ML19317F746
| ML19317F746 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/23/1977 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Roe L TOLEDO EDISON CO. |
| References | |
| NUDOCS 8001230650 | |
| Download: ML19317F746 (4) | |
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Docket Files 1
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NRC PDR MAY 2 3 1977 Local PDR LNR 1 File R. S. Boyd R. C. DeYoung D. B. Vassallo bcc: J. R. Buchanan, Docket ;!o. 50-346 F. J. Williams NSIC J. Stolz T. B. Abernathy, L. Engle TIC T31edo Edison Comoany E. Hylton ACRS (16)
ATTN: !!r. Lowell E. Roe R. Heineman Vice President. Facilities D. Ross Development J. Knight Edison Plaza R. Tedesco i U p]
G ' D 300 Madison Avenue H. Denton lbo Toledo, Ohio 43652 V. A. "oore l
R. H. Vollmer Gentlemen:
- 1. L. Ernst D
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~h,k H. P. Gammill a
SUBJECT:
DAVIS-DESSE, U?!IT 1 ELD Cur review of data received from reactor vessel material surveillance prograss indicates that the materials used in reactor vessel fabrication may have a wider variation in sensitivity to radiation dar. age than origir. ally anticipated.
In addition, some reactor vessels incorporate more than one heat of materials. including weld metals, in their bel:-
line regions, but all of these heats may not be included in the reactor vessel catcrial surveillance program.
Although cur review of these fata 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 ;'aterials employed in reactor vessel construction (in light of this recent data) and a review of the specimens ecoloyed in the surveillance program to detemine if the present snecim.ns reasonably represent the limiting materials in the reactor vessel beltline reqion.
In order to perform 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 cor'.; of the infomation listed in the enclosure within 60 days of receipt of this letter. :If any portion of the requested infomation was previously submitted to the ttRC in connection with our consideration of the 85W Integrated Surveillance Program, that portion may be furnished by referencing the appropriate earlier sutaittal.
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NRCPORM 313 (9 76) NRCM 0240 j ua s. eovannesant PauwTime opricas sero-esume
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MAY iJ 1977 Toledo Edison Company 2-This request for generic information was approved by GA0 under a
. blanket clearance number B-180225 (R0072); this clearance expires July 31, 1977.
Sincerely, Original Signed lig John F. Stolz l
John F. Stolz, Chief Light Water Reactors Branch *fo. 1 Division of Project "anaqenent
Enclosure:
P,equest for Infor:aation cc w/ enclosure:
'ir. Donald H. Hauser, Esq.
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The Cleveland Electric Illuminating Company D
P. O. Box 5000 yU L
Cleveland, Ohio 44101 Gmld Charnoff. Esq.
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Shaw, Pittnan. Potts and Trowbridge 1300 it Street, it. W.
Washington, D. C.
20036 Leslie Henry, Esq.
Fuller. Seney. Henry and Hodge 3001'adison Avenue Toledo, Ohio 43604
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LWR h rTF U4R 1 I Ena_ N
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NRC POty. 318 (9 76) NRCM 0240 1lt u.
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REQUESTFORINF0RiiATION'L.
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REACTOR VESSEL MATERIAL SURVEILLANCE PR6 GRAM 1.
Provide the estimated maximum fluence (E>l Mev) at the inne'r surface of the reactor vessel' wall as of March 31, 1977.
2.
Provide the effective full power yedrs (EFPYi operation had accumulated as o' March 31. 1977.
3.
Identy the firm or finns that fabricated your reactor vessel.
4.
a.
Provide a sketch of the reactor vessel showing all materials, including welds, in the beltline region
- and provide an identification number for each material.
b.
Provide the following information for each, of the we}ds 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. l i
(5) Post-weld heat treatment; (6) Chemical composition (particularly Cu, P and S cer tent);-
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(7) Drop weight TNDTI (8) RTNDTI (9) Charpy upper shel f energy (unirradiated);
(10) Tensile properties (unir' radiated);
(11) Firm performing weld if more than one firm 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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c.
Provice the following information for each of the plates l,
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) ? late or forging heat treatment; (6) Chemical composition (particularly Cu, P and S content);
(7) Drop weight T (8) RT (unirradiated);
(9) Charpy upper shel f energy (unf rradiated);
(10) Tensile properties (unirradiated);
(11) The maximum end-of-life fluence at the vessel inner wall.
List the weld. plate and forging materials included in the vessel 5.
a.
material surveillance program.
b.
For each weld listed in 5.a., provide the ir..~ormation requested in items (1) through (11) of question 4.b.
U For each plate or forging specimen listed in 5.a. provide c.
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 avail abl e.
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