IR 05000302/1979043
| ML19211A375 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/07/1979 |
| From: | Burnett P, Andrea Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19211A370 | List: |
| References | |
| 50-302-79-43, NUDOCS 7912180121 | |
| Download: ML19211A375 (5) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
E REGION 11
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o 101 MARIETTA ST., N.W., SUITE 3100 g*
ATLANTA, G EORGIA 30303
Report No. 50-302/79-43 Licensee: Florida Power Corporation 3201 34th Street, South St. Petersburg, Florida 33733 Facility Name:
Crystal River 3-Docket No.
50-302 License No.
DPR-72 Inspection at Crystal R,iver 3,near Crystal River, Florida Inspected by: _.'
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H.' Johnson
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Date Signed Approved by:
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P. Y BarKettT Actihg'Section Chief, RONS Branch Date Signed SUMMARY Inspection on October 9-12, 1979 Areas Inspected This routine, unannounced inspection involved 23 inspector-hours onsite in the areas of containment integrated leak rate testing (including Type "A", "B",
and
"C" leakage testing), and plant operations.
Results Of the 2 areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- G. P. Beatty, Jr., Plant Manager
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J. Cooper, Compliance Engineer
- G. Williams, Nuclear QA/QC Supervisor
- R. Kennedy, Nuclear Compliance Supervisor G. Boldt, Performance Engineering Supervisor F. Pleubel, Electrical Supervisor
- L. Tittle, Performance /Results Engineer
- W. Cross, Operations Engineer W. Kemper, Technical Specification Engineer K. Lancaster, Compliance Auditor
- L. Hill, Compliance Auditor Other licensee employees contacted included shift supervisors and operators.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 12, 1979 with those persons indicated in Paragraph 1 above. The items described in these details were discussed, and the licensee acknowledged the inspector's comments.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Containment Integrated Leak Rate Test (CILRT) and Local Leak Rate Testing (ILRT)
a.
The following items were discussed:
(1) For those systems that have valves tested in the reverse direction of containment pressure, the licensee must provide a documented evaluatation to demonstrate that the results will provide equivalent or more conservative test results.
(2) The Type A Test (CILRT) procedure should address the performance of air samples (release permits) prior to depressurizing the containment.
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-2-(3) The licensee was made aware that the NRC requires Type A Test (CILRT)instrumentcalibrationsandcertiQcationtobetraceable 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 inspector received an approved copy of the local leak rate test (ILRT) procedure while on site.
(5) 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.
(6) The licensee stated that some form of tagging would be used for valve line up of systems for the CILRT test.
(7) The licensee stated that they would use an event log during the CILRT test.
(8) The licensee stated that local leak rate testing would be per-formed after completion of the CILRT, on penetration used to perform the CILRT test (i.e., penetration used to pressurize the containment), if appropriate.
(9) The valve lineup checklist should include any valves located between the vent valve and isolation valve to ascertain proper venting of the required containment penetration.
(10) The instrument and station air systems need to be vented outside the containment to prevent possible air inleakage through the respective penetrations, while performing the Type A Test (CILRT).
(11) The licensee stated that, to maintain administrative controls during the CILRT, only one copy of the CILRT test procedure would be used and that this copy would be located at the CILRT Test Station.
(12) The licensee stated that the reactor coolant system would be vented during the CILRT test.
(13) The licensee stated 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 communication 1607 298
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t-3-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 ventsd and drained to the extent necessary to assure exposure of the containment isolation valves to the containment air test pressure, such that they will be subjected to the simulated accident differential pressure.
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If the venting and draining of any system potentially 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
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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 comple-tion.
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 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 containment integrated leak rate.
Type B and 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).
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-4-t 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).
The above items were inspected to ascertain whether requirements of 10 c.
CFR 50 Appendix "J"; Technical Specifications; FSAR; Regulatory Guide-1.68; ANSI 45.41; licensee commitments; and NRC positions relative to leak rate testing are being met.
6.
Hydraulic Snubbers The inspector reviewed revised procedure MP 130, Pipe Snubber Maintenance, dated 8/30/79 noting that correction factors to correct functional test data from test temperature to operating temperature was added to the pro-cedure. Also the shock load displacementwere removed from the failure acceptance criteria to the snubber installation acceptance criteria.
The inspector had no further questions concerning the above changes.
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