IR 05000400/1985051
| ML18019A547 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/13/1986 |
| From: | Conlon T, Harris J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18019A546 | List: |
| References | |
| 50-400-85-51, NUDOCS 8601290032 | |
| Download: ML18019A547 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report No.:
50-400/85-51 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
License No.:
CPPR-158 Inspection Conducted:
,December 9 - 13, 1985 I
Inspector:
J.
. Harris Approved bye T.
E.
Con on, Section Chief Engineering Branch Division of Reactor Safety Date Signed Date Signed SUMMARY Scope:
This routine, unannounced inspection involved 37 inspector-hours on site in the areas of structural concrete, coatings, safety-related dams and repai r of water leakage in the reactor auxiliary building, and waste process building.
Results:
No violations or deviations were identified.
860i290032 860ii5 PDR ADOCK 05000400I
,3
REPORT DETAILS Persons Contacted Licensee Employees
- R. A. Watson, Vice President, Harris Nuclear Project
"J.
L. Willis, Plant General Manager C.
L. McKenzie, Director, QA/QC Operations
- N. J. Chiangi, Manager, QA/QC
"R. A. Somers, Superintendent CI
- L. A. Garner, Civil/Mechanical Unit Supervisor
"J.
W. McKay, Resident Civil Engineer
"D. C. Whitehead, QA Supervisor Other licensee employees contacted included construction craftsmen, engineers, and technicians.
NRC Resident Inspector
"S.
P. Burris
"Attended exit interview Exit Interview The inspection scope and findings were summarized on December 13, 1985, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
Unresolved Items Unresolved i tems were not identified during the inspection.
L Independent Inspection Effort Construction Progress The inspector conducted a general inspection of coating activities in the containment building and repair of water leakage problems in the reactor auxiliary building, waste process building and fuel handling building.
Examination of coating activities were conducted on the 286 ft. and 261 f elevation of the containment building.
Observations indicated that ongoing coating activities consisted mainly of repairs to existing coatings which resulted from damage incurred during installation of equipment and pipe supports.
Observations showed that coating activities were being accomplished in accordance with specification CAR-SH-COR-02, Protective Coatings Application for Nuclear Power Plant Concrete and Steel.
Examination of ongoing repairs to water leakage problems at the 190 ft.
level in the reactor auxiliary building, the 211 ft. level in the waste process building, and the 216 ft. level in the fuel handling building showed that these areas are being dried up.
The leakage in these areas, which was identified to the NRC as a concern, was investigated during an inspection conducted on September
27, 1985.
Results of this investigation are discussed in NRC inspection report number 50-400/85-34.
Drying up of the leakage in these areas will allow the walls to be coated with a material which will facilitate decontamination should any radioactive spills occur in these areas.
Within the areas examined, no violations or deviations were identified.
6.
Structural Concrete II (47054) Unit
The inspector examined results of concrete repairs and ongoing concrete repairs to structural concrete.
Acceptance criteria examined by the inspector appear in the following documents:
Specification CAR-SH-CH-6, Concrete Technical Procedure TP-48, Inspection of Concrete and Grout Repair Technical Procedure, TP-37, Grouting Inspection Work Procedure WP-27, Repairing of Concrete and Grout Surfaces Technical Procedure TP-15, Concrete Placement Inspection The inspector observed ongoing repairs to beams on pour number FHB0261011 in the fuel handling building and did a
walkdown inspection of completed repairs.
The walkdown included examination of completed repairs on the 190 ft.,
216 ft.
and 304 ft. elevations of the reactor auxiliary building, the 276 ft. elevation of the waste process building, the 286 ft. elevation of the fuel handling building, the 216 ft ~ elevation of the common building and all elevations of the diesel generator building.
Examination of ongoing work and completed work showed that concrete defects were being identified and repaired in accordance with applicable procedures and specifications.
Within the areas inspected, no violations or deviations were identifie.
Structural Concrete II (47056) Unit
The inspector examined structural concrete quality records for concrete repairs and grouting.
Acceptance criteria examined by the inspector appear in paragraph 6.
Records examined included, concrete repair and grout placement checklists, post placement checklists, batch tickets and test data and strength test results for the following placements:
CBM238001, Beams 1, 2, 3 and
CBGP239007A, 008A, Steam Generator Pedestal CBSL21001, Repair s to Slab CBSL216007, Grouting Under Shear Key Pit Plate CBXW36001Pl, Concrete Repairs to Exterior Mall CBIW237001P2, Structural Repair of Anchor Hole 1CBSL216010 S-1, Grouting Under Pit Plates 1CBSL26002 S-l, Floor Topping on Refueling Canal 1CBGP221036 S.2, Grout Placement For Anchor Plate 1CBGP25003 S.2, Dry Pack Grout for Reactor Lateral Support Plates 1CBGP265001 S.2, Grout Behind Flange of Penetration 1CBGP278002 S.2, Grout Placement Under Plates FHB0236-006 P1, Repair of Concrete Defects FH1W273-004 Pl, Repair of Concrete Defects FHSL261-017 P1, Repair of Concrete Defects RASL216-007 P14, Repair of Concrete Defects RASL216-007 P13, Repair of Concrete Defects RAIW25-001 PS, Repair of Concrete Defects Examination of records for grouting and repair of concrete defects on the above concrete placements showed that grouting and concrete repairs were being done in accordance with acceptance criteria.
Within the areas examined, no violations or deviations were identifie.
Lakes, Dams and Canals Review of Quality Records (45065)
Unit 1 The inspector examined inservice inspection records for the main dam, west auxiliary dam and west auxiliary separating dike.
Acceptance criteria appear in the following documents:
FSAR Section 2.5 Regulatory Guide 1. 127, Inspection of Water Control Structures Associated with Nuclear Power Plants EBASCO Specification CAR-SH-CH-24, Reservoir Dams and Dike Instrumenta-tion Program Corps of Engineers Recommended Guidelines for Safety Inspection of Dams
The inspector examined licensee inspection reports on inspections of the main dam, west auxiliary dam, and west auxiliary separating dike that were performed in June 1981, December 1982, December 1983, and November 1984.
Examination of records associated with these reports showed that the dams were in good condition and that the instrumentation monitoring equipment for the dams were performing in an acceptable manner.
Within the areas examined, no violations or deviations were identified.
9.
Inspector Fol lowup Items (IFI)
(Closed)
IFI 400/84-39-01, Licensee's Final Walkdown Inspection Program to Identify and Repair Concrete Defects.
The inspector examined the licensees program for the final walkdown inspection and repair of concrete defects.
This examination included review of
.procedures for identifying and correcting defects, records documenting repairs of defects and a walkdown of completed repairs in the reactor auxiliary building, fuel handling building, common building, fuel handling building and diesel gener ator building.
Examination of records showed that as of December 5,
1985, the walkdown inspection was 52 percent complete.
Completion of the program is scheduled for March 1, 1985.
Examination showed that the licensee has a good program for identifying and repairing concrete defects and that the program is being properly implemented.