ML19309A383

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Responds to AEC Re Violations Noted in Insp Rept 50-312/69-03.Corrective Actions:Cement Samples at Variance W/Specifications Used Only in Trial Mixes & Aggregate Samplings to Be Taken at Least Once Daily
ML19309A383
Person / Time
Site: Rancho Seco
Issue date: 01/02/1970
From: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Rich Smith
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML17198A048 List:
References
NUDOCS 8003270834
Download: ML19309A383 (3)


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SACRAMENTO MUNICIPA4. UTILITY DISTRICT C 6201 S Street, Box 15830, Sacramento, Califomia 95813: (916) 452-3211 January 2, 1970 Atomic Energy Commission Division of Compliance, Region V g

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D 2111 Bancroft Way Berkeley, California 94704 h

j M' g.k'M Attention: Richard W. Smith U

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Director

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Dear Mr.. Smiths f

O Atomic Energy Commission Inspection s'

of Rancho Seco Nuclear Generating Station. Unit No. 1 by R. T. Dodds and J. L. Crews on October 21, and 22, 1969 We received your letter of December 17, 1969 which noted areas of noncompliance with established requirements in the initial construction phases of Rancho Seco. Yorr findings are answered as fallows:

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1.

Audit Finding i

The Preliminary Safety Analysis Report', Section 5.1.3.1 states that " Cement will be Type II as specified in

' Standard Specifications for Portland Cement', ASTM Designation C 150...".

The results of a chemical analysis by your consultant showed that the sum of the tricalcium silicate and tricalcium aluminate in cement suoplied for the project was 62.48%. ASTM Designation C 150 limits the total proportion of the above constituents in. Type II portland cement to 58% when moderate heat of hydration is required and tests for heat of hydration are not requested.

The results of heat of hydration tests were not contained i

in the project records reviewed by our inspectors..

Action Taken l

The report noted in the finding represents the results from a sample submitted to Lowry and Associates early in the construction phs.se of Rancho Seco.

The cement represented by this sample was sacked cement which was never used on the project except for the purpose of conducting trial mixes.

Subsequent deliveries of cement have been from Silos E and F at the cement manufacturer's l

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plant. The manufacturer's tests on cement from Silos E and F are in compliance with the specifications for Type II cement as verified by his mill test reports on file at l

Rancho Seco.

SMUD has supported these test results with 8003270 b[

independent user tests.

A nonconformance report has now been written and is on file

Richard W. Smith January 2, 1970 2.

Audit Finding:

The Preliminary Safety Analysis Report, Section 5.1.3.1 states that " Cement will be Type II as specified in

' Standard Specifications for Portland Cement', ASTM Designation C 150...".

ASTM Designation C 150 describes the physical requirements for Portland Cement. As required in Table II'the results of false set tests show a minimum final penetration of 50% for Type II cement.

The results of false set tests conducted by your consultant on cement supplied for the projecc showed a final penetra-tion of 8%.

Action Taken:

The problem of false set applied only to the quantity of cement used for trial mixes described in Audit Finding No.

1 above. All subsequent deliveries of cement have been tested for false set and fully comply with specification requirements.

It is to be noted that the false set nonconformsum has also been subsequently documented.on a non. conforming material report.

3.

Audit Finding:

Section 5.1.3.1 of the Preliminary Safety Analysis Report

" states that all concrete work will be in accordance with ACI-318-63 " Building Code Requirements for Reinforced Concrete" and to ACI 301 " Specifications for Structural Concrete for Buildings." The project. records revealed that the results of only a single concrete trial mix were used as the basis for establishing design mix Number C-1.

Concrete prepared in accordance with this design mix was used in forming the floors and walls of the reactor building tendon access gallery.

It is ou'r understanding that concrete prepared in accordance with this design mix will also be used in forming the base mat and walls of the reactor building.

The use of data from a single concrece trial mix in the determination of this concrete design mix is inconsistent with the procedures outlined in both ACI 301, Chapter 3, paragraph 308 "Propor:ioning of ingredients" and ACI 318, Chapter 5, paragraph 502 " Methods of determining the proportions of concrete".

Action Taken:

Concrete trial mixes were..ot taken in strict conformance with ACI requirements. This was due largely to the fact that considerable historical data on coacrete mixes had

~been conducted by the aggregate supplier located in the vicinity of Rancho Seco. By making use of this backup i

ery

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.4 R'ichard W. Smith January 2, 1970 data adequate design mixes were formulated as substantiated by subsequent testing.

All backup data upon which the concrete design mixes were based has been accumulated and is now in the Rancho Seco Quality Documentation Control Center.

4.

Audit Finding:

Section 5.1.3.1 of the Preliminary Safety Analysis Report states that aggregates will conform to " Standard Specifications for Concrete Aggregate" ASTM Designation C 33. On September 17, 1969, a receiving test of a load of 1 1/2-inch aggregate showed that 64.5% of the aggregate passed a one-inch screen compared to the ASTM C 33 specification which limits the quantity passing through a one-inch screen to 20-55%. The-next test of 1 1/2-inch coarse aggregate performed at the site was not made until September 29, 1969.

Action Taken:

Sampling of aggregate is done at least once each day the plant is in operation. This frequency will preclude recurrence of the incident cited in the audit. Cylinder V

break tests of the concrete poured.during 'the period.noted on the audit indicates that the concrete is acceptable.

5.

Audit Finding:

Our inspectors observed that a significant quantity of sand fines, penetrating beneath the surface layer, had accumulated on one side of the 3/4-inch coarse aggregate stockpile at the concrete batch plant. Reportedly, the unloading operation of sand caused fines to be blown onto the coarse aggregate stock-pile. ACI-318, paragraph 409, requires that aggregates be stored and/or separated to prevent the intrusion of foreign matter.

Action Taken:

1 A sheet metal shield has been installed to prevent fines from the stacker conveyor from settling on the aggregate storage i

pile, j

Very truly yours, l

l John. Mattimoe l

Assistant Chief Engineer l

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