ML20066A892
| ML20066A892 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/29/1982 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, IEB-79-14, NUDOCS 8211060267 | |
| Download: ML20066A892 (2) | |
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SOUTH CAROLINA ELECTRIC & GAS COMPANY j
pos7 orries 7e4 COLUMetA. SOUTH CAROUNA 29218 j
O. W. DixON.Jn.
nuc$s5a""o'r*E",'ou.
October 29, 1982 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Ommission 25 Q
Region II - Suite 3100 4
3, o 101 Marietta Street, N. W.
l,o Atlanta, Georgia 30303
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Subject:
Virgil C. Surtmer Nuclear Statich 9h Docket No. 50/395 2 '~
Operating License No. NPF-12 $
Significant Deficiency Cold Space Misapplication
Dear Mr. O'Reilly:
On July 29, 1982, Mr. John Rogge of your office es notified of a potential significant deficiency under the provisions of 10CFR50.55(e) involving the misapplication of criteria in the 1923 Cold Spacing Report. An interim report was issued August 27, 1982, indicating that our evaluation had not been ccmpleted. We have now cmpleted our evaluation and have in fact declared the problen a substantial safety hazard. his constitutes our final report on this subject.
As part of our IEB 79-14 requirements, correct valve weight /0G information as obtained for application to analysis of safety related piping. We correct valve information as then used in a review of chart analyzed piping. Wis review uncovered the fact that four criteria fran the 1923 Cold Spacing Report were not being applied properly. We misapplied criteria were:
1.
proper support of valve weight and power operators 2.
classification of supports in code break regions 3.
maximtzn span length criteria 4.
proper thermal flexibility of long runs A 100% review of safety related chart analyzed problens was implenented to address the four misapplied criteria. One hundred six (106) cases were identified requiring support additions or nodifications. Subsequently, 106 supports were added or nodified. However, in view of the tretendous conservatism involved in the chart analysis, the addition /nodification of 106 supports did not by itself represent a " defect" affecting the safe operation of the plant. In order to adequately address this question, mini-canputer analyses were run of the problen areas. We math models included three supports in each of the three orthogonal directions on both sides of the problem area. W e mini-analyses were performed on the basis of the configuration prior to nodification.
In addition, system evaluations were used to determine those segments required for safe shutdown and to protect the health and safety of the public.
OM 8211060267 821029 h
PDR ADOCK 05000395 S
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e Mr. J. P. O'Reilly October 29, 1982 Page 2 Results of the mini-analyses and system evaluations indicate that two situations, if left uncorrected, could have inpacted the safe operation of the plant. 'No chemical feed lines may not have withstood design basis loading.
'Ihese 1 inch chemical feed lines tie into two 4 inch Emergency Feedwater headers. Although specific analysis has not been performed, it would have to be assumed that failure of the 1 inch lines would result in inadequate supply of Bnergency Feedwater to the steam generators.
In regard to specific cause and corrective action, the misapplication of the four criteria frcm the 1923 Report is the result of the lack of adequate training. 01 art analyzed safety related systems for Virgil C. Stmner Nuclear Station have been reviewed and corrected. In view of the status of design work for the plant, corrective action will be to provide adequate training for future application of the criteria.
If you require additional information, please advise.
Very truly yours, f
O. W Di
. r.
CIN:OWD:glb cc:
V. C. Stamer T. C. Nichols, Jr.
G. H. Fischer O. W. Dixm, Jr.
H. N. Cyrus H. T. Babb D. A. Naunan M. B. Whitaker, Jr.
W. A. Williams, Jr.
O. S. Bradham R. B. Clary M. N. Browne A. R. Koon H. Radin Site OA C. L. Ligon (NSRC)
G. J. Braddick J. L. Skolds J. B. Knotts, Jr.
B. A. Bursey I&E (Washington)
Docunent Management Branch (55e, 21, LER)
NPCF File