ML20127K636

Summary of 670202 Meeting W/Acrs Subcommittee to Discuss Field Erection of Primary Vessel of Plant

ML20127K636
Person / Time
Site:	Monticello
Issue date:	03/08/1967
From:	Jensen W US ATOMIC ENERGY COMMISSION (AEC)
To:	US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9211200457
Download: ML20127K636 (4)

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t'NITED STATES GOVERNMENT Memorandum v/g M% 6 E57 The Tiles 10 dam THRU Roger S. Boyd, Chief '

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Research & Power Reactor Safety Branch, DRL FROM W. Jensen V Research & Power Reactor Safety Branch, DRL

SUBJECT:

REGULATORY STATT AD ACRS SUB-COM>tITTEE PEETINGS CONCERN 1NC THE -

M0'iTICELLO NUCLEAR U';IT NO.1 VESSEL FABRICATION [0 'W On February 2,1967, a meeting was held to discuss the field erection of the primary vessel of Ponticello Nuclear _ Station in anticipation of a meeting with the ACRS Sub-committee on February 3.

Groups represented were:

AEC - DRL AEC - SS AEC - Chienco Onerntions Of fi ce R. S. Boyd A. Ilolt G. W. Reinmuth D. R. Muller M. Bolotsky J. G. Condelos B. Grimes J. J. Shea

p. Check M. A. Taylor MSP CB&I CC D. F. McElroy Janes T. Dunn Jules Pearlman Roland Jensen Perry C. Arnold J. B. Violette Arthur Dienhart Olof B. Johnson Adolph Hubbard Gerald Neils Karl Krasin I. R. Robsa E. C. Ward Edward E. Varnun J. J. Fox Donald E. Nelson Paramete r. Inc., for nnt Sh nw-Pit tman for MS" R. A. Lofy G. Charnoff W. J. Foley J. J. Chyle We had presented the applicant with-a list of items requiring clarifica-tion. These were discussed as follows:

1.

Mnero Snecimn Testine Macro specimens will be f abricated of the vessel plate and welds and.

tested for mechanical properties by Charpy and tensil tests. The staff sucgested that micro etch exa.tinations also be made to identify segrega-tion in the plate.

CB&I, however, stated that the mechanical properties C'

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The riles Nb 6 Docket No. 50-263 alone should be adcquate. To perrlt our further evaluatien of possible local deviations in properties of the vessel from the macro specimen properties, the applicant agreed to supply our consultants with the properties of the veld heat af fected zone as a function of electrode current and to supply additional data of macro specimen testinc.

2.

Charnv Test Ouality To substantiate the quality of the Charpy tests made on test specimens, CB&I stated that every six months their test equipment is qualified by Watertown Arsenal and that new equiprent will be qualified before it is put into service.

General Electric-also checks all notches on all specimens for proper radius. We believe the quality of the test equip--

ment and samples will be adequate but believe that more information should be provided to support the applicant's view that Charny transition-temperature curves for each material heat arc not needed.

3.

Chemical Analvsis Althounh the ASIC Code requires a chemical analysis of the reactor vessel material and such tests are planned by CB&I, these tests do not show the local' concentration of these materials. _ For exarple, soluble aluminum ma1 distributions can alter the strain agine properties of the steel. We therefore believe that more information concernine the extent

-of spectrographic analysis of the vessel plate material = should be pro-vided to permit us to determine if additional analysis supplemented by a gas analysis of at 1 cast sone of the plates is necessary.

4.

Recirculation Mozzle Location CB&1 described the revised recirculation outlet-nozzle design which vill permit the nozzles to be shop-installed and still leave ample roor to weld the adj acent girth seam..The outside diameter of the nozzle forging has been" decreased by four inches and the center line has been raised nine inches which provides a total clearance of fif teen inches to the Firth veld below. The NPSh to the recirculation purps_ will be reduced by.only 3/4 feet from 325 feet.

It-was also stated that with. the exception of the instrument penetrations, all nozzles will-be butt-welded.

5.

Vessel Orientation Since an exact vertical orientation is vital to control rod operation and to weight distributions in -the vessel internal structures,. CB&I-was asked to describe the methods by which the vessel centerline will be established and maintained throughout erection._ This procedure is as

.follows:

An optical theodolite will be beared through the center-drive.

penetration in the bottom head, the top-of the knuckle piece will be

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icveled, and the control rod drive penetrations bored vertically usine bL

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A%4 6 557 The Files ;=

(Docket ~ No. 50-263) 1 l

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templates above and below the bottom head.

Each additional ring vill be i

centered optically and leveled.

Smooth fit-up will be achieved by grinding

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high spots or buildinc un low spots with weld beads.

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6.

Vessel Section Fit-un e

L Since flat spots in the vessel caused by poor fit-up will be susceptible to i

radiation damage, the staff requested the procedure which -would be followed i

in the event of misratch.

CB&I stated that the maximum pernissible mis-l.

alignment will be 3/8" for vertical seaes and 3/4" for girth seams.

Sections "which do not poet these specifications vill be forced into _ tolerance using

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j acks.

One such jackinn operation was performed on the philadelphia Hydro-

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cracker with a 200-ton jack.

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Ves se l In s t rumen t et i on 1

l During the vessel hydro tests, strain nages will net bc utilized.

CB&I does not believe they will be necessary since similar vessels have been so q

instrumented in -the past to prove out the analytical ecthods. _Ue suggested tnat a means be made to monitor the vessel dimensions in service.

It is 4

i expected that lifetire inspectability will be covered at _ a later tinc.

8 Materi ni Testin n Pecorda We presented our opinico thet the vessel quality could be improved-if the Cu&I design analyst were supplied with' the test data of the vessel material j

so that plate with the least flaws could be placed in hither stress locations.

b'e, therefore, questioned the extent of material testine records and the extent to which the analyst will be supplied with this data. -It appears now that only mechanicel specimen test data could be used in -this manner.-

l However, the degree that this information will.be used in determining the i

plate location was not made clear.

Flaus found by' UT, dye' penetrant, and marnetic particle testing will be manually logged and recorded permanently.

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only if repair is necessary.

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9.. Field Radionranhv 60 Only C0 radiography is to be used on field welds. This method was stated to be capable of resolutions to 1/2 the ASME Code penetrometer diameter of 160 mils.

The penetrometer used in the field will have' holes 2,' 3, and-4 times the specified penetrometer sensitivity of 1% (60 edis).- -The pene-trometer thickness will be 60 mils.

Betatrons have. exhibited the ability to detect cracks down to 2. milsL thickness.

CB&I' believes that its ultrasonic inspection-program will be adequate to detect cracks with the sensitivity; of-the Betatron and use of the Betatron would create an undue-hardship on the vessel erection.

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The Files,

0 007 Docket 1:o. 50-263

_ACR." Sub-Commi t t ec ifect in n 1he following ACRS nembers compose the Sub-committee to review the 1:onticello plantt Dr. S. H. Hanauer Dr. S. H. Bush Dr. C. W. Zabel Mr. H. Ethe rington Dr. J. E. McKee Mr. H. C. Mangelsdorf The following information which was not discussed at the meeting with the staf f was brought out in the applicant's presentations and Sub-committee questions:

The 3000-ton press will be used to form all vessel sections since the 6000-ton press may not be operational in time.

Due to the lower capability of the smaller press, some vessel sections may be pressed hot.

This is common practice, however, with other vessel manuf acturers.

All vessel welds will be post weld heat treated at 1150*T. The ASFS Code would allow a 150* tolerance around this temperature.

CB61 will place a tolerance of +25'T and -50*F resulting in one-half the Code tolerance. The vessel steel can withstand at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> at 1150*F without loss of propcrties and records of the heating history of each plate will be main-tained throughout the f abrication.

Flaws in the plate will be ground out and repaired only by CB61 in their Birmincham shop af ter evaluation by CB&I and CE.

Ultrasonic inspections beyond the Code requirements will be used to inspect plates at the Lukens Steel Company Mill and at the CB&I shop.

The reactor primary piping will be tested with the vessel to only 1.25 times design pressure instead of 1.5 times desien pressure as required by the Code for the primary pipine alone.

Di s t rib uti on :

-,_.C D. Muller J. Shea B. Grimes W. Jensen DFL Reading R&PRSB Reading i

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