View source for TXX-6497, Interim Deficiency Rept CP-86-73 Re Installation of ASME Snubber Attachment Brackets.Initially Reported on 870320. Results of Evaluation of 165 Supports Listed.Project Procedures Under Evaluation.Next Rept by 870918

{{Adams
| number = ML20215C023
| issue date = 06/12/1987
| title = Interim Deficiency Rept CP-86-73 Re Installation of ASME Snubber Attachment Brackets.Initially Reported on 870320. Results of Evaluation of 165 Supports Listed.Project Procedures Under Evaluation.Next Rept by 870918
| author name = Counsil W, Keeley G
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000445, 05000446
| license number = 
| contact person = 
| document report number = CP-86-73, TXX-6497, NUDOCS 8706170552
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 2
}}

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J M                          Log # TXX-6497
                                                                        ==                         File # 10110 L                                  903.9         l
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Ref # 10CFR50.55(e)     i illELECTRIC WiHiam G. Counsil ~
Eucutive %cc l>ni&nt                                                                                      'i U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 l

==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446
: l.                                   ASME SNUBBER ATTACHMENT BRACKETS                                                     1 SDAR:    CP-86-73 (INTERIM REPORT)                                                    ;
I
                ' Gentlemen:
By letter logged TXX-6315, dated March 20, 1987, we notified you of a deficiency involving installation of ASME snubber attachment brackets, which we determined to be reportable under the provisions of 10CFR50.55(e). This is an interim report provided to status corrective actions.
As previously reported, an evaluation of 165 supports was conducted in which the predicted pipe movements were compared to the field verified swing angle data.
                -The evaluation summary indicated that 18 of these supports were under further l               .~ evaluation. The evaluation for these supports is complete and a revised summary of the results follows:
{
                           - 83 supports were determined to have' sufficient field verified swing angle to accommodate the predicted pipe movement.
                          - 15 supports were determined to be unnecessary in a previously initiated pipe support requalification effort and are being deleted.
                          - 33 supports are being modified as a result of the pipe support requalification effort (but not as a result of this deficiency).
                          - 31 supports have been identified as having less available swing angle than required by analysis and are being modified to correct the situation.                  "
                          - 3 supports have no safety related function nor impair the safety related function of other components and have therefore been removed from further evaluation.
O  l 8706170552 PDR   ADOCK 0500044     870612    "f                                                                        7
         'S                        PDR-400 North Olive Street LB 81 Dallas, Texas 75201 I' ho

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I TXX-6497 June 12, 1987 Page 2 of 2 Currently, project procedures are under evaluation to determine corrective actions required to prevent recurrence of inadequate swing clearance when a size 3 or 10 snubber is used. As described above, our evaluation of existing installations has identified 31 supports with inadequate swing clearances. Nonconformance reports have been initiated to rework these supports. This rework is scheduled for completion by January 26, 1988.
We will submit our next report by September 18, 1987.
Very truly yours, N
W. G. Counsil By:
                                                                     <b            '
                                                                                   '//
         ~
G. S. Keeley D         /-
Manager, Nuclear Lf'c[ sing BSD:gj c-     Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l 1
1
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