IR 05000483/1980005
| ML19309H329 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/17/1980 |
| From: | Hansen W, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19309H323 | List: |
| References | |
| 50-483-80-05, 50-483-80-5, NUDOCS 8005130055 | |
| Download: ML19309H329 (11) | |
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S U U513 0 cGT
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h U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMEh"I
REGION III
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Report No. 50-483/80-05 D'ocket No. 50-483 License No. CPPR-139 Licensee:
Union Electric Company P.O. Box 149 St. Louis, MO 63166 Facility:
Callaway, Unit 1 Inspection At:
Callaway Site, Callaway County, M0 Inspection Conducted: February 1-29, 1980 Inspector:
W. A. Han e
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a c *~r a/ /+o
/M Approved By:
R. C. Knop, Chief, Projects Section 1 Inspection Summary Inspection on February 1-29, 1980 (Report No. 50-483/80-05)
Areas Inspected:
Routine inspection by the IE Regional Resident Inspector (RI) of safety related construction activities including concrete placement; protection of the reactor vessel and other components of the nuclear steam system supplier; (NSSS), work on the reactor vessel head and core internal instrument tubes; material lay down and storage areas; welding of reactor coolant piping and other safety related fluid systems; drawing control; electrical work; and work associated with the main feedwater system tor-sional restraints. This inspection involved 83 inspector-hours by one hTC inspector.
Results: Of the areas inspected, one item of noncompliance was identified (infraction) failure to assure that applicable regulatory requirements are correctly translated into drawings, procedures, and instructions.
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DETAILS
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Persons Contacted Union Electric Company (UE)
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- W. H. Weber, Manager, Nuclear Construction F. D. Field, Manager Quality Assurance
- M. E. Doyne, General Superintendent, Callaway Construction
- R. L. Powers, Site Quality Assurance Group Leader W. H. Stahl, Quality Assurance Assistant Engineer
- J. Laux, Quality Assurance Assistant Engineer
- J. R. Veatch, Quality Assurance Engineer
- S. Hogan, Quality Assurance Assistant Engineer J. L. Baber, Supervisory Engineer Construction
- L. G. Harmon, Senior Construction Engineer K. W. Kuechenmeister, Construction Engineer Daniel International Corporation (Daniel)
- H. J. Starr, Project Manager
- W. L. Sykora, Assistant Project Manager
- E. D. McFarland, Construction Engineering Manager J. A. Holland, Project Quality Assurance Manager J. R. Cook, Quality Control Manager C. Gardner, Project Mechanical Engineer M. Smith, Audit Response Coordinator The inspector also contacted and interviewed other licensee and contractor personnel, including craftsmen, QA/QC, technical and engineering staff members.
- Denotes those attending at least one of the exit meetings.
Licensee Action on Previous Inspection Findings
(Closed) Item of Noncompliance (483/79-13-02): Failure to promptly iden-tify conditions adverse to quality. Daily monitoring of NSSS components and equipment has begun.
Inspectors have been cautioned concerning pre-placement inspections. Any incidents or conditions where material was
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not properly protected have been promptly corrected.
(See various res-ident inspector reports.) Based on the results that have been observed, this item is closed.
(Closed) Item of Noncompliance (483/79-13-03): Failure to control the work to prevent damage or deterioiration of components and/or piping, j
Work in NSSS components is more tightly controlled by the area superin-tendent responsible to monitor these components on a daily basis. The j-2-
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inspector has observed the monitoring and the other actions that were
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taken such as the sealing of the pump casings, the protective cover on the reactor vessel and the control that has been placed on concrete curing water. Thic item is closed.
Reportable Deficiency 50.55(e) Item Undersize Piping System Socke,t Welds On January 29, 1980, the licensee reported a possible problem with piping steket welds that appear to be undersize. This item will be considered to be unresolved (483/80-05-01) until reported resolved by Union Electric and accepted by the NRC.
Functional or Program Areas Inspected 1.
Plant Tours One or more plant areas were toured several times each week during the reporting period to observe general construction practices; area cleanliness and storage condition of equipment, piping, and cable.
Three tours were made on the second work shift and one tour was made on the third shift of work. During one tour, pipe spools were ob-served to be laying with no cribbing between them and the ground.
This condition was reported to the licensee.
Immediate action was taken to correct the condition.
Items of noncompliance or deviations are discussed in Paragraph 5.
I 2.
Concrete Placement During the reporting period, four concrete placements were observed.
a.
Placemant 2C281W0 (Exterior Dome Lift).
b.
Placement 2C251W23 (West Removable Wall).
c.
Placement 2C251W25 (West Removable Wall).
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d.
Placement 2C251W30 (West Removable Wall),
a For each of tiie placements listed above, some or all of the i
following conditions were noted.
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(1) The forms were secure, leak tight, and had been wetted prior to the placement.
(2) The preplacement inspection had been completed and was in l
order.
I (3) Quality Control inspectors were assigned to each crew in addition to those assigned to perform periodic concrete
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testing.
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(4) The concrete temperature was satisfactory and the area
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of the placement was heated to comply with cold weather concreting requirements.
(5) Concrete testing was performed at the required frequercies.
(6) Adequate numbers of crews and personnel were assig'ned to make the placement.
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(7) The placement was satisfactory.
(8) Surrounding equipment was protected from any concrete spill during placement or the subsequent use of curing water.
(9) Curing was monitored and found to be satisfactory. The area of the concrete was protected from the weather.
No items of noncompliance or deviations were identified.
3.
Drawing Control During the inspection period,' 18 drawings were randomly selected in i
the Auxiliary Building to determine if drawings of the latest revision were being used in the construction effort. All drawings were found to be of the correct revision.
No items of noncompliance or deviations were identified.
4.
Fabrication of Reactor Coolant Pressure Boundary and Safety Related Piping Systems During the reporting period, the inspector observed work including handling, protection, inspection, and welding of reactor coolant pressure boundary and safety related piping systems.
a.
Reactor Coolant System Weld 2BB-01 F302 b.
Chemical and Volume Control System Welds BG-15-F097 BG-23-F002 BG-23-F004 BG-01-F080 BG-21-F014 BG-21-F010 c.
Component Cooling Water System Weld EG-01-F029-4-
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d.
Liquid Radwaste Welds
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HB-01-F001 HB-01-F002 e.
Fuel Pool Cooling and Clean Up System Welds
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EC-01-F027 EC-02-F030
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f.
Residual Heat Removal System Weld EC-04-F007 g.
Main Steam System Weld AB-01-F005 h.
Containment Penetration Piping Welds EJ-04-F018 LF-10-F017 For each of these welds one or more of the fabrication activities was observed. Handling and protection of piping and partially com-pleted welds was satisfactory. Purge gas was correctly used, the oxygen content of the purge was measured by a calibrated instrument.
The joint fit-up dimensions were within procedural requirements and the weld area was free of any grease or particles. Welders were certified as qualified for the procedure specified to be used for welding the pipe joint.
No items of noncompliance or deviations were identified.
5.
Electrical Component Installation and Other Related Electrical Activities a.
During the reporting period some portion of the installation of the following electrical penetrations was observed.
2ZSE 258 2ZSE 223 2ZSE 218 2ZSE 254 2ZSE 224 2ZSE 252 2ZSE 207 2ZNE 268 2ZNE 276-5-
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During the installation of these penetrations, some or all of the following conditions were noted. The assembly was per-formed in accordance with work procedures. The installed com-ponents were protected from construction debris and damage.
Inspection requirements were specified by procedure and com-plied with. The installation procedure met technical manual installation requirements.
No items of noncompliance or deviations were identified.
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Work concerning cables and their respective cable trays essen-tial to reactor shutdown or preventing the release of radio-activity (Class IE) were observed. During the reporting per-iod, work associated with installing Class IE cables was start-ed.
It was observed by the inspector that workers in the area were not protecting installed cables from tools or other equip-ment needed to perform their work. These tools or other objects could damage the installed cable. The presence of the tools and objects was brought to the attention of the licensee. The objects were immediately removed from the cable trays to pre-clude cable damage.
No items of noncompliance or deviations were identified.
b.
During a plant tour, it was observed that a Class IE cable tray was attached to and hanging under the plant North Auxiliary Building stair well.
In reviewing this condition, the licensee has determined that the stair well and the beam that supported the cable tray is not designed nor constructed to seismic re-quirements. This is an item of noncompliance.
(483/80-05-02)
c.
During plant tours it was also observed that in numerous areas drain lines and/or other piping system lines are installed over Class IE electrical cable trays. The licensee reported that Bechtel is performing a study of each area to determine how the piping systems would have to be supported to meet seismic re-quirements. The study was reported to be scheduled to be com-plete March 31, 1980. The inspector informed the licensee that a system of recording and control needs to be established so that the areas where hanger changes are to be made are identified. Area engineers and inspectors should also be made aware of these requirements so that they can identify and re-cord any installations they see that had not been identified to ensure that corrective action would be taken. This is an unresolved item pending review by the inspector of the changes Bechtel proposes to make and the system established to control areas identified where the Class 1E system might be subjected to damage by a missile object caused by a design basis event.
(483/80-05-03)
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Nuclear Steam System Supplier (NSSS) Equipment The inspector observed the inplace storage and protection of a.
NSSS components and piping.
The piping assemblies, reactor
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vessel internals, and reactor vessel head is properly stored and protected.
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b.
The inspector observed a sampling of liquid penetrant examina-tion conductd on the lower lip of the Control Rod Drive Mechan-
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ism Seal Welds.
Portions of the examination of the lower lip of nine mechanisms were observed. The inspectors were observed to be following correct liquid penetrant examination techniques.
c.
The inspector observed the installation of several thermal sleev-es through the Rod Drive Mechanism parts in the Reactor Vessel Head.
The installation was being performed in accordance with procedural requirements. Cleanliness requirements were met and the handling and installation of the sleeves was very care-
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fully performed.
QC inspectors were observing the work performed.
No items of noncompliance or deviations were identified.
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Structural Welding The inspector observed work that had been accomplished on the Main Feedwater tonsional restraints. The welds were observed to meet American welding standards and drawing requirements.
No items of noncompliance or deviations were identified.
Unresolved Matters Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompl-iance or deviations. Unresolved items disclosed during the inspection are discussed in the paragraph describing the reportable deficiency (50.55(e))
and in paragraph 5(d).
Exit Meetings The resident inspector attended exit meetings conducted by RIII inspectors R. Landsman and J. Schapker on February 29, 1980.
The inspector met with licensee representatives (denoted under Persons Contacted) on February 7, 21, and 28, 1980.. The inspector summarized the scope and findings of the inspections performed. The licensee representa-tives teknowledged the findings reported in-previous paragraphs.
Attachment: Preliminary Inspection Findings
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PRELIMINARY INSPECTION FINDINGS
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REGIONAL OFFICE
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DOCKET NUMBERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION
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Within the scope of the inspection, no items of noncompliance or deviation were found.
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The following matters are preliminary inspection findings:
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These preliminary inspection findings will be reviewed by NRC/ Supervision /
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PRELIMINARY INSPECTION FINDINGS
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DOCrIT NUMBERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION S'O-4'83 cM?- /37 24 #- 2-7-ed Within the scope of the inspection, no items of noncompliance or deviation
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were found.
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The following matters are preliminary inspection findings:
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These preliminary inspection findings will be reviewed by NRC Supervision /
Management at the Region III Office and they will corr pond with you
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Nuclear Regulatory Commission Inspector
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6.
Nuclear Steam System Supplier (NSSS) Equipment
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a.
The inspector observed the inplace storage and protection of NSSS components and piping. The piping assemblies, reactor vessel internals, and reactor vessel head is properly stored and protected.
b.
The inspector observed a sampling of liquid penetrant examina-tion conductd on the lower lip of the Control Rod Drive Mechan-
ism Seal Welds. Portions of the examination of the lower lip of nine mechanisms were observed. The inspectors were observed to be following correct liquid penetrant examination techniques.
c.
The inspector observed the installation of several thermal sleev-es through the Rod Drive Mechanism parts in the Reactor Vessel Head. The installation was being performed in accordance with procedural requirements.
Cleanliness requirements were not met and the handling and installation of the sleeves was very care-fully performed. QC inspectors were observing the work performed.
No items of noncompliance or deviations were identified.
7.
Structural Welding The inspector observed work that had been accomplished on the Main Feedwater tonsional restraints. The welds were observed to meet American welding standards and drawing requirements.
No items of noncompliance or deviations were identified.
Unresolved Matters Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of aoncompl-iance or deviat',ns.
Unresolved items disclosed during the inspection are discussed in the paragraph describing the reportable deficiency (50.55(e))
and in paragraph 5(d).
Exit Meetings The resident inspector attended exit meetings conducted by RIII inspectors R. Landsman and J. Schapker on February 29, 1980.
The inspector met with licensee representatives (denoted under Persons Contacted) on February 7, 21, and 28, 1980. The inspector summarized the scope and findings of the inspections performed. The licensee representa-tives acknowledged the findings reported in previous paragraphs.
Attachment: Preliminary Inspection Findings-7-
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