 MORAs. All regular ORAs (38) will be removed from the core. These changes apply only for the remainder of the current cycle, Cycle 1, at which time, BPRAs are usually withdrawn from the core. Based on our evaluation as referenced above, we find the use of these retainers to be acceptable. .The potential consequences of a retainer failure have also been addressed (Ref. 2), although failure is considered unlikely. The neutronic and thermal-hydraulic consequences are considered small. Interference with cgntrol rod motion, for example, would not, according to analyses of stuck-out control rod transients for B&W 177-FA plant <., prevent safe shut down of the plant. The major concern associated with retaincr failure is plant damage, primarily in the steam generators and potential outages for repair. This damage should be precluded by the Loose Parts Monitoring System (LPMS). The LPMS is designed to detect a failed retainer in either the reactor vessel or steam generator. Even though the retainer device is designed for only one cycle of operation, B&W has stated (Ref. 2) that it will recommend that surveillance inspections be made following retainer use. This should provide additional confirmation of acceptable operation. B&W has also stated that definite plans regarding surveillance will be provided to NRC as they are formulated. ? r

( - r In summation, based on (1) analyses and test results on the retainer device, (2) analyses which indicate that failure of the retainers, however unlikely, would not prevent shutdown and (3) failure detection capability of the Loose Parts Monitoring System, we conclude that there is reasonable assurance that the retainers will provide adeouate holddown force on the BPRAs and MORAs and that the' proposed use of tne retainer devices in TMI-2 will pose no significant safety concern. One other cha'nge to the Technical Specifications involves the use of r revised fuel rod bowing model. The original calculations for a rod bowing penalty had been performed with a B&W rod bow model that we found unaccept-able. We have verified that the revised rod bow model as presented in the change request conforms with the NRC-approved rod bow equation for B&W plants. Therefore, we find this change acceptable. REFERENCES 1. "BPRA Retainer Design Report," Babcock and Wilcox Report, BAW-1496, May 1978. ?. James H. Taylor (B&W) letter to Steven A. Varga (NRC), June 7,1978. 3. K. Kniel memorandum to D.F. Ross, Jr., " Proposed use of Burnable Poison Rod Assembly Retainers to Holddown Modified Orifice Rod Assemblies in Davis Besse 1," June 19,1978. i I I l e G -m m P 1 _}}

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