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- November, 1982
)( 855I Office of Nuclear Reactor Regulation Attn:
D. C. Eisenhut Division of 1.icensing U. S. Nuclear Regulatory Commisssion Washington, D. C. 20555
Dear Sir:
Three Mile Isisnd Nuclear station, Unit 1 (THI-1)
Operating License _ No. DPR-50 Docket No. 50-289 Congressionsi Request for Information Concerning
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St ean Cenerator Tube Integrity (Generic Letter No. 82-22)
The following responses are supplied at your request for inforestlun dated October 26, 1982 for TMI Unit 1 operation from 1979 to the present.
1.
Now many days of unscheduled outages can be attributed to steam generator-related difficulties per year at your site?
None.
Although TMI-l is currently undergoing steam generator. repairs, the unit has been shut down since the 'IMI-2 accident as a result of unrelated licensing issues.
Even if no steam generator work had been necessary, the unit would be in outage at the present time.
Because these issues remain to be resolved, the carent to which steam generator-related work may impact the 1983 schedule is unknown.
2.
Daring cach of the years in question, how many steam generator tubes have been (a) plugged and (ti) sleeved in cach generator?
Twelve tubes in THI-l's once Through Steau Generators (O'lSCs) were Plutg'd Prior to 1979.
Three were plugged in 1979, and one in 1980.
In late 1981, intergranular stress assisted cracking ut t h e s e c ar.,
generator tubes was identified which occurred during the current outage.
In most ca6es, the damage is located high in the generator,
'where the tubes are held in place by the two foot thick upper tubesheet.
The loc 6 tion of the damage permit s the use of a repair method called kinetic expansion.
The cube is expanded agr. inst the tu beshee t, creating a trv nechanical, joint belou the dmrage.
The new joint effectively removes the damaged portion f rom servire, while pe rcsi t t ing the remainder of the t ube to be used.
'The kinette expansion is being perforned on the uppet er.ds of all 31,000 TM1-1 tubes.
Where damage has occurred on a tube that is too low to be removed from service by expansion, plug;;ing ik pl h f. tied. Approxim6tely 1200 tube 6 total for the two generators have been er will be plugged as a result of his problec.
No sleeving has been done or is planned.
3.
DO you anticipate major steac (corrator repairs iri any of yt'ur units in the next five > cars and if so, how t acn vowld these repairs cost, please be d[s 8506140166 850125 g.!)
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I speciftet The current repair program is scheduled to be complete in early J983, with no futher major repair work anticipated during the next five years.
The final cost of all phases of this repair effort is estimated to be 535 million.
4 What have been the total costs and specifically replacement power costs associated with steau. generator maintenance, repair and replacement at your plant?
The estimate of $35 million given in response to Question 3 includes i'as pec t ion, maint enance and repair for the current program.
As discussed in Question 1, no additional time has yet been spent in thin outage as a result of steam generator dif ficulties, therefore there are no associated replacement power costs.
Shoilld steam generstar related work become the controlling item in the outage schedule, replacement power costs would be approximately $12-13 million/ month.
Note the following in considering responses to items 5-9.
All man-ren values for O'ISC work are taken from self reading dusincter (SRD) records.
Thermolumenescent doaineter (TLD) data is more accurate, but is cumulative over a period of time, and does not provide breakdown by task.
There ir uncertainty. in the estimates since in some cases records of exposure do not include a task description which is adequate to determine if OTSC work was involved.
5.
What has been the total occupational radiation exposure (in person-rens) caused by steam generator (a) maintenance and (b) repair / replacement ?
Data cannot be separated into maintenance and repair act ivities.
l Exposure estir.ates for 197f were previously reported to the NRC.
Dase from 1980 was not readily retrievable. but, exposure estimates are low since steam generator work was limited to normal required eddy current t es ti ng and=== plugging of one t ube.
For 1979, 198) and 1982, total OTSC exposure is estimated as follows:
l 1979 25 person-rec 1981 16 person-rem 1982 (Jan-Det) 154 person-ree.
It is estimated that 300-380 additional person-rce can be ant icipated in association with the cu r i e nt repaira f or the per itd frun. October 1982 to completion. This es t imate ioeludes coupleting the kinetic expansion, expected plugging and testing of the repuit work.
6 Vnet percentage,o1 tutal atenual employee dose heb been attrabut able to steam generator related work at your site?
As discussed above, data available for 1960 cannot be specifically correlated to s t cac generator activity, but exposures are judged to have been low.
Esticates 1or 1879. 1981. 1982:
1979 3%
1981 111
- pai 1982 (Jan-Oct) 601 Oj fin 7.
During the years in questaon (a) how m any wus kers have acccived 3 $3 measurable radiation doses frue stran. generator reisted work, and (b) what percentage of the total work f orce do these workers represent 7 the Data available for 197Y and 1980 cannot be correlated with steam
..g y generator activity.
,g gy a.
For 1981 and 1982, our best estinates of persons who received snais measurable radiation dose from OTSC related work are as follows:
Nv:t 1981 15 2 trau
,ted 1982 (Jan-Oct) 244 be -
Measurable radiation dose was defined as greater than 10 nr.Ren on a
,wer self reading dosimeter.
in c b.
These represent approximately the following percentagen of all
,tge, individuals monitored, ts.g, 1981 10 1 cdow 1982 ggo/,,
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8.
How many tersporary workers (defined by HRC as all workers other than ilch those hired directly by nuclear plants on a convenional, long term bas!.s) received doses from secem generator related work at your facility each nhet year?
l The definition given for tenporary worker includer a number of individuals at TH1 for loog periods of time.
Included in this
,, c catelory are representatives of specialized iltas retained to assist
.g,
nog in early evaluation of the OfSG damage, Babcock and Wilcox personnel, ner' and advisors from the developers of the kinetic expansion process.
,f There were also a limited number of local craf t union persionnel hired for short periods of tiac to perfore specific tasks in the generators.
g, g Informa. ion available for 1979-1980 cannot be correlated with steam generator activities, but the number of temporary wor kers was small.
for 1981 and 1987, the number of temporary workers receiving J:;)i seasurable caposurra (greater than K nRen) and associated exposure are estima M to be:
d2 mW tio)
No. Temporary OTSC OT5G Workers person-rem
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1981 62 13 ct 1982 (Jan-August) 189 120 atw Remaining Repair (projected) 7.j. 3 $
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What terreentoge of (c) tutal work.ers involved vith e t c a s' gsnarcter-related wark d2 teepsrcry vsrkoro repressnt, ard (b) nf the total work force do temporary workea a, represent?
a.
The temporary workers discussed above represent the following percentages of all temporary workers in the OISCs.
1 0Tsc Workers 1 OTSG person-rem 1981 41 1 72%
1982 (Jan-August) 781 63%
Remaining Repair (Projected) 51 7-10%
Now that the evaluation phase of the 01$C project is over and actuut repair work has begun, approximately 95% of all workers involved with the, steam generator. repair are regular long-tere CPU employees, b.
Available records cannot readily be currelated to provide as estimate of the percentage of the totsi vork f orce that temporary employees represent.
10.
Has your company used independent firms to find temporary employees who have received an occupational dose from steam generator-related work?
Our company has not used any independent firms for the purpose of
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finding and recruiting temporary employees to work for short periods of time in,the steac generators.
However, we have used independent firms to provide specified services in some areas of arcam generator activity.
For example, the NSSS vendor, B&k*, has supplied assistance in the current repair effort and the developers of the kinetic expansion repair method have supplied experts in the process.
In a very limited number of cases, an independent firm hos employed temporary workers to perform portions of a cont racted task in the generator.
Sincerely.
u n Hukill President. 'IM1 - 1 MC.th.JAgteif
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bJr > J Nuslear SPECIAL PROCESSES AND PRO AMS (SPP}
S No.
04324 SPP -Welding Procedure Specificatp R0vlefone O Date 11/16/82 Supporting 094 D 11/16/82 rtin5 Date GPUN PUN PQR No.
PQR No.
Applicability
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4 Base Metals P.No.
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Thic ess Ren uelified fini:
I t Propertes impact Properties ot Required Required (per Codel I M I'3 OI
[FilletWelds N/A With o
d t Treatment
,E ostweld N/A N/A reatment e: gwel Treatmg ents are mined by Applicable Construction / Repair Code.
I Fill;r M y
Preheat 50*F Mininum Process......
W Preheat Temp.
A3 I
F.No.
NicrMo-3 400*F Maximum A.No..........
Interpass Temp.
Spec. No, ISFA)...
5.14 Prehest Maintenance Until completion of weld 1
ER-NiCrMo-3 N/A o,n,
AWS No. (Class)
Die. of 1/16 Postweld Heat Treatment Filler Metal Consumable N/A N/A in ser t..........
Temperature Tungsten Electrode - 2 percent N/A Time Range otner Thoriated Tungsten Electrode of N/A ogn,,
1/16" or 3/32" diameter shall be used.
Position N/A Position of Groove j
Uphill if Vertical
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Welding progression Other All positions - Fillet Type Welds A0000349 Peee l.ef1 g
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m Gas Electrical Characteristics Shneteeng Geeses, Ar1lon cu,,ent DC pese,ity Straiaht ACerDC 99.99 percent Pure
% age 3 yes,,
Page 3 P
Pwcent comoeoit en (Mistures)
(Rangel (Rangel piew Rete 15-20 CFH Travel speed 1 to 3 I.P.M.
(Rangel N/A ome See Page 3 for Amp and Volt rances.
Gee sacking Tresieng/sheelding Gee come sition N/A Gas Backing not required for Fillet g,,
Type Weld.
Technique Joints String er Weeve Seed String Greeve Design See Page 3 Orifice er Geo Cue Sise 1/4" to 3/8" Diameter Backsne N/A initial & Intersees cleaning Brushino. Grindino Omer Fillet Tyne We1d (Note 1)
(Stuohing. Grinding, etc.)
Method of Beck Gougens N/A cescuetion N/A Contact Tube to Work Dietence N/A The applicable joint design for this Mutteess ee s ngle Pose sinaia WPS is shown on Page 3.
seereisei s.ngle er Muttoie Electroces
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(1) Stringer lead k of seeds j
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l NOTE 1: Brushing shall be accomplished usine Stainless Steel tvoe wire brush not nreviously used on cachan Staal nr 1
Iow alloy steel. Grind with alumina or i
silcon carbide wheel.
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The work performed to this specification shall else meet the opp 11 cable requiremente of the GFmt Welding Progren.
Preewed by:
D. K. McConnell Asereved by:
I Feeeletl
Er c11 Nuclear l APPLICABLE JOINT DESIGN SPECIAL PROCESSES AND PROGRAMS OTSG Tube /Tubesheet Plugging i
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Att:chment #1 Nuclear o
n Special Processes & Programs GPU NUCLEAR FROCEDURE QUALITICATION RECORD (FQR)
FOR PLUG TO TUBE /TUBESHEET Procedure Qualification Record No. CPUN-094 Date 11-13-82 WPS No.
CPUN-04324 Welding Procese(es)
Gas Tungsten Arc Welding Types (Manual. Autoestic, Sani-Auto.)
Manuel JOINTS (QW-402)
SeeFigure#1,2,h4,h BASE METALS (QW-403) (Seal Weld)(Tube)(Plug) POSTWELD REAT TeEATWMT (QW-407)-
Material Spec.
ER-NiCr-3 SB-163 SB-166Tamperature N/A Type or Grade N/A Time N/A F. No.
43 to F. No.
41 Other N/A Thicknese Fillet Type Weld Diameter
.710" Other N/A GAS (QW-408)
Type of Gas or Gases Argon Composition of Cas Mixture 99.99% Pure Other Shieldine 15-20 CFil FILLER METALS (QU-404)
Wald Metal Analysis A No. NiCrMo-3 Sise of Electrode 1/16" ELECTRICAL CIARACTERISTICS (QW-409)
Filler Metal F No.
43 Current D.C.
SFA Specification.
5.14 Polarity Straight AUS Classification Fu-NiCrMo-3 Amps.
75 Yolta 10 Other N/A Other N/A POSITION (QW-405)
TECINIQUE (QW-410)
Position of Groove N/A Trevel Speed 1.5 I.P.M.
Weld Prograseton (Uphill, Downhill) N/A String or Weave Read Strinn Other Fillet Weld Performed in Cecillation N/A 2F Poniefon.
Ikitipaes or Single Fase (per side) sinole Single or 1kitip/A le Electrodes sinote FRZutAT (qW-404)
Other N
50 F Minimum Prehest Temp.
Interpass Temp.
400 F Maximum Other N/A Foge 1 of 2
RESULTS Specimen No.
PT Results VT Results Pass / Fail 1
Satisfactory Satisfactory
- Pass 2
Satisfactory Satisfactory Pass 3
Satisfactory Satisfactory Pass 4
Satisfactory Satisfactory Pass 5
Satisfacecry Satisfactory Pass Test Conducted By:
Sam Saha 90668 VT Data Report #
ill Kimick WE-43301-82 Test Conducted By:
PT Data Report #
T. Purin 53-001 B-001 Walder's Name Clock No.
Semp No.
Tests conducted by:
C.,F. Leonard 90668/WE-43301-82 hboraton ' feat h.
We certify that the statements,in this record are correct and that the test welds were prepared, welded and tested in accordance with the requirements of Section IX of the ASME Code, and Section XI of the ASME Code.
Manufacturer GPUN
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Standard Number Nuclear
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5 m s. 012 Special Processes & Programs O
1/13/82 FIGURE f 3 PERFORMANCE TUBE /TUBESHEET PLUGGING MOCK-UP REQUIREMENTS l
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Attreh at #2 Special Processes & Programs RECORD oF WELDER-QUALIFICATION TEST FOR PLUG TO TUBE /TUBESHEET TMI T. Purin ggggion y,,,
11-13-82 B-001 53-001 Date Walder ID Employee No.
TEST PERFORMED IN ACCORDANCE WITH:
GPUN-04324 WPS/ Welder Test No.
'Pruess Gas Tungsten Arc Welding SB-166 (Plug) y, ER-Nicr-3(Existing Seal Weld) SB-163(Tube)
. Nase Metals: ASME Spec 43 43 To y-No. -
.710" O.D.
Thickness Fillet (All sizes Diameter and thickness)
FILLER METALS PREHEAT GTAW Preheat Temp.
Process 400 F Maximum 43 Interpass Temp.
7-No.
Until completion of A-No. NicrMo-3 Preheat Maintenance the weld.
. Spec. No. (SFA) 5.14
' AUS No. (Class) ER-NiCrM -3 POSTWELD HEAT TREATMENT N/A Manufacturer Huntington Alloy Temperature N/A Tr:de Name ER-625 Time N/A 1/16" Heat / Cool Rate Diameter N/A N/A Other Other POSITION JOINTS SeeFiguresi1,2,h4,h 2F Fo:ition of Tubasheet Mock-Up Special Access Condition, Sketch:
Of% HEAD e 4 t h ML 4 Fws/Tuessucrt-Pagel of 2
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- Gas ELsCTRICAL Argon GTAW l-gg Composities 99.99% Pure Current DC Flow Bate-20 CFH Polarity Straight l-Gas Bach 4=_.
N/A Amps 75 l
Other Gas backing not required for Volts 10 l
fillet type weld.
Travel 1.5 I.P.M.
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TECM1QUE 1/16" String or Weave lead String Tungsten 1/16" Orifice or Gas Cup Sise 1/4" - 3/8" Elec. Dia.
No. of Layers N/A
- No. of Beads (1) one i
IIIILII Enae 4== Ma.
PT Reente.
Macro VT Results Pass /Faff i
1-Satisfactory Satisfactory Pama 2
Satisfactory Satisfactory Pass 3
Satisfactory Satisfactory Pass 4f Satisfactory Satisfactory' Pass 5
Satisfactory Satisfactory Pass Test Conducted by:
C. F. Leonard TT Data Report #
90668 WE-43301-82 (VT)By: _ S. Saha (PT)By:
B. Kinmaick FT Data Report i CERTIFICATION OF QUALIFICATIM
-By the results of this test, this welder is qualified to weld under the following conditions:
GTAW Bach 4=
N/A f-Process Material F-No.
43 To P-No.
43 f
' Thickness Bange All thk./ size Pillets To N/A
.710" 0.D. & Over Fosities 2F Eianster Range Special Restrictions Notes See Sketch Under Position Emmarks:
This WQR is based on Walder E-001 qualifyinz P.O.R.-GPUN-094. which established GPUN-WPS No. 04324.
I certify that the statements in this record are correct and that can test welos were prcpared, welded and tested in accordance with the requirements of Sections.II and Section II, cf the ASME Code.
GPUN
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11-16-82 Organisatiost m
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Page 2 of 1
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i-m Inter-Office Memor'andum Date November 16, 1982 Muclear Subject Evaluation of OTSG Stabilizer Plug (Modified Design) Welds for Welding Procedure Qualification
'IMI #1 Lab Nos. - 90668 & 90669 T
on Reading C. K. LEE On November 13, 1982, the GPUN Laboratory was provided with two sets (each containing five welds) of newly designed stabilizer plugs welded to tube /
seal weld. It was reported thar. Set #1 (Lab #90668) was welded by Mr. T.
Purin and Set #2 (Lab # 90669) by Mr. R. Hamilton using manual GTAW process with 1/16" diameter ER-Ni Cr Mo-3 (Inconel-625) filler wire. It was also reported that all of the welds have been accepted by liquid penetrant test.
The laboratory was requested to evaluate the welds to the requirements of ASME'Section XI and B&W Field Wald Deta11'as shown in Figure 1, such that new plug design and welding procedure could be approved.
Evaluation and Cor:clusion a) Twenty (20) weld faces from Set #1 (Lab #90668) were examined at 10X, 50% and 100X. All welds showed sound fusion and none revealed any rejectable defect.
b) The horizor. cal weld leg, vertical weld leg and weld throat sizes at 45 and 67 1/2 were measured on all twenty weld faces of Set #1 and were found to be over.027".
The =4n4="=
accaptable throat size for welding procedure qualification as ASME Section XI is.023" and the same as per B&W calculation is.027,".
The details of the measurement are shown on Table 1.
c) Twenty (20) weld face.s from Set #2 (Lab #90669) were examined at 10X, 50X and 100X. One weld (Weld #2-4) showed a large crack in the weld which was visible at 1X.
d) The crack on the Weld #2-4 of Set #2 does not appear to be related with the design of the plug or plug material at this stage. ~ It appears to be an isolated case and may have been caused by some external factors i
such as welding technique, presence of foreign material, etc. The lab-oratory is investigating further to determine the cause of cracking.
e) Based upon above observations, the writer concludes that:
1 The new plug design is adequate to meet the welding require-ments as set by B&W.
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2.
The welds on Set #1 have met the welding procedure qualifica-tion requirements of ASME Sectica XI.
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C. K. LEE
- Page 2 -
November 16, 1982
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The welds on Set #2 are unacceptable because of the crack observad and the welder should be requalified. Wald throat measurements, however, were over.027".
A M.
S. K. Saha SKS ajs cc:
R. B. Corbit F. S. Giacobbe B. D. Elas F. Faist N. C. Kazanas
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L. D. O!XON. MECHANICAL DESIGli' UNIT s.ei.e e.
TMI-1 OT58 M N0VDBER 2,1982 Additional' infomation is required to' assist in the-evaluation of upper TTS weld and clad integrity and its impact on tube plus designs. Therefore.
Engineering requests thet F. Faist provide the following:
i 1.
PT a minizia of 10 upper TTS OT54 welds.
It is desirable.
although not necessary to split the samples between 0754 A and B.
I 1
- 2. The test should be done all of W way around each weld selected.
and should pick up a portion of adjacentewelds.
'3.
Select the. welds from areas'in the OTSE(s) where corrosive acti'an on tube ends ir most evident.
- 4. Use the type of penetrant and PT procedure that are nomally l
used on site.
5.
Report and characterize El. indications.seen..
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It is requested that this data. be provided as soon as possible.' '
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APPLICABLE JOINT DESIGN SPECIAL PROCESSES AND PROGRAMS 4
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E E R l ]E l l gn., g StandIrd Number EMU I MTWS-013 N' P d 4 Materials Technology 0 y" 1/28/ \\ approximately 5 seconds. 6.4.6.5.1 Replace argon bottles when gas gauge pressure is reduced to 25 psi or less. TECHNIQUES #1 and #2: 6.4.7 There shall be no peening allowed. 6.4.8 The completed weld shall blend smoothly into the adjacent base materials. 6.4.9 Cas The gas used for shielding shall meet the following requirement. 6.4.9.1 Argon Type. 6.4.9.2 99.99% pure composition 6.4.9.3 Durihg welding a flow rate of 15-20 CTH shall be maintained. 6.4.10 Electrical Characteristics: Electrical characteristics shall meet the following: 6.4.10.1 Current shall be direct current 6.4.10.2 Polarity shall be straight. 6.4.10.3 The Amps and volts ranges shall be covered under the applicable WPS. 6.4.10.4 The travel speed range shall be covered under the applicable WPS. 6.4.11 Filler Materials: The filler materials and size to be used shall be addressed on the applicable WPS/ weld record sheet. 6.4.12 Joints: The joint designs to be used are shown on attachments 8.2/8.3 of this procedure and the applicable WPS.
6.5 Inspection
The following inspection requirements shall be met. acoottos
+ Standard Number Nuclear mS-Ou me 12 or 16 Materials Technology o 1/28/82 1 6.5.1 Lighting shall be sufficient enough to distinguish a 1/32" black line on an 18% neutral gray card. 6.5.2 No visual cracks and/or linear indications shall exist in the weld. 6.5.3 No visual porosity and/or blow holes shall exist in the weld. 6.5.4 No visual cold lap shall axist at the points of intersection between the weld and base materials. 6.5.5 Verify the weld is 3600 single pass minimum. 6.5.6 Any indication proving to be relevant shall be removed and repaired as outlined in Section 6.6. 6.6 Repair welding shall be as follows: 6.6.1 Grind out defective area using acceptable grinding wheels as outlined in Section 6.3.5.1. Care shall be taken not to grind into intersecting base materials or surrounding tube-welds or tube extensions. 6.6.2 Perform visual inspection of grind out to verify defect is removed and that no adjacent tubes or adjacent tubescal welds were damaged during grinding. 6.6.3 Once defective area has been removed filler material shall be uniformally added as described in Section 6.4. 6.6.4 Upon completion of welding, repaired area shall be visually inspected as described in Section 6.5.
7.0 RECORDS
7.1 The weld records used to control and document welding shall be considered service life plant records. .--g_
0 0 N %gdg7 O hY-013 Page 6 'I 6 "*" " ' o 5/27/82
- ' Materials Technology FIGURE #4 DLUG/ PLUG CROOVE EXISTING TUBE TO TUBE 3HEET SEAL WELD
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- . m THREE MILE ISLAND MhhMM PUBI.ISHED BY COMMUNICATIONS SERVICES Issue No.
Vol. II, No. 50 Phone: 8197 Date November 19, 1982 I FULL-SCALE TUBE REPAIRS UNDERWAY Repairs of heat-exchange tubes in the ,4 Unit I steam generators have begun on a full-scale basis. As of 2 a.m. November 18 some 7,504 tubes in the "A" steam generator and 10,752 tubes in - ([*- ~ 4 the "B" steam generator had been repaired i through a process known as "'aletic expansion". 1 This process had earlier been qualified and e l tested both in laboratories and at Unit 1 itself. N To date about half of the approximately 31,000 . s.g, ) tubes in the two generators have been repaired. l About 200 GPU Nuclear workers will be involved in sealing the tubes against the two-f 1 foot thick tubesheet that anchors them at the 1 top of the two generators. The repairs are expected to be completed by year's end. j The kinetic expansion will repair small 'h~~ cracks on the inside of the tubes in the upper tubesheet region. The repairs will enable j Unit 1 to be ready to resume operation next year. f WATER BOTTLES MUST BE RETURNED 1 i Island personnel are reminded that the f i Diamond Spring Water Company bottles used in j j i drinking water dispensers are not throw-away { type containers. GPU Nuclear must pay a deposit on each e- ~ water bottle. If the bottle is destroyed or damaged, that money is lost. Cutting up these " JUMP SCHOOL" -- Employees involved in Unit 2 ~ plastic water bottles to make trash containers' polar crane decontamination and repair work or destroying them in some other manner, is learn the 3 roper use of safety harnesses and j misuse of company property and a waste of rescue tec1niques during " jump school" money. exercises in the Unit 2 Turbine Building. l Here, the " victim", Bob Kennedy, left, a j Please remember that these water bottles GPU Nuclear safety administrator, has simu-j are to be reused and are not to be destroyed lated a fall from the crane and is hanging j or damaged. in midair. His rescuer, John Englick, a Bechtel training en ineer, attaches a rescue CHILDREN'S CHRISTMAS PARTY SLATED DECEMBER 11 line to lower the y ctim safely to the floor. More than 100 employees have participated in l TM! Recreation Association is hosting its such training before working inside the annual Christmas Party for children ages 10 reactor building. ] and under of GPU System employees on Saturday, December 11 from 1-3 p.m. at the itiddletown l American Legion, East High Street. -more-l 74L r 4
.,.,.. _g, - November 19, 1982 '{ 'l 4 I Activities will include a puppet show, snacks, a gift for each child and balloons. Deadline for signup is noon November 24. Reservations can be made by contacting Donna f I Hent Ext. 8210;' Betty Barb Ext. 8535; Daughn Silar. Ext. 4014; and Joan Smith, Ext. 8733. EWLOYEES CAUTIONED AGAINST TAM ERING WITH PAGE SYSTEM All TMI es audible alarms ployees are cautioned against tampering with the Island's paging system or or modifying their operation in any way. l Not only does this interfere with nomal Island communications within the plant but can result in a safety problem, particularly when emergency notifications must be made, Recently it's been discovered that some em:1oyees have been muting speakers or alams j by turning them down or by inserting rags or etwr materials in them. i Any problems or concerns with the operation of the page system should be addressed to the Unit 1 I4C Department at Ext. 8072 or the Unit 2 ISC Department at Ext. 8156. ELCOM A00ARDI Beginning with this issue of INF0/ UPDATE, a list of new GPU Nuclear employees at TMI t:111 he published on a regular basis. i' We welcome employees hired since November 1. They include: Richard Brill, Project Coordinator Senior-III Unit 2 Systems Engineering Roberta Strickler, clerk-junior Unit 1 Radiological Controls-Bruce Leonard Engineer-III, Training Department TMI MIXED B0WLING LEAGUE i Twenty-four Island employees are participating in a mixed bowling league every Thursday night at the Clearview Lanes near Elizabethtown. Six teams began bowling about six weeks ago and will continue competition into April. INF0/ UPDATE will publish league standings on a regular basis. If you'd like more infomation, i contact Jim Stair at Ext. 8477 or Terri Lombardo at Ext. 8497. i Here are the current standings: IIM WDN ME EPIC 0R 156 84 j $D5-144 gi STAS 126 116 Rads 10 14 Nukes 10 14 L Nuclides 94 146 CREDIT UNION CLUS ACCOUNTS PAY SAME HIGH DIVIDENDS Your Utilities Employees Credit Union is unique in that it pays the same high rate of dividends on club accounts -- currently 94 percent -- as it does on regular share accounts. p -more-i 3 m i
t 7 e . November 19, 1982 I While the rate of dividends on earnings can fluctuate up or down, your Credit Union has consistently paid higher than average rates. If you don't already have a club account with the Credit Union, why not ask your local agent, Chris Skinner, Ext. 8453, to open one for you today. Payroll deductions makes it easy. SPEAKERS BUREAU BUSY IN OCTOBER l The GPU Nuclear Speakers Bureau made 53 presentations to 2.810 people during October. Groups addressed included civic and business organizations, schools and colleges, and engineer-i ing and other professional groups. If you know of a group that would be interested in hearing about TMI or nuclear power l topics, contact Jack Thorn at the Visitors Center Public Affairs office, Ext. 8643. l UNIT 1 MAC O! RECTOR TO DISCUSS KINETIC EXPANSION AT ANS MEETING Unit 1 Maintenance and Construction Director Sandy Levin will discuss how kinetic j expansion is being used to repair Unit I steam generator tubes at the next meeting of the Central Pennsylvania Section of the American Nuclear Society at TMI. l The meeting is planned for 5 p.m. Tuesday, December 7 at the Training Center, and also j will provide an opportunity for prospective new ANS members to learn more about the organiza-tion. Everyone is welecme to stop in and hear an interesting presentation. For more information { on membership in ANS, contact Chet Rowe at Ext. 8030. FRIENDS & FAMILY OFFERS 'TMI STAFF' SHIRTS l l Friends and Family of TMI are making available polo shirts with the GPU Nuclear emblem and the words TMI Staff below the emblem to TMI employees. The shirts are 50% polyester and l 50% cotton, and come in navy blue, emerald green and bright red. Sizes are small, medium, large, extra large and extra extra large. i s y l N '"3 1 ~ r CiEINudm musus GPUffue" ear ommunications -more-Word Processing 1],
g,. 7 u o 4-November 19, 1982 Each shirt will sell for $13. filnce they will have to be ordered Friends and Family will need for you to pay in advance. Allow three weeks for delivery. Please have your orders in by December 6 to receive your shirt before Christmas. Call Janet Parker ext. 8741, or Sandy Polon ext. 8197, for additional information. Sil!RT ORDER FORM NUMBER CIRCLE SIZES (Men's Sizes) Navy Blue S M L XL XXL Green S M L XL XXL Red 5 M L XL XXL Send $13 check for each shirt ordered to: Jandt Parker Room 109, Unit 2 Administration Butiding Make Checks payable to: Friends & Family of TMI (Purchaseistaxdeductable) VAST MAJORITY OF SCIENTISTS ENDORSE NUCLEAR. POLL SAYS Nuclear energy development enjoys overwhelming support among scientists, contrary to widespread public perceptions that they are sharply divided on the issue. That's the finding of a randum sampling of the 130,000 scientists listed in "American Men and Women of Science." The survey was undertaken by two researchers, Stanley Rothman and S. Robert Lichter, as part of a study of American social and political trends they are conducting under the auspices of Smith College, Columbia University and George Washington University. The results are reported in the August / September issue of "Public Opinion", a magazine published by the American Enterprise Institute. More than half (53%) of the scientist polled endorsed rapid development of nuclear energy, and 36% supported slow and cautious development. Only 7% would halt nuclear energy, and only 3% wished to dismantle existing facilities. Among scientists in energy-related disciplines, moreover, the overwhelming majority (70%) endorsed rapid development. And 92% of scientists in fields related to nuclear energy (including nuclear medicine, radiation genetics, etc.) backed rapid development. One reason that scientist's support nuclear energy is that three-fourths of them regard the energy crisis as "very" or " extremely" serious, the authors say. Scientists in energy-related disciplines, moreover, "are far less sanguine than j the general public about the short-term contribution from solar energy." Only 2% of them believe any form of solar energy will provide a large amount of energy in the next 20 ,l' years. By contrast, they rated nuclear fission's potential behind only coal and oil, f ff(. from among a list of 16 energy options. . 4, j . _ _.}}