ML20024C596
| ML20024C596 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane  |
| Issue date: | 08/16/1978 |
| From: | Cobb W BABCOCK & WILCOX CO. |
| To: | Herbein J, Ohanlon J, James Smith DUKE POWER CO., METROPOLITAN EDISON CO. |
| References | |
| TASK-*, TASK-03, TASK-3, TASK-GB GPU-2031, NUDOCS 8307120855 | |
| Download: ML20024C596 (15) | |
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Sr.' user's Gr:u: Distribution
- At ac.*ec 's a ccpy of the minutes of our User's Group meeting of May 14, 1078.
Vary truly yours,
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W. A. Cobb 84W Representative B&W User's Group
' 'AO : dad A ttachment cc:
P. Cubre (SMUD)
C. Domeck (Toledo Edison) l
- Per attached distribution list l
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- s DISTP.iBUTION LIST O.
84W USER'S GROUP Mr. J. G. Herbein (Jack)
Mr. R. J. Rodriguez (Ron)
Vice President, Generation Manager, Nuclear Operations Metropolitan Edison Company Sacramento Municipal Utility 0! strict P.O. Box 542 Rancho $2co Nuclear Generating $tation Reading, Pennsylvania 19603 P.O. Box 550 Herald, California 95638 (215) 329-3601 (203) 748-275)
Mr. W. A. Cobb
(
. A1)
Mr. G. P. Beatty, Jr.
(Guy)
Manager, Generic Projects Nuclear Plant Superintendent Sabcock & Wilcox company P.O. Box 1260 Florida Power Corporation P.O. Box 1228 Lynchburg, Virginia 24505 Crystal River, Florida,32623 (804) 384-5111 (304) 735-6486 ir. J. Ed Smith (Ed)
Mr. J. G. Evans (Jack) itation Manager henes !!uclear Station
. Assistant to VP, Ener2y Supply Toledo Edison Company 2.0. Box 1175 300 Madison Avenue i
ioneca, South Carolina 2S678 Toledo, Ohio 43652 (803) 882 l
.(41S) 253-5690
- r. J. P. O'Hanlon (Jim)
Mr. G. P. Miller (Gary) nit 1 Superintendent Station Superintendent heee Mlle Island Nuclear station Three Mlle island Nuclear Station a
.etr,opolitan Edison Company
.0. Box 480 Metropolitan Edison Company P.O. Box 480 iddletown, Pennsylvania 17057 Middletown, Pennsylvania 17057 (717) 944-4041 (71'7) S44-4041
. G. H. Miller (Gordon)
Mr. R. W. Montross (Bob) lant Superintendent Plant Superintendent rLansas Nuclear One
.- Consumers Power Company
.0. sex 608 1945 Parnall Road assellville, Arkansgs 72801 Jackson, Michigan 43201 (501) 968-2519.
(517) 788-2242
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REV 7
'8/16/78 O
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DISTRIBUTION LIST (C0!!T'0) 8t,W USER'S GROUP Mr. A. M. Quall s Plant Superintendent Mr. Robert Goyette Nuclear Operations "E
0 Power Authority of the State of New York 10 Columbus Circle WII W, Alahma New Yarir, u= Ya+
19413 (205) 259-0420 (212)397-2396
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Mr. John Ahladas
. Mr. H. Ray Caldwell (Ray)
Station Manager Nuclear Operations Engineer North Anna Power Station Ohio Edison Company P.O. Box 402 76 South Main Street Mineral, Virginia 23117 Akron, Ohio 44308 (703) 894-5151
. (216) 384'-5778 Mr. T. L. Baucom Mr. L. L. Lawyer (Sandy)
. Station Superintendent Manager, Generation Operations Surry Power Station
- Metropolitan Edison Company P.O. Box 315
- P.O. Bog 542 Surry, Virginia 23883 Reading, Pennsylvania 19603
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(703) 683-0300
'(215) 929-3601 Mr. J. E. Holder (Joe)
Mr. C. Goodwin, Jr.
P1 ant Superintendent Vasnington Public Power Supply System.
Assistant'VIce President Portland General Electric Company 3000 George Washington Way 121 S.W. Salmon Street j
P.O. Box 368 Portland, Oregon 97204 Richland, Washington 99352 (509) 946-1611 (503) 226-8388 Mr. T. D. Murray (Terry)
Station Superintendent Toledo Edison Company Davis-8 esse Nuclear Power Station 5501 North State Route 2 Oak Harbor, Chlo 43449
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l MINUTES OF MEETING - B&W USER's GROUP MAY 4, 1978 GENERAL The S&W User's Group met on May 4,1978 at the O' Hare Hilton Hotel In Chicago, IIIIncis.
A copy of the list of attendees Is attached as Enclosure 1.
In general, the meeting followed the previously prepared agenda, a copy of which is attached to these minutes as.
Mr. J. G. Evans, User's Group Chairman, chaired the meeting.
REVIEW OF GTSG TU8E PR081.EM Mr. u. W. Montgomery of S&W presented a review of the OT5G tube problem.
In beginning his presentation Mr. Montgesesry indicated that the 075G tube eroblem was not strictiv a comoonent eroblem, but also involved the Interactions with the secondary system, i.e.,
tne source ano quality or reeowater, procecures usec in operation, teatures or the feed-water cleanup systems, and possible non-documented practices in operation of this overall The first part of the slide presentation was devoted to the geometric features system.
.of the OT5G and the differences In the 075G's on the various units.
Key items described were the open tube lane and the gap between the support plate and the shroud, each of which presented a possible path for moisture bypass.
Mr. Montgomery-then showed a silde of the cross taction of the OT5G tube bundle and indicated the tubes which have had oddy current Indications. In making this presentation he Indicated that some later OT5G units have operated successfully past the time where indications first showed up on some earlier units.
He also indicated that the quantity of Indications appear to be much greater en OT5G's having longer steam lines as compared to their companion OTSG's.
A description was then given of the '"ba w eies which had been removed from QTSG's at Oconee and ANO #1, a total of eight f rom the Oconee units and one from ANO.
Various slides were presented showing micrographs and other photographs of the defects.
He prn-sented the followino oossible causes for the various Indications:
(1) Metal fatigue due to flow-induced vibration (applied stress Insufficient to cause failure without other Initiating mechanism) j (2) Mechanical wear (no failures due to this mechanism) l (3) Liquid-impingement erosion or possible combination of corrosion and
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erosion (4) Corrosion pitting.
He also presnted ehr** emnihie eeneributImo factors:
1 (a) Systen design (entire secondary system)
(b) OTSG features (c) Plant operation.
1
2-Under system design he mentioned feedwater line length, feedwater heating capability, feedwater oxygen control and steam line configuration as passible influences.
Under plant operation he cited the use of the auxiliary feedwater nozzle for startup and shut-down of the unit, as well as turbine stop valve testing, bypass of condenser dominerali-zers, and water hansner in the feedwater system.
Mr. Montgomery presented BsW's overall 0TSG program as being comprised of the following elements:
(1) Site Inspections (2) On-site testing (3) Review of plant operations (8sW Is preparing a proposal to the Owners on this)
(4) Tube sample evaluation (5) Manufacturing review (6) Lab testing (7) Analytical programs
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(8) Chemical cleaning studies (84W-EPRI contract).
Con described each of these program phases in some detall and then concluded his pre-sentation by presenting the seesthie fivas en the OTIC's.
Two specific possibilities mentiones were the QTSG tube stiffeners and mechanteal flow blockers for the open lanes.
He indicated that it has not yet been decided to what extent these mechanical fixes will be employed.
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SECONDARY SIDE WATER CHEMISTRY l
Merl J. Bell of B&W started his presentation by emphasizing the importance of meeting the feedwater chemistry specifications during hot functional testing, not only for feed-water addition but for the water inventory in the steam generator itsglf. He also mentioned the t_emoerature decendence of hydrartne for erecer seaveneino.
fdeoer was identified as havino been found In the unoer region of some OTSC's at a loca-tion away from the coen. tube lane. Copper tunes in tne renester are a possinie source of this esement wnica may oe a catalyst for undesirable reactions. Concentrations in the 075G are accentuated by the ptseping forward of the reheater drains without going through the domineralizers.
Mr. Bell next reviewed the overall 073G feedwater spec's for operation both during normal power production and during startup. He emphasized that Iron was to be held proportional to power level from 100 ppb at startup down to 10 ppb at 100% power.
Feedwater chemistry history was reviewed for 1977 on all the 8sW operating units.
The general conclusion here was that the ehemiterv eeneret dortne 1877 was se<<rbiv ane==
esed as durino le76. The importance of feedwater chemistry during layup was emphasized.
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3 Significant points made were the following:
(I) Possible sulfur attack on incoael under low ph (2) The importance of mixing of chemicals throughout the whole OTSG.
(There should be circulation to turn over one volume in eight hours.)
(3) The undestrahllity of a partially filled generator.
A comparison was presented of the design of secondary plant for the various units. Items compared were the cooling systems, condensate polishlng systems, LPFW and HPFW tubes, and reheater and condenser tubes. Specific points emphasized were the following:
(a) Imoortance of being able to dump HP drains back to the condenser during startup (b) Importance to utilities of having 84W review Individual secondary sys-tems for possible adverse influences on the OT5G's (c) The Importance of proper regeneration of condensate domineralizers (may lead to high sulfur in feedwater (d) Importance that " fines" from powered resins not deposit sulfur in OT5G's.
Merle next described the variation of chemical samples from various places In the TMI #1 cycle and emphasized the Importance to the OTSG of the following:
(1) Never bypassing the damlneralizers
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(2) SuvIng high ouality resins Initially (3) Emoloving good regeneration procedures.
In conclusion he described th'e deposits which had been found in various'steem generators along with the locations of the deposits. He particularly mentioned the white rock-like deposits on the lower tube sheet at Ocones and passed a sample out for Inspection.
1 075G LEVEL CONTROL DURING HEATUP W. A. Cobb of B&W described a problem which had arisen at Davls-Besse 1 regarding 075G feedwater nozzles. The purpose was to describe the proolem and give status and possible I
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consequences. The problem was defined as 84W operating procedures requiring the feedwater nozzles to be flooded during startup conditions (up to 388 Inches level), whereas the standardized Tech Specs specify that the OT5G level should not exceed 348 inches. Mr.
Cobb described the arrargement of the feedwater nozzles on the OT5G and explained that the recur rement that the feedwater norries he f reeded arose from sernet eens ide rs* f ene.
l For the units using 90' minimum feedwater temperature the stresses in the external feed-water supply pipes are relatively high if there is an Interface between water and steam
, existing in the supply pipe, as would occur at zero or low steam flow. If there are a large number of cycles using 90* feedweter, and the supply pipes are not flooded, the lifetime of the welded feedwater nozzles may be less than the desired 40 years. It was further explained that the situation usino oo' minimum feedwater an<l un-fleeded mer?les had aee vet been analvred althouch the analysis was la c rec es s. The
. lifetime was estimated to be in excess of five vears for this conditlen although no Final numMrs nave Deen develeced, r
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UPDATE OM RECENT REFUELING EXPERIENCE Mr. J. D. Phinney of S&W made this presentation. He Indicated that a total of 13 refuelings of B&W plants have now been. completed at an average cost of approximately sfe' t h ml11 ten each and an averace man-ren exoenditure of 21k. During 1977 the over-all refueling outage performance was 73 days from breaker-to-breaker. Over the last three refuelines on Oconee Ill. ANO, and TMI El the averace was 48 davs breaker-to-l gbrner tocoree 118 - 44 An0-1
- 57. TMI di - 46).
He reported the following items j
as arfecting refueling on the listed plants:
Oconee ill - RV nozzle Inspection, OTSG repeles, AC pump motor work. FW t
cleanup ANO /1
~ - Stud cleaning, 21% eddy current inspection (212 on OTSG A; 9% on 8), AC pump motor Inspection, hydraulic snubbers, diesel generator turbo-charger fire TMI #1
- Cutup of Incores, eddy current inspections of OT5G's (12% A; 9% 8), AC pump seal problaes REVIEW OF PROBLEM WITH 80RNABLE PolSON R00 ASSEM8 LIES AT CR-3 This presentation was also made by Mr. J. D. Phinney of B&W. Jim Indicated. that the arablem started with loose cart monf terIno Indiestions on Februarv 17. Te78 and that a decision was moos on February 13 to run the unit on three pumps for approximately two weeks. The unit was shut down on March 3,1978. Upon video inspection of the OTSG on March 7,1978 seventeen places (1 Iarge,16 small) of the 8PRA spider parts were found on the tune sheet of the "B" generator. The "A" generator was clean. Radiation level of 7-8 R/hr. was measured. Upon Inspection of the reactor vessel Internals one BPSR was found hanging out of a plenum flow hole. The two affected BPRA's were 852 and 847 which are both located on the periphery of the core.
Since the Florida Incident the BPRA's at other sites have been Inspected. Results (including CR-3) are as follows:
J (a) CR Two SPRA latches released. Three 8PRA latches worn through.
Significant wear on other SPRA latches. No orifice rod latch wear.
(b) Oconee - Minor SPRA wear (Inspected in spent feel pool). ORA's o.k.,
but some balls fell out on unlatching.
(c) ANO #1 - Results similar to Ocones, but even less severe.
it was pointed out by Mr. Phinney that the SPRA's on the 205 units are of a different design and this problem Is not. anticipated.
(The SPRA's and ORA's are held down with the upper plenum assembly.
The presentation was concluded with a descrlotion of the tube sheet damace at CR-3 The following numbers of tubes received tne camage inoicated:
8500 cubes with rolled over tube ends 300 tubes with broken rolled-over tube ends (no weld damage in either of the above cases) 3100 tubes with minor weld damage 2800 tubes with major weld damage
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- q r4 5-d Jim indicated that there would probably be a two-stage repair; initial reaale l'n which chips would be removed and some crindino of tube ends woute ce eer1ormeo ano an ultimate resair so that an ecov current oroce would pass.
Pt. ANT EXPERIENCE REPORTS Plant experience reports were given in the following order by the station superintendents.
Operations at Crystal River 3 - Florida Power Corporation - Mr. G. P. Beatty reported on operations at Crystal River 3 as follows:
(1) Core support assembly is due to be re-Installed 5/8/78. Orifice rod assemblies are Installed In BPRA slots except for eight locations which will be vacant. An attempt will be made to be back on line the first week In July after making the simple OTSG fix. The domineralizers will be duuped without attempting regeneration.
(2) Recardino the 8PRA croblem the followine events a'doarently cave s-warn-Ino of the Impending 8PRA croblem (althouch not recognized at the time):
(a) A quadrant power tilt was noted on December 11. 1977 (b) There _wes sane flutter signal of the accelerometer detectors on the reactor vessel head.
(c) The letdown filters were changed six times In twelve days because of high pressure drop.
(d) Chemical analysis showed a slight increase In zirconium.
(3) The following capacity factors for CR-3 were given:
Novisnber - 94%
December - #2%
January 92%
February - 3 pump operation for 1/2 month (4) The following miscellaneous results were reported:
(a) Repatching of rods was done on 1/31/78.
(b) Rod drop test went off o.k.
- (c) No noise with three pump operation.
i (d) There has been a problem with the GE main secp up transformers, (e) All A-C circulating pump motors are being rewound.
t (f) Need 84W closures for survelliance capsule holder tubes.
I Operations at Oconee - Mr. J. Ed Smith gave the report on Ocones. Items reported were as follows:
Se (1) The tilt at end-of-l f fe wi th three pumo operae ton Is still a mysterv.
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p (3) There was a 88 capacity factor for the first quarter and the Oconee units provided 332 of the total system power in March.
(4). There was en OTSG 1eak in Unit 1 in late Apell, the first in an Oconee unit since S/27/77 I.e., seven months without a leak.
(5) Unit 3 la scheduled for refueling in June. The refueline is otanned to utilire a 34 day period.
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(6) There have been variations in the chierlde levels of the systems.
Sys-tems have been In and out of spec, particularly on startups.
(7) Problems were reported with the control red drives with four stator s
failures !n six months, also fuse failures.
(8) On Unit 3 there have been low RCPM oil level alarms without apparent reason; now running on three pumps.
(9) Units 1 and 2 have been plagued with high air born activity within the-reactor building. Delay required before purging.
(10) The pressurizer heater bundle gaskets have been leaking. Duke will probably seal weld all joints.
(11) Oconee is planning on going to an 18-month fuel evcie starting with Unit 2 at the second coming refueling.
Doerations at Three Mile island - Mr. G. P. Miller TMl Station Superintendent, reported on overall station operations and on operations at Unit 2 (Mr. O'Hanlon, Unit Superinten-dont of Unit I reported on operations for Unit I).
(1) Last refueling was 46 days breaker-to-breaker (Unit 1)
(2) The following chronology on Unit 2 was given:
8/9/77 - HFT 2/8/78 - Operating IIcense 2/11 to 2/14/78 - Load fuel 3/10/78 - 400*F j
3/28/78 - Critical i
4/21/78 - Breakers closed 4/23/78 - Power operation (3) The following recent problems with Unit 2 were enumerated:
(a) NOAH was inadvertently pumped into the primary system primarily because of differences in piping from Unit 1.
(b) There has been a problem with the AC p e p motor clutch on pump 24.
(c) There was a trip from 30% power in which the system lost 700 pst and l
130*F.
(4) Unit 2 is expected to heat back up during the week of May 8th and to obtain
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hot conditions approximately 5/12/78. 304 power and 100% power are expected on May 16th and May 31st respectively, if no new problems are encountered.
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Mr. Miller Indicated the following problems in administration:
(a) The superintendents are submerged in paper (reports, etc.)
(b) There is some problem in maintaining manpower (level and quality).
(c) An administrative superintendent should probably be added to,
-manage paper.
Mr. O'Hanlon reported on TMI #1 operations as follows:
(1) Refueling was' Just completed as reported by Mr. Miller above.
(2) The following chronology was given on refueling:
Day'6 - Reactor head off Day 14 - Fuel shuffle complete Day 22 - All reactor work completed Day 24 - Letdown cooler replaced Day 30 - Complete Integrated leak rate test Day 32 - Vacunn in condenser Day 46 - Breakers closed (3) Low pressure turbine "A" was Inspecte, and a leak was fixed on the high a pressure turbine.
(4) There has been a problem with the Whiting polar crane (bearings, clutch).
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(5) Both the LOCA leek rate test and the integrated leek rate test were suc-cessfully completed on the first try.
(6) One tubs was plugged on the "A" 073G and one tube with a 65% Indication was plugged on the "8" OT5G after 9% tube inspection.
(7) Nine days were reported for entry Into the OTSG. It was suggested that to do this quicker the vacumn should not be broken until the 075G was cool.
(8) Seventeen snubbers were inspected (ten required by tech spec, one fa!!ed to lock and ten more were inspected).
(9) The first group of Incores were chopped up for disposal. The All-American i
Engineering system did not work and a new system was designed. 300-400 MR average exposure was incurred.
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(10) A problem was reported with the AC pump. Af ter Inspection the purp could not be hand rotated as specified. When dismandling was done to Investi-gate the problem a 4" carbon steel bolt was found which had been lef t from the prior ses! Inspection.
(II) The following general problems were reported:
(a) E3 test was performed (the makeup pump tripped on the way down).
(b) A problem was experienced with the oII pressure switch on the diesel generator.
(c) A problem was experienced on the AC pump with a ground between the housing and the motor.
(d) The OH ptanp shaft is being replaced with one having a radiused key way.
(e) Respitory protection during maintenance procedures Is a very signifi-cant problem.
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- (I:l) TMl-1 is looking at a 18-month fuel cycle, probably two refuelings In the future.
1 (13) Letdown cooler was replaced (one replaced last year also).
Goerations at ANO John Anderson reported on operations at ANO #1 as follows:
(1) A problem was experienced with r**e*er hutidtae erare et t delps.
(2) ANO is chmaetae en af f-mechanical snubbers In the reactor building (except the c,nes on the reactor coolant pump).
(3) RefueIInc was accomolf shed In 55 davs breaker-to-breaker with fuel thuffle being accomplished in five davs. Total radiation exposure was e2o man-rem incluainc 03G insoection.
(4) Twenty-five outace days were experienced with the turbine due to vibration, governor valve leaks, and problems with the last row of low pressure turbine blades (some were replaced).
(5) A problem was Indicated I'n wet tavuo of the OTsc In attaining a completely filled condition (the water volume shrinks after the unit is filled).
(6) Leaks were reported in the HP call of the MSR.
(7) Scheduled date for refueling of brand "X" (Unit 2) was reported at 6/5/78.
Coerations at Rancho Seco - Ron Rodriguez reported on operations at Rancho Seco as follows:
(1) Capacity factor in December was 94%, but was reduced significantly after failure of transformer.
(2) ofI =ddieiens have b::d recutred to RC oump.
(3) The unit has been operating with sprav valve diffleulties.
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(4) Plentiful supply of hvdre oower in California has influenced operation of Rancho Seco.
(5) Refueling anticipated approximately 12/5/78.
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(6)
Mr. Rodriguez then asked Pierre cubre of SMUD to report on the March forced shutdowr, at Rancho Seco. Mr. Cubre reported that on 3/20/78 a shutdown was precipitated by a consolo light which shorted across the l
terminals. Because of the relationship between NNI "Y" and NNI "X" buses the reliability of Infonnetton was lost. The feedwater valves and pumps operated to restrict flow and the unit tripped. Manual HPI Injection occurred. The feedwater pump was manually operated to in-crease flow and the unit went to 285'F RC temperature, with the result t
that the unie was outside the allowed PT curve for aceroxima telv thirty l
minutes.
The "8" OTSG was full of water (and the steam lines were probaoly full). The "A" OTSG was dry. 85W has performed the required ASME analysis to assess the effect en the unit.
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9 Oserations at Davls-Besse Mr. J. G. Evans reported on operations at Davls-Besse-I as foilaws:
(1) The unit was at 100% power for 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> during the first part of April.
(2) The unit helped in carry!ng system loads at 75% during the coal strike (ran on three pumps because of 8PRA problem).
(3) On 4/28/78 the unit was shut down for four weeks (tripped). The following will be accomplished during shutdown:
(a) Remove screens (b) Take BPRA's out and Inspect. Make decision after Inspection whether to replace with ORA's.
(4) 80-90 full power days"have been logged.
(5) There has been one significant trip from 754 power.
There was water hamer In the extraction piping and a water sluo hit the non-return valve and bent the support.
REVIEW 0F CHARTER Mr. J. G. Evans led a discussion of the proposed charter forwarded with Mr. Cobb's letter of April 28, 1978. The document was not reviewed in detall during the meeting, but the consensus of the superin*endents was that we should not have a technical committee, or executive'comittee as Indicated in the merked up copy.
fat.L 1978 MEETtNG lt was agreed that the next meeting of the User's Group would be held in New Orleans, La.
on October 455, 1978. The meeting adjourned shortly after 5:00 p.m. on May 4,1978.
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bu ENCLOSURF I ATTENDEES 84W USER'S GROUP MEETING Name
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Company J. Ed Smith (Ed)
Duke G. P. Miller (Gary)
Metropolitan Edison - TMI #142 J. P. O'Hanlon (Jim)
Metropolitan Edison - TMI #1 G. P. Seatty (Guy)
Florida Power J. W. Anderson (John)
Arkansas Power & Light R. J. Rodriguez (Ron)
SMUD P. Cubre' (Pierre)
SMUD R. W. Montross (Bob)
Consumers
- . G. Evans (Jack) - Chairmen Toisio Edison C. Doneck (Chuck)
Toledo Edison A. M. Qualls (Allan)
TVA J. E. Holder (Joe)
WPPS$
H. R. Caldwe!!
(Ray)
Ohio Edison D. W. Montgomery (Don) 84W M. J. Bell (Merle).
8sW W. A. Cobb (AI) 85W J. D. Phinney (Jim) 8sW R. E. Wascher (Sch) 84W J. T. Janis (Joel) 84W 4
,q ENCLOSURE 2 AGEN0/.
84W USER'S GROUP MEETING MAY 4. 1978 8:15 - 8:30 COFFEE ANO DANISH 2:30 - 9:45 REVIEW 0F OTSG TUSE PROGRAM
- 0. W. MONTGOMERY (00N)
UPDATE STATUS FUTURE 9:45 - 10:00 C0FFEE OREAK I0:00 - 1I:30 SECONDARY $l.0E WATER CHEMISTRY M. J. BELL (MERLE) 11,:30 - 11:50 OT3G LEVEL CONTROL DURING HEAT-UP W. A. C088 (AL) 12:00 - 1:00 LUNCH (BUFFET IN MEETING ROOM) 1:00 - 1:45 (1) UPDATE ON RECENT REFUELING EXPERIENCE J. O. PHINNEY (2) REVIEW 0F PROBLEM WITH SURNA8LE PolSON (JIM)
R00 ASSEMBLIES AT CR-3 1:45 - 2:00 S&W UPDATE ON PRIOR PROBLEMS W. A. C088 (AL) 2:00 - 4:00 PLANT EXPERIENCE REPORTS OCONEE
/J.
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TMI JG. P. MILLER (GARY)
/J. P. O'HANLON (J IM)
ANO J. W. ANDERSON (J0HN)
CR-3
./G. P. BEATTY (GUY)
SMUD
=/R. J. RODRIGUEZ (ROM)
J. G. EVANS (JACK)
TECO 4:C0 - 4:30 (1) REVIEW AND ADOPTION OF GROUP CHARTER (ANNOTATED ORAFT ATTACHCO)
(2) LOCATION AND DATE FOR FALL MEETING l
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