ML17346A186
| ML17346A186 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/10/1984 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR L-84-31, NUDOCS 8402160148 | |
| Download: ML17346A186 (14) | |
Text
REGULATOR'i NFORMATION DISTRIBUTION S fM (RIDS)
ACCESSION NBR:8402160148 DOC ~ DATE 84/02/10 NOTARIZED:
NO FACIL;50>>250 Turkey Point Planti Unit 3i Florida Power and Light C
50 251 Tur key Point Planti Unit 4i Florida Power and Light C
AUTH'AME AUTHOR AFFILIATION HILLIAMSiJ.N.
Florida Power 8 Light Co.
RECIP,NAME RECIPIENT AFFILIATION EISENHUTiD.G.
Division of Licensing DOCKET ¹ 05000250 05000251
SUBJECT:
Forwards pressure ized thermal shock reactor vessel matls data summa ygper 840119 discussion
~ Review L concurrence by 840501 requested'irection of analytical effort will be effected by results of review..
DISTRIBUTI'ON CODE:
A049S COPIES RECE'I VED: LTR J ENCL J SIZE ~
TITLE:
OR Submittal:
Thermal Shock to Reactor Vessel NOTES:
RECIPIENT ID CODE/NAME NRR ORB1'C 01 INTERNAL: ELD/HOS4 12 NRR VISSINGg G04 NRR/DHFS DIR NRR/DL/ORAB 11 NRR/OS I/RSB NRR/OST/GIB RES/DET RGN2 COPIES
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EXTERNAL: ACRS NRC PDR NTIS 10 02 6
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FLORIDAPOWER & LIGHTCOMPANY LTR L-84-31 February 10, 1984 Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G.
Ei senhut, Director Division of Licensing U.S.
Nuclear Regul ato ry Commission Washington, D.C.
20555
Dear Mr. Eisenhut:
Re:
Turkey Point Units 3
8 4
Docket Nos. 50-250 8 50-251 Pressurized Thermal Shock-Reactor Vessel Materi als Data The Turkey Point Units 3 5 4 RTNDT was established for the purposes of evaluating Pressurized Thermal Shock using materi al data obtained from the initial weld qualification report and a chemical analysis of a surveillance capsule.
In a discussion with your staff on January 19, 1984, we presented a
much larger data base of information on the chemical composition of the weld.
This additional information was obtained through the use of information previously held as propietary by the reactor vessel fabricator.
Therefore, please find attached' report summarizing the available data.
The evaluation of this data results. in our conclusion that the RTNnTi i should be 10 F without any standard deviation, Copper content equal to 0.25 wt 5, and Nickel content equal to 0.60 wt $.
We request your review and concurrence by May 1, 1984.
The results of your review are necessary to plan our future PTS efforts.
We plan on continuing all efforts regarding flux reduction and improving our ability to quantify the results.
However, the direction of our analytical effort will be effected by the results of your review.
Very truly yours, ku'.W. Willians,Jr.
Vi ce President Nuclear Energy JWW/JEM/djc Attachments cc:
Mr. Jones P. O'Reilly, Region II Mr. Harold F. Reis, Esquire 8402f60i'48 840210 PDR ADOCK 05000250 P
PDR PEOPLE... SERVING PEOPLE
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The reactor vessels at the Turkey Point Units 3 and 4 nuclear power plant of Florida Power and Light (FP8L) were fabricated by Babcock and Wilcox (BEW) for Westinghouse, the nuclear stem supply system designer.
The intermedi ate to lower shell girth welds were made using automatic submerged arc welding using Linde 80 flux (lot No 8445) and Page copper coated weld. wire (wire heat No 71249).
These welds are identified as SA1101.
The FPL'ffort to resolve pressurized thermal shock revealed the need to better determine the material properties and chemical analyses of the reactor vessels material at Turkey Point Units 3 5 4.
An evaluation has been made to determine the avail ability of applicable weld metal data.
This evaluation has est abl i shed:
(1)
Test data to establish initial RTNDT for our critical welds.
(2)
A much larger data base from which to determine chemical compostion.
Weld SA1101 and weld wire heat 71249 is one of the best defined welds and fanily of welds in the industry.
(3)
The PTP critical welds are present in the Heavy Section Steel Technology (HSST) program.
The data avail able is shown below with a discussion of each source of data.
As noted in appendix E of SECY 82-465, values of initial RTN T measured according to ASME Code rules are not generally available for the welds in question.
For Linde 80 flux welds, the mean value of OoF with a devi ation of 17 F was used in Pressurized Thermal Shock (PTS) calcul ations.
EPRI Report NP-373 characterizes SA1101.
Both dropweight and charpy tests were performed and show a dropweight NDTT of -60oF with a charpy Cv50 of 70oF.
Using ASME Code rules, which require using the higher of 'NDTT and Tcv50-60 F, the initial RTNDT(o)
The use of 10oF with elimination of the 17oF devi ation, yield equivalent results in PTS calculations.
(2)
Co er and Nickel Chemistr The major source of copper and nickel chemistry,has typically been the original weld qualification (Wg) test report.
There has been
.some question as to the validity of these
- values, and since these values are only based on one analysis, it has become practice to analyze surveillance specimens.
Appendix P of SECY 82-465 uses 0.32$
Copper and 0.57$ Nickel for PTP.
These values are based on five analy~es performed by Westinghouse on broken charpy spec'imens in 1977.
l ik
EPRI NP-373 supplies nine additional weld analyses for a production SA1101 weld.
These analyses are also additionally supported by microprobe analysis data.
Babcock and Wilcox contracted with the Westinghouse Owners Group to supply all the propri~tary information which B&W had on the welds in the B8W owners group progran.
This included 26 analyses on weld No SA 1769 which is a Page wire heat 71249 surveillance weld and also identified SA 1229 as a Page wire heat 71249 weld.
The number of analyses performed on SA 1229 is not published, so we assumed it is just one analysis and verified its validity. by its reference in SECY 82-465 as the Oconee 1 girth weld.
Southwest Research performed three retest for FPSL on charpy specimens of surveillance weld 1094.
SA1101 appears in the HSST progran.
Copper content is reported but it is not clear how many analyses were performed but, since both a mean and a range of values are reported, we assume at least two analyses were performed since the mean is the average of the given range.
WCAP76366 and WCAP76607 are th~ surveillance progr ans for PTP 3 and 4
and supply two analyses.
WCAP8743 is the surveillance.progran for Point Beach Unit 1 and supplies one copper analysis for SA1101, the Point Beach circumferenti al weld.
The Barberton Wg reports test reports of 71249 materials identified (SA1101,
- SA1094, SA1229) represent three analyses.
The weld qualification for SA1769 has no specific copper concentration shown but does have a value listed as "other" which probably is copper.
This is presented for information only.
Zion Unit 2 is an SA1769 girth weld and is reported in SECY 82-465.
We add this for verification and information but is not considered an individual analysis.
Ginna Unit 1 also has an upper girth weld of SA1101.
Their analysis is also shown for verification and information but is not considered an individual analysis.
BSW considers SA1101 to be a category 1 weld3 which is defined as a weld for which several sources of actual reactor vessel weldments were available for multiple chemical analyses.
We refer you to BAW 1799 for a more complete description of the statisti,cal techniques used to establish the confidence levels B8W proposes.
Table 1 gives a summary of all the analyses considered including Cu and Ni concentration, number of analyses, weld identification, and the source of each data point.
The copper represents 51 analyses which have a mean of 0.26$ with a standard deviation of 0.04$.
The nickel represents 41 analyses which have a
mean of 0.60$ with a standard devi ation of 0.04$.
The four analyses from table one which are presented for information, generally fall within these data but are not part of them.
SUMMARY
OF.MATERIAL DATA This evaluation is FPL's materials plant specific analysis for PTP 3/4.
We ropose to use RTNDT(o>
= 10oF without the 17oF standard devi ation, 0.26$
opper and 0.60$ NickeT for future screening criteri a,calcul ations.
In addition, both HSST and EPRI 'NP-373 fracture mechanics data derived from this study will be used as pl ant specific in any future fracture mechanics ev al u ati ons.
.FPL has installed ex-vessel dosimetry in the form of foils and'ires around the Turkey Point Unit 3 vessel and is planning to install simil ar dosimetry around the Turkey Point Unit 4 vessel at the next avail able opportunity to better define flux variations as part of our plant specific evaluations.
I I
REFERENCES 1
W.A. Van der Sluys, et al.,
An Investigation of Mechanical Properties and'hemistry Within a fhh!e Nn-Nu-Ni Submerged Arc Weldment, EPRI NP-373, Su lement to FPSL., L-77-113, Weld Metal Copper Data, R.E.'hrig to George Lear, June 27, 1977 3
B&W 177-FA Reactor Vessel Beltline Weld Chemistry Study, BAW 1799, Babcock and Wilcox, Lynchburg, Virginia, July 1983 FP8iL L-77-113, Fracture Toughness Requirements, R.E. Uhrig to George Lear, April TT, PVl 5
R.G. Berggren, Irradi ation Effects, Presented to Vessel Integrity Review Group, June 2, 1981 S.E.
- Yanichco, FPSL Co. Turkey Point Unit 3 Reactor Vessel Radi ation Surveillance Progr an, WCAP 7656, Westinghouse Electric Corp.,
99!
S.E.
- Yanichco, FP8L Co. Turkey Point Unit 4 Reactor Vessel Radi ation Surveill ance
- Program, WCAP 7660, Westinghouse Electric Corp.',
9 1
A.
199 Point Beach Unit 1 Reactor Vessel Radi ation Surveillance Progran,,
WCAP 8743, Westinghouse Electric Corp., Pittsburgh, PA
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C BARBERTON WQ BAW 1799 EPRI 373 MCAP 7636 PTP3 W RETEST HSST PT BEACH 1
WCAP'S 8743/7513 MCAP 7660 PTP4 RETEST SMRI BARBERTON MQ BAW 1799 BARB ERTON MQ ZION 2 SECT 82465 OCONEE FROH RGE BARBERTON SEC Y G INNA MQ 82-465 X CU 0.21 0.18 0.31 0.33 0.21 0.21 0.30 0.29 0.23 0.285 0.20 0.26 0.26 0.21 0.19~
% NI 0.57 0.54 0.57 N/A N/A 0.57 0.60 N/A 0.55 0.63 0.57 0.61 0.61 0.57 0.66 MELO 10 SA1101 NUHBER 1
OF OBSER-VATIONS SA1101 SA1101 SA1101 SA1101 SA1101 SA1094 SA1094 SA1094 'A1769 26 SA1229 SA1769 SA1229 SA1101 SA1769 Presented as "other" on WQ 6 assumed to be CU.
- 'here are 10 microprobe analyses which support these data, but are not used in this data base.
Refer to EPRI-NP373 for details.
- '~
These analyses are shown for. information.
They are not part of the data base, but support it.
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