IR 05000327/1979017
| ML19263E042 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/02/1979 |
| From: | Bryant J, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263E039 | List: |
| References | |
| 50-327-79-17, 50-328-79-10, NUDOCS 7906010034 | |
| Download: ML19263E042 (3) | |
Text
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UNITED STATES
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APR 0 ' 1973
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i Report Nos.
50R27/79-17 and 50-328/79-10 Licensee Tennessee Valley Authority 500A Che: not Street Tower Il Chattanooga, Tennessee 37401 Facility Name Sequoyah Nuclear Plant, Unit I and 2 Docket Nos.
50-327 and 50-328 License Nos.
CPPR-72 and CPPR-7)
Inspection at Sequoyah Construction Site near Daisy, Tennessee J Js /
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Inspector:
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E. J. Vallish Date Signed Approved by:
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J. C. Bryant, pectiongaiet,RChESBranch ate Signed SU.TIARY Inspec t ion on Ma rch 9-1.',
1979 Areas Inspected This routine, unannounted inspection involved 24 i n s;: e c t o r-ho u r s onsite in the areas of test surveillance and the progress of installation of the safety related maj or mechani ca ' ( omponent s in the reat tor buildings of Lnits 1 and 2.
Results Of the areas inspected, no apparent items of nornompliance or deviations were identified.
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2288 355 790601003f :
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APR u G/3
DETAILS t
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Persons Contacted i
Licensee Employees J. M. Ballentine, Power Plant Superintendent
- C. E. Cantrell, Assistent Power Plant Superintendent K. Clark, ILRT Engineer T. J. White, II.RT Test Director R. 11. Bryan, III, Engineer Other licensee employee contacted included 3 technicians, and 2 operators.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 12, 1979, with those persons indicated in Paragraph I above 3.
Licensee Action on Previous Insyection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort - Units I and 2 This effort included the progress of installation of the steam generator lateral supports, the reactor coolant pumps, the pressurizers, containment air coolers and the crossover leg supports of the primary coolant loops.
No items of noncompliance were identified.
6.
Containment St ructural Integrity Test-SIT-Unit 1 Prior to this inspection, Chapter 6.2 of the FSAR was reviewed to deter-mine the licensee's commitments f or this test. Also reviewed wa.s Appendix Q of the TVA Preoperational Test Instruction, TVA-2A, Revision 0, titled,
" Containment Vessel Pressure and Leak Test St ructural Integrity Test" NRC requirements were reviewed in Appendix J of 10CFR50. The cover page on Test Instruction TVA-2A contained approvals by authorized licensee personnel.
The Licensee's representative stated that this SIT was to 2288 356
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APRv4 1319
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-2-proof test only the penetrations in the vessel as the vessel was proof tested before the penetrations were installed by CBI, as, required by the
procurement contract.
j Appendix Q was found technically adequate and complied with the NRC requirements and the licensee's commitments.
During calibration of the test system instrumentation the four Mensor Precision Pressure Guages, the Leeds & Northrup Resistance Temperature Detectors (RTD) and the Texas Instruments Precision Pressure Gauge were verified for the type, range and accuracy as specified.
Calibration data for Mensor Gauges Serial Nos. 914 and 921, the Texas Instruments Gauge Serial No. 2771 and RTD's 24 and 25 were examined and found to be tra.eable to the National Bureau of Standards' standards as required by Part III, Section 3.2 of the Sequoyah Nuclear Plant Operational Quality Assurance Manual.
The licensee's calibration operation for an RTD located to measure con-tainment plate temperature was observed and the installation inspected.
Interviews were tanducted with most members of the SIT crew. The test performance was adequately coordinated and the crew was knowledgeable program and procedures and the care and operation of the with the test test instrumentation. All tranducer outputs were collected by a computer which processed the data and printed the results in aum. rical or graphical form.
Pressurization of the containment shell started at 9:14 p.m.
on March 10, 1979. In accordance with the procedure requirements the pressure was raised to 6.207 psig in the first step; then to the SIT pressure in 2 psig steps with 10 minute intervals between each step. Random data points were exam-ined by the inspector along the way. No unusual occurrences were recorded or experienced during the test. The maximum test pressure of 13.588 psig was reached at 5:48 a.m.
on March 11, 1979. The contained air was held until venting was started at 8:10 a.m., on March 11, 1979. Depressurization was done at about one psig per hour until three psig was reached.
Outgassing was allowed at that pressure f or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During the outgassing period inspection for physical deformat ion or damage to the st ructure was conducted; none was found. Two radiation monitoring system local readout meters on the operating floor walls were found to have their glasses crushed-in. No other lamage was observed.
No adverse environmenta: conditions were encountered during the test period.
No items of noncompliance were ident i fied.
2288 357
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