IR 05000261/1987013
| ML14175B473 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/26/1987 |
| From: | Conlon T, Harris J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B472 | List: |
| References | |
| 50-261-87-13, NUDOCS 8706170160 | |
| Download: ML14175B473 (4) | |
Text
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gRE UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, N.W., SUITE 2900 o
ATLANTA, GEORGIA 30323 Report No.:
50-261/87-13 Licensee:
Carolina Power and Light Company P. 0. Box 1551 Raleigh, NC 27602 Docket No.:
50-261 License No.:
DPR-23 Facility Name:
H. B. Robinson Inspection Conducted:
April 27-30, 1987 Inspector:
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J. R. Harris Date Signed Approved bg T. E. Conlon, Section Chief Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of Quality Assurance/Quality Control (QA/QC) Controls and Work Activities for the dry spent fuel storage facility, concrete dome repairs, and control of coatings inside containmen Results:
No violations or deviations were identifie PDR ADOCK 05000261 PDR
REPORT DETAILS 1. Persons Contacted Licensee Employees
- T. Aiemi, Acting Director, QA/QC
- G. Beatty, Vice President, Robinson Nuclear Project Department J. Epperly, Civil Project Engineer
- E. Harris, Director, Onsite Nuclear Safety
- D. Quick, Manager Maintenance
- D. Sayre, Acting Director, Regulatory Compliance Other licensee employees contacted included construction craftsmen, engineers, and technician NRC Resident Inspectors H. E. Krug R. M. Latta
- Attended exit interview 2. Exit Interview The inspection scope and findings were summarized on April 30, 1987, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The following new item was identified during this inspectio Inspector Followup Item (IFI) 50-261/87-13-01, Applicable Requirements for Coatings and Supporting Documentation for Coatings in Containment, paragraph The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio. Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio. Unresolved Items
Unresolved items were not identified during this inspectio II 2 Independent Inspection Effort (92706)
The inspector conducted a general inspection of controls for coatings inside the containment.. Review of coating controls indicated the licensee does not have any specifications, procedures or documentation to verify coatings are being controlled in accordance with NRC Regulatory Guide 1.54,
"QA Requirements for Protective Coatings for Nuclear Power Plants" and ANSI Standard N101.4,
"QA Requirements for Protective Coatings for Nuclear Facilities" which is referenced in the Regulatory Guide. Robinson was licensed prior to issuance of the Regulatory Guide and ANSI Standar However, Section 1.8.09 of Amendment No. 2 to the FSAR references Regulatory Guide 1.54, 1972 and ANSI N101.4, 1972 and indicates applicable surfaces of Robinson Unit 2 are recoated with original type coating or approved equal in accordance with original specification requirements or equivalent engineering requirements established for touchup and repai The licensee was not able to provide these requirements or documentation that coatings are being inspected to meet the referenced requirement Also, the licensee did not have any data to show that the coatings have been tested to DBA conditions of temperature, pressure, chemical solutions and radiation level This data is necessary to verify that the coatings will not fail during a design base accident and affect the safe operation of the plan Lack of controls for coatings was identified to the licensee as IFI 50-261/87-13-01, Applicable Requirements for Coatings, and Supporting Documentation for Coatings in Containmen.
Independent Spent Fuel Storage Installation (TI 0110/4)
The inspector examined QA/QC controls and records of concrete placements for the horizontal storage module (HSM). The HSM is a reinforced concrete structure for dry storage of spent nuclear fue The nuclear fuel assemblies will be placed in stainless steel, dry shielded, canisters (DSC) which will be stored in the HSM. These facilities were constructed to provide additional interim storage capacity for the spent nuclear fue The HSM is committed to the requirements specified in 10 CFR 72, Licensing Requirements for Storage of Spent Fuel in an Independent Spent Fuel Storage Installatio Subparagraph G., Quality Assurance of 10 CFR 72, requires a quality assurance program based on the criteria in Appendix B of 10 CFR 5 Review of records included certification records for cement, aggregates and reinforcing steel; test data for slump, air, plastic concrete weight, and concrete strength; quantities of cement, aggregates and water being included in concrete mixes being batched at the batch plant; QA/QC records and nonconformance reports. Review of certification records and test data showed that materials met specification requirements and that the concrete being placed met design requirements. Review of QA/QC records showed that inspections were being performed and documented in accordance with requirements and that deficiencies were being identified and reporte Within the areas inspected, no violations or deviations were identifie. Structural Concrete, Record Review (46055)
The inspector examined repairs to the containment building dome surface coat concrete. The surface coat concrete is a two-inch thick topping of non-reinforced concrete which was hand troweled/float finished on the permanent stay-in-place expanded metal mesh which were the exterior forms for the containment dom The expanded metal mesh and the surface coat are not part of the containment building structural concrete. Application of the surface coat was for aesthetic purpose onl The dome was placed between December 1969 and March 197 Since that time, shrinkage cracks developed in the surface coat which resulted in moisture coming in contact with the mesh which caused corrosion in the mesh and spalling and deterioration of the surface coa After removal of portions of the surface coat, the licensee discovered some small voids in the structural concrete under the expanded metal mesh. This repair work is safety-related since it affects a Category I structur During this inspection, the inspector reviewed procedure SP-720, CV Dome Repair, Structural Concrete Repair/Replacement and records for repairs to the containment dome. Review of records showed that the grout materials being used for repairs met design strength and that inspections were being performed and documented. Review of procedure SP-720 CV showed that adequate requirements were in place for inspection and documentation of Within the areas inspected, no violations or deviations were identifie.
Inspector Followup Items (IFI)
(Closed)
IFI 50-261/86-27-01, Review of RecQrds Documenting Quantity of Concrete Materials being Batched at the Batch Plan Review of records documenting the quantities of materials (cement, aggregate, and water) included in the mixes being batched at the plant disclosed several flaws in the record keeping in this are Review of records during this inspection showed that the records had been corrected to show that the correct amount of materials were being included in the batches of concrete. This item is close (Closed) IFI 50-261/86-27-02, Strength Tests for Materials being Used for Structural Repair of Containment Building Dom Review of procedure SP-720 Rev. 2, Civil Dome Repair Structural Concrete Repair/Replacement, indicated the procedure did not appear to address any strength tests for materials to be used in structural repair No materials have been used for structural repair Review of procedures and records during this inspection showed that the procedure had been updated to require strength tests and that the strength tests were being done in accordance with procedures and that concrete strength requirements were being met. This item is closed.