ML19260A100
| ML19260A100 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/18/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7910290719 | |
| Download: ML19260A100 (5) | |
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MAY 181977 NRC PDR gh bd]W@h la r L PDR Cacr.ct *:o. :
Sd-2M ed RIngram GZwetzig Attorney, OELD OI&E(3)
Metropoli tan Edison Cot.pany DEisenhut ATTH: :1r. R. C. Arnold TBAbernathy Vice President - Generation JRBuchanan P. O. Box 542 ACRS(16)
Reading, Pennsylvania 1960s Gray File Gentlemen:
RE: THREE HILE ISL/J13 UNIT NO.1 Our review of data received frm1 reactor vessel raterial surveillance programs indicates that the naterials used in re3ctor vessel tacrication may have a wicer variation in sensitivity to radiation damage than originally anticiDateo.
In adaition, sone reactor vessels incorporate nore than one heat of caterials, including weld retals in their beltline regions, but all of these heats nay not be included in the reactor vessel naterial surveillance progra.m.
Although our review of these data does not reveal a basis for concern regarding continued reactor vessel integrity over the next several years, the infomation does indicate the need for a detailed review of the materials employed in reactor vessel construction (in light of this recent data) and a review of the spectrens emoloyed in the surveillance progran to aetemine if the cresent specimens reasonably represent the 1initing naterials in the reactor vessel beltiine region.
In orcer to perfom tnese reviews we will need the infomation listed in the enclosure relative to each of your reactor vessel (s) and associated surveillance specimens.
Accordingly, you are requested to supply one signed original and 39 copies of the infomation listed in the enclosure wi thin 60 days of receipt of this letter.
If any portion of the reouested inforration was previously submitted to the r!RC in connection with our consideration of the 3&W Integrated Surveillance Progran, that portion may be furnished by referencing the appropriate earlier cubnittal.
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'%tropolitan Ecison Cwnany This reque st for.ieneric infor. ation was coroved a' y G.40 uncer a ulanket citar.arce nu,oer 3-100225 (M'072); this clearance expires July 31,1(.77.
Si ncerely, K.._ ; ':e Robert !J. Reic!, Chief Operating Reactors Branch e4 Division of Operating Reactors
Enclosure:
9equest for Infomation cc w/ enclosure:
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tietropolitan Edison Company cc:
G. F. Trowbridge, Esq.
Shaw, Pi ttman, Potts, & Trowbridge 1800 f1 Street,'N. W.
Washington, D. C.
20036 GPU Service Corporation Richard W. Heward, Project Manager Thomas M. Crimmins, Jr., Safety and Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Pennsylvania Electric Company Mr. R. W. Conrad Vice President, Generation 1001 Broad Street Johnstown, Pennsylvania 15507 f1r. Weldon B. Arehart, Chairman Board of Su:ervisors of Londonderry Township RFD #1, Geyers Church Road Middletown, Pennsylvania 17057 fliss flary V. Southard, Chairman Citizens for a Safe Environnent P. O. Box 405 Harrisburg, Pennsylvania 17108 Government Publications Section State Library of Pennsylvania Box 1501 (Education Building)
Harrisburg, Pennsylvania 17126 4
e 1479 322
?ti:l5 REQUEST FOR INFORMATION REACTOR VCSSEL MATERIAL SURVEILLANCE PROGRAM 1.
Provide the estimated maximum fluence (E>l Mev) at the inner surface of the reactor vessel wall as of March 31, 1977.
2.
Provide the effective full power years (EFPY) of operation accumulated as of March 31, 1977.
3.
Identify the fim or firms that fabricated your reactor vessel.
4 a,
Provide a sketch of the reactor vessel showing all materials welds, in the beltline region
- and provide an identification number for each material, b.
Provide the following infor: nation for each of the welds in the beltline region:
(1) Shop control number or procedure qualification number; (2) Filler metal and heat number; (3) Type of flux and batch number; (4) Welding process (sub arc, electroslag, manual metal arc, etc.)
(5) Post-weld heat treatment; (6) Chemical composition (particularly Cu, P and S content);
(7) Drop weight TNDT; (8) RTNDT; (9) Charpy upper shelf energy (unirradiated);
(10) Tensile properties (unirradiated);
(11) Firm performing weld if more than one fim participated in welding; (12) The maximum end-of-life fluence at the vessel inner wall.
- As defined in 10 CFR 50, Appendix G, Section II.H.
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2-c.
Provide the following infonnation for each of the plates or forgings in the beltline region:
(1) Plate or forging serial number; (2) Plate or forging heat number; (3) Plate or forging material specification number; (4) Piate or forging supplier; (5) Plate or forging heat treatment; g
(6) Chemical cotaposition (particularly Cu, g
P and S content);
(7) Drop weight TNDT; (8) RTNDT (unirradiated);
(9) Charpy uoper shelf energy (unirradiated);
(10) Tensile properties (unirradiated);
(11) The maximum end-of-life fluence at the vessel inner wall.
5.
a.
List the weld, plate and forging materials included in the vessel material surveillance program.
b.
For each weld listed in 5.a., provide the information requested in items (1) through (11) of question 4.b.
c.
For each plate or forging specimen listed in 5.a provide the information listed in items (1) through (10) of question 4.c.
d.
Provide a copy of the report which describes the surveillance program for your reactor vessel (s), if available.
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