IR 05000413/1979008
| ML19246B080 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/16/1979 |
| From: | Ang W, Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19246B073 | List: |
| References | |
| 50-413-79-08, 50-413-79-8, 50-414-79-08, 50-414-79-8, NUDOCS 7907110657 | |
| Download: ML19246B080 (4) | |
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-- - ..___ .. _ . 'o UNITED STATES !" ,,., [ '7, NUCLEAR REGULATORY COMMISSION I REGION il h - - -
o, f toi uanitri A sr.. N n. suira stoo art Aura. ctoncia so3os gv,,. .... Report Nos.
50-413/79-08 and 50-414/79-08 Licensee: Duke Power Company P. O. Box 33189 Charlotte, North Carolina 28242 Facility Name: Catawba Nuclear Power Station Docket Nos. 50-413 and 50-414 License Nos.
CPPR-116 and CPPR-117 Inspection at Catawba Nuclear Station near Rock Hill, South Carolina Inspector: ~An ~ )A f[[f9 / ~ Date Signed ,h f//k/7#1 Approved by:_ _ ,1ection Chief, RCES Branch Date Signed C. B ry SUMMARY Inspection on May 1-4, 1979 Areas Inspected This routine, unannounced inspection involved 22 inspector-hours on site in the of containment penetrations procedures, work actvities and records (Unit areas 1); containment dome concrete work activities (Unit 1); reactor building and pipe f abrication shop work activities (Units 1 and 2).
Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
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.. - .~ . DETAILS 1.
Persons Contacted Licensee Employees
- D. G. Beam, Project Manager
- W. D. Henry, QA Manager, Construction
- D.
L. Freeze, Project Engineer
- R. A. Morgan, Senior QA Engineer
- S. W. Dressler, Senior Construction Engineer
- L. R. Davison, Senior QC Engineer
- M. D. Hopkins, Assistant Project Engineer Design
- Attended exit interview 2.
Exit Int e rview The inspection scope and finding were summarized on May 4, 1979, with those persons indicated in Paragraph I above.
Unresolved items 50-413/ 79-08-01 (Control of specification changes) and 50-413/79-08-02 (Records for contain-ment penetration) were discussed.
3.
Licensee Action on Previous Findings Not inspected 4.
Unresolved Items Unresolved items are matters about which more information is required to dete rmine whether they are acceptable or may involve noncompliance or deviations.
New unresolved items identifed during this inspection are discussed in paragraphs 6 & 7.
5.
Independent Inspection Effort An inspection of the Ucits 1 and 2 reactor buildings was performed, Safety related work activities were observed. Hoesekeeping was inspected.
An inspection of tie pipe fabrication shop was performed. Work activities were discussed with QC inspectors. During this discussion, QC inspectors stated that some Oconee Nuclear Station piping fabrication work was to be accomplished at Catawba. They expressed an uncertainty about the welding and NDE requirements applicable to the Oconee work.
The Catawba Project Engineer was queried on this subject and stated that the QC inspectors would be briefed prior to oacencement of work.
Additionally, he further h '\\ h "\\ 'Q
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2-stated that the standard process control sheets would also be prepared for the Oconee work and it would clearly identify the applicable welding and NDE requirments.
No item.e or noncompliance or deviations were identified.
6.
Containment (Penetrations) Review of Quality Assurance Implementing Procedure Unit 1 The following procedures were reviewed to assure that shipping, receiving, identification, storage, handling, protection, installation, and inspection of penetration assemblies are controlled and performed in accordance with NRC requirements.
a.
Duke Power Co:2pany (DPC) Specification CNS-1206.00-03-0000 Rev. 5-Containment Pentration Piping Subassemblies b.
DPC QA Procedure F-9 Rev. 1 - Process Control for Pre-assembly and Installation of Piping Systems DPC QA Procedure P-1 Rev.18 - Receiving Inspection c.
d.
DPC QA Procedures P-3 Rev. 9 - Storage Inspection e.
DPC QA Procedures M-9 Rev.
11 - Mechanical Equipment Installation Inspection During this procedure review, it was noted that design specification CNS-1206.00-03-0000 had been changed several times but an official copy of the specification contained both the changes and the original pages that contained superceeded information.
Subsequent discussion with the Document Control Center supe rvisor revealed that design specifications were being inconsistently changed by several methods such as addendums, amendments and revisions.
Consequently, Document Control Center personnel were never sure when to remove superceeded information. The licensee was questioned regarding the matter and how he would preclude the use of superceeded information by site personnel. The licensee agreed to study the problem on design specifi-cation changes and to determine Low to preclude the use of superceeded information by site personnel.
Pending completion of this action, this item shall be identified as an unresolved item 50-413/79-08-01.
7.
Containment (Penetrations) - Ooservation of Work and Work Activities - tut 1 Containment piping penetration MX No. IM406 was selected for inspection.
The penetration was inspected to determine licensee compliance with licensee procedures, NRC requirements and applicable standards and specifications relevant to assembly, protection,.nstallation and insocction.
During this ))k \\
. x . _ _ _ _ _.. . o-3- ' inspection, the penetration sleeve was found to be marked " Unit 2".
The licensee indicated that the sleeve was provided with the conta:nment liner.
An attempt to determine if the correct sleeve had been installed in the correct unit could not be accomplihsed since the documentation for the containment liner and sleeve were not readily available.
The licensee agreed to research their records and have the necessary documentation available for subsequent inspections.
Pending availability of the MK IM406 sleeve records, this shall be identified as an unresolved item, 50-413/79-08-02.
8.
Containment (Penetrations) Review of Quality Records - Unit 1 The following records for penetration MK No. IM-406 were reviewed to confirm that quality requirements have been met and whether the records reflect work accomplishment consistent with NRC requirements: Receiving Inspection Information Report a.
b.
Manufacturers certificate of compliance c.
ASME Code Manufacturers Data Report d.
M-4 Weld Process Control Sheet (for welds that had already been completed) No items of noncompliance or deviations were identified.
9.
Containment (Structural Concrete II) - Observation of Work and Work Activities - Unit 1 Work activities for concrete pour number 33 on the containment dome were observed to verify licensee compliance with NRC requirements.
Concrete placement for portions of the dome were cbserved.
QC surveillance and monitoring of the concrete transfer from trucks to crane buckets were observed.
Batch plant operations for the concrete mix were observed.
Aggregate storage areas were inspected.
No items of noncompliance or deviations were identified.
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