ML19319D964

Forwards Request for Info Re Reactor Vessel Matl Surveillance Program.Response Required within 60 Days. Request Approved by Gao

ML19319D964
Person / Time
Site:	Rancho Seco
Issue date:	05/18/1977
From:	Reid R Office of Nuclear Reactor Regulation
To:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
References
NUDOCS 8003270657
Download: ML19319D964 (5)

Text

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DISTRIBUTION:

Wu l 81977 Docket V NRC PDR Local PDR ORB #4 Rdg.

RWReid Docket Ro.:

50-312 RIngram L01shan GZwetzig Attorney, OELD OIAE(3)

DEisenhut

. Sacraraento Municipal littlity District TBAbernathy

" ATTN: Mr. J. J. Matticore 5

JRBuchanan

' Assistant General Manager i

_. =and Chief Engineer ACRS(16)

Gray File t

6201 S Street P. O. Box 15830 Sacramento, California ' 95813 Gentiemen:.

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RE:

RANCHO SECO HOCLEAR GEHERATING STATIOM t

reh. N h ditEYeceiveS fr$n readto$ves el'meteHal' surveil 1ance

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- iprograms' i;ndicates ?that the haterials used in reactor vessel

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fabrication may' have a wider variation _~in' sensitivity to' radiation

- damage. than originally < anticipated.

In addition, some ' reactor vessels

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incorporate more than 'one heat of materials, including' weld metals in their'Deltline regions, but all-of these heats may not be included in '

j the' reactor vessel maprial surveillance program.

t Although our review of these data does not reveal a basis for concern regarding continued reactor vessel integrity over the next st.veral years, the inforMation does indicate the need for a detailed reviev

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of the naterials'eroployed in reactor vessel construction (in light of this recent data)~ and-'a review of the specinens enployed in the

surveillance ' program'toldetemine if the present specinens reasonably I

.._ represent' the liraiting materials in the reactor vessel beltline region.

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-[. In order to~ perform Lthese' reviews we will' nee'd the infomation.

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listed in the enclosure relative to each of.your reactor vessel (s) and associated surveillance specimens.

Accordingly, y~o'u are requested to supply one signed original and 39

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copies of thelinfornatinn listed in the enclosure within 60 days of receipt of this letter.

If any portion of the requested information yas previously submitted to'the KRC in connection with our consideration i)

J Lof the BM/ Integrated Surveillance Program, that portion may be furnished by referencing _the appropriate earlier submittal.

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r This recuest for eeneric informtion was approved by RAG under a

. blanket cicarance nunber B-130225 (R0072); this clearance expires July 31, 1977.

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Robert W. Reid, Chief j

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Sacramento Municipal Utility District cc:

David S. Kaplan, Secretary and General Counsel 6201 S Street Post Office Box 15830 Sacramento, California 95813 Business and Municipal Department Sacramento City-County Library 828 I Street Sacramento, California 95814 hb 0

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A.

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 number for each material.

b.

Provide the following infomation for each of the welds in the bel tline 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 me tal a rc, e tc..

(5) Post-weld heat treatment; (6) Chemical composition (particularly Cu, P and S content);

(7) Drop weight TNDT; (8) RTNDT I (9) Charpy upper shelf energy (unirradiated);

(10) Tensile properties (unf eradiated);

(11)

Fim perfoming weld if more than one fim participated f a 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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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 TtlDT ;

(8) RT fiDT (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 If sted 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.