IR 05000413/1981008
| ML20009E008 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/20/1981 |
| From: | Bryant J, Vandoorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20009D878 | List: |
| References | |
| 50-413-81-08, 50-413-81-8, 50-414-81-08, 50-414-81-8, NUDOCS 8107240582 | |
| Download: ML20009E008 (8) | |
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&# IIZg h'n UNITED STATES
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NUCLEAR REGULATORY COMMISSION e'
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,a E REglON 11
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101 MARIETT A ST.. N.W.. SulTE 3100
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ATLANTA. GEORGI A 30303
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M AY 2 0 m Report Nos. 50-413/81-08 and 50-414/81-08 Licensee: Duke Pcwer Company
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422 South Church Street Charlotte, NC 28242 Facility Name: Catawba Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 anc CPPR-117 Inspection at Catawba site near Rock Hill, South Carolina Inspector:
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P. K. VanDoorn Date Signed Approved by:
J. C. Bryant, Section Chief, Resident and Date Signed Reactor Project Inspection Division SUMMARY Inspection on March 26 - April 25,1981 Areas Inspected This routine unannounced inspection involved 141 resident inspector-hours on site 1n the areas of safety-related piping (welding) - observation of work and work activities (Units 1 and 2); reactor coolant pressure boundary piping (welding) -
observation of work and work activities (Unit 1); observation of housekeeping (Units 1 and 2); observation of storage / protection of components equipment and construction materials (Units 1 and 2); followup of inspector identified items (Units 1 and 2); and followup of licensee identified items (50.55(e)) (Units 1 and2).
Results Of the six areas inspected, no violations or deviations were identified in four areas; two violations were found in two areas; (Failure to provide procedures to control clearance between piping systems / components paragraph 3, and Failure to control storage and protection of flow sections to prevent deterioration -
paragraph 6).
8107240582 810706 il PDR ADOCK 05000413
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M AY 2 0191 DETAILS 1.
Persons Contacted Licensee Employees
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'D. G. Beam, Project Manager
- S. R. Dressler, Senior Construction Engineer
- R. A. Morgan, Senior QA Engineer T. D. Mills, Construction Engineer Mechanical
- M. R. Hemphill, QA Engineer D. H. Llewellyn, Welding Engineer D. E. Gadd, Welding Engineer D. A. Jenkins, QA Engineer T.. R. Stegall, Civil Engineer Other licensee employees contacted included 12 construction craftsmen, four technicians, five inspectors, and three office personnel.
- Attended exit interview 2.
Exit Interview The inspection : scope and findings were, summarized on April 21, 1981, with those persons indicated in -Paragraph 1 above.
The new unresolved items, violations and status of previously identified items were discussed in detail.
3.
Licensee Action on Previous Inspection Findings (Units l'and 2)
a.
(Closed) Unresolved Item (413, 414/80-18-01) - Pipe design and inspection clearance requirements. Tnis item concerned the fact that the licensee had not defined requirements for clearance between piping systems or components. On July 25, 2980 this resulted in Duke Class E liquid waste and recycle system pipe IWL-647-17 being so close to ASME Class B refueling water system valve 1FW-47 that, when operated, the valve position indicator would contact the pipe. Also, on July 25, 1980, ASME Class B steam generator blowdown and recycle system pipe upstream of weld No. 188-10-15 was in contact with a Duke Class E liquid waste and recycle system pipe. On March 18, 1981 nonsafety-related Hanger No. 1-C-WL-6656 was in contact with the operator of ASME Class A chemical and volume control system valve 1NV11-3.
The above examples ara not acceptable in accordance with the guidelines issued recently by Duke Design Engineering and included in site procedure CP-602, Rev.1. Therefore, this item is closed as an un-
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resolved item and upgraded to Violation No. 413/414/81-08-01 - Failure to provide procedures to control clearance between piping systems or compenents.
-b.
(Closed) Unresolved Item (413/414/80-21-01) - Revision of noncon-formance procedure to require evaluation to prevent recurrence. The applicable site procedure (Construction QA Procedure Q-1) has been revised to require evaluation to prevent recurrence. The adequacy of Nonconforming Item Reports (NCI's) was recently reviewed in depth by
- NRC, (See Report No. 50-413/414/81-02).
Followup inspection of the generic aspects of this - item will be included in the followup inspection of items identified _in the above referenced report.
c. ' (Closed) Infraction (413/414/80-23-02) - Diesel generator battery racks
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not seismically qualifiec. The battery racks have been returned to the
. vendor and modified to meet a seismically qualified design.
The inspector reviewed documentation of this action, reviewed the seismic qualification record and observed the Unit 1 modified racks. Licensee f actions are considered satisfactory.
d.
(0 pen) Unresolved Item (413/414/81-01-02) - Control of cutting and
~ forming for NF supports and restraints. The inspector determined that further design evaluation is needed concerning this item. Specifically required is a determination if any edges which are not free edges have been adversely affected and an evaluation of areas inaccessible for repair.
e.
(Closed) Unresolved Item (413/414/81-02-01) - Control of weld filler material. This item concerned an order of weld electrodes which was ordered to ASME Code requirements but required only typical certifi-cations. The inspector verified that the electrode was a one-time special order and was onl/ used in a non-ASME application. The site does not -have an ASME we', ding procedure which uses the questioned electrode (E11018-M). Site welding engineers stated that the electrode would not be ordered in this manner again in order to avoia confusion.
The site system for control of issuance of electrode is considered satisfactory.
No violations or deviations, except as described in paragraph 3.a., were identified.
4.
Uni asolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations.
New unresolved items identified during this inspection are discussed in paragraphs 5.h. and 8.b.
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MAY 2 01981
5.
Independent Inspection Effort (Units 1 and 2)
a.
The inspector conducted general inspections of site work and work activities and observed housekeeping in the auxiliary building, con-tainment buildings and prefabrication areas.
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b.
The inspector conducted an in depth review of NRC reports and open items file to develop an open items history and status from January 1979 to the present.
This area was discussed with licensee personnel in order to improve the licensee's followup system. The licensee has recently assigned followup of open items at a primary duty to a person in the QA department and has indicated that improvements are expected in this area.
c.
The inspector observed work in progress for flow section 2RNFE5800.
Flow sections are manufactured in accordance with the guide lines of the ASME Power Test Code 19.5-1972. -These requirements are implemented by site procedure CP-132. The requirements include machining *of the inside diameter of the piping near the instrumentation flow elements to strict machining tolerances and surface finish. The inspector also observed visual and dimens1cnal inspection of the flow section.
d.
(Closed) Inspector Followup Item (413, 414/79-15-02) - Reportable items and instructions.
Instructions had been completed as requested byNRC.
However, this item had been left open to verify implementation of these
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instructions. A recent in depth inspection in this area was completed by NRC (See Report 50-413/414/81-02). Violation 413/414/81- 02-05 was identified.
Therefore, this unresolved item will be closed and followup inspection will be performed through inspecEion of actions taken concernir.g the violation.
(Closed) Inspector Followup Item (413/414/80-19-03) - Diesel generator e.
engine 1A cleanup documentation.
This item concerned assurance that the diesel generator cleanup required because of severe flooding was properly controlled and documented. The inspector reviewed document-ation and signoffs and considers the actions to have been properly controlled and do.umented.
f.
'(Closed) Inspector Followup Item (413/414/80-21-02) - Review of final closecut action on audit C-80-3.
This item concerned clarification and closecut of Item 5 of the subject audit. The inspector reviewed documentation of these actions and considers the item to be satis-
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factorily closed out.
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(Closed) Inspector Followup Item (414/80-38-01 - Review of RC defects identified by RT.
This item concerned disposition of defects discovered via radiography of reactor coolant weld joints. The
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' inspector reviewed radiographic film, reviend documentation and held
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discussions with licensee personnel concerning defects related to weld Nos. 2NC9-2, 2NC9-3, 2NC13-1 and 2NC15-2.
The inspector determined that. reshots were taken as necessary, vendor film was reviewed as necessary and Level III inspectors were involved as necessary to evaluate the defects. The licinsee determined that the defects were acceptable. These actions are considered satisfactory.
h.
On March 26, 1981, the inspector questioned the spacing of embedded rebar visible in the Unit 2 reactor coolant pump base blockouts. On April 15, 1981, the inspector questioned the spacing of embedded rebar visible in the area of the Unit 2 pressurizer shield wall.
Site personnel have forwarded these questions to Design ~ Engineering for evalauation via documentation on Nonconforming Item Report Nos.10525 and 11667. This item will be unresolved until it can be verified if violations have occurred and significance be determined. The areas in question have been marked as nonconforming to prevent further work.
This is Unresolved Item 413/414/81-08-02 - Spacing of rebar in RCP base blockouts and in pressurizer shield wall area.
No violations or deviations were identified.
6.
Storage Inspection (Units 1 and 2)
a.
Site storage requirements are defined via various documents such as purchase documents,. requisitions and documents intended specifically for this purpose such as Duke Form 302.2, Duke Form P3A and NSSS Lists.
Storage is controlled on site via QA procedures P-1, Rev. 20, Receiving Inspection and' P-3, Rev.12, Storage Inspection.
In addition, the requirements of ANSI N45.2.2, Packaging, Shipping, Receiving, Storage
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and Handling of Items for Nuclear Power Plants have been adopted by Duke.
The inspector observed storage of numerous components, equipment and construction materials for conformance to applicable requirements.
Included in this observation were the pressurizer, reactor vessels, Unit I reactor vessel internals, vendor and Duke manufactured piping spools (all classes), miscellaneous steel, values (all classes),
electrical cable and electrical components.
b.
During this inspection several pieces of stainless steel pipe with general light resting were noted at the outside laydown storage area.
These pieces nad apparently undergone bending at the site fabrication shop. Licensee personnel indicated that they were aware of the problem and the pieces would be cleaned.
Licensee personnel said that some rusting is an inherent result of the normal bending process (slighc
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i nal clean.ng would mandrels) and that addit oshop after beniing and at the f abrication
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contamination from bendingbe performed in the future d
unusually hig's winds ha hold noted that numerous QCspools prior to outdoor storage.
after and soon ical cable Also during this inspection site, the inspectoror blown f ree from elec r The licensee took immediate t
of boen experienced at thewere loose area.
l to be experienced.
especially aware No
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outside laydownand cautioned personne and tags is weather tapes located in the severe action correctiveareas immediately u ter machined carbon aed.
which had spools on hold had been 'stobserved precision storage area laydownExamples are Tag Nos.
ctor outside On April 3,1981, the inspe non-This is in in the mtchined surface.
stored hined parts to 2RN205CC and 2RN205DD.
sectionsof rust on the h
h requires precision macdix B, Criterion XIII w d.
flow steel 2RN58BB, 2RN99-10, 2RN101CC, varying degrees t
of materials to preven with ANSI N45.2.2 whic l
and with 10 CFR 50, Appenand protection /81-08-03 compliance t deterioration.
stored indoors of storage 413, 414 controlThis is Violationof flow sections to preven 6.d., were berequires storage and protection s described in paragraph deterioration.
or deviations, except a violation identified.
50.55(e) (Units 1 and 2)
The inspector No personnel and reviewed mounted limit switches.
Licensee Identified Items d
d switches were identified an Stem 413/414/78-01-01 -with responsible licensee 7.
held discussions verify that all affecte (Closed)
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documentation to weld deficiencies. personnel, panel licensee mine replaced.
- Controlresponsiblerepaired panels to deter 413/414/79-12-01with discussionsd observed the (Closed)
d ls had been properly repaire.
held not seis-b.
reviewed documentation an inspector k
that the deficient pane Diesel generator battery rac s413/414/80
as item h 3.c.
413/414/ 80-23-01 -
same This item is thed is described in paragrap (Closed) qualified.
Followup inspection performere identified.
d Work A.i.ivities c.
mically violations or deviations we ) - Observation of Work is the No Safety-Related Piping (Weldingof saf ety-related piping 974 Edition (Units 1 and 2)
code for installationsel Code,Section III,1 8.
applicable ASME Boiler and Pressure Ves The a.