ML20032E789
| ML20032E789 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/13/1981 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8111230182 | |
| Download: ML20032E789 (9) | |
Text
_
O Omaha Public Power District 1623 HARNEY 5 OMAHA. NEBRASKA 68102 a T E L.E P H O N E 536-4000 AREA CODE 402 November 13, 1981 bM@ y.
w Y84 f\\
l Ngy8 l--i,, %,g IS8/ A Mr. Thomas M. Novak Assistant Director for Operating Reactors y
%s,h 4 Division of Licensing U. S. Nuclear Regulatory Commission p,
%k's.. &'Q '
Washington, D.C.
20555 Y
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Reference:
Docket No. 50-285
Dear Mr. Novak:
This is in response to your letter of October 28, 1981 concerning Fort Calhoun reactor vessel weld material Womation.
In our 60-day response of October 20, 1981, we indicated that the weld metal RTNDT values were based on generic material properties.
This point requires clarification in that those RTNDT values were in fact based on plant specific Charpy test data for the Fort Calhoun reactor vessel weld qualification test materials.
The generic data referred to in our letter were used as a benchmark for the Fort Calhoun Charpy weld qualification test data so that a conservative RTNDT estimate could be established for the weld seams. The generic data, consisting of indi-vidual RTNDI determinations for 81 submerged arc weldments had a mean value of -5/ F and a standard deviation of 180F. The Fort Calhoun weld 0
seam materials were judged to fall within the range of RTNDT for the generic weld nopulation based on the equivalence of weld fabrication procedures (i.e., sample processes and the same types of welding materials) and the magnitude of the weld qualification test measurements.
There-for these weld seams was conservatively estimated to fore, the RTND l
be -200F, the { sigma upper limit of the generic population.
Subsequent to October 20, 1981, drop weight tests were completed on an archival sample of a weld representative of that used in the fabri-cation of the Fort Calhoun reactor vessel (the surveillance weldment).
The drop weight results were then used to establish an initial RTNDT -500F for that weldment.
Since the RTNDT of this weldment is very close to l
the mean RTNDT of the generic data (-570F) and because it is more closely representative of the Fort Calhoun vessel weld seams than the generic data base material, it was used to establish more accurate estimates of the initial RTNDT of tt.a weld seams.
j b
8111230182 811113 L
PDR ADOCK 05000285 Si \\
P PDR l
Mr. Thomas M. Novak November 13, 1981 Page Two This new plant specific information is being submitted in Enclosure (1), Sheets 1, 2, and 3, and Enclosure (2) as a supplement to our 60-day response of October 20, 1981, as requested in your October 28, 1981 letter.
In addition, the methodology used to establish the revised RTNDT values is discussed in Enclosure (3).
We trust that this information will be sufficient to permit you to complei" your evaluation without recourse to the more conservative approaci, entioned in your letter of October 28, 1981. The District is participat,'g in the CE Owners Group on pressurized themal shock and will provice additional infomation and analyses in accordance with previously arranged schedules.
Sincerely,
/
d@M W.CfJones Divi ion Manager Production Operations WCJ/KJM:jmm tnclosures c.c :
LeBoeuf, Lamb, Leiby & MacRae 1333 New Harpshire Avenue, N.W.
Washington, D.C.
20036
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s-Sheet 2 Designation on Figure FORT CALHOUN Longitudinal Seam Welds -
Upper Shell Course 1-410 A, B and C Intermediate Shell Course 2-410 A B and C Lower Shell Course 3-410 A, B and C Girth Seam Welds -
Upper to Intermediate Shell 8-410 Intermediate to Lower Shell 9-410 '
Shell Course Plates -
Upper D-4801-1, 2 and 3 Intermediate D-4802-1, 2 and 3 Lower D-4812-1, 2 and 3 Assumptions Residual Chemistry - as measured or:
Copper 0.35%
Upper Bound Phosphorus 0.012%
Upper Bound Nickel (as measured)
Initial RTNDT -
As measured or Branch Technical Position MTES 5-2 for plates See Enclosure (3)..for welds J
Peak Vessel ID Fluence (using 1500 MWe = full power) 18 2
5.12 EFPY 7.04 x 10 n/cm (12/31/81) 8.15 EFPY 1.12 x.1019n/cm2 (12/31/85)-
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TRANSITION TEMPERATURE SillFT P.ETil0DOLOGY l
FOR ALL PLATE MATERIALS -
REGULATORY GUIDE 1.99 (REV. 1):
.08) + 5000 (P
.008) )[ (3lrs)
FOR ALL WELD MATERIALS -
2 REGULATORY GUIDE 1.99 (REV. 1) IF NICKEL CONTENT.!S MORE THAN 0.30%
MODIFIED REGULATORY GUIDE 1;99 IF 3
NICKEL CONTENT LESS THAN 0.30%:
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S3HONI (2) s.ansopu3 73 37220N WOW 3 33NUIS10
Enclosura(3)
BASIS FOR PLANT SPECIFIC RT WELD VALUES NOT The plant specific RT values were obtained using actual Charpy data from weld qualification teEEI for each of the Fort Calhoun weld seams,used in conjunction with data from the surgeillance program weldment for which the has now been determined (-50 F). The individual weld RTtekk.Tresults (three Charpy impact specimens tested at +10 F) qualification are listed in Table 1.
Each weld which exhibited an average Charpy energy of 57 ft.-lb.
or greater (the average Charpy energy for the surveillance weld at 10 F) was 0
considered to be af least as tough as the surveillance weld; fe, that weld seam RT was For those weld qualification test results exhibith an av-50 F or less.
erage Charpy energy less than 57 ft.-lb., the RT was increased by an amount equivalent to the temperature difference EhIween the averagy Charpy energy transition curve for the surveillance weld and the average Charpy energy for the vessel weld test results (+20 F). Effectively, 0
the temperature at which 50 ft.-lb. or better exists was detennined, and the RT was established at a temperature 600F below that value. The resultant esEkdated RT given in TabygT) values for each of the Fort Calhoun vessel weld seams are es
d TABLE 1
)~
FORT CALHOUN REACTOR VESSEL WELD SEAM TOUGilNESS DATA Charpy(Energy at 100F AverageEnergy Estimated ft.-lb.)
at 10 F (f t.-lb.)
RTilDT ( f)
Weld Seam 1-410 A/C 79, 86, 80 81.7
-50 2-410 A/C 50, 60, 73 61.0
-50 a
3-410 A/C 60, 64, 56 60.0
-50 b
74, 63, 82 73.0 8
63, 60, 49 57.3 8-410 62, 83, 99 81.3
-50 9-410 35, 50, 48 44.3
-30 d
Surveillance.
'd 51, 55c 57
-50 a
Tandem submerged arc weld wires b
Single submerged arc weld wire 0
c Test results at 0 F d