ML20028F646

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Discusses 790222 Telcon Re Psosible Loose Metallic Matl in Rcs.Util Initiation of 11 Westinghouse Recommendations Prior to & During Power Operation Should Be Verified
ML20028F646
Person / Time
Site: 05000000, North Anna
Issue date: 02/26/1980
From: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Ferguson J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
Shared Package
ML20028F641 List:
References
FOIA-82-534 NUDOCS 8302020348
Download: ML20028F646 (1)
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Text

{{#Wiki_filter:. ?, '. UNITED STATES NUCLEAR REGULATORY COMMISSION 3 ?. E REGION II I 107 8JARl7TTA ST., N.W., $UITE 31oo % 4 m,o ATLA.NTA stcftGtA v.x3 In Reply Refer Tot RII:JP0 50-338 Virginia Electric and Power Company 'O ATIN: J. H. ~erguson ] Executive Vice President-Power P. O. Box 26666 .. 2 g, Richmood, VA 23261 ~0 Gentlemen N 2

Subject:

Confinnation of Acdon A .A Th.is refers to the telephone conversation of February 22, 1979, between B. R. Sylvia, Director Nuclear Operaticasi and R. C. I.cwin of my staff, regarding return of North Anna. Unit I to powce operation with pcusible loose metallic-ca terial in the re'accor coolant system.

  • Based on che referenced conversation, it is our understanding that the eleven Westinghouse reccaneadations concerning abnorreal noise detected in your North Anna 1 facility w*ill be car'ried out by your staff prior to and during power operation.

Further it is understood thatiou will: 1. Submit a sp'ecial taport to NRC concerning the' Icose parts raonitor alarm on February 20, 1980, and subsequent testing and analysis conducted. 2. Conduct testing to correiste the.*i2e of the suspected objects in the reactor coolunt systens and report your findings to the NRC. 3. Report any unexpected abnormalities resulting freci eenduct of the Westing = house reconnendations and any failure to conduct the recommendations to the NRC. Please inform us i:nediately if your understanding of'these itcas is different from that stated.above. Sincerely, ) e t.- pfb_..g. r 'Jacies P. O'Retily Director REGIONAL AD/AlNISTRATOR' cc: see Page 2 WUTY ADMINISTRATO 8302020348 82121'3 ASS'T TO Ant INISTPATOR-PDR FOIA SCHLISS82-534 PDR D!?ECTOR, PRp DIRECTOR, ETP hW D!REcion h, pysg

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Dear Mr. O'Reilly:

Pursuant to North Anna Pcwer Station Technical Specifications, the Virginia Electric and Poser Company hereby fsubciits the following Licensee Event Report for North Anna Unit No.1..- . Report No. Applicable Tec!.uical Specifications , [LER 80-02J/99X-0., ' ' ii r p ;',,., I -f 1 None. Special Report Requested This report has been reviewed by the Station Nuclear Safety and Operating Cor:raittee and will be placed on the' agenda for the next eeeting of the System Nuclear Safety and Oper,ating Cc::nittee. 5 Very Truly yours, ,/ N i s j' fp l i W. R. Cartwright 1 Station Manager i 4 1 Enclosures (3 copies) Mr. Victor Stello, Director (30 copies) cc: Of fice of Inspection and Enforcec:ent I weJI2dddN45.%Y5rT$...$$ 7(N T**TIlTN 7 1YeTto'r R pies) I ~ ,h* Of fice 'of Management and Prerra= Analysi O i i / ku - (e m

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.5 E:n t ric and Puer Cc;uny N o r t h M r.n a P Act S t a t t <; n, L~n s t -1 Att ut.nera na 1 .t hockrt 50-118 Rc; "r t %. ht?. 30-27/99X-0 L. u r apt ion of E.cnt Cc.ruident with a reactor trap cn February 20, 1950 an alarm soun ted 21.dicating a notse in "C" steam generator and upper reactor s pj vessel. Icpact noise could also be heard on the loose parts monitoring ?j speaker. The "C" reactor coolant pump was shut dewn and the noise .h disappeared. The noise resumed when the pump was restarted and then W. disap; eared when full flow was reached. Subsequent testing revealed catal iepacts from as many as four separate distinct sources possibly l originating frco inside the Peactor Coolant System. q probable Consequences of Occurrence Analysis of noise data obtaiEed by Westinghouse concluded that the 4 reactor is presently in a safe and cperable condition as long as the indicated loose parts do not migrate and affect internal plant equipment or interfere with control rod sovecent.- Because the unit recained in a ~ hot standby condition througheut the durat' ion of this analysis, the public health and safety were not~ affected. There are no generic icpli-j cations associated with this event. f f Cause of Event ~~~ Although the cetal impact noises cik be att.-ibuted to loose parts, ~ ' the exact cause and origin of these indications is not known at this ji time. L. I' Immediate Corrective Action. 7 Westinghouse specialists were called in to obtain noise data and analyze the results. The ' objectives of this investigation was to determine ,4' if actual loose parts exist and if so the nusber of objects present, their approxf= ate size. sad if possible, their origin. To collect the necessary data, special signal conditioners vere substituted for the installed Rockwell sigeal'ccc4itioners in the Loose Parts Monitoring 5 System. The in-centain:aeot Reckvell equipecnt was' used without modification ~ I With special test equipment available, data was recorded on a 14 channel FM recorder, allowing for a fre-{uency of 0-20 kHZ. Signals from the "V tape recorder then allow siruitaneous recording of several channels on a visitorder chart, shere time differences of the various impacts of a loose object (s) fres different locations cay,be dete rmined. Additionally, N:f af ter noting impacts fres the visicorder charts, or by directly scanning h' the magnet ic tapes, the (epsets may be examined very closely in the Line 4; and f requency domain by use of a spectrum analyzer. Conclusions of the analysis were as follcws: y" 1. There are no indications of parts in the bottom of the reactor vessel, therefore the part is considered to be on 9l1 the T side. H 2. Upper vessel detector signals are approximately the sa.se 7[ shen the rods are latched and the RCC's raisei approxim. ate;y ]t one foot, then unlatched with the drive shifts free f r.m i ~ga t ur 'i

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. team generator during reactor coolant purp transacnts; I however, no impact indications sere noticed during steady full flow operation of the pumps. These impacts could be detected by listening by car to a ectallic rod not that was in contact with the channel head. I Since testing showed that plant instrucentation and rods were p rat ir.g ncr= ally and because no activity was rer::ted in the stea.2 { sen-rators, the plant was detera:ined safe for opernica provided the indicated loose parts in the steam generator channel head do not nigrate j as to affect internal plant equipment. Rod drop tests were satisf c-so t t r tly performed which confirmed free rod covement. Atte= pts to link { the noises with loose parts in the plant secondary side vere partially successful in that changes in steam and feed flow tended to produce noticeable effects on detected netal impact frequencies. f Actions reco:cended by Vestinghouse have been conducted on a con-l 1:nuing basis to ensure that the indicated 1 ct.e parts do not migrate i and that the plant rec.ains in a safe and opsrahle ccndition. Trea the h three, sets of nuclear noise dat4 taa* ca,- it has been observed that the signals in the 5 to 10 hertz frequency range have increased 33Y.; hcwever, (E there'is no indication of any structural dy,radation. The latest analysis vf obsersed ect.nl impacts has concluded the following: i 1. The iepacts are originating frca the stean generator secondary side and are being trans=itted to the sensors (located on outside of straa' generator) by indirect code. ? The upper reactor head 5coises differ fro 3 the stea:s [ generator soundings 'in pr.pliettJe only and are suspected to be the result of noise carry ver. l 2. The object weight is_ believed to be a 1/4 pound or less h od as a result co safety concerns exist at this time. e 3. Vestinghouse now believes that there is at le.ast one scall object in the seccadary side of "B" steam generator u with t!.e possibility of more in steam gener.itors "A" and - h "C". i; E hheduled Corrective Action .g During the next outage of sufficient duration, the secondary side [ 5 or "B" ste. :n gener.itor will be opened and inspected for loose parts. Due to the conclusions recently deduced from the ongoing evaluations, Ep the tollowing changes will be u de to the original eleven Vestinghouse p irc m endel actions. fhese changes will not be irplezested until NRC h-et n !! concurrence is obtained. ,4 1. P-cause the loose part(s) is no longer constdered te be in f the Reactor Coolant System. present prima ry side sur. ai.- y-lance fre.;uencies st:1 be reduced to their normal rc p tred

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l .it t a ctmen t : Page 3 >i 3 ";.e r at t on in reverse fins, due to cne e,r r.cre reactor c oolant pumps t ripping, will rio longer require an lysis to determine if loose part indications have migrated. 3. Investigations will be performed for secondary side i transients Instead of primary side transients as previously recomended. f 1 ba th the preceeding changes incorporated,- all k'estinghouse reco:enen-datirns will continue to be perforced on a regular basis to assist in s t t.e a t t ecep t to identify and resolve the Icose parts proble:s. Actions T.eken to Prevent Recuru nce-Actions to be taken will be deter:cined af ter further evaluation and identification of the indicated loose part. l a s' 'm P 1 3 i 4 5 + 1

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3 m m. s' t p 507FLUCNUJtT UTOD9CN CQ ?-s n c: Fe.: 50-302/73-17/01T-0 1 .? 2. Ta 111:7: Crystal River Unic #3 3. Tx p:: 04u: 14 March 1975 4. Occurre cs Mca: 5 Arch 1975 (discevarad 17 Februx:71978) 5. Idutifice.tiva cf Cecurrenes: 'Discovary of icoes ;srts in the "B" Occa hrcush Stasa Generater (OTSC) reported in accerkca ' rich Section (g) of Lichnical Specificatica 6.8.1.3. 6. Ccniliticu Prior to Occurraces s Mads 1 cparatica. 7. Descriptics of Cecurrasest - ~' - 1: i At 0005 on 17 72bruary 1978.a consthe alarra"es ths nac.ctor C1 cacatie Systes (I,cosa ) i Parts 7. niter) o *currst es ths "3" Ot3G.' Isttisr ictied ed.en ves 'to==sitor other pime parcmtsrs 'or sic.s of dopchtica.7 cetsefpth:e par::nters 'inditstad no the:- n11eM. ' i tuat*c cles rsv.ethdisd.Gt 1xasiparts la the tla sheet rngica c f t.h4 "B" CT50 and thens =c120 ud v1MacdEdr2idep.ddist ci tha reactor c olant. ficw P Mhd 5I+"7.9, rscetice cEoldt' p't;r02 /3d$ .3-parae tr Iea J hca.7STpc.csc[la[d:d8:nt.di'6MTic!i.4ac '[ i; M KC pc=picperstica~ cad radnesi 3 (9* c t M Invastir.L ires? ten s fn n 11'J es ps. rte diq=is.1 ' ?re; art:1cf.s#c%ds11kd_isidd-t, heir %~sinationiccufirmad the Joose 1 ccantehfar:blist ;stiutdtv:i' sad Jeh'saguant is:pr. tics euncad'ca 5 Edth 19732~At-15cofodTWis;hjlS78f fuspEction?of 'th's --i 7 v1th vids o l cadara Ms1Ncicularid' c'ddff.%Ethafo f; app roxisdra.ly - 17: 1cida"p arts' identifie d 4' 33 part3Ldff.hiccWiing eiespid3'tNIEMi[df h st.ble poiSc3 tGd (871) 13-47 vsra s estthsTo6r ibTippe 666a'shdG 7hd ithic Efor. furthorf drairidcun and E.ss.ctor. 1 7<scalhard. rt=:ntd cc.dac: fred:d;ahdiodical head varausd'ca 13 !! arch 1973.- Inspectict'alsoirevsalad [ din:Ih Off nifyi5;;ldsg*c$ htd'ocedred to e*, 7 of the."3" star 2 tamtstar t-5.ii cads.' Jhdeksi.2 dfin:pactl.n of"the Pisatcr is a.sticipated to be ~ f cc ?leted by 15 liden 1978. 'EssIta df thz ?tifs inspectier Md paths to b's tzksa ~ suhtagv.act to this investigatiesivill bs farthcodag lu"n add: d :: to this'rcport. ~ Oasi;; nation of 4parast Causst : ~ '.h: As of this da:n, tha' apparant 'cabe '6f this occurrence was due to a failure of tha coupling ud spidar 'asse=bly 'of BP1 fB-47. -- ^ 9. Analysis of Occurrence: 'ha health cad safety of the plant and general public vara net ec= precised as a result of this svsat. s 10. Correctivs Acti.:n: I ( t t l Ehn.m. ra at this cima. As isvestigatie:s ccac1=us. corrective action vill be i=ple:enced as a rasult of the investigsziens. LN. Failure Osca: First eccurrenes of this event.

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/43'ON '^y n u won n w j, !!, S ' I) $ umao<v t t ers t ti. c w :m r,,, L ,~e cu u, et om e. 2,.ra (n) -5.f.W....he , g I t F.crortEo.: 50-302/78-10 I l Docket No.: 50-302 i i License No.: DPR-72 F Licent.ee: Florida Power Corporation p 320i 34th Street South [j P. O. Box 14042 ) St. Petersburg, Florida 33733. (, I-Facility Na:na: Crystal River 3 Inspection at: Crystal River site, Crystal hiver, Florida l Inspection conducted: April 24-28, 1978 e f. Inspector: R. H. k*csscan [ g - Accompanying Personnel: F. J. Long (April 27, 1978)" -- i [lf H. C. Dance (April 27-28, 1973) .5-!r[!7[ i Mw F.eviewed by: )l i 'DatE )' H.'C. Dance, Chief. Reactor Projects Section No. 1 E - ' Reactor' Operations and Nuclear Support Branch g D 'nspection Su=arv a [ insfection on April 24-28, 1978: (Report No. 50-302/7E 101 n Areas Inspected: Toutine, unannounced inspection of plant operations { and outage. activities; folicvup'on previous nonce =pliance items and g unresolved itecs;. and f acility tours., f.nnounced canagecant =ee:ing on [, April 27, 1978, to-discuss FFC-licensed activities; review enforcer.cnt inspection resul's; and to discuss NRC organi:stional t history; review recent relationships and cox:unication' philosophy. The inspection involved 58 inspector-hours on site by three NRC personnel. R e sul t s_: Of the five are:s inspected one ites of noncompliance was identified in one area (Defici~ency: Failure to subnit Monthly Operation Report as required by Technical Specifications (78-10-01)). i / a P0& 21'l . - c-

,7 I ) w ac 1 EII Kpr. 1:s. 53-332/78-10

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^ ly 1k OCAILS I Prepared by: _ _ 6, R. H. Wessman, Ecactor Inspector Date Reactor Trojects Section No. 1 Reactor Operaticns and Nuclear Suppcrt Eranch Dates of Inspect me: A ril 24-28, 1978 Reviewed by: 8% 3 /27 if.TC.:Danca, Chief Datd ' Reactor Projects Section No. 1 l React'or[OperationsandNuclear Support 3 ranch s ( 1 }. '7 1. Persons Contseted Florids ?over Corporatten~(FPC) i ~__

  • C. P. Beatty', Jr.1 Nuclear PIhnt Manager

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  • W. R. Nichols,.,0perations Superintendent-

' *P. F. McKee.. Technical Services Superintendent l,!

  • J. L. Harrison, Ashistant Chemistry /Rsdiatien Protection Engineer j'j
  • J. C. Wright, Chemictr /Rajistica Protection Engineer W. R. Klein, Reactor EngineerC e J. Cooper, Co:splianie7Enginier$$[

m E.

  • C. M. WilliamsLCes;snsEca7 Plant Engineer
  • G.R.Vestafer,Maintsnjnie)Sujerintendent C. C. Goring, Cceplience'Additor.

L P. 'L. Breaux, Nuclear SNic? Supe'rvisor ~ } W. M. Harsha11dNaclear;0$yator - ~ ~ M. P. Holces Nuclear Operstor' K. O. Vogel, Ope}ati6ns En' ineer g

  • Oenotes those persons at Exit Interview.

2. Managernent Heeting - Apri1 27,' 1978 ~ The NRC eet with Florida Power Corporation on April 27, 1978, to discuss FFC-licensed activities. This meeting was convened at the request of Region II to review Crystal River 3 enforcerent histcry and licensee events; review recent inspectio.1 results; snd to discuss NRC organizational relationships and comunication philosophy. Attendees included: {& ~

ls t (i E4 ,A 22: rpt. h. ! S 302/78-10

-3 Ek:l

,,,j-f. (Cicsed) Outstanding Ite= (Details I, paragraph 5 of KII Ept. g 77-17), Identification of Alternates in FRC Minutes. The ( { inspector reviewed =inutes from IRC =cetings 78-9, 78-10, cad 73-11 to determine this is being acco plished. t g. (Closed) Unresolved Item (Details I, paragr.1ph 6 of RII.4pt. 77-18), Ju=per Controls. The licensec has reviewed all outstandi W jucpers to assure require =ents of Technical Specification 4 6.5.1.6(d) and 10 CFR 50.59 concerning cafety evatustions are opt. 4 g 4. Unresolved Ite=s 4 Unresolved ite=s are catters about which core inforr. tion is required JJ in order to ascertain whether theylare acceptable ite=.1, itees of <n.' noncocpliance, or deviations.. _ Tuo unresolved ite=2 (Decontamination N. Cleaner 10-02, and Decontamination Procedures 10-03) were 1. identifted and are discussed,in' para 5raph 13. t 1 5. Exit Interviev ). dl A meeting was[ held b,i R.[H.Nesscan with G. P. Seatty, Jr. and ~ f / l' eembers of his~ staf f'on April-28, 1976.'- Itces covered by the (J. inspection were. discussed.wTheinencompliance iten relating to the late submitta) of_the;Ma'rch. Monthly Operating Report was discussed a j vith the licensee by;: telephone May,1,1978. ~,.. o: Q:;-::-?ssh-v ,ccy: ~ 6. Submittal of the Monthly Operating Report. ,iL.:fR 7;$ P F' v ~ De Itcensea advised tlia;inspedt'of that due to c.n administrative

4

'l oversight' the Marcli 1978 Monthly' Operating Report was not transt:itted viti.inthet'inerequiredb[TechnicalSpecifications. Technical U Specification 6.9'.1.6 requires that routine reports of operating '4 statistics and shutdown ~ experience' be submitted on a conthly basis i later than :he-15th of the month follouing the calender conth not covered by the report. 4 ~ ; ContrarytothisTecknicalSpecification,theMarch1978 Monthly Q Z Operating Report was not sub=itted until April 25, 1978. nis has been identified as e deficiency in the Wtice of '.'iolation. (76-10-( Q 7. Reviev_of Puel Inspection Activities and Retrieval of Parts _..s of the Broken Burnable Poison Fods ,w l M The inspector reviewed procedures and selected data'tsisn during inspection cf the Crystal River 3 fuel assemblies and retrieval of ]* parts of ti.e broken burnable poison rods (BPRA). 3e following !d ' [$ aspects of thst activity were reviewed: g1 \\;3, m

q LO

i f. l r a 3 } w- ..u.. m ) m., [j Fil Epc. Fe. 50-302/73-10 I-4 y Co ple:e fuel assembly inspection data for assemblies 3C35 and 3C37 (which had contained ~ the failed burnable poison reds). Guide tube integrity test reccrds en fuel assemblies 3C35 and 3C37. Inspection records for all fuel cese blies (documentation generated durin5 core unloading). Records of " debris re= oval" for fuel assemblies identified i as having pieces of the broken burnable' poison rods in the { lower end fittings. j Recordsforrc=ovalandinspectionofotherburnablePoison Rod Assc=blies. All EPRA's have been recoved. o ~ .e.

  • r ' ';)

. _ic + - ~, Records of inspection of_ fuel a'sse=blies upper,and fittings ~ and,latchtubesforvearinduced,by}3PRA'sororificerod ~ ~ ~ assemblies. (No wear. induce'd by"orificeL rods.vas identified i by the licensee. VArio'us fuel;sssemblies had minor upper end. j y fitting vaar induced by the.3PRA's) s V. 'M ~. v; : : .. ;. 2 g,;-3 .:s - ~ Records for orifice rod ~ assembly. inspection.: (No evidence .] l of vear or loss of. ball _locksjvas. identified.)- .g c t ~ 1 The inspector has not reviedcd"inspec. tion procedures and records ] for reactor vessel, core' support assemblyl or plenum assembly inspection 1 as this verk had not been~ coupleted at-the" time of the inspection. 3 The inspector stated his intent to'revieOlthis data, and any other i ~ procedures / data relating to the fuel' assemblies and core reload. l prior to initiation of cerc reloading (78-10-04). Kev _ev of Logs and Short Tern Instructions I S. t ~ The inspector reviewed selected p1 ant logs and short term instructions 4 for the January-April 1978 paried. These docu=ents were reviewed for consistency with the rdquitecents of Technical Specification 6.10.1 and the procedural guidance of A.I. 500, Conduct of operations. Docurents reviewed included: 1l Control Room Nuclear Operators Leg - March 22, 1978 - April 24, 1978 Shift Supervisor's Log - April 4, 1973 - April 10, 1978 and April 23, 1973 - April 27, 1973

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  • ..CLc AC C *.C UU,TO.~.Y Cou ': :;gON F

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~ ATLAMA Cf cmc 4A M Encrt Fo.: 50-302/70-16 Docknt No.: 50-302 Licenso No.: D72.-72 Licensca Florida Power Corporation 3201 34th Streit Scuth P. O. Ecx 140'.2 St. Petersburg, Florids 33733 racility ikss: Crystal P.ivar 3 Inspectica st: Crystsi P.ivar Site Crystal' River Florida Inspectica cenJu. tad: Jtma 12-15,1978 Inspcetorn R. 11. Ues. ss i4 iB. W. Riley U B. T. IBea ~ i r> K > P.2,-- Lw,.. - y /,. /7 F 3 app rov a t,y: pr11.C.Dancs, Chief 3 ;. .7,3 Data ~ Resctor Projects Sectica No/ 1.: :[ - ] Reactor Operations' and Nuclear Suppre Branch. _Inepeetion Su m ry i ~ i i Inswerien on June 12-15. 1970: (hoort M. M-302/70-16) j: Arcas Inspected: T.ctstins unannounced inspection of plant' cperations end h catege activictes; fc11ovup of licenses events; observatica of fuel E landlin:; activities end rcvic:a of docu :atecton; i=picenntation of 10 CFR 21 requircmantal verifiestica of ecnfor=nca to limiting safety c systen settings and liniting conditions for operation; cad facility P The inspectics involved 78 inspect;r-1ours ca-site by three EC ' ll t ou r. personnsl. Results: Of the six areas inspected cna itea of nonec pliance was ,) y identified in ens area (Deficiency - Failure to met postics require:'ents cf 10 CTR 21 (78-16-01)); and three itms of neaccuplicaco vera identified in ons ares: (Infraction - Failure to fo11cu procedural require.ents of a F.adiation Work Peruit (70-16-02); Infraction - Failure to establish ceasures to prevent uso of incorrect or defectivo catcrial (70-16-03); Infraction - Failure to teko adequato correceive action (73-16-04)). ~] , _W) y M k.t P &

  • n w s2nf

,e p t'V' EII Ept. !!o. 50-302/78-16 I-1 DETAII.S I Prepared by:Dt 7!u R. H. Wass:::an. Reactor Inspector Date Reactor Projects Section !*c. 1 Reacter Cporations and !*uelear Support Branch Dates of Inspection: ' June 12-15 '1978 Reviewed by: / . d k +. '*.., 3 ~!

.' H. C. Dance. Chief.

Date Reactor Projc:ts Seccion No. 1 Reactor Cptraticas,and Nuclear Support Ersach-y 1. Par ens Contiete'd \\' .n .b .l ^f

  • C. P. Esatty..Jr.,f ac.. lear' Plant Mans;or

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t
  • W. R. Nichols. Operatiens Superintendent:.
  • P. F. McKea. Technical Servicca Superintohhnt
  • J. C. Uright Ch:=istry/Radistics Frotectica Enginest,

~*V. R. Kleine Estctor Engincor: . ~, p4. '

  • J.' docpr. Ceupliahce E=gineer

?'

  • C., M. 'Willitas. Ceepliance Plant Engineer

~

  • C. R. Weseafer. !!aintenencm. Superintendent'
  • V. A. Cross.- Technical Speificatiens En;incer C. G. Coring., Planning Coordinator '

P. L. Breaux. Nuclear Shilt Supervisorc

5. W. Johnsen. Inservice Inspection T.cgineer -

J. d.1*urtz, lisintenance Engineer - ~ J. J. Patrich Plant Engineer ^- H. M. Ecbech Nuclear Shift Supervicor D. B. Et;;1eston, Chief Euclear Cyrator T. R. Zi=:22nck, Assistant Noelear;0perator ~ J. N. Ecssinger Cocpliance Auditor I. M. Erovn. Power Plant Clerk W. M. Duncan. Power Plant Clark ~

  • Denotes those persons at Exit Interview.

2. 1.icensee Action on Previous Inspection Findings

  • 1'
  • inspected.

3.. Unresolved Items

w None identified during this inspection.

\\ n i- ^ RII Ept. 16. 50-302/78-16 I-2 4. Exit Interview - 4 A neeting was held by R. !!. liessaen with C. P. Bostty, Jr., and mecbers of his staff on Jr.a 15. 1978. Itees covsred by the inspectica vere discussed, including the four nonec:pliance items speified in the follcuing paragraphs.; 5. 10 CFR Fart 21 Inspection - Theinspectorreviewedaportion'ofth$licensca'spro;rt.arelating to caeting 10 CTR Fart 21. toporting of Defects and ".onconpliance. Procedures revieved veros. 15.' Ccwplisndo uith IO C7a' Part 21', Pakorcirst of rofec'es_ N33 pwt 1%nce Mier.ce ' tdaconforming Operatiensa' ( C7-111. Procedura for to:ue.:nting the Repstein3 esd T.:nrics of t ] ~- Varioue portions of tha Quality I'acal

<+

a f...,* g r.- 2.. 1..~ i Tcp1hasatatica of various.cge. cts of the:s n c1:o'. 0-verified by ths' insp2ctor. V x? . ~ '..,..pctif nes u. ~ ' , _..K b 's, ' ' ' ' ' ' ~_ m.. n w. -, ;.;., e. " ', ? ' ~h r Q ~, hf %.

j..

Within the areas inspcte'd.'c:is' discre7sticy ess id:ntified. G5D-' a 15 requires thz posting of 10 CF2 21. C-tetica 205 of t';a racray _..j Raorganizatics Act of -1974 ca.d a copy of !!33D-13 ntfycricusl1.,, g,; ' j locaticas in. the Florids Povar Corportte syste% ;iheca doct:2:nts-were not posted, as required by 1135D-15, ot' ths Crystal Rivor ' site ' ] warehouse. This van identified es a C:ficichey in the !*ocica.of.- Violation (73-16-01). ~ In that corrective cetica was talen prior to the inspector's departura frca the cite this ites is censidered clotsd. 6. Failure to To11cv Frocedural Reviirceants of A Eadiation Work Feruit n. As part of a general revieJ.of'cutage activities,.the~ inspector reviewed selected portions of Chenrad Section less and radiation work perraits. Dr.e discrepincy was identified by the inspector in that procedural requirements of a radiation work permit (RWp) were not followed.

  • 'T e
  • .~o e

RII T,pt. No. 50-332/70-16 I-3 RP 105 Radiation Work Permic Procedure, establishes requircnents for the use cf tha E7 for work in creas requirin: cpacial radiological controls. Section 5.1.3 of RP 106 requires the Chentsd Coction to identify specific controls, as applicable, on the E7. E7 No. 73-1045 of Juna 5,1978, was issued for the " Investigation of FP.CR-45 Restriction cad Repair." nis E7 ctates that Chearsd vill provida continuous covarage when the divers era in the pool. At about 1800 on Juns 10,1973 (according to licenses records) divers were in the reactor buildins pool, undar the cus;1ces of this RL7, without Chenrad coverata. n is has been identified as en Infraction in the Notica ok Violation (70-16-02). .q 7. Dropped Uev Fool Elevator Test Walshe (f.E170431), ns inspcctor investicated the cir'eunstancss of the dropped new fuel elevator test vaishe which occurred at 1450 ca Juns 9,1978. This was reported to tha ICC at 1600 en Jens 9,1978.. R io event was the cecidental drop of a 2050-15. tast weight while noving it (cubrged) froc en up:nder to the fusi otorc;o rccks.. A pinut febricated crens heck fail:d, drcypina ths weight dich cay have =gp decoged feel ecoisly A-43 c:d pc:sibly bu:: ped fuel asse bliss A20 a and A34. 'Ifo rolcaea of radiumctivity feco tha fc?1 c.sacdlics had been identified byltha licences. Tha inspector's rcview included sc1cceed repair setivities to fusi handling equipncat' conducted during Esy and Juss 1978, the 11ccacco's.cetivities at the time of ~ the event's occurrence, and correctiva cetions taken cubsequent'to the event. The inspector interviewed 9eyaral members of jha liccasee's ~ staff as part of his review.S p, .,,] R ". ,L na inspector confir=sd that events occurred na described in I.ER 73-31 and that tha'11censee's' ir.=ediate response to the event was appropriate. Tvo discrepiticles vare identiflod which have been classified as Infractions in the notice of Violations a. (73-16-03) na heck used to lif t the 2050-1b. test weight in the spent fuel pool (adjacent to nuclear fuel assen.blies) was locally manufactured froa non-certified catorial, was not lor.d tested or qualified prior to use, and v s not tagged or marked as to the limitations on its use. The failure of this book while in use on June 9, 1973, contributed to the da sge to fuel assembly AAS. (? R

t c __ ~ ..m 1 T.II Kpt. No. 50-302/78-16 I-4 I The use of this hook was contrary to Critoria VIII end IIV of P Appendix 3 to 10 CTR Part 50. Criterien VIII to 10 CFa 50 Appendix B (Identification and Control cf mtarial Tcres, and [l Conponents) requires the establist:.cnt of teesures to prevent . i. the use of incorract or defectiva ratorial in caf:ty-ralated C activities. Criterien Xtv to 10 CER 50 Appucilx 3 (Inspection, Test, cnd Operating Status) requIrcs ths estdlichic.nt of I acisures, such as, tagging or r. arkin: to indic:.ta ths stetes of I inspoetion or tests en ecx;cacnts, to preclaJs their in hnetont These criteria cre inicncated, la p.re, by Ccction uns. i 1,7.6.7 (0paratica QA Progrcn) of the F1'4 cc.3 by ths licc=20's { Quality Prest:s Poli,cles 8,1 (Id:ntificatha cal Trecadility of Itc=s Used During tha 0;craticnal Phass):c5314.1 (In:;actica, L t Testi and Opctating Statss).3. 'T-2 f

c. ; S ~

1, p.: 3 f _., i,;, 7-b. (7f-16-04),0a Jena 11, 1978, two of ths pctenticily 4:222.4.. y fual assenblics sars in.dvertently cored prior to ths'cenpleta evalustien as to' the catant cl data;,oftSt esy havo be:21 t incurred by. tha,dec; ped nc.i fusi cIcratet cut vcic'2c. ArecS ly- ' A20 vaa ecved to tha resctor cera.cc.1 !2:=bly M3 vas essd:- twics within ths opant' fusi rool. Tbt:0 cctiscs cora'ecatrary '.~ '[? J " ~. x~~. to Criterich IVI'of Appendix Il to 10 Cra 50. Criter ba El coJ. 6 h 10 Cra 50 Appe'ndisc 3 (correctiva Actica) ettuir:2 tha estelisk: cat: ./ r of cessures to cacura conditien.2 cherca to 6 as defective estarial; cra prcaptly identified;ger,11ty, cc y cc:1 corrected. This critarica is inple= sated, ~1a pcre by Sectica 1.7.6.7. (O i (operation QA Program)~ of.ths FEAR, cad by tha Idcenseo'al - Quality Progres Precedura 16.50 (Cerrectira Actica for Operatiens I 6;' thano).

P The inspactor discus:ed the eb' ora ncnecceplicaces with ths licensca and reviewed tbs licensea's evaluation prop ~2 for tho effected fuel asemblies.

The criteris fer edditicati covenent of fual f r asacclies A20, A34, and A48 vera cotsblished by ths licces tha inspector. Portions of tho licensca's inepoction effort for fuel assemblies A34 and A48 vero vitnessed by tha inspector. 4 a ~ 8. Review of Safety Limits. Linitin,q Safety Systen C stting k and Limiting Conditions for Oparation w Tha inapactor reviewed selected plant records for tha Deceder 1977 - February 1978 period to deternine coepilanco (on a ae:spie basis) with Technical Specification requircaants for cafety li=its, + limiting safety systen settings, end limiting cenditions for L opera tion. Docurents reviewed vero J ~ O OF R

f R1*! n.t. f:s. 50-302/70-16 I-5 r SP 110, Tcactor Trotectiva Systen Tunctional' Tatin3 SP 303, Op: rating Daily Surveillanco Los. SP 320, 0;crzbility of Eoros Inlection Sources ced Pu:ps SP 321, Pouar Dietribution Ercakar Align = ant 'and Availebility ?' Veriftention ?-hC j7 ,y g-Within the cress inspected no discrepancies vers identified bd D't, 9. Observatten of fuel l'andlint Activ_ities - [ ~ .x ,,Ah The inspector cb crv 3 portions of the raft: lins activitics occurring in ths Spsnt Tc:1 Cuilding, ths Reactor faildit, c.4 tha 4 Control 2o0=. Cenplinnea with Techniesl Specificarica r @irecento' > h and procedural ccatrols of F?-203. Dafu: ling l m3 Jafuelica C y reticas, '. vas verified.. Hinst procedural discrepsactes esta discu:::d with M ' @L 1 IIcenses parccnnal'., Vicusi,tochniq6cs in foal hindlin3 veri. - y#" l improved upea 1.~/ crentatica of ~ ~ths ; inspector's as a:tica of 'usin3 ', L' sc a li;ht in tha reactor, vessel. ' Tha'insp: tor'and tha 11cinico y, * '. < M[d! discussed a procedurel chen~;( tisestien 5.22 'of FP'203 thich M.' /. allcus chance 8 to..the. approved feeling cdq*icaceNbal:!:,!s by thi 76 Refuslins consultrat.., Thaintest 'oflthis cEtsy una to oUcu uf.c:rs W s:quence chem;cs (cuchlcs'attirnato' carrica c3adr."Esakse".I ' 'd. stven coro location to facilitate cesting a fc1 cas.51yT.: tw: var. . '~ y$ tha cheated SecticaL5.22,fes writ. tan, uculd c11 cwa ccapletafciqedca: , O f h% change %Ithout c2ns; : int involveh:nt.. *Tho -licen cs i reed eMt - ~, " - ? - Ni review this portion of FP 203fto'pecvido" controlling ~Euidanco for

  1. b.Y

.e-t. m the f.efcoling Con:ultr.st.~.f* Q ; P W E i ys a'. ?..., ? i;;'"i i 1- - Q[ t I" .s; ,s'~ C- ,y - *..'.,*s, Within the areas inepected r.o disc, r _epencies, car.e identifiedd. }.w.;. l!rf+...,

f..,,

s Z .y..;.S... z ' '. .: w ~ . ' a:s.- . ;Mg m.. p. p ~ ' ? b, zy'fp f g 10. Inservice inspectica_Activitt <3 f ,u ;w n The insrector revicued uith licensca 'paroonnst a jartion of,inhervics !Q inspection docu:,entation generated duric; this outage..Tha'11censee Z has been conducting aca-destructivo examinstica of vsrtous valds' in' ' ' y accordance with Technical Spelfication 4.0.5 and rection XI of the j4 ASitE Eo11er cnd Pressure Vessel Ccda requiremato.. C" .r3 The 11censeo, has identified two discrepnetes requirins corrective T. ,e sction. Radiographic exasinscion of v31d.Po. f*d107A on the. feed. 5y line to the "A" OTSG revealed a elon sted 11odt indiestion'sbeut, - 7. 3/8" - long. This h.as been identified as a possible ~ crack or lack f.W of fusion. The licensee plans a weld repair cad a hydro:tstic k.M test. A second indication (about 5/8" by 3/6") has been identified Q in the base natal adjacent to a veld in,the emargency fee 4 vater NM header to the "B" OTSG. Thickness sicasurements have verified tha g nets 1 is thinner than the ASnt standard. The licensee plans to gh veld a pad on this ptpa and conduct non-destructive testing. The %j@ inspector had no additional cc:went concerning the licensco's p progrca in,this area..~- '? ~ ~ n M Th 'E 'q _ PYM }g 7Wf f 'f* F * *?****,;* r*****'St= 9*W-R,-..yec ( -, - yes, p.es. eggp se--- +g. m. +: <,n,e 4

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i [ L F - b RII Report No. 50-302/78-21 I-5 g. (Closed) Deficiency 75-10-01 (Paragraph 6 to RII Rpt. 78-10): [' I. ate Submittal of Monthly Operating Report. The licensee has ,i' established a tickler system to assure sub=ittal of this report .2 within Technical Specification tine limits. No other late reports b ',., have occurred. This item is closed. IlS r'. (Open) Unresolved Ites 78-10-02 (Paragraph 13 of RII Ept. 78-10): 1 Cleaner Used in Ultrasonic Sink. This ites concerns the accepta-Lility for nuclear application of the cleaner currently in use. Q[.;pd E The licensee has not received certification as to this cleaner's " KJ.l',. acceptablility. a W;r Mgy; s. (open) Unresolved Item 75-10-03 (Paragraph 13 of RII Ept. No. c;(7 l,; 78-10): Deconta:ination Procedures. This ites related to three . i< activities that were not addressed by facility decontamination i procedures. Although the licensee is writing specific decontani-untion instructions for safety-related items (en a case basis), , %j "Els. this unresolved ites has not been addressed. This itca rensins ? open. ,',., 4 R(:mw[ , Moced) Outstanding Item 78-10-04 (Paragraph 7 of RII Ept. t. i -10): Additional Inspector Review of Fuel and Reactor Internals 3# Data. Based upon the inspector's continued inspection of outage 4$.@ and core reload activities, as documentated in RII Rpt 78-16 and M@ this report, this is ites is closed. D 7. ".. s. e 4 '.i .a 7'f$.'- $,n;f.'l.*l A

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e = I e% o @$Ji \\ % n.gw > STATE OF NEW YCHK EXECUTIVE DEPARTMENT STATE CONSUMER PROTECTION BOARD 99 WA SHINGTON AV LNUE. AL B ANY, NEW YORK 12210 M A REN 5. BURSTEIN November 1, 1982 unuTY iNuavE~on uNif c.*ata amo e n tc utive ospe cion ".. c4 ws FREEDOM OF INFORMATION ACT REQUES F o r g g a _T Mr. Joseph Felton Di c r, Mvision of Rules g Freedom of Information Act Office Q h // ~ y g g U.S. Nuclear Regulatory Commission 1717 H.

Street, N.W.

Washington, D.C. 20555 Re: FREEDOM OF INFORMATION ACT REQUEST Mr. Felton: Pursuant to 5 U.S.C.A.S552, the New York State Consumer Protection Board, Ms. Karen S. Burstein, and David A. Schlissel hereby request that the records listed below be made available-for iinmediate public inspection and copying. As the documents will be used by the Consumer Protection Board in Public Service Commission Case 28166 on behalf of the interests of the ratepayers of the Rochester Gas & Electric Corporation, we request that all fees be waived pursuant to 5 U.S.C. AS552 (4) (A) and lo C.F.R. 59.14 (a). Public Service Commission Case 28166 concerns the accident at the R.E. Ginna Nuclear Facility last January and will decide who should pay for excess fuel and purchased power costs, ratepayers or stockholders of RG&E. The documents sought in-this request will be used as part of cross-examination and direct testimony filed by the staff of the Consumer Protection Board on behalf of RG&E ratepayers. We request a substantive reply to this Freedom of Information Act Request within 10 working days. 5 U.S.C. A.S552 (6) (A) and 10 C.F.R. 9.8(c). This Freedom of Information Act Request seeks access to the following documents for inspection and copying: ) ) y d o19 ('{I y .s*

1. Copies of all reports, memoranda, correspondence, or other documents, records, or work products, identifying, listing, discussing, analyzing, suggesting, recommending, or reporting the procedures used for the downcomer flow resistance plate removal modifications at the following facilities: Turkey Point Unit 4 in May, 1975; Robinson Unit 2 in November, 1975; Turkey Point Unit 3 in November-December, 1975; Indian Point 3 and Point Beach Units 1 and 2 in 1976. This' request includes, but is not limited to all reports, memoranda, correspondence, or other documents, records or work products, identifying, listing, discussing, recommending i or reporting the quality assurance procedures and/or the procedures for material accountability used during those removal modifications. (' ASH 1283) and the Orange Book 2. A copy of the Gray Book W (WASH 1284) in effect in April, 1975. 3. Copies of any technical information letters, advisories, alerts, reports, studies, analyses, or other correspondence, documents, records, or work products, distributed to the Rochester Gas & Electric Corporation and/or any other owner or operator of a pressurized water reactor facility, by the NRC or NRC personnel (as that term is defined in 10 C.F.R.S9.3a) concerning any of the following events: The October, 1979 steam generator tube rupture at the Prairie Island 1 facility; The September, 1976 tube rupture at the Surry 2 facility; The 1979 discovery of loose parts in a steam generator at the North Anna 1 facility; The February, 1980 discovery of loose parts in a steam generator at the North Anna 1 facility; The March, 1978 discovery of loose parts at the Crystal River 3 facility; The July, 1977 discovery of loose parts at the Davis-Besse 1 facility.

4. Provide copies of any technical information letters, advisories, alerts, reports, studies, analyses, or other correspondence, documents, records, or other work products distributed to the Rochester Gas & Electric Corporation since January 1, 1975 from the NRC or NRC personnel advising, recommending, suggesting, or discussing the need for inspection for the presence of foreign objects or loose parts inside steam generators. 5. With regard to page 5-47 of the Ginna Restart Safety Evaluation Report (NUREG 0916), provide copies of any reports, studies, analyses, or other correspondence, documents, records, or work products, prepared by the NRC, NRC personnel, the Rochester Gas & Electric Corporation, or the Westinghouse Corporation, their agents or employees, which were developed or used in arriving at, and/or are in support of, the conclusion that " Material accountability controls in use during the 1975 downcomer resistance plate removal modification were ineffective in detecting the presence of foreign material located in the secondary side of the steam generators." Provide copies of any such corresponde~nce, documents, records, or work products for each of the four specific deficiencies identified on page 5-47 immediately following the statement quoted above. 6. With regard to the statement of page 5-22 of NUREG 0916 that "Many of these features are suggestive of a mechanical or peening-like action on the surface of the tube such as might be cause by a foreign object", provide copies of any correspondence, documents, records, or other work products which were developed or used in arriving at, and/or are in support of, this statement. Please also provide copies of any studies, reports, analyses, correspondence, documents, records, or other work products prepared by the NRC consultant identified in that same paragraph on page 5-22 of NUREG 0916. 7. With regard to the statement on page 5-12 of NUREG 0916 that "This peripheral pattern of tube degradation is not typical of the corrosion problems which have been experienced by the industry" and the statement on page 5-9 of NUREG 0916 that "With the exception of tube degradation at the periphery of the hot-leg in B-steam generator..." provide copies of any studies, reports, analyses, correspondence, documents, records or other work products prepared since April 1, 1975 by the NRC, NRC personnel, RG&E, or Westinghouse Corporation, their agents or employees, which identify, indicate or discuss in what manner the tube degradation was not typical of that experienced by the industry and/or which identify, indicate, analyze, study or discuss possible causes for this atypical degradation.

On behalf of the State Consumer Protection Board, Ms. .Burstein and myself, I would like to thank you in advance for your prompt attention to this request. Sincerely, . d*:t l .u David A. Schlissel, Of Counsel t '1 l l l i l l l .}}

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