ML19308D457
| ML19308D457 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/07/1971 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Low L US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19308D439 | List: |
| References | |
| NUDOCS 8002280769 | |
| Download: ML19308D457 (1) | |
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'q UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON. D.C. 20545 1Y DEC j}
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j 7,l11 L. D. Low, Director, Division of Compliance REQUEST FOR CONFIRMATORY IFFORMATION REGARDING CRYSTAL RIVER UNIT 3 OPERATING LICENSE-FLORIDA POWER CORPORATION-POCKET NO. 50-302 One of the special problems encountered during the course of the construction permit review for Crystal River was the assessment of foundation worthiness for Unit 3.
The near surface site geology j
revealed solution voids and zones of loose material. The applicant proposed a consolidation grouting program to remedy these problems.
The proposal was reviewed by DRL and our consultants and it was concluded that the procedures of the proposal would be adequate for the foundation of Unit 3.
Construction permit issuance was based in part on the adequacy of this proposal.
The applicant's proposal utilizes a procedure called a split-spaced stage grouting technique.
The concept involves drilling primary holes, making initial grout injections, then grouting again in split-spaced holes (drilled midway between original holes).
This procedure was to be repeated until the cubic feet of grout injection per lineal foot of injection hole (grout take) is decreased to a predetermined value.
Tha ::erm stage grouting refers to an intermittent grout injection where succeeding injections form on the base laid by previous injections.
In addition, the applicant was to place a curtain grout around the entire reactor building complex to t t imize the lateral flow of ground water.
DRL requests that you provide confirmation that this grouting program as proposed and accepted for issuance of the construction permit has been fully carried out.
If modifications or additions were made to the basic procedures, please discuss the extent to which such changes were actually performed.
Because of the importance of this item to basic plant safety, we request a reply by January 1,1972 to permit ample lead time to resolve any deficiencies which might be identified.
P. A. Morris, Director Division of Reactor Licensing 8002 280 h 7
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