IR 05000269/1982037
| ML20027E553 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/05/1982 |
| From: | Brooks E, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20027E544 | List: |
| References | |
| 50-269-82-37, 50-270-82-37, 50-287-82-37, NUDOCS 8211150487 | |
| Download: ML20027E553 (4) | |
Text
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Report Nos. 50-269/82-37, 50-270/82-37, and 50-287/82-37 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: Oconee Docket Nos. 50-269, 50-270, and 50-287 License Nos. DPR-38, DPR-47, and DPR-55 Inspection at Oconee site near Seneca, South Carolina
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Date Signed Inspector:
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Approved by:
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/d/f8 J F. Jape,'Section Chief
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Date Signed
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Engineering Inspection Branch Division of Engineering and Technical Programs O
SUMMARY Inspection on September 13-17, 1982 Areas Inspected This routine, unannounced inspection involved 37 inspector-hours on site in the areas of pipe supports and restraints and types B and C containment leakage rate testing.
Results Of the areas inspected, no violations or deviations were identified.
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REPORT DETAILS
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Persons Contacted i
j Licensee Employees
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- J. Smith, Manager
- J. Davis, Superintendent, Maintenance
- T. Owens, Superintendent, Technical Services
- T. Barr, Performance Engineer
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NRC Resident Inspector
- W. Orders
- D. Falconer
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- Attended exit interview i
2.
Exit Interview The inspection scope and findings were summarized on September 17, 1982, with those persons indicated in paragraph 1 above.
The licensee was informed of the inspection findings listed below. The licensee acknowledged the inspection findings with no dissenting comments.
Inspector Followup Item. 269, 270, 287/82-37-01 Summary analysis report,
paragraph 6.
3.
Licensee Action on Previous Enforcement Matters
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(Closed) Infraction (269/79-15-01): Inadequate inspection to verify snubber operability.
The inspector found that procedures have been revised. to provide for adequate snubber inspection and a training program for snubber
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inspection has been instituted.
(Closed) Unresolved Item (270/78-31-01): Inoperable snubbers identified on Unit 2 by the NRC inspector and unreported by the licensee. The licensee has subsequently conducted 100% inspection on all snubbers in Units 1, 2,
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and 3.
4.
Unresolved Items Unresolved items were not identified during this inspection.
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I 5.
Surveillance - Routine Pipe Supports and Restraints (61729) - Units 1, 2, i
and 3.
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The inspector visually inspected approximately 75 accessible hydraulic and
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mechanical suppressors (snubbers) listed in the Oconee technical specifi-l cations for operability. All snubbers appeared to be undamaged, properly i
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installed, and free from lockup.
Following are the results of snubber inspections and next scheduled inspections as documented in the licensee's data sheets:
Snubber Inspection Failure Inspection Next Inspec-Location Date Number Frequency tion Date i
Unit 1 Accessible 12-14-81
12 12-14-82 Inaccessible 12-03-81
18 06-24-83 Unit 2 Accessible 08-26-81
18 04-26-83 Inaccessible 01-11-82
18 07-12-83
Unit 3 Accessible 11-13-81
18 02-16-83 Inaccessible 05-20-82
18 11-18-83
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Functional testing of snubbers to verify correct piston movement, lock-up and bleed has been conducted in accordance with Oconee technical specifica-tions and meets the acceptance criteria as specified in Oconee functional testing procedures.
A previous unresolved item (270/80-11-02) concerning operability of three empty snubbers with uncovered fluid ports was reviewed with the licensee.
The licensee has revised technical specifications to permit functional
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testing of empty snubbers to determine operability and corresponding changes to snubber inspectfon schedule.
The licensee was advised at the exit interview that it is the position of NRC that empty snubbers with fluid ports uncovered are considered inoperable and increased inspection frequency
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as indicated by technical specifications apply.
The licensee stated that this item would be taken under consideration for discussion between Duke Power Company reactor licensing and NRC/NRR.
This item (270/80-11-02) remains unresolved pending the licensee's discussion with NRR.
6.
Surveillance - Containment Leak Rate Testing - Types B and C Tests (61720) -
Units 1, 2, and 3 The inspector reviewed the licensee's documentation for Units 1, 2, and 3.
Following are the dates for the most recent containment integrated leakage rate tests (ILRT) and subsequent types B and C (penetrations and isolation valves) leak tests.
ILRT B and C Unit 1 2-11-80 7/81 - 12/81 Unit 2 5-30-80 1/82 - 4/82 Unit 3 2-14-81 5/82 - 9/82 i
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Data sheets that recorded leak testing failures of various isolation valves on all units were reviewed by the inspector.
In several cases the isolation valves could not be pressurized due to excessive leakage. These valves were repaired and the "as left" leakage rate was recorded. No record of "as found" leakage was recorded.
As a result, it could not be determined whether containment maximum allowable leakage rate (La) as specified in the technical specifications would have been exceeded in the event of a loss of coolant accident.
Appendix J to 10 CFR 50 requires that a summary analysis of types B and C tests that were performed since the last ILRT be included in a report submitted to the NRC. Although the licensee did include a summary report of type B and C test results as required, the absence of "as found" leakage precludes assessment of containment integrity and/or potential containment degradation. The licensee was requested, at the exit interview, to include sufficient detail in future summary analysis reports to permit a determina-tion of containment integrity.
Followup on future summary analysis reports to ensure sufficient details for containment integrity determination is identified as an inspector followup item (269, 270, 287/82-37-01).
The licensee acknowledged the inspector's findings with no dissenting comments.
7.
Inspector Followup Items (IFI) and Open Items (OPE)
(Closed) IFI (270/80-11-01): Kinked supply tube on snubber 2-01A-0-1401A-R14. The snubber was inspected by the inspector and the defective tube had been replaced or repaired.
(Closed) OPE (269/79-15-03): Submit report to Region II concerning main steamline suppressor anchor plates pulling away from concrete.
Report submitted by licensee and suppressors found to be suitably anchored by the inspector during this inspection.