ML17296B000

Interim Deficiency Rept Re Excessive Shear Stresses in Concrete Slabs Supporting Safety Injection Tanks 1B,2A & 2B. Seismic Loads on Safety Injection Tank Supports Will Be re-evaluated by C-E.Final Rept to Be Submitted by 801231

ML17296B000
Person / Time
Site:	Palo Verde
Issue date:	09/26/1980
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
10CFR-050.55E, 10CFR-50.55E, ANPP-16430-BSK, NUDOCS 8010060253
Download: ML17296B000 (10)

Text

REGULAT Y INFORMATION DISTRIBUTIO YSTEM T ¹ (RIDS)'CCESSION NBR:8010060253 DOC ~ DATE: 80/09/26 NOTARIZED: NO DO FACIL:STN-50-528 Palo, Verde Nuclear Stetioni Unit ii Arizona Publ j 500 5 STN 50-529 Palo Verde Nuclear Stations Unit 2i Arizona Publi 05000529 AUTH'AME AUTHOR AFF IL'IATION VAN BRUNTPE ~ ED Arizona Public Service Co. F'> L RECIP ~ NAME RECIPIENT AFFILIATION SPENCERPG ~ ST Region 5P san FranciscoP Reactor construction 8 Engineer

SUBJECT:

Iterim deficiency rept re excessive she'ar stresses ini concr'ete slabs supporting safety injection tanks 18i2A L 28 '

Seismic loads on safety injection tank supports will be revaluated by C-ED Final rept to be submitted by 801231,,

DISTRIBUTION CODE: B019S COPIES RECEIVED:I.TR L EiVCLi / SIZE:

TITLE: Construction Deficiency Report (10CFR50.55E)

NOTES:Standardized Plant. 05000528 05000529 ACTION:

INTERNAL: AD/RC I/IE

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ARIZONA NUCLEAR POWER PROJECT l'os( ()llu'.o Itox P I (i(i(i 'ouix, Riin>na (ibO,'i(i September 26, 1980 ANPP-16430-BSK/JAR U. S. Nuclear Regulatory Commission Region V Walnut Creek Plaza Suite 202 1990 North California Boulevard Walnut Creek, California 94596 Attention: Hr. G. S. Spencer, Chief Reactor Construction and Engineering Support Branch

Subject:

A 50.55(e) Potentially Reportable Deficiency Relating to Excessive Shear Stresses in Units 1 and 2 Goner'ete Slabs Supporting the Safety Injection Tanks 1B, 2A and 2B Interim Report File: 80-019-'026

Reference:

Telephone Conversation between R. Dodds and B. S. Kaplan on August 28, 1980 (DER 80-24)

Dear Sir:

The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. 'At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and eval>> ation required, an interim report is attached. It is now expected that this information will be finalized by December 31, 1980, at which tinfe a complete report will be submitted.

E. E. Van Brunt, Jr.

APS Vice President Nuclear Projects ANPP Project Director EEVBJr/BSK:skc

$ o/f Attachment J )

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"U. S. Nuclear Regulatory Commission Attention: Hr. C. S. Spencer, Chief AHPP-16430-BSK/JAR September. 26, 1980 Page 2

'cc: ~Victor Stello, Jr., Director j

'Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C, 20555 A. C. Gehr Snell & Wilmer R. L. Robb D. B. Easnacht W. E. Ide J. H. Allen A. C. Rogers J. A. Brand W. H. Wilson W. G. Bingham W. J. Stubblefield J. E. Bashore R. H. Grant R. W. Welcher D. R. 1lawkinson

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INTLRIN RLPORT POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COHPANY (APS)

PVNGS UNITS f11 AND fI2 I. Potential Problem During final checking of the Containment Building calculations for the Elevation 100'-0" concrete slabs, it was disc'overed that the shear stresses in the con-crete slabs supporting Safety Injection Tanks 1B, 2A and 2B exceed the Design Criteria allowable values due to high seismic forces. The concrete slabs were origi-nally designed based on Safety Injection Tank support loads. This information was changed. by Combustion Engineering after the slab design was issued for con-struction.

II. A roach To and Status Of Pro osed Resolution The present Safety Injection Tank seismic forces are the result'f an analysis based on spring stiffnesses of a preliminary layout of the sturctural steel framing at Elevation 140'-0". The structural steel framing has since changed. The present steel framing plan at Eleva-tion 140'-0" provides much greater stiffnesses at the upper lateral supports for the Safety Injection Tanks, thereby significantly reducing the seismic loads at the lower supports.

In addition to the above, the,cex~tified loads were based on a conservative seismic analysis using generic response spectrum curves. The use of Project response spectra curves will lower the resultant seismic loads.

It is our belief that using the actual spring stiffnesses of the current structural steel framing at Elevation 140'-0" and Project specific response spectra, the concrete slabs at Elevation 100'-0" will meet the Design Criteria allow-able stress values.

The seismic loads on the Safety Injection Tank Supports will be reevaluated by Combustion Engineering using the actual spring stiffnesses of the current structural steel" framing at Elevation 140'-0" and Project response spectra curves. Then the concrete slabs at Elevation 100'-0" will be reevaluated by Bechtel with the revised loads to see if

,they meet the Design Criteria allowable stress values.

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Interim Report Page 2 III. Pro ected Com letion of Corrective Action and Submittal Date of the Final Re ort The Combustion Engineering/Bechtel analysis and final report is anticipated to be. completed by December 31, 1980, at which time a final report will be 'submitted.

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