IR 05000261/1986022
| ML14175B415 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/02/1986 |
| From: | Jape F, Lenahan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B414 | List: |
| References | |
| 50-261-86-22, NUDOCS 8609110197 | |
| Download: ML14175B415 (6) | |
Text
64 REG&L4.UNITED STATES o
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report No.: 50-261/86-22 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: August 5 8, 1986 Inspector:
. LF12-9le(
J. J. Lena
'Dat4 Signed Approved by:
9__
F. Jape, Section Chief Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope:
This special unannounced inspection was conducted in the areas of the snubber surveillance program, the containment building dome surface coat concrete repair program, followup on a previously identified inspector followup item and on licensee action on previous enforcement items, and Quality Assurance/Quality Control (QA/QC)
controls and work activities for placement of the independent spent fuel storage foundation basema Results:
No violations or deviations were identifie PDR ADOCK 05000261 a
REPORT DETAILS 1. Persons Contacted Licensee Employees
- G. Beatty, Manager, Robinson Nuclear Project Department
- J. Curley, Director, Regulatory Compliance J. D. Epperly, Civil Project Engineer
- S. Griggs, Aide, Regulatory Compliance
- D. Koss, Civil Engineer, Nuclear Engineering Department D. Prosser, Civil Project Engineer
- H. J. Young, Director, Quality Assurance/Quality Control Other licensee employees contacted included civil construction engineers and technician NRC Resident Inspectors
- H. E. P. Krug, Senior Resident Inspector
- R. M. Latta, Resident Inspector
- Attended exit interview 2. Exit Interview The inspection scope and findings were summarized on August 8, 1986, with those persons indicated in paragraph 1 abov The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license One new item was identified during the inspection:
Inspector Followup Item 261/86-22-01, Review Licensee's Actions to Repair Minor Concrete Defects in Containment Building Dome, paragraph Proprietary material was reviewed by the inspector during this inspection, but it is not included in this inspection repor. Licensee Action on Previous Enforcement Matters (Closed) Violation Item (261/84-46-01):
Failure to Securely Fasten Platform Grating to Supporting Structural Steel in Containment Buildin The licensee's actions to correct these violations are stated in the licensee's January 11, 1985, response to NRC Region II for Inspection Report 50-261/84-4 To correct this problem, licensee maintenance personnel reinstalled the grating chips which securely fasten the platform grating to
the supporting structural stee A licensee engineer inspected the containment building platforms and verified that the grating clips had been reinstalled. This inspection is documented in a CP&L memo dated January 2, 1985, Subject: Grating Clips in Containment. To prevent this problem from recurring in the future, training was conducted for maintenance foremen and technical support unit personnel for removal and reinstallation of grating clips. The inspector reviewed records documenting this training. Violation item 261/84-46-01 is close. Unresolved Items Unresolved items were not identified during the inspectio. Independent Inspector Effort (92706)
a. 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 was 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 purposes only. The dome was placed between December 1969 and March 1970. Since that time, shrinkage cracks have developed in the surface coat which resulted in moisture coming in contact with the mesh which caused corrosion of the mesh and spalling and deterioration of the surface coa In order to repair the cosmetic concrete surface coat, the licensee prepared work package W-020, Containment Dome Concrete Removal/Repair. Since deterioration of the surface coat did not affect the structural integrity of containment building, the repair work is considered to be non-safety-relate However, after removal of portions of the surface coat, the licensee discovered some small voids in the structural concrete under the expanded metal mesh. In order to repair the concrete in these small areas, the licensee plans to prepare a procedure for repair (grouting) of minor defects in the structural concrete. This repair work will be safety-related since it affect a Category I structure and this will be inspected by licensee QA/QC personne The inspector will examine the repair procedures and the results of the repairs in a future inspection. This was identified to the licensee as Inspector Followup Item 26/86-22-01, Review Licensee's Actions to Repair Minor Concrete Defects in Containment Building Dom b. The inspector examined procedure number EST-028, Main Steam Safety Valve Test. The inspector also examined result of tests performed on the 12 safety relief valves in March 1986 to check valve set point During these tests, two valves, SV-1B and SV-2B, lifted at pressures slightly below those specified in the test procedure acceptance criteri The two valves were adjusted and reteste The results of the retests demonstrated that valves lifted at their proper design pressure Within the area inspected, no violations or deviation were identifie. Snubber Surveillance Program (61729)
The inspector examined procedures and quality records related to the snubber surveillance program. Acceptance criteria utilized by the inspector appear in Technical Specification 3/4.1 a. Review of Snubber Surveillance Program The inspector examined the following procedures which control surveillance and inspection of snubber (1) Procedure number EST-032, Visual Inspection of Hydraulic and Mechanical Shock Suppressor (2) Procedure number EST-033, Functional Testing of Hydraulic and Mechanical Shock Suppressor b. Review of Quality Records The inspector reviewed quality records which document the results of visual inspection and functional testing of snubbers. Records examined were as follows:
(1) Results of visual inspection of snubbers completed in February
198 (2) Results of functional testing of snubbers which was performed in February 198 (3) Results of testing performed on steam generator snubber valve blocks in February 198 Review of the visual inspection records disclosed that all snubbers were visually inspected and found to be operable during the visual inspection. Therefore, in accordance with the Technical Specification requirements, the next visual inspection interval is 18 month The functional test results complied with acceptance criteri Within the areas inspected, no violation or deviations were identifie. Independent Spent Fuel Storage Installation The inspector examined QA/QC controls and work activities for placement of the foundation basemat for the horizontal storage module (HSM).
The HSM is a reinforced concrete structure for dry storage of spent nuclear fue The nuclear fuel assembles will be placed in stainless steel dry shielded
canisters (DSC) which will be stored in the HSM. These facilities are being constructed to provide additional interim storage capacity for the spent
nuclear fue The HSM is classified as a non-safety-related structur However, the licensee committed to apply their Radwaste Related QA program as defined is Section 19 of the CP&L Topical QA program for procurement of materials and construction of the HSM. Areas examined during this inspection were as follows:
a. Review of Quality Assurance Implementing Controls Quality Assurance implementing controls examined by the inspector included the following specifications, procedures and drawings:
(1) Specification L2-C-021, Fabrication Specification for the Horizontal Storage Module (2) Plant Modification M-885, Independent Spent Fuel Storage Installation (3) Drawing Number RNT 162-C-1101, Horizontal Storage Modules, General Layout and Details (4) Drawing Number RNT 162-C-1102, HSM Foundation, Plan, Section, and Details b. Observation of Concrete Placement Operations The foundation basemat for the HSM is 25' 0" long by 28' 9" wide reinforced concrete sla The inspector observed preplacement preparation and placement operation Preplacement observations included verifying that the forms were tight, level, and had the proper dimensions, that the size, number, and spacing of reinforc ing steel complied with drawing requirements, and that the placement had been properly cleane Observation of placement activities showed that the placement was continuously monitored by construction QC and QA inspectors and that activities pertaining to delivery time, free fall, flow distance, layer thickness, and consolidation conformed to specifi cation requirement Samples of plastic concrete were obtained from designated sampling points and were tested in accordance with procedure requirements. Test results indicated that plastic concrete being placed met the procedure requirement for slump, air content, unit weight, and temperatur Within the areas inspected, no violation or deviations were identifie. Previously Identified Inspector Followup Item (92701)
(Closed) Inspector Followup Item (IFI) 261/84-47-01, Complete Data Review for EST 028, Main Steam Safety Valve Tes This IFI concerned main steam safety valve SV-1A on the A main steam line which lifted at a low pressure
when tested in November 198 As a result of this problem, the licensee adjusted the valves and retested it on January 3, 198 The inspector reviewed the results of the retest and verified that they met the test acceptance criteria specified in procedure EST 028. Inspector followup Item 261/84-47-01 is closed.