IR 05000338/1980039
| ML19341D279 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/18/1981 |
| From: | Andrea Johnson, Kellogg P, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19341D275 | List: |
| References | |
| 50-338-80-39, 50-339-80-37, NUDOCS 8103050272 | |
| Download: ML19341D279 (5) | |
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UNITED 8TATES 8'
NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST., N.W., SUIT E 3100
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ATLANTA, GEORGIA 30303
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Report Nos. 50-338/80-39 and 50-339/80-37 Licensee:
Virginia Electric & Power Company Richmond, VA 23261 Facility Name: North Anna
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Docket Nos. 50-338 and 50-339 License Nas. NPF-4 and NPF-7 Inspection at North Anna Power Station b
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A. H. Joh A
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P.J Anes Saet4 n Chief, RONS Branch Date Signed
SUMMARY Inspection on October 23-24, 1980 Areas Inspected This routine, unannounced inspection involved 12 inspector-hours on site in the areas of containment integrated leak rate testing and surveillance activity on pipe supports and restrakt systems.
Results Of the two areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- W. Cartwright, Station Manager
- J. Harper, Superintendent Maintenance
- W. Woodsmall, Staff Assistant J. Eastwood, Mechanical Maintenance J. Smith, Engineering Other licensee employees contacted included technician:;, mechanics, security force members, and office personnel.
NRC Resident Inspector
- E. Webster
- Attended exit interview 2.
Exit Interview The inspection scope and ~ findings were sumarized on October 24, 1980 with those persons indicated in Paragraph 1 above.
The licensee was also contacted by telephone on November 21, 1980 to clarify NRC con-tainment integrated leak rate test requirements and NRC Staff positions.
3.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance Item 338-79-04-03:
No response required as documented in inspection report 79-04.
(Closed) Open Item 338/79-16-04:
Verified documentation by vendor on lockup and bleed rates of all but one remaining hydraulic snubber, this remaining snubber was corrected by work order NI-79-09270211.
4.
Unresolved Items Unresolved items were not identified during this inspection'.
5.
Containment Integrated Leak Rate Test (CILRT) and Local Leak Rate Testing (LLRT)
a.
The following items were discussed:
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(1)
For those systems that have valves tested in the reverse direction of containment pressure, the licensee must provide a documented evaluation to demonstrate that the results will provide equivalent or more conservative test results.
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(2) The licensee is to ascertain that all commitments made to the NRC in the Question and Response Section of the FSAR are met by the Leak Rate Test Procedures. Responses to NRC questions address both local and integrated leakage rate testing.
The inspector stated that requests for exemptions that were rot addressed by NRC is not an approval for those exemptions.
(3) The licensee was made aware that the NRC requires Type A Test (CILRT)
instrument calibrations and certification to be traceable to National Bureau of Standards (NBS) or other recognized standards.
This documentation will be made available to the inspector prior to performance of the test.
(4) The licensee was made aware that the isolation and venting of the pressurization (air compressors) source is required upon reaching test pressure and start of official CILRT test data collection.
(5) The licensee was made aware that some form of tagging should be used for valve line up of systems for the CILRT test.
(6) The licensee was made aware that they would use an event log during the CILRT test.
(7) The licensee was made aware that local leak rate testing would be perfonned after completion of the CILRT, on pene-trations used to perform the CILRT test (i.e., penetration used to pressurize the containment), if appropriate.
(8) The licensee was made aware that the reactor coolant systems would be vented during the CILRT test.
(9) The licensee was made aware that applicable station procedures would be used to make changes to the approved leak rate test procedures.
b.
The inspector informed the licensee that the following NRC Staff positions would be used while performing the inspection of the licensee's leak rate test program:
(1)
Venting and Draining Position The reactor vessel, those systems that are part of the reactor coolant pressure boundary and could provide direct comunication with the containment atmosphere under post-accident conditions, and those systems which are postulated to rupture (i.e., not designed for post-accident function)
shall be vented and drained to the extent necessary to assure exposure of the contianment isolation valves to the containment I
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air test pressure, such that they will be subjected to the simulated accident differential pressure.
If the venting and draining of any system potentailly jeopardizes the maintenance of a safe shutdown condition, then those systems shall not be vented and drained; however, in this event, the local leakage rates (Type C) for the isolation valves in these systems shall be added to the upper 95% confidence limit of the CILRT before determining the acceptability of the test.
(2) CILRT Correction for Local Leakage Position If, during the performance of a Type A test, identifiable local leakage occurs to the extent that it could cause failure of the Type A test, e.g., through penetrations or isolation valves, the leak may be isolated and the Type A test continued until completion.
A containment penetration which is isolated during a Type A test must have a design which will permit local leak testing of all potential leakage paths through the penetrations.
Local leakage rates measured before and after repair must be reported, and the sum of the post-repair leakage rate and the CILRT upper 95% confidence limit must meet the Appendix J allowable leakage rate (0.75 La).
However, the difference in Type B and C test results before and after the repair of local leaks may not be deducted from the Type A test results in order to achieve an acceptable cortainment integrated leak rate.
Type B anc C leak rate testing and repair prior to containment CILRT is also considered to be acceptable.
(3)
Inclusion of Instrument Errors Position The uncertainty in the measured leakage rate shall be established by calculating the 95% upper confidence limit (UCL) of the least squares fit of the leakage rate data. The test results will be considered acceptable, if the 95% UCL is less than or equal to 75% La (75% LT for reduced pressure tests).
The accuracy of the measurement of the Type A leakage rate will be verified by the supplemental verification test.
The measured difference between the supplemental verification test leakage rate and the Type A test leakage rate must be within 0.25 La (0.25 Lt for reduced pressure tests).
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9 6.
Hydraulic Snubbers and Restraints The inspector reviewed the licensee's surveillance program for safety-related hydraulic supports and restraints.
This included a visual examination of various (random sample) installed dynamic and fixed supports and restraints on both units.
The inspector had no further questions regarding hydraulic snubbers.
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