IR 05000483/1979010
| ML19254E128 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/24/1979 |
| From: | Knop R, Wescott H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19254E124 | List: |
| References | |
| 50-483-79-10, NUDOCS 7910310127 | |
| Download: ML19254E128 (4) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-483/79-10 Docket No. 50-483 License No. CPPR-139 Licensee: Union Electric Company Post Office Box 149 St. Louis, MO 63166 Facility Name: Callaway, Unit 1 Inspection At: Reform, MO Inspection Conducted: September 11-14, 1979
'/ p g 8 Inspector:
H. M. Wescott Approved by:
R. C. Knop, Chief
[C
f s
Projects Section 1 Inspection Summary Inspection on September 11-14, 1979 (Report No. 50-483/79-10)
Areas Inspected: Routine, unannounced inspection of containment base mat documentation; site tour; ASME Code Certification; Cable Tray documentation, and; Ware House fire. The inspection involved twenty-three (23) inspector hours on site by one NRC inspector.
Results: No items of noncompliance or deviations were noted.
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DETAILS Persons Contacted Union Electric Company
- J. E. Davis, Operations QA Supervisor
- S. M. Hogan, Qa Assistant Engineer
- R. C. Powers, Site QA Group Leader
- W. H. Weber, Manager Nuclear Construction Danielson International Corporation
- W. L. Petrie, QA Engineer
- M. K. Smith, Audit Response Coordinator
- Denotes those present at the exit interview.
1.
Review of Containment Base Mat Compressive Strength Test Data The inspector reviewed the containment base mat compressive strength data for the 7, 28, and 90 day compression breaks of test cylinders.
All test breaks for the 28 and 90 day breaks were well above 5000 psi as required by specification 10466-C101 for the base mat.
A compilation of the test data follows:
Compilation of Cylinjer Test Breaks for 7, 28, and 90 Day Compressive Strengths (Callaway Unit No. I Base Mat)
Cyl. No.
7 day Cyl. No.
28 day Cyl. No.
90 day 7402 psi 6609 psi 25S
=
4811 psi 22938 =
High 25168
=
5692 psi 5076 psi 24888 3648 psi 24153
=
Low 25488
=
=
Note:
1.
Required test strength per Specification 10466-C114 =
5000 psi mix at 90 days.
2.
110 pours for base mat dated April 6, 1977, all test cylinders breaks for the 28 and 90 day breaks were above the required 5000 psi.
3.
Average strength for the 90 day breaks were 6488 psi /
or approximately 30% overstrength.
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4.
All of the above data is based on a computor print out made from the raw data.
No items of noncompliance or deviations were identified in this area of the inspection.
2.
Site Tour The inspector was given an extensive site tour to become familiar with the site and view the current status of construction activities.
Specific areas toured include; (1) containment; (2) auxiliary building; (3) cable spreading room; (4) control room; (5) barge dock; (6)
water intake and discharge; (7) fuel pool; (8) concrete batch plant; (9) warehouse and laydova storage areas; and (10) pipeline construction.
No items of noncompliance or deviations were identified in the areas toured.
3.
Review of ASME Code Certification The inspector reviewed the Daniel International Corporation's ASME Certificates of Authorization numbered N-2119(N), N-2120(NPT),
(Corporate) and N-2119-1(N), N-2120-1(NPT) (Site). These certificates expire on June 9, 1981. Further review of these certificates to verify compliance with the ASME B & P Code, Article NA-3000, will be completed at a subsequent inspection.
4.
Observation of Transporting Steam Generator The inspector observed the transporting and lifting of steam generator No. 3 from the barge to the containment. Steam generator No. 4 was scheduled to be in place on September 15, 1979.
No items of noncompliance or deviations were identified.
5.
Cable Tray The inspector reviewed the " Technical Specifications for Purchase of Electrical Cable Trays for the Standardized Nuclear Unit Power Plant System (SNUPPS)" Specification No. 10466-E-034, Job No. 10466, Revision 2 and made observations of installed cable tray and tray stored in the lay-down area.
Items discussed were: (1) straight cable tray was pre-galvanized and resistance spot welded leaving the spot weld areas exposed to the environment, which is allowed by Revision 2 of the purchase specification; (2) tray fittings such as EL's, reducers, T's, etc. were brazed rather than welded; (3) the purchase specification requires that tray capacity be 50 lbs. per linear foot for all tray widths. The inspector could not verify that the required seismic tests had been performed as these records were not available on site.
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Ybe inspector will review cable tray and fittings documentation at a sabsequent inspection.
No items of noncompliance or deviations were identified.
6.
Warehouse Fire The inspector made observations in the area of the warehouse where a recent fire which took place. All items suspect of damage are in a hold status and are to be inspected and reworked as required.
Exit Interview The inspector met with the licensee representatives and personnel from Daniels International Corporation (denoted under Persons Contacted) at the conclusion of the inspection at the site on September 14, 1979. The inspector summarized the scope and findings of the inspection.
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