IR 05000389/1979004

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IE Insp Rept 50-389/79-04 on 790227-0302.No Noncompliance Noted.Major Areas Inspected: Concrete Lab,Intake Structure, Concrete Placement,Weld Repair to Containment Vessel & Site QA Audit
ML17206A804
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 03/20/1979
From: Gouge M, Herdt A, Wright R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17206A803 List:
References
50-389-79-04, 50-389-79-4, NUDOCS 7905230153
Download: ML17206A804 (10)


Text

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kp*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30303 Report No.

50-389/79-04 Licensee:

Florida Power and Light Company P. 0. Box 529100 Miami, Florida 33152 Facility Name:

St. Lucie Nuclear Plant, Unit 2 Docket No.

50-389 License No.

CPPR-144 Inspection at St. Lucie Site, Hutchinson Island, Florida Inspectors:

R.

W. Wright M. J.

uge Approved by:

sd A. R. Herdt, Section Chief, RCSES Branch Date igned Date Signed Q Jo 7 Date Signed SUMMARY Inspection on February 27, 1979 - March 2, 1979 This routine, unannounced inspection involved 51 inspector-hours onsite in the areas of licensee action on previous inspection findings; concrete laboratory inspection; intake structure concrete placement; weld repair to containment vessel; procurement control; design control - site; site gA audit and 10CFR21 posting.

Results No items of noncompliance or deviations were identifie DETAILS Persons Contacted Iicensee E

lo ees Florida Power and Li ht Co an (FPL

  • B. J. Escue, Site Manager

+J. E. Vesseley, DirectorQuality Assurance

+N. T. Weems, Assistant Manager, QA - Construction

  • W. M. Hayward, Supervisor Engineer, QA - Construction

+W. M. Gaines, Site Engineer, EPP

  • J. L. Parker, Project QC Supervisor
  • E. W. Sherman, QA Engineer J.

W. Adams, QA Engineer R. A. Symes, QA Engineer K. VanOevern, QA Engineering Record Custodian T. P. McKinon, QA Engineer B. M. Parks, QA Engineer L. T. Page, QA Engineer D. R. Cooper, QA Engineer C. Carlo, Area QC Supervisor - Civil M. Meiley, QC Inspector, Calibration E. Rutkowski, Senior Purchasing Agenct Other licensee employees contacted included several construction craftsmen, technicians and office personnel.

Other Or anizations

  • R. A. Garramore, Senior Resident Engineer (EBASCO)

L. V. Pelosi, Site Project Engineer (EBASCO)

V. Gerley, Design Engineer - Civil (EBASCO)

L. J. Shapiro, Design Engineer - Mechanical (EBASCO)

R. Hartin, Design Engineer - Mechanical (EBASCO)

J.

A. Baysinger, Process Control Specialist (EBASCO)

C. L. Fields, Project Welding and QA Superintendent (CBI)

D.

M. Swan, QA Technician (CBI)

+Attended exit interview.

Exit Interview The inspection scope and findings were summarized on March 2, 1979, with those persons indicated in Paragraph 1 above.

The licensee was advised that no items of noncompliance or deviations were identified during the inspectio.

Licensee Action on Previous Ins ection Findin s (Open) Noncompliance 389/78-10-01:

Failure to report safety significant deficiencies.

The inspector examined Ingersoll - Rand's (I-R) Instruction Manuals and material receiving reports for St. Lucie Unit 2 containment spray pumps (CSP)

and low pressure safety injection pumps (LPSI).

I-R drawing numbers C-8x23WDF500x7A, Rev 2, and C-8x20WDF500x24A, Rev 2, contained in these manuals show details depicting the latest design change for the impeller locking nut assembly which has been employed by Arkansas Nuclear One - Unit 2 (i.e., only one nut is involved, a tab washer was added and the large impeller washer was modified by the addition of a pin).

Additionally; an Ebasco Vendor gA Report examined entitled

"Mechanical Equipment Report No. 5" for order No.

NY-422527 (two I-R CSP's)

dated March 16, 1978, specifies,

"the vendor has resolved the above (see FPL letter November 21, 1975) via Ebasco Engineering NY and have redesigned the CSP's to correct the potential problem area".

This item remains open pending further evaluation by IE.

4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Inde endent Ins ection Effort a.

Concrete Laborato Ins ection The concrete laboratory maintained by the Civil guality Control group was inspected.

The testing facility was clean and all measuring and test apparatus was observed to be in calibration.

The Region II inspectors noted an out of specification reading on the strip chart used to record temperature in the concrete cylinder moist curing room.

The observed temperature was 79~F; ASTM C511 requires a

temperature in the moist curing room of 73.4 F plus or minus 3 F.

The out of specification moist curing room temperature was due to a

failure of the room air conditioning unit.

Repairs were effected to the air conditioning unit and the out of specification temperature was documented on draft NCR.

The inspectors observed a calibration check of wire-cloth seives used for gradation analysis of fine aggregates and soils.

The calibration check was conducted by use of a measuring microscope as described in Appendix Al of ASTM E 11"70.

No items of noncompliance or deviations were identified in the above areas inspecte b.

Intake Structure Concrete Placement The Region II inspector observed concrete placement IS-27D,F in the transition hood areas of the seismic category I intake structure.

The following documents were reviewed to ascertain licensee commit-ments and procedures in the area of concrete placement and inspection; PSAR Sections 3.8.1 and 3.8.3 FPL Quality Instructions (QI) 10.3, 10.6, and 10.71 Ebasco Concrete Specification FL0-2998.473 Drawing Numbers 2998-G-643, 644, 646 Areas inspected included pre-placement inspections, in-process concrete testing and documentation, delivery of pumped concrete, placement of category I concrete, and consolidation of placed concrete.

In-process testing was conducted in accordance with applicable procedures with properly calibrated instruments.

Civil Quality Control monitored the entire placement.

There was no reinforcing steel in this placement but the licensee was utilizing wire mesh screens in the forms.

Initial placement of concrete through these screens resulted in some separation of larger aggre-gates from the concrete mix.

The Quality Control (QC) inspector noted this and directed the placing crew to deposit the concrete between the wire mesh grid and the formwork.

The QC inspector documented the potential aggregate segregation on the QC inspection report.

During initial placement pumped concrete was allowed to free fall 7 to 8 feet due to interference with the wire mesh.

The normal limit is a free fall of no greater than 5'nless specifically approved per FLO 2998.473.

Prior approval had been obtained and documented for the 7 to 8 feet initial free fall for this placement.

No items of noncompliance or deviations were identified in this area.

Co Weld Re air to Containment Vessel The Region II inspector observed in-process repair of defects identified during the removal of the 24 "A-frame" supports from ring D of the steel containment vessel.

Chicago Bridge and Iron Company (CBI) is the subcontractor responsible for fabrication, inspection and repair of the steel containment vessel.

The subject defects had been identified as nonconforming items on the CBI nonconformance list and were being repaired in accordance with CBI Repair Procedure SRP-73-7302-100R2.

The welding repair observed was in the area where support gl had been located.

The repair was conducted in accordance with SRP-73-7302-100 R2 and had been documented on the Repair Check List per Section 7.5.10 of CBI Nuclear Quality Assurance Manual.

The qualification record of the welder was examined to verify qualification in accordance with the repair

-4-procedure.

Identification of nonconforming items and documentation of weld repair and associated nondestructive examination were in accordance with the CBI Nuclear Quality Assurance Manual.

No items of noncompliance or deviations were identified in the above areas inspected.

6.

Procurement Control FPL has delegated responsibility for procurements of systems, components and structures to Ebasco Services and the NSSS supplier, Combustion Engineering.

FPL (site) may procure safety related services and materials within specified money limitations established by procedure, and all such safety related requisitions on purchasing agenct (RPA) and subse-quent purchase orders are required to have QA review and approval.

The following QA and purchasing procedures are the controlling documents reviewed by the inspector:

a

~

b.

c ~

d.

e.

Administrative Site Procedure, ASP-8, Procurement FPL - General Operations Procedures GO 30, GO 30.1, GO 30.2 Control of Special QA Documents QI6, QAD3 Quality Requirements for Nuclear Related Purchases, QA1001 and QA1002 Quality Procedures, QP4.2, 4.4, 7.3, 7.4, 7.5 Administrative Site Procedure, ASP-11, Qualification of Bidders The inspector selected the following purchase orders to determine compliance with procedure requirements.

a.

b.

c ~

d.

e

~f.

86506 - 26775 SI SL-14766 50275 " 26119 S SI-14501 68921 - 23996 S SL"13572 68921 - 25301 S SL"14183 68921 - 25290 S SL"14173 68921 - 24805 S SL-13882 The inspector verified by review of the purchase orders, review of pertinent receiving inspection documentation, and discussion with respon-sible personnel that processing of the above procurement documents and surveillance of procurement activities was performed in accordance with procedure requirements.

No items of noncompliance or deviations were identifie "5-7.

Desi n Control - Site Permanent plant design is accomplished by the architect engineer, Ebasco Services (EBASCO) who has an on-site personnel extension of their design services called ESSE (EBASCO Site Support Engineering).

Presently the ESSE group consists of approximatel nineteen designers and engineers of various disciplines.

ESSE's on site design effort for the permanent plant to date has been primarily limited to; 2-inch and under piping design of all non-safety piping; preparation of piping isometrics for 2-inch and under safety related and non-safety related piping; 2-inch and under piping support and restraint design for seismic and non-seismic, safety and non-safety related systems; lighting and communication conduit and occasional items which appear on an open engineering items (OEI) list which EBASCO feels are preferrable to be accomplished on site.

ESSE's site originated design efforts are controlled by EBASCO internal procedures.

In accordance with FPL's procedures gP 3.5, ASP-10 and ASP-16 ESSE reviews and dispositions all field change requests (FCR's)

and nonconformaing reports (NCR's} and assures design documentations are completed in accordance with all approved FCR's.

ESSE also has the authority to prepare and issue design change notices (DCN's)

and is responsible for insuring that effected design document revisions are completed in accordance with approved DCN's.

The inspector held discussions with responsible personnel, reviewed the controlling site procedures, examined the current OEI list and selected the following field originated design documents for review.

a.

Cable Tray Designs 4 Trays Hanger No T39 3 Trays Hanger No T 194 2 Trays Hanger No T 250 b.

Calculation LJS.041 - Mall Thickness Verification c.

Support/Restraint 4R, Calc.

No. C-4B Support/Restraint 5F, Gale.

No. C-5F Support/Restraint Sl-43-R1, Gale.

No. C-SI-43-Rl The inspector determined that site design control activities and associ-ated surveillance activities were being implemented in accordance with controlling procedure No items of noncompliance or deviations were identified.

8.

Site alit Assurance Audits The Region II inspectors examined the audit program conducted by FPL site QA group.

The following procedures from the FPL Quality Assurance Manual set forth requirements for site management and activity audits:

QP 18.1 Conduct of Quality Assurance Department Quality Audits QP 18.2 Scheduling of Quality Assurance Department Audit Activities QI 18 QAD 1 Audit Program Plans and Schedules The inspectors reviewed quarterly audit schedules from January 1978 to March 1979 to determine the scope and depth of the site audit program.

The projected audit schedule'or calendar year 1979 was reviewed to determine that the scheduled audits provide adequate review of projected construction, design and procurement activities.

The following site QA audits were reviewed for scope, completeness, deficiencies found, corrective action taken and implementation in accordance with the licensee procedures QP 18.1 and QP 18.2:

Audit Number Title QAC-PSL2-78-9 78-17 78-18 78-25 78-30 78-31 78-35 78-37 78-46 78-48 78-49 78-51 Ebasco Site Support - Engineering Bigge Power Corporation Records Design Control QA Records Control Control of Contractor Drawings and Specifications Design Drawing Changes Audit of Batch Plant Operations Drawing Control Receiving Inspection Procedure Control RCB Placement g7 Procurement Control Trend analysis reports for each quarter of 1978 and the overall 1978 trend analysis report were examined to determine if significant, recurring weaknesses or findings had been identified.

The auditor training program was reviewed and the qualification/training records of two auditors were examine The inspectors determined that a meaningful audit schedule was being maintained, the auditor training program was effective, audits were performed in accordance with established procedures, findings were identified and closed in a timely manner, and that a comprehensive trend analysis program was in effect.

No items of noncompliance or deviations were identified.

9.

CFR Part 21 Ins ection The site facilities were inspected to determine if the posting require-ments specified in 10CFR21.6 had been implemented.

The licensee had posted notices prepared per 10CFR21.6(b) in two conspicuous locations in the construction office building.

The posting requirements of 10CFR21.6 had been implemented at St. Lucie Unit 2.

No items of noncompliance or deviations were identified.