IR 05000389/1976001

Letter Informing the NRC That the Enclosed Inspection Report 05000389/1976001 Contains No Proprietary Information

ML18109A417
Person / Time
Site:	Saint Lucie
Issue date:	09/08/1976
From:	Murphy C NRC/RGN-II
To:	Robert E. Uhrig Florida Power & Light Co
References
L-76-328 IR 1976001
Download: ML18109A417 (13)

Text

September 8, 1976 L-76-328 Norman C. Moseley, Director Office of Inspection and Enforcement, Region II U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303

Dear Mr. Moseley:

Re: IE:II:DHD 50-389/76-1 Florida Power 6 Light Company has examined the above-referenced inspection report and has determined that contains mo proprietary information.

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Very truly yours,

Robert E. Uhrig Vice President REU/MV/hlc cc: Jack R. Newman, Esq.

PCOPLC... SEIRVINo VFOI'Lfi

~o q IIE00 UNITED STATES

4p 4V NUCLEAR REGULATORY COMMISSION n

REGION I I ge 230 PEACHTREE STREET, N. W. SUITE $ 18 ATLANTA,GEORGIA 30303 4+*+4 AUG 2 6 1976 In Reply Refer To:

IE II:DHD 50-389/76-1 Florida Power and Light Company ATTN: Dr. R. E. Uhrig, Vice President of Nuclear and General Engineering P. 0. Box 013100 9250 West Flagler Street Miami, Florida 33101 Gentlemen:

This refers to the inspetion conducted by Mr. D. H. Danielson of this office on July 28-30, 1976, of activities associated with your applica-tion for an NRC Construction Permit for St. Lucie Plant, Unit 2 and to the discussion of our findings held with Mr. B. J. Escue at the con-clusion of the inspection.

Areas examined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective examination of procedures and representative records, interviews with personnel, and observations by the inspector.

Within the scope of this inspection we identified no significant devia-tions from the requirements of 10 CFR 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants," of the NRC regulations.

In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the .

enclosed inspection report will be placed in the NRC's Public Document Room. I'f this report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office requesting that such information be withheld from public disclosure. If no proprietary information is identified, a written statement to that effect. should be submitted. If an application is submitted, it must fully identify the bases for which information is claimed to be proprietary. The application should be prepared so that information sought to be withheld is incorporated in a separate paper and referenced in the application since the application will be placed in the Public Document Room. Your application, or written statement, should be submitted to us within 20 days. If we are not contacted as specified, the enclosed report and this letter may then be placed in the Public Document Room.

I Florida Power and Light Company Should you have any questions concerning this letter, we wi11'be glad to discuss them with you.

Very truly yours, Reactor Construction and Engineering Support Branch Enclosure:

XE Inspection Report No.

50-S89/76-1

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'ItII Ci REC0, Np UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I I i

230 PEACHTREE STREETt N W SUITE 818 ATLANTA,GEORGIA 30303

+**++

IE Inspection Report No. 50-389/76-1 Licensee: Florida Power and Light Company P. 0. Box 013100 Miami, Florida 33101 Facility Name: St. Lucie Unit 2 Docket No.: 50-389 License No.: Pending Category: Al tt Location.'utchinson Island, Florida Type of License: 800 Mwe (CE)

Type of Inspection: Routine, Unannounced, Preconstruction t

Dates of Inspection: July 28-30, 1976 Dates of Previous Inspection'. December 16-18, 1975 Principal Inspector: D. H. Danielson, Reactor Inspector Projects Section Reactor Construction and Engineering Support Branch Accompanying Inspector: R. M. Wright, Reactor Inspector Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Other Accompanying Personnel: C. E. Murphy, Chief Reactor Construction and Engineering Support Branch Principal Inspector:

D. H. Danielson, Reactor Inspector Date Projects Section Reactor Construction and Engineering'upport Branch

IE Rpt. No. 50-389/76-1 Reviewed by:

C. Brya~ Chief ate rojects Section Reactor Construction and Engineering Support Branch

IE Rpt. No. 50-389/76-1 SUMMARY OF FINDINGS I. Deviations None II. Licensee Action on Previousl Identified Deviations Hone III. New Unresolved Items None IV. Status of Previousl Re orted Unresolved Items None V. Desi n Chan es None VI. Unusual Occurrences None VII. Other Si nificant Findin s None VIII. Mana ement Interview On July 30, 1976, the inspectors met with Mr. B. J. Escue, Prospect Construction Superintendent, and members of the plant staff to review the scope and findings of the inspection. It was noted that within the scope of the inspection we identified no signi-ficant deviations from the requirements of 10 CFR 50, Appendix B.

IE Rpt. No. 30-389/76-1" DETAILS I Prepared by:

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D. H. Danielson, Reacto Inspector Date Pro3ects Section Reactor Construction and Engineering Support Branch Dates of Inspection: July 28-30, 1976 Reviewed by:

C, Brya t', Chi 'f Date rojects ection Reactor Construction and Engineering Support Branch 1. Individuals Contacted Florida Power and Li ht Com an (FPSL B. J. Escue Project Construction Superintendent N. T. Weems Assistant .QA Manager, Construction A. M. Anderson Senior QA Engineer, Electrical.

D. R. Stone Project QC Supervisor 2. Sco e of Ins ection This inspection was performed to review the licensee's site audit activities and onsite contractor organizations'A/QC programs for site preparation activities. authorized under an LWA-2.

3. Site Audits The PSAR, Chapter 17, paragraph 17.1.18.5, specifies the FP6L audit commitments. The detailed instructions for conducting and scheduling audits are provided in Quality Procedure Nos. QR 18.1 and QP 18.2, respectively.

To verify compliance with the above commitments, the inspector examined reports and related records for five audits performed since February 1976. This examination covered audit planning, scope and purpose, documentation of results, management review, and followup of corrective action. FPGL reports of audits that were reviewed are as follows:

a. EBASCO Document Control, QAC-EBASCO-76-16

'b. FPSL Document Control System, QAC-FPL-QC-76-17

ZE Rpt. Ho. 50-389/76-3. I-2 c. FP&L QC Construction Material Control, QAC-FPL-CONSTR-QC-76-2 d. EBASCO Indoctrination and Training, QAC-EBASCO-76-3 e. FP&L Construction QA Indoctrination and Training, QAC-FPL-CONSTR-76-6 Within the areas examined, there were no deviations disclosed.

4. Review of Contractor A Manual The PSAR, Chapter 17, paragraph 17.1.4.3, specifies the FP&L suppliers'A program evaluation commitments. The detailed instructions for evaluation of a suppliers QA program are provided in Quality Proce-dure No. Qp 4.3.*

W ~t Raymond International, Inc. is installing sheet piling for the reactor containment building cofferdam and the intake structure cofferdam. The inspector reviewed the Raymond International QA manual to assure adequate plans and procedures had been established for their scope of work. This review included site organisation, management review, control of material and processes, control of conditions adverse to quality, document control, test control and control of test equipment, control of quality records and audits.

In addition, documented evidence of FP&L evaluation and acceptance of the Raymond International QA program and procedures was reviewed by the inspector. Within the areas examined, there were no devia-tions disclosed.

DETAILS II Prepared by: Fi9 7G R. W. Wright, React r Inspecto'r Date Engineering .Support Section No. 1 Reactor Construction and Engineering Support Branch Dates of Inspection: July 28-30, 3.976 Reviewed by:

T. E. Conlozi,:Chief- Date Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch l. ersons Contacted a. Florida Power and Li ht Com an (FPSL)

N. T. Weems Assistant QA Manager, Construction A. M. Anderson QA Engineer, Electrical L. T. Stone QA Engineer, Civil B. J. Escue Project Construction Superintendent D. R. Stone Project QC Supervisor R. G. Reesby - Area QC Supervisor (Civil)

b. Contractor Or anizations (1) Ebasco Services Inc. (Ebasco) ~

J. C. Murphy Sr. Resident Engineer (2) Moretrench American Cor oration MAC)

C. Williams 2. ~8co c This inspection was conducted to observe and evaluate the work in progress and to ascertain whether activities relative to site preparation are being accomplished in accordance with NRC requirements and SAR commitments, and to determine if procedures and recordkeeping requirements have been developed and are being properly implemented in the subject inspection areas.

Procedure Review The following Ebasco specifications, FP&L quality control procedures, construction site procedure, and contractor operating procedure

were examined for conformance to SAR commitments, applicable codes and standards.

Document Number Title FLO-2998.472 (R5) Dewatering FL0-2998.471 (R2) Excavation and Backfill QA lo.8 (Rl) Checking/Record Review of Dewatering Systems and Components QI 10.10 (Rl) Inspection of Excavations and Fill Compaction CSP 25 Excavation and Backfill COP-2-1 Sheet Pile and Excavation No items of procedural noncompliance were identified.

4. Observation of Work Activities a. Pro ect Status Prior to Commencement of LWA-2 Work The soils above elevation minus 60 feet were excavated and recompacted to a relative density of 85 percent AASHO over the entire plant area to provide satisfactory bearing, settlement and resistence to liquefaction characteristics. The final site grade is at elevation plus 18 feet and the ground water level is esthnated to be the normal high water level in the Indian River at elevation plus 2 ft.

b. Activities Observed Raymond International has completed the driving of sheet piling and the installation 'of the top wale for the reactor containment building cofferdam. The inspector observed the driving of sheet piling for the intake structure Cofferdam.

Moretrench has reactivated wells formerly used for Unit 1 to draw down the water level within the construction boundaries of Unit No. 2 from elevation plus 2 to minus 15. Excavations below elevation minus 15 will require individual systems set up for each particular excavation.

The IE inspector observed the contractor installing such

a system for the reactor containment building base mat excavation. The well casing utilized was 8 inch diameter PVC pipe capable of withstanding 160 psi and meeting code requirements ASTM 1785 and ASTM 2665. This internal well system should be capable of lowering the water table within the reactor containment building area to elevation minus 30.

(3) Blastin Excavation Fill Placement Since no structure has its foundation below elevation minus 60 no blasting for ease of excavation is anti-cipated. The contractor has removed the fill to ap-proximately elevation plus 5 in order to commence with the driving of the intake structure sheet piles. Ho other excavation nor backfill opeations have begun.

(4) C Ins ection and Laborator Testin Facilities The IE inspector observed the QC coverage being implemented for the above earthwork activities and conducted conversations wit% several QC inspectors during the course of their surveillances. These discussions indicated the inspectors were knowledgeable with their respective quality control procedures and they were found to be satisfactorily implementing them. An inspection was made of the FPGL soils laboratory facilities, noting particularly their testing capabilities, checking for up-to-date calibration of equipment, and the experience of its personnel.

No items of noncompliance were identified in any of the above areas of inspection.

5. Record Review The following quality records were selected for review to ascertain that the work was being accomplished and documented in accordance with applicable codes, commitments and procedural requirements:

a. Reactor Containment Building Cofferdam Report Package containing QC surveillance inspection reports for pile driving and associated nonconformance reports for the period 6/3/76 to 7/27/76 b. Main Yard Dewatering System Testing Records conducted 7/27/76

t IE Rpt. No. 50-389/76-1

~ ~ II-4 c. Certifications and personnel qualification records for various soil inspectors d. Inspector training records e. Sheet Piling Welding (1) Welding procedure qualifications (2) Welder performance qualifications (3) Welding materials control records No items of noncompliance were identified in any of the above areas of record inspection.

6. Nondirected Ins ection Activities The IE inspector made a cursory inspection of the concrete batching facilities. The inspector also observed the sampling and testing of a non-safety related pour (warehouse foundation) for slump, air content, temperature, yield, and the molding of concrete cylinders

~'Nor compressive testing. All testing is similar to safety related.

pours.

No items of noncompliance were identified.