ML20024C614
| ML20024C614 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 02/26/1979 |
| From: | Cobb W BABCOCK & WILCOX CO. |
| To: | Ohanlon J, Seelinger J, James Smith ARKANSAS POWER & LIGHT CO., DUKE POWER CO., METROPOLITAN EDISON CO. |
| References | |
| TASK-*, TASK-03, TASK-06, TASK-10, TASK-3, TASK-6, TASK-GB GPU-2033, NUDOCS 8307120879 | |
| Download: ML20024C614 (45) | |
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3 L5 G-W u. :-:.12 Babcock & Wilcox mc..ca 30 33 P.O. Box 1250. Lyrcr urg, Va. t45C3 Tweenoner (7c3) 234.stu *
- February 26, 1973
.To: SsW User's Group Distributien*
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Attached is a ecpy of the minutes of our User's Group meeting of Octcher 445, 1978.
Very truly yours, M.k N L
W. A. Cobb
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BsW Representative S&W Users croup VAC:ded Attachments p.
cc: w/ attachments 1
P. Cubre', SMUD 7-
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L H. Miller, APSL
- 5. C. Denisen, WPPSS
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R. F. Smith, WPPSS J. Anderson, APsl f
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- Per attached distributien list l
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B307120879 790226 PDR ADOCK 05000289 l
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asw user's cacUP
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Mr. R. J. Rodriguez (Ron)
Manager, Nuclear Operations Sacramento Municipal utility District Rancho Seca Nuclear Generating Station P.O. Box 550
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Herald, Catil'ornia
$5638 (203) 748-2751 Mr. V. A. Cobb
-(A1)
Mr. G. P. Beatty, Jr.
(Guy)
Manager, Generic Projects Nuclear Plant Superintsndent -
Babcock s Wilcox Comoany Florfda Power Corporation
.P.O. Bait 1260 P.O. Box 1228 i
Lynchburg, Virginia 24505 Crystal River, Florida 32523 (804) 384-5111 (304) 7*5-4486 Mr. J. Ed Smith (Ed)'
Mr. J. S. Evans (Jack)
Statien Manager Assistant to VP. Energy Supply Oconee Nuclear Station Toledo Edison Company P.O. Box 1175 300 Madison Avenue Seneca, South Carolina 29678 Toledo, Ohio 43652; (803) 882-4037 (413) 259-5690 Mr. J. l.. Seelinger (James)
Mr. G. P. Miller (Gary) l Unit 1 superintendent station superintendent' Three Mlle Island Nuclear Station Three Mlle Island Nuclear Station
. Metrepo11 tan Edison Company Metropo1Itan Ed! son Company l
P.O. Box 480 P.O. Box 480 l
.. Middleto.c, Pennsylvania 17057 Middletown, Pennsylvania-17C57 4717) 344-4041 (717) 344-4c41
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Mr. J. P. O'Hanlon (Jim)
Mr. R. V. Montress (Bob) i Seneral Plant Manager Plant Superintendent l
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- Arkansis Nuclear One Consumers Powr Company l
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- P.O. Box 608 3500 E. Miller Road
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Mr. A. M. Qualls Mr. B. V. Delst Plant Superintendint Nuclear Operatf ans Sellefonte Nuclear Plant Power Authority of the State of New York
(212) 337-42c0 l
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REY 10 1/22/73 Mr. Js 5. I.ogan (Joseph)
Mr. John Ahladas pnit 2 Suoerintendent Statien Manager Three Mile Island Nuclear Station North Anna Pcwer Station Metropolitan Edison Company P.O., Box 402 P.O. Scx 480 Mineral Virginia 23117 Middletown, PennsyIvanla 17057 (703) 8 51 (717) 944-4041 Mr. J. W. Junttila (John)
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Superintendent of Nuclear Operations Ohio Edison Company 76 South Main Street Akron, Chlo 44308 (216) 384-5776 l
Mr. B. K. Mel.aod (Bruca)
Plant Superintandent Washington'Puh11c Power Supply System 30C0 George Washingt=n Way
' P.O. Box 368
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Richland, Washington S*351 e
(503) 377-2323 Mr. C. Goodwin, Jr.
Mr. T. D. Murray
'(Terry)
Assistant Vice President Station Superintendent Portland General Electric Company Toledo Edison. Company 121 S.W. Salmon Street T
Davls-Besse Nuclear Power Station -
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Portland, Oregon S7204 5501 North State Routi 2 Cak Ha M r Chio 43 Q (503) 226-8333 i..
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MINUTES OF MEETING - B&W USER 8 3 CRCUP OCTOBER ks5, le78 GENERAL.
The B&W User's Group met on October 4,1978 at the New Orleans Marriott in New Orleans, I.oulslana. A copy of the list of attandees is attached as Enclosure 1.
In general, the meting followed the previously prepared agenda, a copy of which. Is attached to these minutes as ' Enclosure 2.
Mr. W. A. Cobb, B&W representative to th User s Group, acted 8
as Chairman in the absensa of Mr. J. G. Evans, User's Group Chairmen.
REVIEW 0F 073G TUBE PROBl.EM Mr. M. J. Bell of B&W reviewed developments on the 073G tube problem sines the last User's Group meeting. The sildes which Mr. Bell used in his presentation are attached to these minutes. Mer1 first presented three slides showing the crack discovered in ere of the Aricansas steam generators (tube #77-17). The slides presented the crack details at various magnifications. Next, a slide was shown presenting internal diameters of steam generator tubing taican at various locations from the upper tube sheet on the ANO generator. The results showed no evidence of tube denting (all tubes wars within the original tolerance. Merl next presented a silde showing the CT3G Inspections which have occured since the last meeting of the Group. The results are shown on the attached sildes.
Mr. Bell then presented a number of slides showing vertous chemistry sampling results.
Among these were results of analyses of water treatment estarials and results of chemical
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analysis of feedwetar at various locatibns within the Oconsin system. hts also presented a graph showing concantratien ratios for various moistura separator efficiencies. The main thrust of Mr. Bell 8s presentation was that the CT3G tube problem is related to overall
- feedwater chemistry control and that many plant operations can c=ntribute to poor feed-water chemistry and thus a poor environment for CT3G tubes. Mr. Bell gave the following responses to questions from the superintendents.
(1) On the nature of the CT3G tube problem, Mr. Bell responded that it is now believed that the 0733 tube problem is mainly a chemical problem. He also indicated that we were not sure that we were through requesting tubes be pulled.
(2) Responding to Mr. G. H. Miller's question, Her!
- answered that the ANC tube recently found cracked was the only one to data showing Intsrgrannular ccerosion.
In respense to a second question he Indicated that it is impossible to te!! whether the deposits o
on the failed tube were deposited early or late.
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(3) Responding to a question from Mr. Anderson, Mr. Bell responded that sulfate is definitely a bad actor in the CT3G tube problem.
- pe (4) Responding to a question regarding the nature of the lane bJocker, Mort described it as a plate installed ever the ' holes in the support plate in a manner yet to be determined.
(5) in response to a question regarding the EPRI study on deep bed regeneration, Mert indicated that the results were not available yet. He mentioned that changes at i
TM1 did produca excalient quality feedwater.
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(1) Conduct records investigation on welds.
l (2) 'Obtain irradiation data from Crystal River 3 reactor vessel surveillance prograrn.
'(3) Obtain fracture toughness data on unieradiated materials.
(4) Recalculate the pressure-temperature curves assuming the poorer materials properties of the atypical weld material.
8PRA AND ORA LATCN PROBt.EM Bill Spangler of BsW made the presentation on this subject, and copiss of his slides ara-attached. Bill described the problem and gave the status of BPRA/ ORA rennaval plans at the verlous sites. The s11 des, used are self-explanatory and need not be amplified.
INCORE DETECTCR EXPERIENCE Bill Spangler also reported on this subject and copies of the slides Mich he used are attached. Bill described the following:
(1)
Insertion / withdrawal problems of the incere detectors.
(2) $ltes at n ich failures have occured.
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(3) Sheath failure hypotheisis.
-(4) Assembly improvements. Mr. Spangler pointed out that although' magnostise oxide (Mgo)
.had been identified as.a. bad actor in early incore detectors, failures of detectors utilizing aluminum oxide have occured at Davis-Besse and TMI, although these were not the gross type of failures previously noted wl,th magnesttas oxide.
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CA::M STATOR PROGRAM
- Mr. R. A. Wallin of 85W ande this presentation
- and'ceptes of his st. ides'aia attached. Mr.
.Wallin reviewed the performance of the varnished bifliar stators as compared to the previcus epoxy stato'rs. The performance with bifilar stators has been several-fold better than that with epoxy stators as can be noted from the attached slides. Bob also described the CKDM
' stator upgrade program as ilsted on the attached slides.
l At the conclusion of Mr. Wallin's presentation, Mr. Beatty voteed his views that Bsv was ultra-conservative on the reconnended venting practices for CRDM's. He suggestad that we vent only the center drives to make sure that the air was out of the vessel.
l Pt. ANT EXPERIENCE REPORTS A
Oconee station - Mr. ;l. Ed Smith reported on operations at econee as follows:
(1)
Overall station capacity factor 753 so far this year - 103 better than last year.
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(2) A problem with radioactivity on Unit 2 was described. Mr. Seith was hopeful that this will go away with the new fuel.
l (3) Mr. Smith described an outage control organization under the direction of the opera-i tions engineer. The organization includes a.mai.ntenance coordinator and representa-tives from the major disciolines.. A trailer is used for an outage control canter.
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~5-(4) Mr. Smith described problems In finding small GTSG tube leaks. He described diffi-culties in finding leaks in January and March,1978. Both Isaks wra v'ery small (approximately.2 spm) and difficult to find. His advice was that when small leaks exist reduce power first to see if the leak goes away befors shutting completely dcwn.
J. Ed also described an arrangement of Tigen tubing on the steam generator sec=ndary side so that one can see when the unit is full of water during tubs leak tasting.
(5)
Mr. Smith Indicated critical path problems during refueling were scheduled 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day, 7 days a week, but were modified for human factors. He Indicated that particular attention should be paid to heat stress and radiation expesure.
(6) Expertenes with a disgruntled employee was described in elch the empi.oyee would ne.t work in radiation. He finally quit and wanted unemployment compensation.
(7) Mr. Smith Indicated that there were approximetaly 550 ' operating personnet' at Oc= nee, and that the number was more liks 700 when guards, laundry employees:, etc. were in-cluded.
At the conclusion of Mr. Smith's report, the following obsa'evations warm made
. by other Users:
(a) Mr. Montress Indicated that standardized tsch specs require more peo~ le as evi-danced by the experience of TMI-2.
p (b) Mr. Beatty suggested usleg dry ' cleaning rather than faundry for radioactive cloth Ing. Plerre cubre' confirmed that this was a.saving.
.TMI Unit 1 - Jim O'Hanlon reported as follows:
(1)
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(2) Somewhat later in June seven' rods dropped of nine in a particular group.due to had l
diodes.
(3) Even later l'n June there was a RC pump problem, an inner seal was bad.
A carbon chip from the second stage seal dropped dows and popped out the first stage. Unit,was dcwn seven days.
(4)
There was also a pressurizar sprey valve leak (WLrbonnet flange)., carbon steel boits wre cut by boric acid.
(5)
Turbine stop valve testing is now being done at 65: power vs 50 power with asw approve (6) in 1977 load.was requi red to be reduced because of vacumn prebiams. This has not been required so far this year.
TMI Uniti-Jim Seelinger reported as follows on operations:
.(1) Jim reported on an ECCS actuation on 4/23/78 in dich there was a 120* cooldowt in tire minutes.
The cause of the event was one RPS channel was out of service (trip status) and a noise spike occured on another channel.
The mein steam valve stuck open and finally shut after 31/2 minutes (problem - operator cannot hear valves blowing - have installed microphone).
(2) Jim described the probinn with safety valves. The expansion joint liners blew out, literally blew all over the site (liners undersized).
(3) A problem was recounted on I.onegran valves. Met Ed finally threw in the towel en these (they wouldn't ressat). They installed Dresser valves and completed tasting by the end of August.
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e (4),)Im described a IIcensing prebl'em relating to loss of offsite pcwer. The aux!!!ary transformer would pick up load before the diesel generator causing icw voltage and blow fuses. Plant modifications were made to get loads off the auxillary transfermer The NRC is still questioning.
(5)
Inspection revealed no wear on ORA and BPRA latches.
(6) Problem was described with reactor vessel head leakage possibly due to reuse of "C" ring.
(7) Difficulties with fuel handling equipment were described on (1) sprocket / chain probiern '
and (2) spent fuel pool leak.
(8) Modification on steam piping was canpleted in early September. Modification involved changing snubbers.
(S) Unit presently at 403 power.
This concluded discussions for October 4,1978.
Plant experience reports continued at 8:30 a.m. on October 5,1S78.
Flort_da Power Careeratten - Guy Beatty reperted en operations at Crystal River 3 as follows (1) Difficulties with refuelinir equipment were encountared as follows:
(a) The fuel transfer carriage malfunctioned with fuel in both pools requiring repair of the fuel transfer carriage under water.
(b) Fuel transfer carriage rides very unevent'y along tracks (Jumping, etc.)
(c) Seventeen days were spent repairing fuel transfer. mechanism during refueling. No
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trouble was encountered with,the bridges.
(d) One transfer mechanism lodged in the tube white transporting a dunury fusi assembl-
-(2). In transporting the dussay fuel assembly, the hook opened and the assembly feil on. an APSR in the fuel storage pool. When the element was Tnstaffed in the core, TV inspe:t showed that it had been shortened by 1/2 to 5/8 inches. Duke supplied four replacwen-elements (spent) for substitution. Overall cost was 2 weeks on the critical path.
(3) 410 finear feet' of approximataly 420 IInear feet of BPRA was found. Some was ledged
&n the distributor plate layer of internals.
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(4) Guy cenplimented 8sW on its assistance in the recovery program (with snail W's, etc.)
(5) seven tubes in "3" OTSG had BPSR particles. These were plugged.
(6) Exposure in total outage was 238 men rem of Witch 134 men rem was for 073G work. shie Ing used in the 073G's paid off.
(Tepee was used.)
(7) Thiers was a disagreement between Zetec and BsW regarding a tube defe~ ct in "A" generato 2etec said'258 throm.h weil and BsW said 40 through wil. The tube was finally plugg
.4 (8) A small 0753 prime. 7-asendary leek has been difficult to find (approximerely cne a,...
gallon per day). Tube still leaking even after attempting to find leak by flooding tube sheet.
.(S). In answer to a question by Merl Bell, Guy indicated that he would replace rather than regenerate the resin of the deep beds.
(10) Heatup was started on September 10, 1978.
(11) Guy related the following regardin ghe shutdown and startup:
(a) A total of $1.5M was spent on the heater drain system modifications.
(b) A complete turbine generator inspection was done.
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(c) There was a main steam relief ' valve leak (thru valve). Valve was gagged.
(i!) Five leaking incere detectors were encountered-(ene closure and four hydro test plugs). All hydro test plugs had previously been welded chut, but four still leaked and these were formaultad.
(e) On startup a tilt was noted in the core found to be due to a red being unc=upied.
The system was drained dem and recoupled.
(f) A 3/4" valve IIterally fell off the sein steam lines.
(12) 1003 power was attained on 10/4/78.
(13) Guy voiced his view that the chain /spro.kat delw on Em fuel transfer carriage was a " Mickey Mouse" design and that the transfer carriage shculd be a. cable drive. He also noted that the air motor failure problems also plagued FPC. He notad that when
'under water failures occured work was required under water in a 120* environment.
After the comment regarding the cable drive on the fuel transfer carr'lage, Mr. Smith of Duke indicated that he had had prior experience yvith c:ble drives 'and they wars not satisfactory either.
Arkansas power & l.lcht = ANO #1 - Harvey Hllier reported as follows:
(1) His most significant problem has been with RC ph seelt. He replaced all seals in.
1977 and has replaced one more since that time. Two others are cycling 200 to 3C0 ps!.
(2) The capac!ty factor of 63 7 has been attained this year to date. He ' hopes for 75 for the year. Reactor avail. ability has beer 752. He has been off line three times.
(3) in May '78 the unit was dem for seal' welding pressurizar bundles (It was noted herc that of,the operating plants CR-3 and Rancho Secq have not yet welded heater bundles).
I (4) A noise was detected on the acoustical prche on the reactor vessel't.~ It turned out th the probe was just loose.
l (5) An RC systne leek was detected in August.. It appeared to be the.RC pianp seef, but
- r turned out to be a sensing ifne from the pianp.
(6) kNO is running close on shutdown margin (1.52 vs 13 required).
-(7) Harvey related the following series of events on S/16/78:
(a) 1002 power on Unit 1.
(b) Main steam isolation valves weren't closed.
(c) Unit 1 tripped.
(d) Voltage went from 4160 to 3300.
(e) Engineered safeguards operated at 922 voltage.
(f) Diesels came on s safety systems operated.
(g) 50.000 gallons of water in containment (spray plus backflow). Ph in sump was 6.8.
(h) Recovery operations included inspection of ali Junction boxes and removal of all Insulation.
(I) Containment isolation during incident caused loss of two pump seeis (containment isolation was automatic).
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"I' (8) There was a general discussion on performance of B-J RC pump seals. One item menticned:
was that ANO does not hand rotate pumps after Insta11atica of seals. John Andersen expressed his view that it is better to raplace seals while they are still performing.
satisfactorily rather than to try to obtaii maximum life and worry about lack of per-formance.
(S) A thorough inspection of hydraulic snubbers was made In August. Plan is for 120 day Interval on Inspections.. Previous problems may have heen caused by inadequa a.mainta-nance. On this same subject it was mentioned that the second APSt. unit will utill:e mechanical snubbers whereas the first uttll:es hydraulic snubbers.
(10) la closing his report, Harvey mentioned a couole of ' precautions as follows:
(a) Assure that fuel mast Ilmit switches are set such that fuel assemblies are with-drawn cogl'ately into mast (a fuel assembly impacted guide stud because of fust assembly extension).
(b) Exercise caution regarding the. guide tubes in the plenum.
Rancho Seco - Pierre cubre reported as folicws on operations at Rancho Seco:
8 (1) A 1 spo leak was experlenced on tho pressurl:er relief valve.' It was replaced.
(2) A leak through the RC pum "C" ring (on 3 pumps) deposited boric acid on the RC ou=o studs. The'0* rings were form nited and leakage on two almost comotetely stopped.
Plans are to come dow every.6 to 8 weeks to inspect the pumps. The pugs are now-operating with three stage seals without any real problems.
'(3) Refueling is planned for November 15, 1978.
(4) On July 20, 1978 a second mein transformer was received and Installed.
l (5) capacity factor for the year is 76.52 as ccupaced to a 752. goal for the total year.
(6) Plant staff is as follows:
Plant staff - 168 Security - 78 Engineering.- 13 tontract maintenance personnei'en staff - 24 Construction personnel on site - 265 I
(7) There was considerable discussion regarding security requirements. Pierre reported the following significant items on this subject:.
(a) There are 5 pilt boxes around the plant.
, (b) $175,000 was spent for three armored cars.
(i:). Guard training and qualification is becoming a big problem.
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(d) New security requirements are expected to require two licensed operators in the control room at aff times.
(e) Guards are used as part of the fire response team (Note: ANO w s told'no*en this).
(f) Security plan not yet approved.
(8)' ALARA 1s limiting use of people, such as for welding pressurizer heaters.
(3) The use of ilthium hydroxide was discussed as a means of keeping the radioactivity In the system and unloading it with the fuel (radiation goes to the hottest point in the systam).
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(11) 'EG&G is on site for NRR. Objective is to -look at wasts disposal system decontacina-tion fac. ors, etc. -
(I2) There is a problem of seal plate warping due to being hung between refuelings.
Davis-fesse #1 - Bill Spangler of B&W reported on operations at Davis-Besse i for' Terry Murray as follows:
(1) system is now in power escalation test program.
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(2), Problem has been egerienced with victormen Instr'.anents (a temperature problem).
(3) A natural circulation test' is planned as 'Is a trip test to determine ICS runback capabilities.
(4) An any1If ter failed in a BY transmitter causing a trip. Difficulty of calibration of BY caused excess lost time. Note: At this point ANO and TMt noted that they wars planning to replace all SY's with Rosemount Instruments..
(5) Congletion of test program is scheduled for the end of October,.
(6) Fuel handling equipmsnt. problems have plagued coeretions.
This concluded the plant experience repori:s. The remaining items were general items brought up by various meeting par:Icipants:
(1) Jim O'Hanlon suggested the desirability of using generic bounding curves for tech spec so that these would not have to be continually changed.
(2)
J. Ed Smith discussed the five rem annual limit for personnel with partlevlar regard to keeping EsW people within the Duke administrative limit of 3.5 rem. Ed mentioned
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that he had had to waive the Duke standard for several BsW people previously, but would not do so in the future..There was some discussion about a higher B&V manhour rate to support a larger staff and thus lower exposures. There seemed to be 1Tttle Interest In this possibility.
i (3) Pierre cubre' Indicated scme delay in obtaining BsW Master Service personnel. B&W Indicated this might be a sales office delay and that steps would be taken to speed response.
.(4) Quales Inquired whether anyone had developed procedures for handling radiation exposur-while removing pressurizar heater bundles fras reactor building. He obtained scme in-put and will pursue leads separately.
~(5) John Anderson inquired where the outage engineers for the various utilities reperted.
Most utfiltles responded and Indicated that he reported to the superintendent.
(6) Buzz smith of WPPss reported a cost of $140,000 per outage day per his canpany's studi.
(including 7 for cleanup and 20% for planning). Other users thought this was high.
(7) Guy Beatty Inqui red about incere disposal. Jim O'Hanlon stated that the chopper at TMI was manufactured by All American Engineering and that it did not work properly.
TMI developed a new design. The new design involves a pipe approximately 208 1cag (lead lined) plus a pair of scissors. The operation sequence involves pulling all except 20' of the incore through the pipe and then severing the last 20'.
Then the pipe is lowered and the remaining incere segment pu11ad into the pipe. The hot 20' portion is then chopped up and dropped into a vault in 8" segments.
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,(1)
It was decided to establish a subcomittee on fuel handling equipment and to have this subcomittee report back to the User's Group at their next meeting.
(2)
W. A. Cobb announced on behalf of Mr. Evans that Gary Miller and Ron Rodriguez were nominees for the upc= ming term as Chairmen of the BsV User's Group.
It was agreed that Mr. Cobb should send sout ballots for f?nal election.
It was also agreco-that the membership would vote on whether the tenure of Chairman should be increased to two years.
(3) The Group agreed to hold Its next meeting on May S and 10 in Atlanta (the exact loca-tion In Atlanta to bs determined).
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ENCLOSURE 1 LIST OF ATTENDEES BsV USER'S GROUP MEETING NEW ORLIANS, LA.
OCTOBER %, 1978 NAME C3MPANY
- 5. C. Dentsen WPPSS l
Bux Smi;h WPPS3 J. P. O'Hanlon Met Ed - TMI #1 J. L. Seelinger Met Ed - TM! #2 J. W. Junttila Chlo Edison Pierre cubre'
$ MUD Guy Seatty FPC John Anderson APst.
- 8. M. Miller APst.
Terry Miller TEco g
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Al quells TVA R. W. Montress Consumers J. Ed Salth Duka - Oconee s
W. k. Cobb EsW
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i R. A. Wallin B&W I
R. E. Vascher EsV t
Ray Luken BsW i
l J. D. Phinney B&W R. J, Maggi BsW M. J. Bell SsW i
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'S ENCLOSURE 2
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AGE!!DA FOR B&W USER'S GRCUP MEE71NG QCTOBER 4&S, 1978 80NAPARTE ROOM MARR10TT HOTEL NW ORDM, u.
VEDNESDAY. OCTOBER 4, 1978 8:15 - 8:30
. COFFEE & DANISH 8:30 - 5:15 REVIEW 0F CTSG TUBE PROBLEM
- h. J. BELL 5:15 - 3:45 OWNER'S GROUP. PROGRMS' R. E. WASCHER S:45 - 10:30 REVIEW OF RECE)(T REFUELING EXPERIENCE J. D. PHINNEY
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10:30 - 10:45 C0FFEE BREAK 10:45 - 11:15 FUEL HANDLING Equ!PMENT PROBLEMS F. R. FAHl.AND 11:15 - 11:45 RC PUMP SEALS - BINGHAM & 5-J W. H. SPANGLER 12:00 - 1:00 LUNCH (BUFFET IN MEETING ROOM) 1:00 - 1:45 ATYPICAL REACTCP. VESSEL WELDS R. C. LUKEN 1:45 - 2:00 RELIABILITY & AVAILABILITY PR03 RAM R. E. WASCHER 2:00 - 2:15 BPRA & ORA LATCH PR05 LIM W. H. SPANGLER I~
. 2:15 - 2:30 INCORE DETECTOR EXP BXENCE R. t. LUKEN on W.'N. SPANGLER 2:30 - 2:45 CRDM STATOR PROGRAM F. R. FAHLAND 2:45 - 4:45 PLANT EXPERIENCE REPORTS (OCONEE,TMI,CR-3,
{%30 MINUTES / STATION)
AND #1-
.98 #1), RANCHO SECQ, THURSDAY, CCTOBG 5, 1978 8:15 - 8:30 COFFEE & DANISH 8:30
.10:00 PLANT.EXPERIE.NCE REPORTS (CONTINUED) '
10:00 - 11:00 QUESTION & ANSVER PERIOD (QUESTIONS FOR BBW OR FROM, PLANT-TO-PLANT) '
, ',, ', - 11':00 - 12:00 ELECTION OF NEW CHAIRMAN ESTA8LISNMENT OF FHE SU8 COMMITTEE'
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.i INSIDE DIAH.ETER.HEASUREHENTS..
?
I.ocation Average Diameter (Inches)
'l l
3.24 inches from top of upper tubesheet'
-0. 5'5i. s.
l.
4.00 inches from t.op of. upper t!ubdsheath d.550 25.3. inches from top of upper tubasheet,'.'
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ms(es-ih hb OTSG INSPECTIONS OCONEE 3 JUNE, 1978 VISUAL INSPECTION
~
CLEANER THAN 3EFORE
~
, tex. ficW LEYEd '
Enw. CURRENT, N,0 SIG'tIFICANT INIh! CATIONS,
PRoFILCMETER -
NO INDICATIONS l
- TMI-1 MARCH, 1978 VISUAL INSPECTION ESDY CURRENT ONE TUBE PLUGGED (OD)-
EACH OTSG l.
PRoFIL0 METER Na INDICATICNS
~ '
OCONEE 1 OCTOBER, 1978 VISUAL INSPECTION CLEANER THAN BEFORE (Ex. IFd LEVE0 Enw CURRENT NOT COMPlate
ak.,s TABLE 4.
ANALYSIS OF WATER T?L m CNT MATERIAI,3 i
8 c.
t (All samples collected on 2-2-78)
=
pem C1 pE, 2'4 C' cemFO,f'..
pote Na E "4 2agesarant 26*3e
^ ~
2 0.54 Nac3 Itagensrant 50%
12.4
< 5.
W a:ine 54%
10.7 680'.0-
< 5.
8 Armonium Eydroxide 26 3e
, 4.06 -
10.4 420.,
.s III' CL-85 Silt control Treatment 514.0 36,000 1750.
[
CL-05 In solution 4.*4 2hw Powdcred A= ion,Dasin (CR' form) 96.
~'
"' sol 1* 7nti oc agulant 270 (1)
Tot:1 sulfur as sulfate (504) was datarmined after a wet M ' cal digestics of the resin was performed.
1
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Calcu1Atad to Origtr.a1
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c,e j
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-cob cab ob'
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- 757l
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. c.)
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.277.0 2.4 i 1.2 N30 "0"
~
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,757-11.4
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0.'2 s
Heater Drain "E"
- 1514 21,2
- 0.1
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. '4.5.
<0.1
.<0.1 Powdex outlet Mixed 2271 0.1
<0.1
<0.1 Cond. Storage Tank 757
' 5.4
- 0.1 0.2 Hotwell 757
'8.3
=0.1
<0.1 l
l '
- It is strongly sushicioned that the high iron observek on this sample -
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..ANAI,Yf1 CAL.RESULTS - ppb
((Calculated to original sample voluna concentration correatpd) l Sample.
small voinue Sample Conc.
Crab samples identification Factor as receivur Cr Hg Na Pb S10 Al.Fe M1 Cu Cr SO C1 ", K Zn Na ci 2
4 IAI Demin. Effluent 1345
~207.8 0. 1,1. T 0.9 0.5 21.2 l <2.0 1.0 0.3 0.2 <0.1.<0.6 0.4 <0.1 0.1 1.0 13.
1 Ilotwell 1505-1540 102.1 0.2 1.4 0.6 1.0 0.3
<5.0 1.1 0.1 0.1 0.3 <0.5 0.5 0.1 0.1.0.1 15.
'.2 0.2.25.8 0.i 0.7 0.6 <0.2 <10i 4
Powder "C" 1500 104.8 1.3 0.5 0.1 1.0 0.5
<5.0 1.0' 5.3 2
l Powde4 "E" 1510 104.9 0.7 16 0.7 <1.0 1.2
<5'.0, 1.0 1.8.1.1 0.2 12._4, 1.0 0.4 0.2 0.4 14.*
I l
Hixed Pow'dex Erf. 1930 274 5 0.4 0.Il 0.4 0.4 0.6
<2.0 9.0' 1.1 0.3 '2 4 1,2.8 1.5 0.5 0.2 0.4 10.
llentar Drain "E" 1203 208.6 0.5,1.8* 1.2 0.5 0.5 -
'2.'4 0.6 0.2' 5.0 0.1.17.2*
0.6 0.6 0.1 <0.2 <10; Heater Drain "D" 1255 91.7 2.5 0.732.2. 1.1.12.0
<5.0 5.5 0.4. 0.1 0.1 2.7 6.8 8
0.945.*1.3 10.
2 Combined Reheater
)
Drains 1230 207.8 0.5 0.7 0.9 <0.5 2.7 2.4 1.1~ 1.7 1.1 0.1.7.6' O.3 0.2 0.4 0.7 14.
Final Faedwater 1332 189.7 1.1,h6 1.4 <0.5 0.5
<3.0 2.2 0.2 0.1 1.4 8. 7 ' 0.5 0.7 3.1 1.3 10.
Cond. Storage Tank 1458-98.0 1.2,4.6 13.1, 1.0 5.1
=5.0 2.6 2.81.2 Ort 13. g,'
O.6 1,30.5 1.3.11.
Hofstura Sep. l1 rain "A" 1202 91.2 1.8,9.,8;11.1 ' 1.1 48.2 45.0.12.08 1.1 0.2 0.2 12.1 5.3 f.5 3.1,' 12. 36.
g j
Holsture Sep. Drain i
"a" 1245
,53.0 3.4 10.8 '12.8I 1.9 25.3*
<9.0 40.9. 1.3 0.2 0.2 *0.9 0.3 2.5 f3.8.11.
- 38.
}
- Circulating water
-~
i 1315 50.4 1369. 704.1090. 2.0 67.6 79.4 76.6 2.6 421. 1.6 4.2 1.6 1400.1000.
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- ' _a t I, _ __________ _ __ ________ _
~
- 4. 9, L.,, %., A.s u n m a \\.l hfD RERIEUNG EXPERIENCE
- UNITS
,6
- EREUNGS.
14..
2.t*.~
.v
- EOC 1 PER!EUNGS -6
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- EDC 2 REREUNGS -5 0 EOC 3 RER!EUNGS
- 3' 9.'..
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- 7
~
AVER 3.E ELSOSURE
.. 23rg g,n ggg
.},,
1976 DEA!S TO EREAXER AVE, 76 DAYS 1977 BE1ER TO BREAKER AVE.
- 69 DAYS ISTS E.URR TO BREE-3 AVE.
- 47 DAYS 5-3 * * !
4 LAST EFEUNG BREAXER.TO EEAKER AVE. - 64 EAYS
- e qy.
g 4
as.u.. _
-..... 0/
7
'E.T"
==.. CATALOGMC. 1510:54
...ca.......s-MADE IN U. S. A.
,,_,.,,,,-,.,-..,-.,,_-,-,,,,..,c.,,--
.s s D P w,,o 3
3b38 l
=
n..
RERiELING SPAN TIMES l.AST REFUELING
~
~
GAYS)
J
. AVERAGE SHORTEST
.i VEHDOR
- UNITS GKR-TO-3KR)- GXR-TO-BKR)
~
t,,aW m
5 64 39
- 3
~
E 6
- 89 63
(
~
18 68 24
%w 2
21 76 31
.f.
-=
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O' T
A,d CATALOG NO. 15 1006 4 3M CENTER. ST.PAUI., MINN ~5101 MADE IN U. S. A.
i
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N
. _, ~. _.Q ~ ._ _3 P2 FUELING PEEFORPMCE ANALYSIS 1. NOPNL SCOPE FOR.ES REPUELING 2. OUTAEE EXTE! SIDE ETtQMD COG.at sccyg. , J.. .. ~ j "* 'gj~ ~ A. RERIELING SUPPORT EQUIPENT FAILURES MilG EXTEND NO. VAL SCOPE EVEiT SPAN TIES aM.J COI?CNENT PAINTBiANCE OR FkIUIRES W!ilCli4A a. I EXTE!D PRIMRY PUJ!T CRITICAL PATH EEYOND ' r.h i!!AT REQUIRED TO CGI?LETE NOPSL SCOPE c. INPLUS!CE OF BOP WGPZ LM..e. (D ES.AY EXPERIENCED AS A PISULT OF g f,, a, .EGP IRABILITY TO SU? PORT PRII%TI .df' u.a.a ~ PUUtT ,4 a J,, (2) STETCH GUT OF PRIET( PLANT k'OrX AA DE TO EDP CONTE 0LLING OVEPl.LL PU4T ~ ~ CPJTICAL PATH. i.k.4.Id4 e u.,. i I f.M, CATALOG NO. 15 1005 t. 3[4 CENTE.f.ST.PAut MINN 551c-
q. -~ g -['.. v;-A..._, c,r.. JD?(ch.d 7 yi %.l'jl O) f!0RFtc.L SCOPE FOR NSS REFUEL!!G S< ..g 1. COOL DOUN 3 DRAIN "'I 2. REMOVE /REPMG SHIELD BLOCKS l 3. UNCOUPLE / COUPLE'CRDWS g. 4. RSCVE/EPLACE RV HEAD IliSULATION 1 n 5. INSTALL / REMOVE CANAL S,EAL P!JiE ? 6. PETENSIO!UTEiSIO!! RV CLOSUPE STUDS 7. REOVE/REPLAE STUDS 8. INSTALL /REROVE GUIDE STUDS ~; e 9. PS UVE/REPLAE RV HEAD .1 10. INSTALUPGDVE INDEXIHG FIXTUE. ~ 11. PEEVE /EPME PWM1 ASSEFELY _- 'E ~ 12. FILL /DRAI!! FEL TRANSFER CA!GL 13. EFUELIfiG 14 IllSTALL/PS DVE STUD HOLi PLUGS IE. CLE:Yi 0-RING EP.00VES 1G. CLEA!' STUD HOLES 17. ISI (PERIODIO :
- i....
18. It!TEGRATED RIi LEAK RATE. TESTING (FERIODIO 19. FILL AS VEHi 20. G.hTL? i 21. IEP.0 FC2ER FHYSICS TESTING .~ '.) ~ W CATALOG NO.15 10CS 4 3r.1 CENTER. ST. PAU! MINN EST01 MAOE IN U. S. A. e
ar(cwin) N l, } \\ ACTllALR5FUELINGOUTAGEP'ERFOPS.5.NCE EOC-1 REFUELING ~ GAYS) NORJit. ' Ol[iAGE ' TOT,1
- JT SCOPE EXTENSI0ii BFSJ S -TO-M S KER j
i 3?!EE 1 (10/74) 33: 112.. 145 fu as r
- e.o s~s e EiEE 2 (4H5)*
34 61.. 95 - =-7 I).1EE 3 (995)* 32 ' ' 23 55 - =Er O i!-1 (2H5)* 34 '62 95 - =u-r
- l'( Y/7) 33 ' -
33 EB -- " 4 (?) .'!CHO SECO (897) 33 44 77 - - %w % AVEP#4 34 55 89 5.9T OUTAGE ~ = * *
- g l
.h../ ........s_-.i-......... 7eTg =+w CATALOG NO 15 1w 4 3M CENTER"I. ST. PAUL MINN 53*01 e-w .,,-,e -w -,---%= .-g y -v, m,
w-.-w
-.,w--,,-,-yi.,w,- --w..-- --aw-,-..w--, ---w-----w-w
1 ~' ' hhfI\\ 4 D F (c.wrk \\ N -g g.-.- ~ ) - ~ .s ACTUAL RER R TNG OUTAGE'PCRFORM M CE. ~ EOC-2 FRA TNG (DAYS.) NOPJiAL ' OUTAGE TOTAL ~ SJI SCOPE EXTENSION (BKR-TO-EKR)
- .0!!EE 1 (2/7s) 31 25 55
@ *"> " + ; 70XEE 2 (5H7) 32 61' ' 93 1@w ,=9
- 0..CI 3 (10n7) 31 13 LE
.I ) ace',, m a d 11-1 (367) 30 29 59 . g M e~ ace -u '0-1 (2B8) 37 20 57 -@w 2 AVE?. AGE 32 30 62 e 4 f. 4 } 1 1 I / r...-..-- u~ O5 CATALOG NO, 15 1006 4' d ~. - r-,.,. -..,v .,---,-,--,-.,,,,m- ,, - + -,..,.
h' , - m, . - -../.,. t-J Di(ce*W 9 ') .. ~.... ACTUAL RERJELING OUTAGE PERFOUWICE ~ EOC-3 REFUELING i (DAYS). NOEAL. OUTAEE. ' TOTAL IIT SCOPE - EXTEi3!0!i BKR-TO-2XR qh.,JGa* *"- t-s '~0i;EE 1 (8n7) 30 -'43 ~ 73 f ~ .;Mc>p.anA E!EE 3 (EH 8) 29 .10 33 r a -- ~y PI GHB) 36. 8 44 p re-6 d .e.' AVERAGE 32 20 52 .:.e g r t 1, .y
- ,4..
. A... g-. ,r .~ = .s. ,:.1,4. s, 1 .x.:a'] .h,An..-d%.~--.- A* F M GTALCG NO.15 1006 4 3*.1 CENTER, ST. PAUI MINN 53101 ME IN U. S. A. S ,v-, ---,,.~- n.,
fg . _ - -. ~,.. @e(oar.o. i u. o ACTUAL REFUELING OUTAGE PERFOR'U.NCE, ) AVEPAGES GAYS). o TOT!4 M LING liORiMi. SCOPE OUTAGE EXTENSIOf EPD.12R-TO-3REN2?, g jST 33 31 64 1* i'* ' 1 1C-1 34 55 ES 'ec-2 32 -33 E2 T . 00-3 ' 32 20 52
- .1
~ . i, ( e I 2 'l s +. - CWi ww CATALOG NO. 15 1006 4 3*. CI?.TER, ST. PA'. f.*'!!!! 2"* *
- UADE IN U. 3. A.
-..__.__m, ,,.-_...__._-.v_ .,-_. _. -___,,- -~, _._.....- __.,.
r_.. o . n-
- f. --
l Actual refuciing outage perforrnance r-69 90 N EOC-1,2 & 3 Average-all units M - BREAKER TO DiiEAKER' i N N t .:b N N i l 'N j s,'N.n G2, g c0 , s. a-p x n .N h:
- \\
f 50 N s2 ud. s>6 Q" 1 >8 40 e 4t<4n .4 N0filAL SCOPE v 3 32 - ~. ~.,,,, g si e..u.a. 30 ~ c. \\ r 4 ,a. g7 e4 a ..-__.-._..._.......L.._..= 'l -i cg = [.fer 1 UJC 2 .EGC 3 ~ assacand/ i V i :.0 us4L.'.n...: J: AJ.tJ.u.h
- d M
- 4. s26.J:..iwJL:.
. 4Ctila.i'J; ass:.ie . ~,,,...
97
- a..
.y;. ,9.. fv M ,.19 i (cu, c) ?.I \\ u M l i]s .r. .a, ..e... s .n .4l a, 1 1 e ..E . 3, a. .i. ACTUAL RERELING OUTAGE PE::GP"ANG 3 AVEPs.sEs i ... w_.,, [ y.. . r.; 1975,1977, t 1973 d.
- WY:
...,,y. GA.ys) .e. ~ ' ~ TOTAL .i Y~-f.P. IN.TS E0r"al S' COPE OUTAGE. EXTENSION EXR-TO-3"R ..J I so 4 33. bw 75 ~ 2, 77 6 32 37 69 2 ? 70 3 3'4 13 47 e ,y n..
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.1 SUSJECT .56L4 cimoc No. t 3M CENT ER. ST. ?; NO MAD E IN U. S. A. g m
' ?. h Y (.ONTD tra fd M e c O m 'O to ! o* C. = ~ w. a. p. g taa er, t7 cc. 6 s .:a.a L. U O
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j. l g I l ~. ta. .:? l _ e_lt 2.M l ,3 t t I f f . m O C Q C C C C s co r= t., la v to. W (SAVG) E!I.I. I i 4 ,,y-,_,__-,,,....--.,,,--,.-y w.. --,.,_,-_,r,. y ,,,w-, v. ,--_.m.,,,,._..m ...nm, - _ -.., _. ~ - - - -.
1= i,~,r a ,.,., i <, i .e z,.,.. ~. .. y.~ r. - s 49?(c=do). t ACTUAL PEFUELING CUTA~E PE2:Os:rf : ~ ~ t L,ST ec m-. L..- .s G.. 5) s.1 O!ITAG~ t:0Tl91 ' 0'JTAGE TOTAL t.".n.. p.n. i ;_ cia ; g.
- nm.=;
r cx m. t _.w i r., :, _s,v.....m,, .; tu OCOEE 1 (2H7) 3-30 . 43 73 c,:.- 4 (.,H7) 2 m d, c- _a 0,...c 3,so.no,) a 22n
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10 x ~. s. e ' H si -1 UOv,) 3 33 . 3. If i"0-1 (2/78) 2 37 20 57 T'J:DQ (8/77) 1 .3 4 77 pes . 1q t, .f e.=Pa::, ms-x pee
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l. a o a g Actual refueling outage performance 1 i Last refueling i NORMAL SCOPE..... OUTAGE EXT.ENSION i, i i i t i ,i l 1 29 39 i OCONEE 3 / y I .N I ~ e ,[~ / / / / / / /, .( OCONEE 1 v / ~ 32 93 OC0 HEE 2 ~~~Q / ~/ / / / / [/'~ / ] / q, 53 77 RANCIO SECO ,'~ _ ]~ ~j'> f f f f f f f f f j f 3.
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_l 10 20 30 40 50 60 70 80 90 100 gp l l t j o \\ / '~ _.
) mGs,a 8 i I i I ~ OBSERVATIONS-I ~ SPECIFIC: 1. OCONEE 3'HAS THE BEST.0VEPAl.i. GUTAGE PERF0PTANE.- i 2. OCONE 2 HAS THE WORST OVEPALL OUTAE PEPf0RFME. OCONEE 3 ilAS THE BEST N0$'AL REFUELING SPNi PEPEOPJWi i 3 4. NiO-1 HAS THE WORST NORMAL REFUELI!!G SCOPE PEPEOFliANE. 5. TMI-1.HAS THE BEST OijTAGE EXTE!SION PERFOREq!E. 1 i I I I i 6. OCOMEE 2 HAS THE WORST 00TAGE'EXiaiSIdN PERFORVNE. ; i-7. ANO-1 NID TMI-1 T00X 3-4 DAYS LCGER TO FERFO.51 NORMAL i REFELING SCOPE WORK IH 1978 WHIC!! IS AN IHCPS.SE OVER PEVIOUS PZFUEOHGS AT THOSE LetITS. l I 8. TFil-1 AND OCONE 3 HAD IS.ST If?ACT EUE TO OUTAE EX-i
- TENSIGHS, AN INDICATION OF:
A. FE SURPRISES s. GOOD SCHEDU!.ING c., CONTINGStCY PLANNING D. SPARES AVAll. ABILITY' s. GOOD OUTAE FAHAGEENT/ COORDINATION COVERAE j ~~ e } ~ i 1 t JBJECT 32 CATA1.OG NO.15 100 - ], 3M CENTER. ST Pt vL. P.*- Mmeh is, w. a. -.,.---.,.,...-,-,~.,--.,.,--.---.m,_,m.-w-, ...-r-,e-----+vv,voy.,--,7.,-,--....-c---,, yw-,-.-,yM,,.,
b., .>a l}l l . ape (curh e. '0BSERVATIONS ~ GENERAL: 1. Et,W UNITS HAVE 00T PEPEORP.ED C0iFETITOR UNITS ON REFUELING SPAN TIMES IN 1977 AND 1978 TO DATE.
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2. PERPORi%NCE ON NORPAL PEUELING S. COPE WORK HAS SHO'M SLIGHT 119ROVEIST. l 1 3. PEPf0RPANCE ON OUTAGE EXTENSI0tl WORK HAS SH0ta SIGNI-l FICANT IIPROVEMENT ON BOTH CYCLE AND YEARLY BASIS. j I 1 J l f 1 i i ~ d""-4.2 CATALOG NO.15 10C " " J E C ~I' ), ?.1 CEa*T2R. ?7 * * "..u MADE Ifi U. S. A. O .------v,. c ~...an
j -~ y- ~ ~ um ,/.- (..., jr t 1meunsw ar(caco) ) ~ OUTAGE EXTE!SION CAUSES TOTAL OF LAST RERE.INGS.. *.. ,. CAUSE DAYS DA AY HUMN ERROR 45 TURBINE 23 i i OTSG'S' 27.~ I i FUEL /FH EQUIPIEhT 24 - AIF30RRE ACTIVITY IB RCP'S 7 I n EUILDING PURGE FILTERS 5 a i i i GIEilSTRY (PRIMP 3 & SEC0JGAFJ) 5 , 011!ER 7,5 1 i i e -l = a ,,,,,a-, ,e-,
.e .h, e S.' .j' g 5g(<-ce i r . a. ,r HUMAN EPRO'R i 1. DROPPED FILE IN OTSG'. 2. OTSS FILL.4iD LEETEST q.a,i, i g 3. LPI SYSTEM TESTING t. j 4..PI?kIRSTOT!NSTATORS 5. TURSIllE E0VEF30R VALVE REASSEiGLY A s,. e-6. EOLT Ili RCP INTEPRALS 2 .t.. .u F 1 a.- i 4_.G.e. Q = m .Iffi-f. 1 l
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.u g, .l M'h's ;.. / i.c; ._4Mdi:g.1_ -- 5dECT um_. CATALOC NO. m.ai 15 1006 i 2.ees:r e MACE IN U. S. A. .. ~
.'? ?- ~ y R.A.W Assia Yar.s arxne-REL MOLING EUIREfr RERE.ING OS.G$ DELh"VJUFGP.E. FiUiG A. EEFAL 3 B. REL MELING E31IXE5 C. REL iPRiSFER SY5iEE D. EPRI PFE#ii ( 4 [ e e. e M S ee e e.. en 4 A
g gxg(c.s,59) NfY ? M e = g s..,.li! E g M, 'M l W i g =8 b M i* e= I e e. ~ B = = k g 4 ~ - g tr 80 E it: 5 g a e ~3 B e Y $E _E $m N N 8 E d g E' U h a l a a a y-w -e---- .p.,-- --,e --,,n ._,-,,,,m,-.ww-,-,,---_, -,i.,-.--..,,----m --,4-...-,ee+ -,---,---,-m-- --e
~ ' ' l \\ ^- l .f l FUEL HANDLING EQUIPENT i I. REFUELING OUTAGE DEGRADERS II. UPGRADE PROGRAM l B.FUELllANDLINGBRIDGES 1.CRACKEDGUIDEPLATES 1.BRAZEENT i 1 l
- 2. IlYDRAULic SYSTEH HAINTENANCE 2.HULTI-FUNCTION MST j
DESIGN
- 3. LIMIT SWITCil ACCESSIBILITY 3.HULTI-FU!iCTI0d NAST DESIGN /GEHCo li. FA t CRA flolSJ SPEEDS fl.HULTI-FUNCTION HAST
~ i DESIGN PLUS RELAXATION 0F " SLOW" 20ilES ~
- 5. INDEXING' TIE
- 5. AUTOMATIC IflDEXING/
i INClllNG CIRCUITS l Q l W$ i t ~~ i NT k. 4 I 0 ~
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grx. %iM {oa& \\ FUEL HANDLII!G EQUIPFBIT EPRI PROGRAM 1. MULTI-FUNCTION PAST QUALIFICATION 2. AUT0FATIC INDEXING 3. INCHING CIRCUITS / STEPPING MOTORS 4. GEMCo/ LIMIT SWITCHES IMPFSVDEiTS 5. PHEUIMTIC GRAPPLE SYSTEi 6. IP. PROVED SELTm GUARDS t I 7. FRONT AC' CESS POWER SUPPLY 8.' TRANSPER SYSTEM AIR ICTOR AIR SUPPLY l l 8 4 9 -~. -. . -.. ~.. - -.. -.}}