IR 05000327/1981029
| ML20010H326 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/26/1981 |
| From: | Burnett P, Fiedler R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20010H322 | List: |
| References | |
| 50-327-81-29, 50-328-81-37, NUDOCS 8109240345 | |
| Download: ML20010H326 (4) | |
Text
{{#Wiki_filter:P r . p*fug UN' TED STATES j
,;i; NUCLEAR REGULATORY COMMISSION y g REGION 11 O.
- E 101 MARIFTTA ST.. N.W., SUITE 3100 Q
g ATLANTA, G2ORGIA 30303 %.
+...+ Report No 50-327/81-29, 50-328/81-37 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Sequoyah Docket Nos. 50-327/81-29 and 50-328/81-37 License Nos. DPR-77 a d DPR-79 Inspector _ / //) g f-g-97 ". Fiedfer '~ Date Signbd Approved by- __ g kc78-[[ P. T. Burnett, Acting Section Chief Date Signed Engineering Inspection Branch Engineering and fechnical Inspection Division SUMMARY Inspection on July 28-July 31,1981 Areas Inspected This routine announced inspection involved 28 inspector-hours onsite in the areas of licensee action on previous inspection findings, preoperational test results, review of license DPR-79 conditions, licensee identified items, power ascension test procedure review, and a tour of the control room and auxiliary building.
Results Of the six areas inspected, no violations or deviations were identified.
8109240345 810827 PDR ADOCK 05000327-G PDR
f~ <, . REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. M. McGriff, Assistant Plant Superir,tendent M. Halley, Pre-Op Supervisor R. Fortenberry, Nuclear Engineer
- D. Kulisek, Nuclear Engineer NRC Resident Inspector
- E. Ford, Senior Resident Inspector S. D. Butler, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on July 31, 1981 with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved item (UNR) 328/81-20-01: Failure to meet FSAR commit-ment for an integrated system test. Following the inspection conducted in May 1981, Preoperational Test W-6.1F, " Integrated Engineering Safeguards Activation, Unit 2", was develnped and conducted during June 1981.
This test adequately fulfilled the commitment for an integrated system test therefore this item is considered closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Preoperational Test Results Review Preoperational test W-6.1F " Integrated Engineering Safeguards Activation" results were reviewed to verify the following: a.
That individual test steps and data sheets were properly initiated and dated, b.
That data sheets were completed.
c.
That test deficiencies were identified.
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d.
That test changes wera approved in accordance with pertinent admin-istrative procedures, e.
That the procedure was annotated to identify test changes.
f.
That test changes did not constitute a change in the basic object;ves of the test.
Within the above area inspected there were no violations or deviations identified.
Review of the completed test results by ENDES had not been completed at the time of this inspect.on. The test summary report by the test engineer stated that none of the acceptance criteria were met.
There were eighty-seven (87) test exceptions and fifty-eight (58) test deficien-cies written during the Londuct of the test, many of these test exceptions and deficiencies remained open pending review of the test results by ENDES.
Additional review by the inspector will be accomplished during a subsequent inspection.
6.
License 0PR-79 conditions a.
(Closed) Item 19 of attachment 1, Prior to Initial Criticality, of license DPR-79: the concerns addressed in IE8 80-06 were test' d during e the performance of preoperational test W-6.1F " Integrated Engineering Safeguards Activation."
b.
(Clo; a) Item 15 of Attachment 1, Prior to Initial Criticality, license DPR-79: NEB 8115 possible error in safety injection system preopera-tional test. TVA submitted a final report on April 10, 1981.
Change 29 for item 4 of preoperational test W6.1E was written and performed in July, 19 1 in order to verify that there was no backflow leakage through the opposite train check valves. The inspector held discussion with responsible licensee representatives and reviewed the results of the retesting to verify that the corrective action identified in the report have been completed. This item has been corrected.
7.
Licensee Identified Items (Closed) LII 32P'81-20-12 (NEB 8115): This item and the action taken is summarized in paragraph 6.a of this report.
8.
Power ascension test procedure review.
The following power ascension test procedures were reviewed: a.
SU-7.1 Revision 8 NSSS Startup Sequence, and b.
SU-9.1 10% Load Swing Test.
t-
/ e.
...
The inspector reviewed the above procedures to verify the following.
a.
FSAR commitments were included.
b.
Management review and approval indicated.
c.
That test objectives vfere clearly stated.
d.
Acceptance criteria were specified, e.
Step-by-step instructions for the performance of the procedure were complete to the extent necessary to assure that the test objet nes are met.
The procedures appeared adequate.
9.
Tour of the Control Room, Auxiliary Building and the Unit 2 Reactor Building A tour of the accessible areas was conducted to determine by observation that plant conditions and activities were in acoordance with applicable requirements.
Within the areas inspected there were no violations or deviations identi-fled.
. _ }}