ML20101T191
| ML20101T191 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/22/1985 |
| From: | Blanchard B INTERIOR, DEPT. OF |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| ER-84-1449, NUDOCS 8502060030 | |
| Download: ML20101T191 (1) | |
Text
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DUKE POWER GOMPANY P.O. HOX 33189 q
CHARL&PTE, N.C. 28242 HALH. TUCKER nurnon gjgpdem0ek,"2h,l1984.
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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:WPA 50-413/84-100
Dear Mr. O'Reilly:
Please find attached a response to Violation No. 413/84-100-01 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, fM L
al B. Tucker LTP/ibh Attachment cc: NRC Resident Inspector Catawba Nuclear Station Robert Guild, Esq.
P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 2135 Devine Street Columbia, South Carolina 29412 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207
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[50-413/84-100 31
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~ VIOLATION' 110CFR50,.-Appendix 0 B,-
Criterion'_V, requires that activities affecting quality-: be 7 prescribed f by ~. documented : instructions,.proceduresE or drawings and.shalli be accomplished 'in accordance with these instructions,
- procedures and; drawings. ~ LDPC pipe support / restraint drawings R-ND-1052, RevisioniS;^1-R-ND-0265, Revision-3;.1-R-ND-0506, Revision 3; DPC Construc-
. tion Procedurei CP-385;z andf QAL Procedure M-51_ provide. installation, and inspectionc requirements for. pipe support / restraint numbers 1-R-ND-0152,_
- 1-R-ND-0265'and 1-R-ND-0506.
Contrary to~the.above,:12 noncompliances with procedure and drawing require-ments L were identified : on pipe' support / restraint 'l-R-ND-0506, two noncom-L pliances were : identified :on 'l-R-ND-0265 - and. one noncompliance, was noted
+
p fon' 1-R-ND-0152..
1-R-ND-0506 had been' inspected and accepted by both Con-struction' and NuclearJ Production QC.
~1-R-ND-0265 and - R-ND-0152 - had -
been inspected.and accepted by Construction QC.-
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RESPONSE
1..
Duke Power Company admits the violation.
2.
Cause of Violation This violation can be categ' rized as 1) anticipated ' minor human errors o
associated with : the number. _ and complexity of inspections and 2) the -
failure to remove travel stops from spring cans.
Eight of the noncom-i pliances can be attributed to the Construction phase and are. discussed -
in a letter to J P 0'Reilly dated November 20, 1984 referencing Catawba i
Nuclear Station, Docket _#50-413.
The remainder ;of. the noncompliance j
can be attributed to operation _ and/or maintenance ~or modification I
after construction.
I 3.
Action As a result of the inspector's audit,-Nonconforming. Item Reports (NCIR) i 3
j.
CN-181, CN-192, and CN-193 were generated. - All discrepancies identi-fied as 'a result of. the inspector's audit and Duke Power's; follow-up audits are documented by these : NCIR's.
With the exception of travel j'
stops not being removed from spring cans, all discrepancies were deter-mined : to be minor in nature and. require no corrective ~ action.. - As '
for the travel stop -problem, a sample -from all QA supports identified that only _ two Other: supports 1(both QA Condition 4).had travel stops in < place.
. Therefore, all accessible QA Condition.4J supports still
.where spring cans'were-employed were rechecked.
No other discrepancies.
t were' identified.
In none - of the three cases would the piping Esystem o
fail to perform its-intended function due to the remaining ; travel.
stops.-.
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- 4. ' Corrective Action 4
i:
As discussed above, all_ discrepancies, with the exception fof..the
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remaining. travel c stops, Lare ~ minor.in nature'..
It has also been shown.
thati the2 remaining travel. stopsiwere an isolated n incident in which j
no loss Loflintended-function ~ of the piping ' system would result.
There-
' fore, no : breakdown in the QA: program ~ is indicated by these findings.-
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,50-413/84-100-01.
To minimize recurrence of this problem Quality Assurance procedure F-13, Construction Procedure CP-424, Maintenance Procedure MP/0/A/7650/
59 and MP/0/A/7650/53 and Maintenance Management Procedure 1.0 will be. revised to ensure proper inspection.of piping supports and any supports affected by modifications to supports.
In addition, a new Construction Procedure CP-864 is being developed to minimize the. type
.of.nonconformances identified by the NCIR's.
5.
Status The new Construction Procedure and other procedure revisions referenced above will be implemented by February 15, 1985, Catawba Nuclear Station will be in full compliance at that time.
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