ML20125B257

Forwards Draft Ltr Re Insp Repts That Have Been Prepared in Connection W/Construction of Plant

ML20125B257
Person / Time
Site:	Monticello
Issue date:	05/26/1970
From:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
To:	Engelhardt A, Morris P US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212090275
Download: ML20125B257 (4)

Text

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t llay 26, -1970 NOTP TO P. A. lDRf;!S AND T. F. !!NG.".t.' tai!DT I havo attnehed for your review n drsft of the proposed !ctter to be used for forwarding the ins;*cetion reports'to tho ;4mticello L

! Dontd. In addition, I have'nttached en'oxarplo~of_tho-fort'nt and" content for I nclosure 2 to the letter which will identify _ cach '

outstandinr. itea requiring resolution.

Our objectivo is to try to ;.ect with t'r. Price tiednesdsy; afternoon. ...

! vould ap;irodate it it va could caut itednesday r.ornin:: in or.for_

to reach ar,reecent on the versica to be subsitted to Mr..Prico'.. I-suR2 cst 9:00 a.r:. in 'iy offico, room 172-A. ,

.. 3 ,a u n..a by eteo cumdusso

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A.' Cla busso.

Attachocats:

1. Proposed lotter

2. tixsaple of.Fornat and Content-

. ec: H. M. P. san, UE, w/att. ,_

L. D..Lowj C0, w/att.

II. K. Shbpor, - 00, w/att.

s- R.11. In .c1 ken, CO, w/att.

-I L. Kornblith, CO, w/att._. '

D.11. !;uller, DRL, _ w/att.

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DRAFT #2-NSP Honticcilo Board

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In accordance with our response, dated May 8, 1970, to the Atomic Safety; and Licensing Board's subpoena,sa are transmitting to the board (see Enclosure #1) and to the parties in the captioned proceeding copics of all AEC inspection repcrts that have been prepared in connection with the construction of the Monticello Nuclear Generating Plant, Unit #1. A's indicated in the AEC response of Pay 3, 1970, we have' deleted from the e

enclosed inspection reports (1) the naces of persons, other than AEC personnel, who provided information during the inspections (when a name is deleted,^the name of the person's organizational or company affiliation is identified); (2) references to AEC internal menoranda, instructions, including inspection techniques, and acetings; (3) references to other identified facilities; and (4). information of a proprietary nature. The deletions from the enclosed inspection reports are identified by entering the appropriate above number in the margin to indicate the category of the information deleted.

The enclosed inspection reports are periodic interim field reports covering the status of construction as of the date of the inspection. Anong other 3., .,

things, these reports identify certain specific technical data, information, i

and personni observations and initial judgments of the inspectors, some of which identify items requiring further resolution (unresolved items) at the time of the inspection.

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2-The unrosolved items relato primarily to defects in fabrication, deviations from specifications or codes, quality of materials and components, incomplete documentation, incomplete or inadequate procedures, and lacomplete construction and testing.

Except for those itens identified in Enclosure #2, all items have been resolved by repair or replacement of inadequate materials and components, further analyses and evaluations, completion of documentation, construction, and testing, other corrective actions by the licensco or its agents, or.

determination that the safety significance of the item does not warrant further action. The unresolved items described in Enclosurc #2 comprise an elaboration of Supplenent 1, as amended as of April 27, 1970, to the AEC regulatory staff's Safety Evaluation and will be required to be resolved prior to the issuance of the license for full power operation. As indicated in Supplenent 1, the regulatory staff has concluded that there is reasonable assurance that the pending list of items can be resolved prior to initial loading of the reactor with nuclear fuel.

AEC Division of Compliance inspection personnel who participated in inspections and the preparation of the enclosed inspection reports

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will be availabic at the hearing to be resumed on June 15, 1970, in this matter for examination by the board and parties.

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(EXAMPLE OF FORMAT AND CONTENT)

ENCLOSURE 2 ITEMS REQUIRING RESOLUTION PRIOR TO ISSUANCE OF LICENSE FOR OPERATION Status and Plan of Resolution '

Identification of Items .

Deficiencies

1. An evaluation underway by regulatory sta#~ ,

1. One spool of pipe was stress relieved to determine if the higher temperature at 1300*F vs the specified 1150 + 25*F altered the metallurgical characteristics

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References:

. 'IR #70-4, DDR 2591T of the material.

The pressure transmitter range for the 2. The applicant is proceeding to correct the

2. deficiency by calibration.

high containment pressure switches did not agree with the receiver range it was feeding.

Incomplete Items A decision has been nide by SNP to 3. Regulatory staff presently evaluating

3. acceptability of cladding procedures and replace certain safe-ends and to related quality control.

clad others. (68-7)

The centrifuge hopper discharge and the 4. Work is proceeding at the site. -*

4 drumming and capping stations of the ,

i liquid waste system remain to be completed. The solid waste system was also incomplete. .

Procedures and Administrative fhtters Preparation of operating procedures is ' 5. The applicant is continuing to preparc-

5. operating procedures and to revise the incomplete and maintenance procedures maintenance procedures.

considered unacceptable, e

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