IR 05000413/1982006
| ML20050J275 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/19/1982 |
| From: | Bryant J, Vandoorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20050J213 | List: |
| References | |
| 50-413-82-06, 50-413-82-6, 50-414-82-06, 50-414-82-6, NUDOCS 8204140177 | |
| Download: ML20050J275 (8) | |
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tg UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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REGION 11
o 101 MARlETTA ST., N.W., SUITE 3100 ATLANTA, GEORotA 30303
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Report flos. 50-413/82-06 and 50-414/82-06 Licensee: Duke Power Company 422 South Church Street Charlotte, flC 28242 Facility llame:
Catawba Docket Hos. 50-413 and 50-414 License flos. CPPR-116 and CPPR-117 Inspection at Catawba site near Rock Hill, South Carolina Inspector:
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P. K.
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Da'te Signed Approved by:
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g ryant, Section Chief, Division of Date Signed
J j Ject and Resident Programs SUltitARY Inspection on January 26 - February 25, 1982
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Areas Inspected l
This routine, announced inspection involved 181 resident inspector-hours on site in the areas of reactor coolant pressure boundary piping - observation of welding and non-welding activities (Unit 2); safety-related piping - observation of welding and non-welding activities (Unit 2); safety-related components -
observation of work activities (Unit 1); safety-related pipe support and restraint systems (Units 1 and 2); electrical (components and systems) -
observation of work activities (Units 1 and 2)>, electrical (cables and termi-nations) - observation of work and work activities (Units 1 and 2); and followup of licensee and flRC identified items (Units 1 and 2).
Results
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In the areas inspected, no violations or deviations were identified.
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DETAILS
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1.
Persons Contacted Licensee Employees W. H. Owen, Executive Vice President, Engineering and Construction J. C. Rogers, Project Manager J. R. Wells, Corporate QA flanager
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S. W. Dressler, Senior Construction Engineer W. O. Henry, QA flanager, Technical Services L. R. Davidson, QA Manager, Projects Division
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- T. H. Robertson, Construction Engineer, Civil / Welding
- R. A. Morgan, Project QA Engineer
- J. W. Rowell, Construction Engineer, Electrical
- J. C. Shropshire, QA Supervisor
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- H. D. Mason, QA Supervisor
- R. W. Quellette, Licensing Engineer J. E. Cavender, Level III Inspector
H. L. Atkins, QA Engineer J. W. Glenn, QA Engineer D. H. Llewellyn, Welding Engineer Other licensee employees contacted included construction craftsmen, technicians, inspectors and office personnel.
- Attended exit interview 2.
Exit Interview I
The inspection scope and findings were summarized on February 26, 1982, with those persons indicated ir paragraph 1 above.
The unresolved item and
inspector followup item described in paragraphs 11.c. and 15.c. were discussed in detail.
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3.
Licensee Action on Previous Inspection Findings a.
(Closed) Unresolved Item (413, 414/81-17-02):
Control of electrical cable pulling tension. Licensee actions concerning this item have included clarification of the applicable specification (CNS-1390.01-
-00-0070) and procedure (CP-434), training of appropriate personnel, l
and evaluation of pulled cables.
It appears that no adverse effects resulted from the confusing specification and resultant increased pull angles.
The inspector verified the licensee actions and considers them to be satisfactory.
b.
(Closed) Violation (413/81-22-03):
Failure to follow ASME Code requirements for repair welding.
Licensee actions concerning this item
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have included providing required inspection for the repair identified, clarification of the applicable procedure (CQAP-F9), and training of appropriate personnel.
The inspector verified these actions and considers them to be satisfactory.
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c.
(Closed) Violation (413/81-22-05):
Failure to follow procedure for i
control of surface applied materials. Licensee actions concerning this item have been to clean the affected stainless steel pipe and train the appropriate personnel.
The inspector verified these actions and considers them to be satisfactory.
d.
(0 pen) Unresolved Item (413, 414/81-24-01):
Verification of appro-priate corrective action for nonconforming items. The inspector
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reviewed additional licensee actions concerning flCI's 10360, 10425 and 12594.
Additional action concerning flCI 13187 is yet to be performed.
Actions concerning flCI 10360 included verification of defect removal via radiography and verification that no welding had been performed in
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the area of the indication. Action concerning flCI 10425 included an additional evaluation. The inspector verified the actions concerning f4CI's 10360 and 10425 and considers them to be satisfactory.
i Further review details of fiCI 12594 are discussed in paragraph 6.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-
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tions. A new unresolved item identified during this inspection is discussed in paragraph 11.c.
5.
Idependent Inspection Efforts (Units 1 and 2)
a.
The inspector conducted general inspections of site work and work
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activities; observed protection and storage of mechanical equipment, electrical equipment, electrical cables, instrumentation and piping; and observed housekeeping.
These inspections were performed in the
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auxiliary building, containment buildings, pipe fabrication shop and l
storage areas.
b.
(Closed) Inspector Followup Item (413, 414/80-19-02):
Followup of I
corrective actions reported on R2A forms. Licensee actions concerning l
this item have been to require upgrading of repeated storage violations
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(CQAP-P3) and initiating an analysis of all R2A's for generic trends.
It appears that no significant generic trends of items identified by R2A's have gone undetected.
The inspector verified the above actions l
and considers them to be satisfactory.
c.
The inspector observed handling and protection of the Unit 2 reactor
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l vessel head during its movement to the reactor building.
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d.
The inspector observed reactor containment penetration sleeve weld 2-FTT-C for conformance to code (ASME NE71&72) and procedure require-ments.
e.
The inspector observed ultrasonic testing of a portion of Unit 2 steam generator upper lateral support weld No.1B for conformance to procedure requirements. The inspector also verified qualification of the inspectors.
f.
The inspector observed the public document room to determine if required documents were being properly maintained and made available for pubic review.
No violations or deviations were identified.
6.
Nonconforming Item Report Review (Units 1 and 2)
The inspector reviewed numerous nonconforming item reports (NCI's) to determine if requirements were met in the areas of documentation, approvals, evaluation, justification, and corrective action.
Included in this review were NCIs 12594 and 10325.
Licensee action concerning NCI 12594 included reevaluation resulting in reporting of a significant deficiency (SD 413/81-26) in accordance with 10 CFR 50.55(e) on November 23, 1981. The purge dam problem identified in NCI 12594 appears to be an isolated case and the probability for detection during later planned tests was high.
For flCI 10325 the inspector reviewed an additional corrective action to the report. The corrective action is considered to be satisfactory.
This NCI was previously identified in NRC report No. 50-413, 414/81-11 as requiring additional review by HRC.
7.
Licensee Identified Items 50.55(e) (Unit 1)
a.
(Closed) (CDR 413/81-16) - Safety-related 6-inch riser clamps from unapproved supplier. The licensee submitted a final response on October 20, 1981.
Licensee actions have included removal of the subject component from safety-related application, training of appropriate personnel, and verification that no other components were af fec ted.
The inspector verified these actions and considers them to
be satisfactory.
b.
(Closed) (CDR 413/81-20) - Welding arc strike on bonnet of safety-related relief valve 1XC836 in CCW system. The licensee
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submitted a final response on September 21, 1981.
Licensee actions have included repair of the affected valve, implementation of a procedure to control arc strikes, and training of appropriate personnel.
The inspector verified these actions and considers them to be satisfactory.
No violations or deviations were identifie.
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8.
IE Bulletins (Units 1 and 2)
The following IE Bulletins will be closed since it has been verified that they are not applicable to the Catawba fluclear Station:
79-05 - Nuclear Incident at Three flile Island 79-068 - Review of Operational Errors and System Misalignments Identified During the Three Mile Island Incidents 9.
Safety-Related Pipe Support and Restraints Systems (unit 1)
The applicable code for safety-related pipe support and restraint systems installation is the ASitE Boiler and Pressure Vessel Code,Section III, Subsection NF,1974 Edition plus addenda through summer 1975.
The inspector observed fabrication in process for hanger nos.1-R-RN-103 and 1-A-GS-3093 for conformance to requirements in the areas of control of welding, use of specified materials, conformance to drawing, inspections, and in process documenta tion.
No violations or deviations were identified.
10.
Safety-related Components - Observation of Work Activities (Unit 1)
The inspector observed cleanliness and control of entry and exit of the Unit I loop 3 steam generator secondary side. DPC personnel were entering the steam generator in order to plan for modifications scheduled to be performed at the DPC ficGuire site.
No violations or deviations were identified.
11.
Electrical (Cables and Terminations) - Observation of Work and Work Activities (Units 1 and 2)
a.
Requirements for cable terminations are delineated in various DPC specifications and site procedures CP-388 and CQAP-it41.
The inspector observed termination in progress for Unit 2 cables 2ATC1059 and 2EPL549 for conformance to requirements in the areas of cable identification, use of appropriate lugs, location of wires, cable entry into cabinets, tool calibration, and condition of wires.
b.
The inspector observed installed cables in various areas in both units for protection of cable and cable trays from construction activities, securing of coiled cable, protection of cable ends, support of cable, and debris in cable trays.
c.
On February 23, 1982, the inspector noted numerous non-safety-related cables in the diesel generator areas installed within 6-inches of safety-related cables.
Site separation criteria requires at least 6-inches separation between safety-related and non-safety-related cables. Licensee personnel indicated that separation is inspected at
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the time of termination inspection and the Unit 1 areas had been identified by inspector personnel.
Unit 2 has not been final inspected.
However, since non-safety-related cables do not get an inspection it appears that additional inspection criteria may be necessary to assure separation criteria are met. The licensee indicated that a final walk down inspection is being considered along with providing additional barriers for use in conjested areas.
Implementation of adequate controls in this area will be verified by the NRC.
This is an Unresolved Item (50-413, 414/82-06-01):
Veri fi-cation of electrical cable separation.
No violations or deviations were identified.
12. Electrical (Components and Systems) - Observation of Work Activities (Units 1 and 2)
Electrical equipment is being installed in accordance with various DPC specifications and procedure CQAP-M41. The inspector observed polarity testing of Unit 1 diesel generator control panel 1A for conformance to drawing requirements and QC surveillance. The inspector also observed protection of electrical equipment in storage and installed equipment.
Included in this inspection were the diesel generators and diesel generator ba tteries.
No violations or deviations were identified.
13.
Safety-Related Piping (Welding) - Observation of Work and Work Activities (Unit 2)
The applicable code for installation of safety-related piping is the ASME Boiler and Pressure Vessel Code,Section III,1974 Edition plus addenda through summer 1975.
The inspector observed in process welds at various stages of completion and reviewed records for confomance to code and (
procedure requirements in the areas of documentation of pertinent infor-
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mation and QC signoffs via a weld traveler, availability of pertinent instructions, use of appropriate qualified welding procedure, provisions for l
weld repair provided, certification of filler material, verification of base material certification, control of welding parameters, verification of l
welder qualification, use of specified shielding and purge gas, condition of welding equipment, provisions for voltage and amperage checks, verification I
of proper fitup, control of preheat and interpass temperature, condition of weld and base metal surfaces, and verification that appropriate inspections
were being performed.
The following welds were observed:
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Weld No.
Size (In Dia.)
Stage of Welding Observed 2CF60-15
Final 2NI90-7
Intermediate
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Intermediate 2NI296-2
Final 2NI370-5
Root 2NI370-6
Root 2NI2-10
Root 2NI28-1
Intermediate 2NI281-2
Intennedia te No violations or deviations were identified.
14.
Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work and Work Activities (Unit 2)
The applicable code is delineated in paragraph 13.
The inspector observed intermediate welding of weld nos. 2NC45-5 and 2NC45-6 for conformance to code and procedure requirements in the areas delineated in paragraph 13.
No violations or deviations were identified.
15. Safety-Related Piping - Observation of Work and Work Activities (Unit 2)
a.
The applicable code is delineated in paragraph 13. The inspector observed handling and protection of piping for fabrication of the welds listed in paragraph 13 for conformance to procedure and code require-ments in the areas of control of tools for grinding, brushing and filing; use of appropriate handling and rigging equipnent; control of cleanliness; and control of cold spring where applicable.
The inspector also observed machining of piping for weld 2ND18-5 for control of tools, b.
The inspector observed QA visual inspection of pining flow sections 2NIFE5460 and 2NIFE5530 for confonnance to procedure requirements. The inspector verified qualification of the inspector.
c.
On February 18, 1982 the inspector noted that most mechanical inspectors were listed as having limited qualifications.
It appears that many of the varying limited qualifications is confusing and is difficult to control.
The licensee conducted a review and determined that no inspectors had exceeded the time limitation for requalifi-cation.
However, the licensee does agree that the present system is confusing and is in the process of implementing an improved program.
The inspector informed the licensee that NRC followup inspection of the improved program would be perfonned.
This is an inspector followup item (50-413, 414/82-06-02): Verification of improved mechanical QC inspector qualification progra._
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No violations or deviations were identified.
16.
Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities (Unit 2)
a.
The applicable code is delineated in paragraph 13. The inspector observed handling and protection of piping for fabrication of the welds
listed in paragraph 14 for conformance to procedure and code require-ments in the areas of control of tools for grinding, brushing and
filing; use of appropriate handling and rigging equipnent and control
of cleanliness.
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