IR 05000395/1982014

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IE Insp Rept 50-395/82-14 on 820125-28.No Noncompliance Noted.Major Areas Inspected:Previous Insp Findings & Quality Records & Qa/Qc Controls on Site Preparation on Foundations
ML20041C524
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 02/05/1982
From: Conlon T, Harris J, Lenahan J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20041C523 List:
References
50-395-82-14, NUDOCS 8203020178
Download: ML20041C524 (5)


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UNITED STATES NUCLEAR REGULATORY COMMISSION o

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E REGION 11

o 101 MARIETTA ST., N.W, SUITE 3100 Y

ATLANTA, GEORGIA 30303 g*****

o Report No. 50-395/82-14 Licensee:

South Carolina Electric and Gas Company P. O. Box 764 Columbia, South Carolina 29318 Facility Name:

Summer Nuclear Plant Docket No. 50-395 License No. CPPR-94

Inspection at Summer site near Columbia, South Carolina Inspectors:

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.2-/f/g-2 J.J.ynahan Dat'e S'igned 0h 1A$

EL/58r2-J. R. Harrff' ~

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Approved by:

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__,f f f 2 T. E. ConFon,~ Sect. ion Chief 0 te Signed Engineering Inspection Branch Engineering and Technical Inspection Division SlJMMARY Inspection on January 25-28, 1982 Areas Inspected This routine, announced inspection involved 56 inspector-hours on site in the areas of licensee action on previous _ inspection finding, quality. records and QA/QC controls on site preparation, and quality recordsend'QA70C c'ontrols on

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foundations.

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l Results i

Of the areas inspected, no violations or deviations were identified.

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REPORT DETAILS 1.

Persons Contacted Licensee Employees

  • 0. S. Bradham, Station Manager
  • J. M. Woods, Construction Site Manager
  • R. Lindler, Civil QC Supervisor D. Moore, QA Manager R. Bouknight, QA Surveillance Specialist
  • H. Radin, Director, Project Engineering
  • H. I. Donnelly, Licensing Engineer
  • D. A. Nauman, Group Manager Nuclear Service
  • W.

Irvin, Civil QC Inspector

  • R. Clary, Manager Nuclear Licensing Other Organizations
  • R. C. Mayew, Licensing Engineer, Gilbert NRC Resident Inspector
  • J. L. Skolds
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on January 28, 1982 with those persons indicated in paragraph I above.

3.

Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (395/81-19-01):

Post-tensioning Ram Calibration Records.

These records were unavailable for review during the previous inspection (81-19). The licensee obtained records for the calibration of the stressing rams after completion of the onsite stressing work from the post-tensioning system contractor, INRYCO, Inc.

The purpose of the post-work ram calibrations is to determine if the rams remained in calibration during the onsite stressing work. The inspector reviewed these records and verified that the rams had been calibrated as required by the project specification. This item is closed.

4.

Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 6.

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5.

Site Preparation - Review of Quality Assurance Implementing Procedures The folicwing procedures and specifications were examined to determine if work activities and quality control and quality assurance functions were provided for as stipulated in NRC r4quirements, FSAR Sections 2.5.4 through 2.5.6, and the SER:

a.

GAI specification SP-211-4461-00, Excavation and Placement of Structural Fill b.

Procedure number FQCP 5.1.1, Structural Backfill and Earthwork c.

Procedure number FQCP 5.1.2, Surveillance and Control of Rock Basting d.

Procedure number FQCP 5.1.4, Earthwork Test Traceability e.

Drawing number E-401-021, Site Preparation Excavation Plan f.

Drawing numbers E-401-022 through E-401-025, Site Preparation

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Excavation Sections No violations or deviations were identified.

6.

Site Preparation - Review of Quality Records The inspectors examined the following quality records relating to site preparation:

a.

Results of relative density tests performed on Zone III fill supporting the fuel oil storage tank b.

Verification of results of nuclear density tests by use of sand cone density tests for the period April 1976 through October 1977 c.

Nonconformance Notices, numbers 195C and 287C d.

Results of compaction tests performed on Zone II fill materials Acceptance criteria examined by the inspectors are those procedures listed in paragraph 5.

Review of the above records and discussions with QC personnel disclosed that backfill under and around safety related piping and ductbanks in the West Embankment area may not have been controlled as required by specification requirements.

Licensee engineers and QC personnel stated that records may be available to document that the fill materials under and around the safety related piping and ductbanks was placed in accordance with specification requirements. The lack of quality records to document the fill placement for safety related piping and ductbanks was identified to the licensee as.

Unresolved Item 82-14-01 " Piping and Ductbank Fill Placement Records."

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No violations or deviations were identified.

7.

Foundations, Review of Quality Implementing Procedures:

Procedures, drawings and specifications concerning control of foundations were examined by the inspectors to determine if work activities and quality control and quality assurance function were provided for as stipulated in Sections 3.8 and 17 of the FSAR, the SER, and NRC requirements. In addition to those documents listed in paragraph 5, the following drawings, procedures and specifications were examined by the inspectors:

a.

Specification SP-701-4461-00, QA Program Requirement b.

Specification SP-207-4461-00, Structural Concrete c.

Specification SP-202-4461-00, Placing Reinforcing Steel d.

Specification SP-214-04461-000, Drilled Caissons e.

Dames & Moore Field Procedure for Resident Engineer-Caisson Foundations f.

Drawing number 4461 E-413-042, Intermediate Building Caisson and Basement Supporting Pier Plan g.

Drawing numbers 4461 E-413-043 and 044, Intermediate Building Caisson and Basement Supporti. 3 Pier, Sections h.

Drawing number E415-041, Fuel Handling Build ng Caisson and Basement Supporting Pier i.

Drawing number E-303-027, Diesel Generator Fuel Oil Storage Fank - Plan and Sections J.

Drawing number E401-026, Foundation Mat Plan and Outline of Building Foundations Discussions with responsible engineers and examination of the above listed documents indicated adequate instructions, plans and procedures were established for control of foundation construction.

No deviations or violations were identified.

8.

Foundations, Review of Quality Records Records examined by th. inspectors were those for the foundations of the reactor, control, intermediate, fuel handling, auxiliary and diesel generator buildings, and the condensate and diesel generator fuel oil storage tanks. The reactor, control ano auxiliary buildings are founded on rock. The diesel generator, fuel handlit g, and intermediate buildings are founded on caissons extending into rock.

The diesel generator and condensate storage tanks are founded on crushed rock (Zone III fill).

Detailed records on inspection and installation of caissons FHB-22, FHB-26, FHB-27 and IB-35 were examined by the inspectors.

Acceptance criteria examined by the inspectors are those applicable procedures listed in paragraphs 5 and 7.

Records showed that the caissons were inspected and installed in accordance with acceptance criteria.

No deviations or violations were identifie,.

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9.

Containment (Prestressing) - Review of Quality Records The inspector examined the following quality records related to installation of the post-tensioning system for the reactor u ilding:

a.

Fabrication records for tendon numbers BA 43, AC 43, CB 39, BA 39, AC 20 through AC 22, D 117, D 118, D 216, D218, and D316 through D 318.

b.

Certified material test reports for stressing wire, heat numbers 17658, 17662, 17960, 20022, 20200, 20204, 20206, 20842, 29817, 29818, 31609, 35000, 35407, 35680, 40911, 41063, 41667, and 51605.

c.

Report on 1000-hour stress relaxation test on Armco "Tufwire 8" stressing wire d.

Reports for 20 hour2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> stress relation tests performed on wire from heat number 20022, 29817, 29818, 35000, 40991 and 41063.

Discussion with licensee QA personnel and review of the above record disclosed that the stressing wire used in fabrication of the tendons was manufactured by Armco and designated as "Tufwire 8."

Acceptance criteria examined by the inspector appear in FSAR Section 3.8, Specification SP-207, and the INRYC0 Field Installation Manual.

No violations or deviations were identified.