ML20024C730

Forwards Summary & Comments on B&W Operating Seminar.Notes Finalized 790327,1 Day Prior to Accident.No Attempt at Update Made,Nor Have Notes Been Distributed Previously

ML20024C730
Person / Time
Site:	Crane
Issue date:	04/24/1979
From:	Seelinger J METROPOLITAN EDISON CO.
To:	Herbein J, Geoffrey Miller METROPOLITAN EDISON CO.
References
TASK-03, TASK-3, TASK-GB GPU-0394, GPU-394, NUDOCS 8307130146
Download: ML20024C730 (14)

Text

{{#Wiki_filter:, l i .q w W ;t ) y~[ 3 -{1 METROPOUTAN EDISON COMPAN Y a.e.,,, % = u,,,,,,,, t, 4 a j W B&W OPERATING SEMINAL MARCH 18-20, 1979 { 14EI SUENA VISTA FLCEIDA Lassties THI-I Nuclear Stat: Middletown. Fa. 17( g To Den J. C. EERREIN 24 April 1979 i C. F. MILLER 1 Enc 1: (1) Detailed Notes and Action Items 1 (2) List of A:tendees l. 1. D2 closures (1) and (2) are forwarded. 2. Personscopiedtakeaccianindicated. e nm . L. SEELINCFR ( Unit 1 Superintendent k JL3 mt l ses E. L. Basey J.B. Logan D. ((,f't.))

1. O.,3arle7 W. J. Marshall W.

1. W. Bensel T. O. Orleadi l

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AND CCHMENTS ON MY ATTENDANCE AT TEZ B&W OPERATING SENINAR I. John McMillan opened the Seminar with a brief introduction and description of the purpose of tha meeting and the R&U organisation. II.' Andy Hines, President of Florida Power Corp., then gave a brief introduction and welcoes to Florida sad the Crystal River site. III. Bernable Poison Red Problem Larry Tittle Florida Power Corporation The indications of the problem were an unaspected 71 t.ilt, which went avsy when the zenon egualised, makeup filters rapidly depleting and short lived loose parts elers. In retrospect Florida Power had so definitive indication that there was a problem votil a loud noise with significant impact la the steam generator was continuously heard. A tape recording of the impact noise was played for the group..Itema to come out of Florida Power's review of this incident were: (1). A tilt monito ing, program which is useful La early detection of , power anomalies -(2) a loose parts monitoring program following proposed Reg. Guide . 2 1.133; and ? (3) the fact that activated almine is so short lived that reliance en finding this isotope la the makeup filters is improbable. An additional itam-to come out of this is that Florida Power feels that reliance on a single computer system for incore detector analysis is not advisable ,..j: and a backup system with a mini-computer is advisable. further investigated. This should be. .n. ACTION:

• Uayne Barris investigate and propose TMZ action to Seelinger by IT.

Systes Modifications to support Unit Operation with a Primary to Secondary task Jim Barrison Florida Power Corporaties - .~l k*k.". hr'ysta River's & Ste'am"Gener tor is le e 'i,"ma i ude 't5ano e . *b . eek '9 J,'.YQ *N.{ss11oa 'per' day. *-3ts'ildentiffcation. at this" time *ls.usksoen,' howey~e'; it.is ,,,possibly from a,saal w' eld on the steam generator head., Items which should, j % r, be considered relative to'TMI for contingency la the case of having to ' operate with a primary to secondary leak ares (1) Coating the basement of the Turbine Bull' dias' with special paint sealant.to avoid absorbefon of radioactive nucleide into the concrete la the event of leak or spilla ,(2) construction of dans or harriers around sumpe.and around equipment' I which could become contasiasted should the Turbine Building basement ~ become flooded with water e e o k I

e I. ,, 9 ...4 9,, M.',*g, *., a p a ,. 7 (3) the piping of outside tank overflow lines back to the Turbine Building sump to prevent these overflow lines being discharged to the ground; and (4) piping of the vacuum pump discharge to the Auxiliary Building enhaust header. It should be noted that modifications at Crystal River to combat the situat$on cost approximotely ena-half million dollars. .ACTIOWs.Ed Fuhrer investigate, propose TMI action by .Y. Dry Cleaning Protective Clothing and Equipsent Greg Ferkina Florida Power Corporation During their steam generscor outage Crystal River used a portable dry cleaner as opposed to Isundering clothing with wet laundry. The'y found the dry cleaner to be very successful. With the dry cleaner they were able to signifi-cantly reduce the inventory of clothing they needed to maintain on band, and they did not need to. deal with off-site transportation or an off-site ver. dor. They t' educed handling and monitoring, and better atilised their manpower. In - additio'n to this, they saw increased garment life and finally saw the ability to clean things other than cloth garments, such as rubber, welcro and plastica. They were also able to get en increased decontamination factor with the dry cleaning method. Crystal River experienced some problems af ter respirators were laundered in that the lenses became scratched. However, they did devise a method to get around this by padding the inside of the dry cleaning equipment.. Crystal River has established a lease by option on their dry cleaning equipment and further has built a small Butler building to contain the equipment. Construction of this building was necessary because of the freon which exhausta from the building. Crystal River performed a cost benefit analysis on the dry cleaning of cont =(nated clothing and came up with the following botton 11aet (1) To wet launder protective clothing on site at the rate of 300. pairs per day for a six week outage would cost $103.000. (2) to have a vendor on site to perform the dry cleaning function with his own equipment would cost $36,000. (3) to perform dry cleaning in house with their people for a sia . week outage would cost under $25,000. -> 1-Q *$$.,h.i 2 ~.. ~Akiys ~'"!*w'.*.~... .n.** O ~ % -- C :s L W,.:%? 'Diek 'DubIe1'inUet1 ~te'*s'af.'pr'ohose,'TKI. action'by '- E Q p yACTTCN: .y .$M[.M,", -N.I" h. -k. [.h..*a . s....

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s.;; .2.m) 1% ,2 7 YI. 1978 Cperations Jim Phinney a Babcock and Vilcoz TMI-I remains the unit with the highest capacity factor of 76.3%. It is followed by Oconee III with capacity factor of 69.7Z. In third placs is Arkansas with 63.3%. Average breaker to breaker refueling outage rime

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t for B&W units is now 48 days. Rancho Seco set the record for a tsfueling outage for 34W units in 1978 of 36 days. Specific problems experienced by the varioua 34V uni'te during the year 1978 were as follows: Oconee I Failed CRD stators Feedwater Esater repairs Steen Generator tube plugging difficulties, Fuel Bandling ' equipment difficulties, and Steam Generator tube pulling problems. ^ Oconee II ' Failed CED stators, steam Cenera' tor tube leaks, laaking pressuriser relief block valves, Reactor Coolant pump seal' problems, inoperable rod, stuck incore detector assemblies, a stuck Reactor Vessel Read closure stud, Fuel Bandling equipment difficulties and a damaged Reactor Yessel internal vent valve. Oconee III Leaking Core Flood tank valves and le king Feedwater check valves. TMI-I Besctor Coolant Pump seal problem, ABO *I Law pressure turbine rotor, turbina goverror valve reassembly problems, failure of an LYDT for the main turbine generator, turbine blade problems. It should be noted tbst Unit II should look into this last oroblem. 1 AcT1ous Don 3erry investigate and report to Logan. takchoSeco Fertial loss of Non-Nuclear Instr uentation, turbine oil pressure problem, leaking code relief valves, failed CRD etators, Fuel Bandling equipment problems and Core Internal valve problems. Crystal'11ver Burnable poison rod ' problems, repair the steam generster as a result of burnable poison rod problems. Fuel Eaadling - problems and a dummy weight belas dropped on three fuel assemblies.. Davis Besse Loss of Feedwater pumps, radiation monitor repairs, orifice rod and burnable poison rod problems, reactor coolant

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~ " * ' ' Generic conclusions which can be drawn from thil presentation are that problems will probably continue with CRD mechanisms which have been wetted and Fuel Bandling equipment will also experience problems. One area for possible significant improvement is in operator and maintenance training such that human error can be significantly decreased. THI-I should devise a positive t

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i l 1 k i i 1 i ? ._~ 994.,a% g I program to do this, and 'in particular shou'1d look at those evolutions which are infrequently performed and have the potential for causing the greatest disaster. A good example would be tMI-I's recent overfilling'of the geactor Coolant system. ACTION: Mike Ross formulate a plan of action for crew briefings os major evolutions. At the end of Jim Phinney's presentation, a guestion was asked relative to TMI-I's high reliability and good operating record. Jim Phinney's. answer, I. feel, hit the nail on the head. Es answered TMI-I does a very good job of outage planning and Dt1 does a very good job of contingency planning, that is, being ready for the unexpected. VII. Fuel Performance Update Jim Telesko .f_ Babcock and Wilcos t k-Axial r $baping rods were removed during the cycle 3 design of Ranchai Seco( This produced a savings which is estimated at $300,000 in terms of fuel' costs. Three MW plants are going to 18 henth fuel cycles, ANO-I and Oconee I & II. THI-I should closely look it the 18 month f.ael cycle prcgram ar.d make a determination whether it should go to an 18 month cycle as well. Durin's 1978 step changes in quadrant power tilt occurred at Oconee I & III and ANO I and Rancho Seco. R&W analysis showed that this effect came from ? variations of taactor Coolant system flow or camperature. The cause of tbs J. RP1 and OgA problem was presented and the respective control component floati~g in the varioss flow combinations was given as the reason for the p wear.,, N W is working on the design of an improved high burnout fuel assembly with the Department of Caergy and Arkansas Power and Light. One such-assembly is due to be inserted during AJto's Cycle 5, which is scheduled 4 . for operation in November of 1980. The following items are is various stages of study and completion at MW extended fuel cycles, increased batch burnup AFSR removal, a low leakage burnable poison shuffle scheme,. a low. absorption spacer grid using sine vice inconal and reduced fuel pin diameter called a wet lattice modification. Fuel savings on the order of $1,000.000 to $1,500,000 per year are estimated to be possible for units which fully implement all t(e J4W fuel utilisation programs, once these ......m . pioirans are' fully developed.2.0t' er' items to come out of Telenko's presentar,"

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h c.g(og/were th'at the radio' chemistry.co TMI-I shuwed that all the les!.ing e-w*Y n=*-

1. fueTTins',should b' ave kee~n,1redaced,during this pait"1rdfuIsling outage.

MW estimates this number'o( pins to have been 18. During fuel fabricatios 7 ' *', the fuel is now put through an additional drying process and the gas pressure f inside the fuel has increased by 100 pounds. At oparating temperature this decreases clad pellet interaction. Based on new studies on ovelling, control rods can now stay in for 10 cycles of operation. Het Ed has been notified. Duke Fower has made some estimates relative to going to an 18 month fuel cycle which are relevent. One ites that Duke uses in their estimating is ' i 1

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= I 1 i: 1 i the fact that they figare 250 man days per day for labor during a refueling Further itema which they have consideres are the man rem exposure outage. during an outage, licensing implications and storage space for the fuel. ACTION: Bill Fotts monitor 18 month cycles of other R&V units by maintaining contact and long term update TMI's evaluation of 18 monta cycle. VIII. Availability Improvement Programs Don Roy Babcock & U11cos i steam generator tube leaks were discussed next. In 1978 of the 15 leaka which were experienced, all occurred at Oconee. Nine of these were in Oconee I,14 were in the 5 Steam Cenerator,13 occurred in the upper tube sheet or on top of the 15th support place along the open lanes. Steam generator anomalies and failures were discussed in general. On the upper span and open lane, the failures appear to be circumferential cracks at the lower side of the upper tube sheet and at the 15th support place. It is felt they Laitiate from a combination of corrosion and fatigua. The corrosion is possibly due to a concentration of moisture droplats which travel up the open lane. 14th Tube Support Plates - There have been perifery Eddy Current indications in tubes in the area of the 14th tube support plates. Most appear to be associated with debris accumulation. i 9th and 10th Support Plates - These have chiefly been seen in Oconee I as well and appear to be the result of tube deformation rather than metal loss or cracks. They appear to correlate with the location of wedges between the tube support plate and the cylinderical shroud. 1,ower tube sheet banana indicacions have been seen by Eddy Current and appear to be related to deposits and are not necessarily correlatable to defects. Tests are underway to determine what effect is 'being seen in the upper tube sheet area. There is hope of determining the initiating mechanism for the circumferential cracks. Design of lane flow blockers to keep moisture out of the open lane is under.way. Internal sleeves to stiffen the tubes

• a are in service on two units. Preliminary results from the THI-II instrument-scion program appear to correlate to the program undertaken at Oconee II.

Pressure oscillations can be dampened by adjustment of the steam generator orifice plate. Another item which was briefly covered was fuel handling l problema.. It was mentioned that a cable drive concept in transfer mechanisms should be ready for prototype installation by the middle of 1979.

Further, Oconee will install a malti-function mast lata in 1979.

ACTION: Ross consider sending a TM1 representative to Oconee to witness operation.. M 6e .m* .ase G , Se em me em em me em o I 4

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11. Availab(11ty Improvement Programa Frank Fahland Babcock & Wi!com teactor Coetant pump motor oil level problems have been experienced.

Some of these involve leskage and MW is sending a representative to the units to look into these problems. It should be noted that someone came to TMI during the past refueling to loos at this problem. B&W recomends continuous monitoring of teactor Coolant Fump seal parameters. B&W is currently recommending the installation of an on-line performance analyser for all teactor Coolant pumps. This analyzer would continuously monitor Reactor Coolaat pumps seal instrumentation and calculate and dispaly performance parameters as well as alarming when limits are exceeded. It was not clear whether S&W was marketing this type of analyser or if such a monitor is available. This should be investigated with 34W. ACTION. W. E. potts investigate. Two very real items with respect to reactor coolant pump seal performance were strongly reconnended by B&W. They included detailed procedures for sesembly and installation and training for Operators on the operational limits.. purposes and precautions with respect to reactor coolant pump seals. With respect to the procedures which should be used for reactor coolant seal replace eat, the "as left" dimensions should be recorded. ACTION: W. E. Potts review and insure our procedure is adequate. ACTION: M. L. Beers add more detailed course on seals to regual program. "As lef t" settings on the reactor coolant pump seals should be closely reviewed by engineerios personnel to insure that proper inacallation of the seals occurred. ACTION: W. E. Potts insure that this happeas. Control Red Drive Mechanisms - During 1978 the last of the epoxy stators were replaced by isrnished stators. 34W has concluded that there are two major causes of the cad stator failures. One is moisture, the second is temperature. With respect to the temperature, thermocouples should monitor the temperature on the service structure and be set to alarm when this 8 temperature is high. ACTION: W.1. Potts confirm DtI-1 adequately alarmed. Additiona'11y. with respect to temperature, there should be an interl'ock between the Intermediate Coolin6 system and the CID stators, such that stators can not be energised without intermediate cooling flow to the stators. TMI-II should be updated to include thia modification. ACTION: l C. A. Eunder update to include this modification .+ l ~ i l 1 ) n... - -.

x ~ O ~ .p. 1 / i Y ~ j s i / i I y With respect to moisture, ethylen'eorspolane 0-Tings should.be replaced'wiin silicon o-rings. It should be naced this nWification is presently being Jaccomplished on TMI-I as a stault of the watar'probi m co the stacore. It was pointed out ahat once se,ato.-" have teemie wet, theyasnally respond well after a drying procedu.'e, whi:h dries the moistura out absorbed by the insulation. Bovever, it. was also pointed out,that the Gamage done to the insulation is not totally ra nraible since the preseetc of water causes a breakdown of icrulation ca the coil winding wies. It was stated that stators having indications of cresiderable taoisture expousra, which include corrosion, low insulation resistance, and chemical deposits should be replaced. Further modif t:stionis which sho41d be considered are flexiMa stator cooling lines, quick disconnecte, and the installation of the 6ew venting assembly. ~ s ACTION: U. E. Frcze investigaca for'ThI-I. One CCg3 ites whb ~was disivened was reed rwitch failures on position indicato-a.- It was stated that a filra Wilds up on the reed switches s arh that although the reed switches maintafo me hanical contact they do. so make electrical contact. A procer!ure has been developed and will soon, be issued to the field to correce enia probles. Basically the procedure vill say to put a higher than normal current to the positi_on indicarar With tends to burn this film off the reed switch contacts. ' S&W stated r. hat a?.y stators which need to Le replacet should be replaced by monofilar wound stators. q ACMCM: 14e Rogers steh this available to TMI., The presentacion by 'Mr. Fahland which is summaariasd in kataileJ p.cacocation notes, included an extensive discussi_ a of fu.s! hanellag syste:s 7toblurns. s While the spee8,fic fizes will not be Jiacusse.1 in these cotes, a quick suammary of the probiens will be. Th47 include drivs' and aligtrisat problems, limit switch reliab*lity problems,' Inasequata unter air supply, tratishe tube cover leaks, emergency disengage problems, voar through of dissagage pies, gate valve bushings, slippage of guide rullers, control red speed. .dillon load power problems and calibration problems, fuel grapple disengage bi/ro, improperly adjusted hydraulic pump relief ralves and selsen slippage. Raplacement of 3Y transmitterg with BQ transinittars was briefly discussed, so was the gate drive modification for t% control rod drive system. r~ i I. (714nt chemistry Update ' M r1 Boll 3docock and Wilcom .Hn1 reviewed the differences between the secondary configurations of many s of the plants, and the type of s x densate polishing systems used at tbs reepective plants. We discussed the program entered into at Arkansas for t,he upgrade of feedwater chemistry and stated that one of che iignificant . problems found was that Ste pipias configuration did not t.pticalze sampling - nor'did it give a true reptstantation of Wat was being ftd into the sesom generators. One potential recmanendettor, es coas from tierl's coements' included steam senerate 'slw-dows lines bebt routed to the condenser e . g. -.= mar ---6--- 4 h U l 'c ~

g f ~ t' vice routed to a drain system. In this way, water could be reclaimed rather than be treated as contaminated or secondary weste for processing. ACTION: Dick Dubiel investigate for TMI. II. At the start of the second day, Doo Bay briefly discussed some problems which had been experienced with incore detectors. These involved certain ) i incores being broken off when they were being extracted at Oconee. The - problem involves restrictions at the radius of the bend whers the incores go into the reactor vessel. 34W is in the process of building a special underwater profilometer to map the incore tube restrictions. 34W has fa.rther determined re*ative to electrical problema on intores, that the aluminum oxide used to make the detectors varies in dialectric properties. B&W has been working to get this insulating material to meet proper specifications. Approximately 3.5I of the incores have been failing. Of this 3.51 failures, approximately 21 are attributed to connector failures. Multi-detector failures in a single assembly cppear to be due to the incursion of water through the sheath. It is felt that this is typically due to manufacturing defects. III. Startu'ps Bill Spangler Babcock and Wilcos l It was brought out that Davis Sasse is the first 3&W reactor with a " raise-of-loop" configuration. " Raised loop" means that the base of the steam generator is at the approximate elevation of the reactor coolant outlet piping. The THI-II flow problem was also discussed and 36W talked about looking at elinisating the flus flow trip and eliminsting the rod how penalty as methods of further working on this particular problem. It should be noted that both TMI-II and Davis lesse I had 170 days of down time in 1978 post fuel load. Of these 170 days, 87 days at THI-II sad 88 days at Davis Besse I were due to design problems. Next fuel leads scheduled for B&W plants are Consumers in the fall of 1980, Bellefonte in the spring of 1981 and UFFS in 1983. ( IIII. Befueling Performance Dick Newcomb , l Babcock & Wilcox The following outage times were set la 1978: f tancho seco 36 days l Oconee III 39 days l TMI-I A4 days Average outages in 1978 included 2,000 activities, 150,000 manhours, 4,000 manhours of pre-outage planning, augmentation of normal staffs by 200 people, 220 saareas of exposure, and an average cost of $5,000,000. l .Mighlights follow l .g.' t

g .y. = j e 3 i* 20 Low p'ressure A Turbine rotor replacement, plugging 5 tubes in the steam generator, errors made in turbine generator governor valve resssembly, high chloridee in the reactor coolant systas due to a breakdova in demineraliser resins, and a fire in the diesel generator turbo-charger. It should be noted that ANO used A113 for laservice inspection. THI-I Folar Crane problems rad leakage C.*?ough the high pressure 5 talection valve. OC0entEZ III A centralised outage p1maning function was added during their 1978 refuelang.. OC0itNEE I Staan generator t'.be plugging difficulties, rad waste difficulties which resulted in the reactor building basement being flooded. malfunctions in Fuel Handling equipment. OColorE1 11 stuck intore detectors, reactor vessel internal vent valve problems, stuck reactor vessel stud. EsWD Fuel Randling equipment difficulties, handliog coutrol components with a manual tool, vent valve renova 1, inspectira and repair. IIV. M W Spare Parts System Howard Stevens Sabcock and Wilcos M W has established a parts distribution center in Lynchburg, Va. This was established in late 1977, and looks as if it has the ability to help us significantly. spare parts which are evilable to the customer en both a routine and anThe p energency basis. the apare parts and even with M W's markup, parts could still come to saThe p cheaper than individual psrchases. Another function of the parts center is to insure that proper marking is accomplished and proper packaging of parts is accomplished. are scheduled to includesFuture activittee performed by this parts center 1. A cooperative stocking with MW utilities, specifically related to ~ , improving availability. The concept behind this is that parts in utilities participaties.the center, that is selected parts, could be jointly owned by the 2. grecial quality assurance testing or non destructive Mr.'Stev e s made the comment that ehe inventory maintainsd by the Nuclear what type of spare parts MW maintains in stock. Parts Center would be made av It looks like this particular area has the ability to save Het Ed significant dollars in terms of both the inventory and in terms of reliable operation. insure that we get a copy of MW's inventory and that we work with MW We should g. ~ - - - ~ ~~ e 2 -~--"

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s e = i 3 6 1 I as necessary and other cuatomera to jointly purchase selected long lead g time items. Our Materials Management group should review the details of this presentatios in the formal notes. g ACTION E. L. Saney IV. Technical Support Services Bob Wascher i Babcock and Wilcos This discussion included such trema as the availability improvement programa that are being discussed with the various utilities, positive feedback and preliminary probles analysia by the RADCA.S system, and items being undertaken by the Cwners Group and the Users Group and various subcommittees of these groups. Other items which were discuoted was the fact that sia 'B&W units have demonstrated the ability ta separate from the grid without a trip of the reactor. Finally it was ment!.oned that Crystal River is unJergoing the engineering to get a power upgrade from 2452 segawats thermal to 2544 messwats thermal. XVI. Fanet Discusalon Jim Fhinney, MW, Manager Operating Flant Services Paul McKee, Crystal River. Technical Superintendent Terry Murray, Davis Besse. Superintendent Fierre Oubre. Rancho seco, Superintendent John McMillen. MV, Vice* Fres., RFCD Enrold Tucker. Duke, Manager Nuclear Freiuction Div. Jim Seelinger. DtI, Unit I Superintendent Jim O'Hanlon, ANO, General Manager Don Roy, M W, Manager Engineering John McMillan opened the discussion by asking for spontaneous remarks from each of the varioua Seuperintendent. J. O'Raalon opened the discussion by saying that he had really no specific remarks in that he had been at Arkansas such a short time. J. Seelinger then delivered some remarks relative to outage planning and cantiaguency planning. Jim went through some of the refueling outage areas whick are used and defined at TMI, how pre-refueling outage meetinds are conducted and how seatings are conducted during the refueling outage. Jim also went t5 rough some specific emaaples of continguency planning that are used at THI. These included such things as how fuel band 11ag probleno are anticipated by having Stearns representa'cives on ' site during the fuel handling evolutions, how THI proceeded with respect to anubber operating fluid temperature problems, and how THI sends operators to the simulator every Further, Jim sede saae remarks relative to the success TMI has year. experienced with the MW on site'aupport tese, stating thtt tho team, in addition to givies specific coverage during the normal year and refuelias i outages in given areas, also provides an objective independent view of plaat { S e ee ~ s i

o l operations and maintanance with availability and espacity Larrovement as the goal. E41 Tucker of Duke Power discussed the transition of people at oconee where I dVery two to three years 0 cones lossa 25% of their staff in order to staff the other nuclear stations : bat are being constructed and started up La the Duke system. Ea1 also mentioned that Duke's reliance on S&W is slightly 1ess than some of the other utilities, based on thel' own in-house experience la that they have now been through 10 refueling outages. Pierre cubre delivered some remarks with roepect to productivi:y aLd his frustration that productivitiy is so adversely affected by some of the new regulator.y requirements. These included the security requirements and new Fire Protection Tech. Specs. and surycillances required by these Tech. Specs. Pierre mentionsd that his engineers are so busy writing reports that they do not get out into the plant to observe the plant and track the plants' operation with an idea of looking for increased reliability and anticipating equipment failure. Pierre also mentioned that being on a dry land site he uses from 6 to 7 people just to comply with the Environmental Tech. Specs. Terry Murray of Toledo Edison echoed the sana type of comments and frustrations as Pierre Dubre. Faul McEse of Florida Power in his introductory' remarks mentioned the difficulty they have with sea water sa circulating water for their condenser and the recent dif ficulties they have arperienced with seal failures and wear ring failures in Decay Beat pumps. Questions were then opened to the floor. The first guestion that was posed was, has critical path time over been used to clean up the fuel transfer canalf ,JLa Seelinger answered this guestion by talking about the recent problema asperienced by Met Ed with the clarity of the water in the fuel transfer canal. SMUD mentioned that they had installed a special filtration system which has worked, not so much for elarifying the water, but for significantly reducing the level of radioactivity within the water and the residual radio-activity lef t on the walls and floors of the fuel transfer canal af ter the ' fuel transfer canal was drained. This should be further investigated by TMI. ACTION: Mike Ross lavestigate by Ed Seith from the audience mentioned that Duke had used critical path tLas for cleaning the fuel transfer canal. the question was asked on the number of tubes inspected in Eddy Current testing. Seelinger and Fhinney responded with the number being inspected this year on TMI and why that number was what it was. 11 , ggggg , es., g g esses me em

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o e !l l l In response er some of the other questioco, one item came out from SNUD i that a small PIT computer was used for various I&C calibrations and h been a very significant time sever. SMUD uses this computer for gFS cali-bration and for calibration of RMS area monitors. This has the potential j to save significant time and should be investigated by TMI. ACTION: T. Hawkins investigate by j ZYII. the next portion of the opegating seminar conalsted of a trip to Crystal River. Crystal Elvers' site is far more compact than' THI's. Buildings era tightly packed together and rise. vertically higher than TKI's buildings. It has no outbuildings beyond the protected ares and its' protected area is also, roughly circular in dimension. The warehouse appears to be the only building that is outside the protected area. In terna of geographical area, Crystal River appears to take no more space than a complaz approximately the site of the buildings within the protected area of THI-II. (I have used TKI-II j in this example because it is smaller in size than TM1-1.) The design I at Crystal River appears to be very functional with one exception. There is a co,1umn in the middle of the control room, that is located at the optimum place where the Shif; Supervisor should be standing in the case of a tranalent. The res; of the control room design appcora to be slightly better than that of TMI-I of II. The control room is more s. aspect than TNI-I with in deseral emaller controls and indicatio'us. However, there is no back psac1. There is only ene front panel and the operator can range across that front I panel and does not have to look nearly as far to see the penalarna or other indications. Security procedures also are slightly dNforent than at *Dt!. At the processing center there are, of course, the explosion and metal detectors. Ecwever, only one set, vice the three sets that we have, are in amistence. yurthar, with respect to security, Crystal River does not guard their grade level d oors, but only guards access into the vital aroaa such as the control room and the euxiliary building. It appears that this practice allows thee to utilise fever guards than TMI. The compactness of crystal River does not sees to Iend itself to a lack of space. Thetr architect engineer was CAI as was ENI-I and adeguate space on tre turbine building operating floor exista just as it does on TMI-I. In addition to this, the other two floors of the turbine building also appear to have adequate space. One other item th.at lent itself to the compactness of Crystal River was the lack of redundant components. Crystal River has only two condensate pumps, two condensate booster pumps, and two beater drain pumps. I was impressed by the cleanliness of Crystal 1[ver. The operating floor of the turbine building was a showcase with a buffed and polished deck. It seemed that everywhere that I went in the turbine building Enere was someone cleaning. Itama and gear were not left adrift but rather were picked up and stowed. I looked for evidence of oil leakage and found none.. ( i

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s,- ) i' 4 l .. o i I e l ,1. i 4 i e t a I Any leakage that went to drains was piped with hoses or tubing to avoid caceae water on the floor, t As I earlier rentioned, there are no out buildings. Things such as the circulation water pumps and other pumps which would equate to our river water pumps are is the basement of the a.ziliary building, although we could not get into the auxiliary huilding The anziliary building is five 3 stories high, which also lands itself to compactness. I am unclear on how l 8 many support pumps such as secondary service river water, nuclear service river water, etc. Crystal River has, but all these pumps are contained within a small area. This appears to land itself well to good management l ef the work force. The semia building, adjoining the' turbine building, appears to be adequately sized, and is three stories in height.

• Je talked with their outage planning group, and it should be noted that a Project II outage schedule was stretched across their planalog board and their planalog board is not currently in use nor planned fur see during their upcoming refueling outage.

Crystal River has been very pleased with the performance of Project II and feels that it ascoeds planalog's espabilities significantly. We should send 1. Troutman to Crystal ELyer during et least one or two dsys of Crystal River's outags to assess the performance of a system such as Project II in conducting - a refueling outage. 87.9'A17: The opsrating Seminar was a useful exchange o" information. The most useful concepts have been recorded in this set of minutes and will be passed out to applicable individuals for follow up. IKI-I continues to be the leader among 34V plants although it is clear that the othat plants are etssting to utilise contingency planning and detail planning and other tools which will narrow the gap between their performance sad THI-s performance. We should insure that follow up on the inovative ide s that they have come up with happens and get adeguately evaluated. A few such developments that stand out are Crystal River's dry cleaner, SMUD's pet computer and Crystal River's outage scheduling system. Many of the attendees of the conferecco were from non-B&W utilities. Many of the guestions that were asked were asked by these individuals. All sets,trying to learn of the suceps.ses and pitfalls of the R&U plants for applicability to other vendor N$8s units within their utilitiet. We should insure people from the operating level attend similar meetings conducted by Westinghouse, combustion Engineering, and Caseral Electric to insure that information developed by these vendors and utilities utilising their plants are evaluated for applicability in R&W plants and systems. J. L. SEILIlocEt Unit I Superintendent, TKI e b es e .e e e ? 9 b}}