ML19329D645
| ML19329D645 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/19/1977 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Rodgers J FLORIDA POWER CORP. |
| References | |
| NUDOCS 8003160269 | |
| Download: ML19329D645 (5) | |
Text
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. Docket f
MAY 19197I
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ORB #4 Rdo.
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RInaram Docket tio.: 50-302 ehson g
JStolz
'GZwetzip dont Attorney, OELD -
Florida Power Corporation OI&E(3)
AT.n: Mr. J. T. Rodgers, Assistant Vice President DEisenhut and Nuclear Project Manager P.O. Box 14042 TBAbernathy JRBuchanan St. Petersburg, Florida 33733 ACRS(16)
Nay File Gentlemen:
RE: CRYSTAL RIVER UtilT !J0. 3 Our review of data received from reactor ve..el material surveillance prograns indicates that the materials used in reactor vessel fabrication may have a wicer variation in sensitivity to radiation vanage than originally anticipated.
In addition, some reactor vessels incorporate nore than one heat of naterials, includin0 weld netals in their beltline regions, but all of these heats may not be included in the reactor vessel material surveillance program.
Although our review of these data does not reveal a basis for concern egarding continued reactor vessel integrity over the next'several years, the infornation does indicate the need for a detailed review of the materials enployed in reactor vessel construction (in light of this recent data) and a review of the specimens employed in the surveillance progran to detemine if the present specimens reasonably represent the.liniting natorials in the reagtor vessel beltline region.
In order to perform these reviews we will need the information listed in the enclosure relative to each of your reactor vessel (s) and associated surveillance specinens.
Accordingly, you are requested to supply one signed original and 39 copies of the infomation listed in the enclosure within 60 days of receipt of this letter.
If any portion of the requested infore.stion was previously submitted to the HRC in connection with our consideration of the B&W Integrated Surveillance Program, that portion may De furnished by referencing the appropriate earlier suonittal.
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^4 Florida Potter Corporation,
This request for generic information was approved by GA0 under a blanket clearance number S-180225 (R0072); this clearance expires July 31, 1977.
Sincerely, a=%
Joha F. Stolz, Chief Light Water Reactors Branch fl Division of Project Management
Enclosure:
Request for Information cc w/ enclosure:
See next page
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Florida Power Corporation cc:
Mr. S. A. Brandimore Vice President and General Counsel P. O. Box 14042 St. Petersburg, Florida 33733 m
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1 REQUEST FOR INFORMATION REACTOR VESSEL 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 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 g
number for each material.
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b.
Provide the following infomation for each of the welds in the beltline region:
(1) Shop control numt.er 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 TNDTI (8) RTNDT i
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(9) Charpy upper shelf energy (unirradiated);
(10) Tensile properties (unirradiated);
(11) Firm performing weld if more than one firm participated in welding; 1
(12) The maximum end-of-life fluence at the vessel inner wall.
- As defined in 10 CFR 50, Appendix G, Section II.H.
a
2 c.
Provide the following information 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 5 content);
(7) Drop weight TNDT; (8) RT NDT(unirradiated);
(9)
Charpy upper 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.
.