ML19308D705

Interim Deficiency Rept Re Concrete Void Under Containment Structure Personnel Access Hatch.Pour 535RB Removed to Existing Const Joints.Final Rept by 721101

ML19308D705
Person / Time
Site:	Crystal River
Issue date:	09/14/1972
From:	Raymond R FLORIDA POWER CORP.
To:
Shared Package
ML19308D703	List: ML19308D705
References
21340, NUDOCS 8003120847
Download: ML19308D705 (4)

Text

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$ l F LO HIDA POWER C O R P O R ATI O N l s ST. PETERSDURG PLORIDA

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September 14, 1972 Mr. S. E. Kruesi, Director The Directorate of Regulatory Operations U. S. Atomic Energy Commission Washington, D.C. 20545

Subject:

Crystal River Plant - Unit #3 Docket No. 50-302.

Dear Mr. Kruesi:

In accordance with Federal Regulation 10CFR 50.55E, we wish to submit this interim report regarding a concrete void located under the personnel  ;

access hatch on the Crystal River Unit #3 containment structure. Verbal ~

notification concerning this void was made to Region II, DR0 Personnel during the site visit of August 15 to 17. The approximate dimensions of the void are shown on the enclosed Florida Power Corporation drawing (MISC-CR3-4-D-0). These dimensions were taken prior to the removal of any reinforcing or tendon conduit, and, as such, must be considered (O ,/ approximate. The concrete void occurred during the placing of the Pour No. 535RB on August 3,1972; the pour consisted of approximately 50 cubic yards of concrete.

The void was discovered when the exterior form work was removed on August 9,1972, at which time a void approximately 4 inches high by 18 inches wide by 5 feet 6 inches deep was discovered directly under the personnel hatch. A Florida Power Corporation non-conformance report was issued at that time and FPC Generation Engineering was notified of this condition. On August 15, 1972, an inspection opening was cut in the reactor building steel liner at the approximate location of the void.

After observing the size of the void then visible through the liner open-ing, it was decided by Florida Power Corporation that extensive evaluation was necessary and that this non-conformance required official notification to the Atomic Energy Commission in accordance with 10CFR 50.55 (E).

All available data regarding the history of this placement was gathered and an engineering evaluation was initiated by Gilbert Associates Engineers.

After physically viewing the void and studying the possible actions to be taken regarding its repair, Gilbert Associates Engineering recommended on August 30, 1972, that the entire Pour No. 535RB be removed to the existing construction joints. Gilbert Associates Engineering prepared criteria to 26 %

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A Mr. S. E. Kruesi September 14, 1972 be used for the preparation of the construction procedures required for removal of the material within this pour. A copy of the criteria and the construction procedures used for the removal of this material have been reviewed by Region II, DR0 Personnel. The replacement of the re-inforcing and the concrete in this area will be covered by a separate criteria and separate construction procedures to be prepared at a later date.

Florida Power Corporation has reviewed the activities of the engineering, construction supervision, inspection, and quality personnel concerned with this placement to detennine what procedural or physical changes are necessary to assure that this type of non-conformance will not re-occur. Necessary changes will be implemented prior to the placement of any materials in this area.

A complete report encompassing the entire incident will be filed upon the completion of the replacement of this pour. It is expected that the  ;

final report will be filed by November 1,1972. '

If you have any further questions regarding this matter, please advise us.

Very truly yours ,

b .y ,y 7

f f, / 4 '; > ~ , '

FLORIDA POWER CORPORATION Richard E. Raymond Senior Vice President RER/iw Enclosures.

cc: Mr. John S. Davis Director, Region II

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