IR 05000259/1981025
| ML20031E734 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/18/1981 |
| From: | Brooks E, Burnett P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20031E725 | List: |
| References | |
| 50-259-81-25, 50-260-81-25, 50-296-81-25, NUDOCS 8110160364 | |
| Download: ML20031E734 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
a REGION il
101 MARIETTA ST., N.W., SUITE 3100 o%g
ATLANTA, GEORGIA 30303
.....,o Report Nos. 50-259/81-25, 50-260/81-25 and 50-296/81-25 Licensee:
Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, TN 37401 Facility Name: Browns Ferry Docket Nos. 50-259, 50-260 and 50-296 License Nos. DPR-33, DPR-52 and DPR-68
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Inspection at Browns Ferry site near Athens, Alabama Inspector:
Y-/ 7-f'/
E. H. Brooks
'Date Signed Approved by: 'd,l d //)b YZu, / //w
$~ /f-h P'. T. BurnMt, Acting Sect' ion Chief Date Signed Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY
Inspection on September 2-8, 1981 Areas Insr i.ed
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This routine, announced inspection involved 39 in.per tor-hours onsite in the areas of containment integrated leakage rate testing.
Results Of the areas inspected, no violations or deviations were identified.
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0110160364 810921 PDR ADOCK 05000259
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. Bynum, Assistant Plant Manager K. Clark, CILRT Director C. Miller, CILRT Test Section J. Denny, CILRT Test Section NRC Resident Inspectors R. Sullivan, Senior Resident Inspector
- G. Paulk, Resident Ins actor
- Attended exit intervit 2.
Exit Interview The inspection scope and findings were summarized on September 8, 1981 with those persons indicated in paragraph I above. The inspector stated that the
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integrated leakage rate test results appeared to be acceptable.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Containment Integrated Leakage Rate Test This CILRT was perfccmed by the licensee as required by Appendix J to 10CFR50 due to modifications to the containment suppression pool.
Coincident with modification of the suppression pool a new access hatch was installed in the torus. The containment was subjected to a full pressure test at peak accident pressure of 64 psia. The previous CILRT was performed in February 1980 at a reduced pressure of h peak accident pressure.
Surveillance Instruction 4.7. A.2, Primary Containment Integrated Leak Rate Test Units 1, 2, or 3 including the latest revisions dated 8/11/81 was j
provided by the licensee and was reviewed by the 'nspector.
The inspector noted and discussed'with the lir,
a the fact that some e
systems identified as necessary to maintain safe atdown of the reactor but which could be exposed to containment atmosphere af ter a design basis
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accident are not vented and drained.
The NRC position in this matter is that if 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 ILRT before determining the acceptability of the test.
This matter was previously identified for review by licensee management and future inspection (259/80-08-01)
The licensee stated that the isolation valves in the above systems are locally leakage rate tested but the leakage rates are not included in the ILRT test results.
This matter is identified as ar, open item (259/81-25-01).
During the period of September 2-8, the inspector conducted the following reviews and inspectior s:
a.
Inspected compressor to containment lineup and preparations for initiatin- -nntainment pressurization.
b.
Confirmed removal of ali pressure sources from the containment.
c.
Reviewed containment integrated leakage rate te (type A) instrument calibration records and verified that all in:.cusents have been calibrated within the last 6 months to standards traceable to the National Bureau of Standards (PN.
d.
Reviewed valve lineup / sign-off ch:klists in preparation for the CILRT to assure that isolation valves are positioned to demonstrate design basis accident cc. tions.
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Inspected installation and NDE of new torus access hatch.
f.
Reviewed log book of activities prior to and during ILRT.
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Reviewed local leakage rate test results of the following primary containment penetations:
Penetrations Leakage Rate, SCFH Equipment Hatch-1 0.0031 Equipment Hatch-2 0.0037 Personnel airlock 20.6378 CRD flange 0.0002 Torus Hatch (X200A)
'0.0002 Torus Hatch (X200B)
0.0002 Torus Hatch (newly insta' led)
0.0 Drywell Head 0.0115
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The above test results are notable since most of the above penetrations are locally leak tested at full pressure with pressure applied only between flange double seals, and are only fully e < posed to i peak s
accident pressure during regular CILRT as permitted by Appendix J.
However the penetrations were subjected to peak accident pressure
/.oring this test.
Containment pressurization was initiated September 5 at 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />, and a pressure of 64.7 psia, was achieved at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on September 6 at which time the compress:rs were stopped and isolated from the-cuatainment. During tt e stabilization period the containment and penetrations were surv, eyed for local leakages. The drywell head was bubble tested (" snooped") and no leaks were found.
The start of a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test was initiated at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on September 6 and continued with no major perturbations occuring in the leakage throughout the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test.
Based on the absolute test method, nass-point analysis, the leakage rates and acceptance criteria are as follows:
Calculated leakage rate 0.16530%/ day Upper 95% Confidence liait 0.17065%/ day Maximum Allowable lea' ige rate 2.0%/ day 75% of Maximum Allowable Leakage rate 1.5%/ day Leakage SCFH 88.01 A verificatir,n leak rate test was performed to confim the accuracy of the Type A test. As required by Appendix J the difference between the Type A test and the verification test was within 25 percent of maximum allowable leakage rate at the calculated peak containment nressure.