IR 05000250/1979032
| ML17339A742 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 01/04/1980 |
| From: | Comptor R, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17339A741 | List: |
| References | |
| 50-250-79-32, 50-251-79-32, NUDOCS 8003270260 | |
| Download: ML17339A742 (8) | |
Text
~R A~00
~4
~o Cy 4V O
Vi O
~O
+w*e+
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-250/79-32 and 50-251/79-32 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, Florida 33101 Facility Name:
Turkey Point Docket Nos. 50-250 and 50-251 License Nos.
DPR-31 and DPR-41 Inspection at Turkey Point site near Miami, Florida Inspectors:
R.
C Approved by:
A. R. Herdt, Section Chief, RCGES Branch
~
SUNDRY Da e Signed
/ at Signed Inspection on November 14-15, 1979 Areas Inspected This routine announced inspection involved 14 inspector-hours onsite in the area of IE Bulletin 79-14,
"Seismic Analysis for As-Built Safety Related Piping Systems."
Results No apparent items of noncompliance or deviations were identified.
s sossvII Z6>
vo
DETAILS 1.
Persons Contacted Licensee Employees
<<J.
E. Moore, Operations Supervisor
+D. Mantz, Project Manager
+D. Coleman, Area Construction Supervisor Other Organizations
- G. K. Wang, IE Bulletin 79-14 Coordinator, Bechtel Power Corp.
(BPC)
- W. Brown, Plant Design Group Supervisor, BPC J.
C. Crim, Stress Group Leader, BPC
+J. R. Sharpe, Design Supervisor, BPC-Attended exit interview 2.
Exit Interview e
The inspection scope and findings were summarized on November 15, 1979 with those persons indicated'in Paragraph 1 above.
3.
Licensee Action on Previous inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
(Open) I. E. Bulletin No. 79-14, "Seismic Analysis for As-Built Safety Related Piping Systems" The inspector examined Bechtel procedure 5177-102-P-001,
"Implementation Procedure for As-Built Configuration of Nuclear Safety Related Piping Components, IE Bulletin 79-14" and the procedure titled "Pipe Support/
Restraint Design Review by Subcontractor" for content, completeness and compliance with IEB requirements.
Inspection Team Personnel Qualification Records, instructional handouts, quizzes and training seminar attendance lists were reviewed.
The completed field inspection documentation package for Unit 3 stress problem CCW-Ol,comprised of isometrics E-2387-IC-341 and 341Aqwas examined for completeness and types and extent of discrepancies identifie "2-Portions of the following Unit 3 isometrics were walked down to compare completed inspection documents with the "as-built" piping:
3" and 4" Safety Injection - ISO IC-335, Revision
Hangers 3 SIH-62, 63, 64, 68, 72, 73, and
Restraints SR-128, 160 Valves 879B, 888B 3" and 4" Safety Injection - ISO IC-335A, Revision 3 Hangers SIH-55, 65, 66, 69, 70, 71, plus 2 unnumbered Restraints SR-125, 126 Valves 879A, 888A, 845A, 845B, 878A 14" Residual Heat Removal-ISO IC-269, Revision 2 Hanger ACH-9 Restraint SR-252 12" Residual Heat Removal - ISO IC-249 Hanger ACH-22 2" Safety Injection/Residual Heat Removal - PSK-M-631, Revision
Piping Only 12" Auxilliary Coolant - ISO IC-346 Restraint SR-305 Valve 835E 18" Auxilliary Coolant - ISO IC-347 Hanger ACH-117 plus one unnumbered 16" and 18" Auxiliary Coolant - ISO IC-345 Hanger ACH-ill, 112 Restraints SR-307 Valves 713C, 787H, 787G, 713B, 787F, 713A'
'C
Two minor discrepancies were noted.
On restraint SR-125, accepted as built per the drawing, a specified 3/16 inch weld was in fact missing.
An auxilliary coolant system lateral restraint had a clearance of approximately 1/4 inch where l(16 inch was indicated on the drawing.
Considering the very minor nature of these discrepancies and the large number of items inspected these two items were not considered a significant safety question.
However, the need to accurately document all conditions was discussed at length with responsible personnel.
New as-built isometric drawings are being developed by Bechtel and stress analyses are to be run on all systems at Turkey Point.
Piping analysis is being performed by EDS Nuclear and support/restraint design review has been subcontracted to Capacetti-Martin.
The field installation and QC documentation for main steam relief system support modification shown on S 177"102"3-MSRH-5A and the three new steam generator blow down supports were examined.
Records examined for the modified support included Inspection Checklist for Expansion Anchors, Construction QC Hanger Inspection Report, Final Pass VT Report and Activity Inspection Report. Process Sheet C-504007-1, Equipment Seismic Support Inspection, Activity Inspection Reports, Weld Travelers and concrete base QC reports were examined for the new supports.
The inspector examined the control and documentation of maintenance items identified during the walkdown (discrepancies in installations that do not result in stress problems, but do not meet original designs).
Ways to improve control of these items at Bechtel's design office were discussed.
No deviations or items of noncompliance were identifie J
'