ML20101C857
| ML20101C857 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/07/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20101C860 | List: |
| References | |
| NUDOCS 8412210223 | |
| Download: ML20101C857 (3) | |
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DUKE POWER GOMPA.NY P.O. BOX 33180 C11ARLOTTE. N.C. 28242 HALB. TUCKER
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'lll.* gember 7,1984 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Re: RII:JJL 50-413/84-92
Dear Mr. O'Reilly:
Please find attached a response to violation No. 413/84-92-01, as identified in the above referenced inspection report. Duke Power Company.does not consider any information contained in this inspection report to be proprietary.
Very truly yours, d /3 Hal B. Tucker RWO: sib Attachment cc: NRC Resident Inspector bec:
K. S. Canady Catawba Nuclear Station N. A. Rutherford R. O. Sharpe Robert Guild, Esq.
R. W. Ouellette P. O. Box 12097 C. L. Hartzell Charleston, South Carolina 29412 M. S. Tully R. C. Futrell Palmetto Alliance J. W. Hampton 2135 Devine Street A. V. Carr Columbia, South Carolina 29205 J. M. McGarry SREC Mr. Jesse L. Riley NC MPA-1 Carolina Environmental Study Group NCEMC 854 Henley Place Group File: CN-801.01 Charlotte, North Carolina 28207 Group File: CN-801.02 Group File: CN-815.01 8412210223 841107 PDR ADOCK 05000413 G
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. Duke Power Company Catawba Nuclear Station
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VIOLATION 10 CFR 50, Appendix B, Crit'erion V, as implemented by Duke Power Company's Topical Quality Assurance Report, Duke 1-A, requires that activities affecting quality be prescribed.by documented instructions, procedures, or drawings, and be accomplished in accordance with these instructions, procedures, or drawings. Duke Power procedure number TP/1/A/1200/21 and TP/1/A/1200/26 require, as test prerequisites, that all final piping system
' hangers be installed and all temporary hangers be removed prior to conducting the vibration tests. The procedures'also require that exceptions to test prerequisites be noted on the test data sheets.
Contrary to the above, steady state and transient vibration tests were conducted in the reactor coolant, safety injection, residual heat removal, containment spray, fuel pool cooling, nuclear service water, main steam, auxiliary feedwater, and steam generator blowdown piping systems prior to
-installation of_all final system pipe hangers, and prior to removal of all temporary pipe hangers.
In addition, exceptions to the test prerequisites were not identified on the test data sheets. The data sheets indicated that all prerequisites had been met, where in fact they had not.
RESPONSE
1.
Duke admits the violation as stated.
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-2.
The violation occurred because temporary hangers, which were in the field at'the time of the tests, were not noted on'the test data sheets.
At the' discretion of the test coordinator, temporary hangers were not noted by the technicians performing the test. The test coordinator felt that the presence of temporary hangers at the time of the test would not i.
adversely affect the. test results. This decision was based upon infor-nation ~that the permanent hangers, replacing the temporary hangers, were l
to be of_the same configuration (i.e. rigid, spring can, etc.) and be placed in the same location as the temporary hangers.
- 3..After researching the condition of the plant at the time of the original 1
-tests, a complete retest of Test Procedures TP/1/A/1200/21 and TP/1/A/1200/26 l'
was determined to be the best course of action since during Hot Functional i
Testing there were permanent hangers in_the field which were not complete.
There were also temporary hangers, placed in the field at the discretion L
of construction supervisors, which had no record of location or type of
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hanger. These temporary hangers were removed during final walkdown inspections.
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Retesting of all systems.will be complete prior to criticality with the t
following exceptions:
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1-1.-~ Main Steam and Feedwater Systems will be tested during power escalation as originally scheduled.
2.
The Steam Dump _ Systems will be tested during power escalation.
3.
The Spent Fuel Pool Cooling'and Cleanup System will be tested
'after the Fuel Pool is filled and the system is operable.
- 4. - In order to prevent-future violations of this type, a change will be made to the FSAR. The change will involve dividing the test into two parts. The first part will be a preliminary, visual inspection of all code piping. This preliminary test will be performed during Hot Functional
- Testing of_the plant to check for any noticeable damage to piping and
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supports. The second portion of the test will be performed during pre-critical heat up when the plant is in the final as-built condition and
- will continue through power escalation. During this second part,
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actual vibration measurements will'be taken and recorded on the code ii P P ng.
5.
Full Compliance will be achieved after the plant undergoes the 100%
full power loss of electrical load test and after the Spent Fuel Pool System is operable. The change to the FSAR will be completed prior to testing of Unit 2.
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