IR 05000328/1981041
| ML20032D174 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/16/1981 |
| From: | Fair J, Jape F, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20032D170 | List: |
| References | |
| 50-328-81-41, NUDOCS 8111130463 | |
| Download: ML20032D174 (3) | |
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UNITED STATES s
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?Q1 MARIETTA ST., N.W., SUITE 3100
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Report No. 50-328/81-41 Licensee: Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, TN 37401 Facility Name: Sequoyah Unit 2 Docket No. 50-328 License No. DPR-79 Inspection at TVA Offices in Knoxville, TN and Sequoyah site near Chattanooga, TN Inspecto s:
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H. L, Whitfp(, region II Dats Signed 4Qw
/V/b/ Pt J. R. Fair /Heufquarters Specialist Date Signed'
Approved by:
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F. Mpe, Section Chig /
Tlate' Signed Engineering Inspect'fon Branch Engineering and Technical Inspection Division
SUMMARY Inspection on September 2-4, 1981 Areas Inspected
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This special, announced inspection involved 46 inspector-hours on site in the l
areas of review and observation of primary and secondary piping thermal expan-L sion, and snubber test results review.
Results Of the two areas inspected, no violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees TVA-Engineering Design (EN DES)
- E. G. Beasley, Manager OEDC QA
- D. Wilson, Group Head, Nuclear Safety Analysis, NEB V. D. Lee, Supervisor Piping Analyses Section
- B. K. Williams, Engineering Design Preoperational Test Representative W. Smathers, Civil Engineer, EN DES T. Lee, Mechanical Engineer, EN DES TVA-Sequoyah Site
- J. M. McGriff, Assistant Plant Superintendent
- W. M. Halley, Preoperational Test Section Supervisor.
D. Hutsell, Thermal Expansion Test J. Barlok, Therma'. Expansion Test Director L. Alexander, Mechanical Engineer, Outage NRC Resident Inspector E. Ford, Senior Resident Inspector S. Butler, Resident Inspector
- Attended exit interview at EN DES, 9-2-81
- Attended exit interview at Sequoyah, 9-4-81 2.
Exit Interview The inspection scope and findings were summarized on September 2 and 4,1981, with those persons indicated in paragraph 1 above.
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Licensee Action on Previous Inspection Findings Not inspected.
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4.
Unresolved Items J
Unresolved items were not icentified during this inspection.
5.
Thermal Expansion Test Results Thermal expansion testing of the reacter coolant system and secondary system piping was performed during the plant initial heatup in the period March 3 -
May 10, 1981. The requirements for this test are specified in Table 14.1-1 of the FSAR and reflected in preoperational test procedures W-1.7 (reactor i
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coolant system) and TVA 23A (main steam system). Review of these procedures and. observation of test performance was performed during a previous inspec-tion and reported in IE Report No. 50-328/81-26.
For the reactor coolant system there were four procedure changes,15 test exceptions and 49 test deficiencies; for the secondary systems there were 7 procedure changes, 6 test exceptions and 38 test deficiencies. Some of the above items were resolved during the test while others were identified for corrective action
.4nd further testing during a subsequent heatup. All of the above were submitted for Engineering Design (EN DES) review and approval. As a result of the EN DES review, 5 test exceptions and 19 test deficiencies on the reactor coolant system and 2 test exceptions and 13 test deficiencies on the secondary system were identified for further corrective action and reinspec-tion during the next plant heatup. On a sampling basis, the inspectors reviewed the initial test data, data obtained on the retest during a subsequent plant heatup, and resolution of identified test exceptions and deficiencies.
The type of documentation reviewed for W-1.7 and TVA-23A included initial data sheets, retest data sheets; and disposition of deficiencies Preoperational Test Deficiency Report for identified deficien-cies; chronological test log and EN DES Interim Review and Approval of Preoperational Test Results memoranda. The inspectors concluded that the licensee had met the test requirements specified in Section 14 of the FSAR.
6.
Followup Inspection Items During a previous inspection (IE Report 50-328/81-26) two items were identi-fled for further review as follows:
a.
Licensee evaluation of movement of safety related systems attached to the reactor coolant system by evaluation of the reactor coolant system movement (328/81-26-01).
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Reinspection of hot shimmed areas on a subsequent heatup (328/81-26-02). The inspector reviewed an evaluation by EN DES dated May 13, 1981 which indicated that the reactor coolant system measured movement was acceptable.
The basis for this conclusion was (1) the piping moved in the correct direction and was consistent loop to loop and (2) the difference in measured and calculated values was probably attributable to the inherent measurement inaccuracy of scratch gauges and the difference in temperature used in the calculations (650 F)
versus the temperature at which measurements were taken (546 F). The inspectors did not find any gross differences between measured and calculated values in the review of piping movement data at selected points.
The inspectors also obtained thermal expansion calculated values and isometric piping drawings to conduct an independent inspection of several systems attached to the reactor coolant loops.
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Piping movement was inspected for systems as follows:
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RHR Hot Leg #4 fo Penetration X-107 Drawing No. 0600102-03-1, Rev. 11 EDS fc nputer output problem 03-1 dated 3/19/81 Points observed:
2 RHR-5, 6, 7 2-RHR-3 b.
Normal Charging Line Drawing No. 0600102-08-11, Rev. 9 EDS Computer output problem 08-11 dated 3/18/80 Points observed: 2-CUCH-360, 361 c.
RTD Line from Hot leg and Cold Leg #4 To Crossover Leg #4 Drawing No._0600102-13-07, Rev. 5 EDS computer output problem 13-07 dated 2/25/75
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Points observed:
2-RC-282 The piping movement was consistent with the calculated values. Item (328/
81-26/01) is considered closed.
Test personnel stated that shimmed areas were inspected at both hot and ambient conditions. Where a problem was suspected the shimmed area was inspected again on a subsequent heatup. Review of the retest data indicated that a number of shimmed areas were reinspected and in some cases adjusted.
Item (328/81-26-02) is considered closed.
7.
Snubber Tests A letter to H. G. Parris from R. L. Tedesco dated July 21, 1981 specified a preoperational snubber testing program to be performed at Sequoyah which required manual testing of a selected sample of snubbers. Since only one failed snubbler was identified, testing of an additical sample was.not required.
The inspector reviewed the test data and determined that the licensee has met the requirement of the test program. This item is closed.