ML19343A520
| ML19343A520 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/23/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011140509 | |
| Download: ML19343A520 (4) | |
Text
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,e-ORB #1 Reading Docket,4 50-29--
ASchwencer p--
SMSheppard Yankee Atenic Electric Company M14M AfTH:
'tr. Rouert H. Grece OELD Licensing Engineer OI&E(3) 20 Turnpike Roaa DEsienhut i
Westboro, liassachusetts 0i531 TBAbernathy
)
JRBuchanan Gentlemen:
ACRS(16)
JZwetzig RE:
YAllXEE-ROWE ATOMIC POWER STATION PDiBenedetto Our review of data received frcm reactor vessel material surveillance prograns indicates that-the ma*.erials used in reactor vessel fabrication may have a wider variation in sensitivity to radiation damage than originally anticipated.
In addition, some reactor vessels incorporate more than one heat of materials, including weld metals in their beltline regions, but all of these heats inay not be included in the reactor vessel material surveillance program. '
Although our review of these data does not reveal a basis for concern regarding continued reactor vessel integrity over the next several years, the information does indicate the need for a detailed review of the materiais eraployed in reactor vessel construction (in light of this recent data) and a review of the specimens employed in the surveillance program to detemine if the' present specimens reasonably represent the liniting materials in the reactor vessel beltline region.
In order to perfom these 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 tne infonnation listed in the enclosure within 60 days of receipt of this letter.
fhis request for generic 'nformation was approved by GAO under a blanket clearance nteber 8-180225 (R0072); this clearance expires July 31, 1977.
y Sincerely, N
l c-A. Schwencer. Chief b
N...M' Operating Reactors Branch fl Division of Operating Reactprs y,g _
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e Yankee Atomic Electric Company May 23, 1977 cc: Mr. Ot. :ld G. Allen, President Yankee.4tomic Electric Compaay 20 Turnpike Road Westboro, Massachusetts 01581 Greenfield Public Library 402 Main Street Greenfield, Massachusetts 01581 1
1 i
1 I
REQUEST FOR INFORMATION REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1.
Provide the estimated maximum fluence (E 1 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 firm or fims 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 infomation 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) RTNDTI (9) Charpy upper shel f energy (unirradiated);
(10) Tensile properties (unirradiated);
(11)
Firm performing weld if more than one firm participated in welding; l
(12) The maximum end-of-life fluence at the vessel inner wall.
- As defined in 10 CFR 50, Appendix G, Section II.H.
n
.m f
. c.
Provide the following infomation 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) Plate or forging supplier; (5) Plate or forging heat treatment; (6) Chemical composition (particularly Cu, P and S content);
(7) Drop weight TNOT; (8) RTNDT (unirradiated);
(9) Charpy upper shelf energy (unirradiated);
(10) Tensile properties (unf rradiated);
(11) The maximum end-of-life fluence at the vessel inner wall.
5.
a.
List the weld, plate and forging materials included it, the vessel material surveillance program.
b.
For each seld listed in 5.a., provide the infomation requested in items (1) through (11) of question 4.b.
c.
For each plate or forging specimen listed in 5.a. provide the infomat'.on 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.