IR 05000483/1980021
| ML19347B942 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/12/1980 |
| From: | Knop R, Wescott H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19347B938 | List: |
| References | |
| 50-483-80-21, NUDOCS 8010160250 | |
| Download: ML19347B942 (6) | |
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' ;*i U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT REGION III-
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Report No. 50-483/80-21
Docket No. 50-483 License No. CPPR-139 Licensee: Union Electric Company Post Office Box 140 St. Louis, MO 65166 Facility Name:
Callaway, Unit 1 Inspection At:
Callaway Site, Callaway County,l'9 Inspection Condu 'ed: August 26-29, 1980 c.ft Inspector:
H. M. Wescott 7- /c2 - fr')
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R.C. Knop,(CNfY C/ - / E - 70
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l Approved By:
Project Section 1 Inspection Summary-Inspection on August 26-29, 1980 (Report No. 50-483/80-21)
Areas Inspected: Routine, unannounced inspection:
followup of 10 CFR 50.55(e) reports; fire prevention / protection; weld material control; safety related structures; QA records. The inspection involved a total of 26 inspector hours onsite by one NRC inspector.
Results:
Of the three (3) areas inspected, no item of noncompliance
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were identified.
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e DETAILS
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t Persons Contacted Union Electric Company
- M. I. Dayne, General Construction Superintendent
- J.
V. Laux, Supervising Engineer, QA Construction
- C. J. Plows, QA Consultant
- R.
VeatcL, QA Assistant Engineer Daniels International Company W. E. Columbus, Fire and Safety Inspection Engineer
- J. R. Cook, QC Manager
- C. Gardener, Construction Engineering Manager (Acting)
- A. Harmon, Procurement Analyst
- W.
L. Petrie, QA Engineer
- G. M. Stephens, Construction Manager
- W.
L. Sykora, Assistant Project Manager
- Denotes those persons attending the exit meeting on August 29, 1980 at the Callaway Site.
1.
Licensee Action on Previously Identified Items (Closed) 10 CFR 50.55(e) Report. Reported on January 18, 1980 to USNRC RI concerning faulty operation of Ruskin Fire Dampers used in the HVAC system. The inspector reviewed documentation as follows:
(1) Letter, SNUPPS to USNRC RI dated February 15, 1980, SLNRC 80-8, w/" Final Report on Vertical Fire Dampers for the SNUPPS Project"
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l by Bechtel Power Corporation dated February 12, 1980.
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(2) Letter, SNUPPS to USNRC RI, dated April 3, 1980, SLNRC 80-16
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(3) Letter, SNUPPS to USNRC RI date.d May 16, 1980 SLNRC 80-24,
- /" Supplement to tre Final Report on Vertical Fire Dampers w
Supplied by Ru, skin Manufacturing Company for the SNUPPS Project" by Bechtel Power Corporation, dated April 24, 1980.
(4) " Seismic Simulation Test Qualification Addendum A" by Ruskin Manufacturing Company, dated April 24, 1980.
The inspector visually examined the fire dampers located in the warehouse, nine inch and larger, to verify that the modifications
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had been made. This item is considered closed.
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t (Closed) 10 CFR 50.55(e) Report. Reported on March 23, 1979 to
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USNRC RI concerning pressurizer anchor bolt support design defi-ciency. The inspector reviewed the letter from SNUPPS to USNRC
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RI dated May 1, 1979, SLNRC 79-6 w/ attached " Final Report on
Pressurizers Support Anchor Bolts for the Callaway Plant, Unit
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No. 1 of the Union Electric Company and Other SNUPPS Units" dated April 30, 1979. Drawing C-052905 has been revised to eliminate the welded connection at the bolts. The location of the bolts
has been maintained and twenty four (24) new ASTM A450 bolts are provided to fasten the support frame using a combination of methods.
This item is considered closed.
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(Closed) 10 CFR 50.55(e) Report. Reported on December 22, 1976 to USNRC RI concerning cracks in American Bridge girders. The inspector reviewed the final report from SNUPPS to USNRC RI dated April 27, 1977, SLNRC 7-4, stating that all inspections and repairs have been
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completed. The inspector also reviewed NCR No.'s 2-0379-C-A and 2-0397-C-A dated March 9, 1977 and March 16, 1977, respectively, with associated weld repair records.
This item is considered closed.
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(Withdrawn) 10 CFR 50.55(e) Report.
Reported on November 30, 1979 concerning nonconforming threads on three and one half inch (3-1/2")
studs and nuts for the steam generator lateral supports. The inspec-
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tor reviewed the " Final Report Investigation of Nonconforming Threads on 3-1/2" Diameter Studs and Nuts for the NSS Steam Generator Lateral Supports" by Bechtel Power Corporation dated August 26, 1980. Worse case nuts were threaded onto studs selected at random and tested at t
Lehigh University and were found to meet the required strength. The inspector concurs with the withdrawal of this item.
2.
Functional or Program Areas Inspected
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a.
Fire Prevention /Protecticn
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The inspector reviewed and made observations to ascertain that approved controls exist relative to fire prevention, protection, and suppression, as follows:
(1) Approved Procedure, AP-XIV-03, " Fire Prevention and
Investigation," Revision 1, dated December 20, 1978.
(2) AP-XIV-06, " Fire Prevention and Control" Revision 0,
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dated December 22, 1978.
I (3) " Monthly Fire Brigade Training" records from September j
1978 to August 1980.
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(4) The inspector made observations of seven (7) fire extin-
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guishers in the warehouse and found that two extinguishers had not been inspected monthly as required, although they
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had been inspected for the current month. One extinguisher
i did not have the required inspection tag.
All extinguishers l
were fully charged, however.
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(5) The dry sprinkler system used for protection of Class A l
equipment had been inspected as required.
4l (6) Observation of approximately twenty extinguishers in the j
power block established that several did not have inspection
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tags. One extinguisher had no inspection tag and had been
discharged.
The above dis repancies were noted by the licensee and corrected.
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(7) At present there is no back-up for the existing fire
pumps, which is dependant on off-site power. The two (2)
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diesel driven fire pumps to be used for fire protection loops are scheduled to be completed and tested by March 1981. 'The licensee stated that a standby engine driven j
fire pump would be considered for back-up use durir.g the interim.
j (8) The licensee is also aware that a fire brigade is not avail-able during week-ends and holidays. The security force may be trained for these periods and full fire brigade coverage j
would be available prior to arrival of fuel.
b.
Review of Safety Related Structurca QA Records
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The inspector reviewed quality records relative to safety related steel structures outside of containment to ascertain that these
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i records reflect work accomplishment consistent with NRC require-I ments and SAR commitments, as follows:
(1) Structural steel welds numbered 26B2 through 26B6, located in the fuel building at elevation 2047 feet were selected for the QA records review.
(2) These welds were performed by welder I.D. numbers S-120, a
M-120, and D-1.
A review of the welder qualification j
sheets and welder qualification records established that they were qualified to weld to WPS N-1-1-A-6A.
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(3) Review of weld traveler records indicated that weld material used was traceable and in accordance with drawing No. C-056311.
(4) Welds numbered 26B2 through 26B6 are assigned unique numbers
(50 through 53 and 57) and are traceable to the drawing and
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the Welding QC Surveillance Report.
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(5) The inspector reviewed Weld Control Record rios for weld j
No.'s KC-21-F003 with three weld repair radiograph reports, j
2-KC-21-F001, and 2-KC-21-F002, temporary attachments.
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(6) Review of welder qualification records of welder No.'s K-11 i
and M-28.
i No items of noncompliance were identified in this area of the j
inspection.
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Weld Material Control c.
i The inspector reviewed documentation and made observations of
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j weld material storage and handling associated with steel struc-tures to determine conformance with applicable code requirements,
as follows:
(1) Daniels Procedure No. WP-503, " Control of Welding Consumables," dated July 22, 1980, Revision 11.
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l (2) The following weld rod heat No.'s with associated identi-i fication No.'s were randomly selected and traced to tcld
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material certifications and purchase erdci:
i Issue Point Ns. 1:
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i Oven No.
Heat No.
I. D. No.
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7C2B WE 58
741881 WE 26
782835 WE 35 I
421J2461 WE 115 Issue Point No. 2:
Oven No.
Heat No.
1. D. No.
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421J2461 WE 115
402H9361 WE 93
f (3) Three weld rod hold ovens were randomly selected and tem-j perature was verified to be within the proper range using
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a calibrated contact pyrometer.
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l (4) Daily oven temperature checks are made and recorded by the attendant.
(5) Weld material issue slip were reviewed. The issue slip No. is recorded on the weld traveller to establish I
traceability.
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Exit Interview The inspector met with licensee representatives (denoted under Persons Contacted) at the conclusion of the inspection on August 29, 1980. The inspector summarized the scope and findings of the inspection. The i
licensee acknowledged the information.
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