IR 05000413/1979015
| ML19275A679 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/04/1979 |
| From: | Bryant J, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19275A673 | List: |
| References | |
| 50-413-79-15, 50-414-79-15, NUDOCS 7910180110 | |
| Download: ML19275A679 (4) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
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+r REGION 11
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o 101 MARIETTA ST N.W.. SUITE 3100 o
ATLANTA, G EORGIA 303o3
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Report Nos. 50-413/79-15 and 50-414/79-15 Licensee: Duke Power Company P. O. Box 33189 Charlotte, North Carolina 28242 Facility Name: Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117 Inspection at Catawba Site near Lake Wylie, South Carolina d
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!)9 Inspector:
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. McFarlardV ~ ~ ~
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Date S'igned
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VM[Fj Approved by:
f4 J.p. ' Bryan Se Mion Chief, RCES Branch Da te' Sip,ned SUMMARY Inspection August 21-24, 1979 Areas Inspected This routine, unannounced inspectiin involved 28 inspector-hours onsite in the areas of containment structural con: rete repairs (Unit 1), evaluation of noncon-forming items for 10 CFR 21 and 10 CFR 50.55(e), IE bulletins, and project schedule revisions.
Results Of the four areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- R. L. Dick,-Vice President, Construction
- D. G. Beam, Project Manager
- D. L. Freeze, Project Engineer
- R. A. Morgan, Senior QA Engineer
- S. W. Dressler, Senior Construction Engineer
- J. C. Shropshire, QA Engineer (QAE) Mechanical, Welding
- H. D. Mason, QAE Civil, Electrical M. D. Johnson, QAE, Mechanical C. L. Biggers, QA Technician, Civil
- L. R. Davison, Senior QC Engineer
- J. W. Cox, Licensing and Project Engineer, Operations
- W. H. Rasin, Design Engineering, Mechanical-Nuclear Division Other licensee amployees contacted included various construction craftsmen, technicians, anu office personnel.
Other Organizations Hartford Steam Boiler Inspection and Insurance Company
- J. W. Kosko, Authorized Nuclear Inspector (ANI)
- C. F. Toeg?l, ANI
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on August 24, 1979 with those persons indicated in Paragraph 1 above. No new items of noncomoli-ances or unresolved items were identified in the areas inspected.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items There were no new unresolved items identified during this inspection.
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Independent Inspection a.
Management Information The inspector reviewed with responsible management persons from construction, operations, and licensing the projected change in fuel loading and commercial operation dates for Catawba Units 1 and 2.
Unit 1 is now scheduled for fuel loading in April,1983 with commercial operation following in July,1983. Fuel loading of Unit 2 is scheduled for October,1984 with commercial operation in January,1985.
The development of detailed schedules for construction work, verations procedures and operations work are scheduled to be completed in September,1979.
b.
Facility Inspection The inspector inspected the Unit 1 and 2 reactor buildings, auxiliary building, the control room, the hanger fabrication shop, the pipe fabrication shop, and the pipe storage yard and receiving area. The inspector observed work on the removal of the cofferdam between Lake Wylie and the standby corling water lake dam, and also observed work on the repair of the inside surface of the Unit 1 containment dome concrete. Six additional Case II honeycomb deficiencies have been identified (NCI 6431).
6.
(0 pen) Inspector Followup Item 413-414/79-05-01, Nonconforming Item (NCI)
System. The inspector reviewed 116 closed NCI's selected as representative of the NCI's issued in the last six months (NCI's 5000 through 6430).
The
'.;i.I's were on work related to civil, mechanical, and electrical hardware and work, welding practices and procedures, warehouse practices, documenta-tion, and vendor supplied items.
The NCI's were issued by a representative cross section of the staff. The timeliness and the suitability of the evaluations were reasonable.
Personnel changes relative to the NCI report-ing system have been made recently.
This item remains open pending the review of the effectiveness of the modified reporting system over a longer period of time.
7.
Licensee Identified Items (LII) 10 CFR 50.55(e) Items a.
(0 pen) LII 413-414/79-14-01, Steam generator water level errors. RII has received the Duke Power Company (DPC) August 21, 1979 interim report concerning the subject along with the Westinghouse June 22, 1979 letter NS-TMA-2104 to the NRC which reported the item under 10 CFR 21 and 10 CFR 50.55(e). A generic resolution is being pursued.
The corrective action for Catawba Units 1 and 2 will be reported by DPC in a subsequent report to NRC.
b.
(0 pen) LII 413-414/77-13-01, Valve operator natural frequency. The
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inspector reviewed the DPC final report to Region II dated August 14, 1979 and discussed the subject with the staff mechanical 1184 350
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engineer. This item remains open pending a review of documentation of the implementation of the corrective action program described by DPC in the initial report dated October 11,1977 and the final report.
(0 pen) LII 413-414/79-15-01, Safety Related Instrumentation and c.
Controls. On Augast 10,1979 DPC informed Region II that DPC's review of safety related systems during the as-built confirmation stage of the McGuire project has identified the following design deficiency in safety related instrumentation and controls that would also apply to the Catawba project. Air operators for modulating control VMves in engineered safeguards systems are designed to fail the valves in the safe position upon loss of air. However, in some cases, the applica-tion of nonsafety grade controllers, positioners, solenoids, and instrumentation could result in failure of these valves to go the safe position upon loss of air, or to control prc9erly if air is available.
An evaluation of this deficiency and the required corrective action is being made.
8.
IE Bulletins (IEB)
a.
pen) IEB 413-414/78-BU-12,12A and 12B, Atypical weld material in reactor pressure vessel (RPV) welds.The DPC responses to Region II dated May 16,1979, July 2, 1979, and August 9,1979 indicate that the Unit 2 RPV was supplied by Combustion Engineering Incorporated (CE);
not the Unit 1 RPV as reported in 50-413-414/79-14. The Unit 1 RPV was manufactured by Rotterdam Dockyard Company.
b.
(Closed) IEB 413-414/79-BU-11, Faulty overcurrent trip device in circuit breakers for engineered safety systems. The inspector reviewed the DPC response dated July 19,1979 and discussed it with the senior QA engineer. The DPC review of the subject revealed that no Westing-house DB-50 or DB-75 circuit breakers are used or planned for use in safety related syc at this station.
9.
NRC Reporting Requirements The inspector reviewed the QA department prccedure QA-121 and the Design Engineering department procedure PR-290, both entitled, " Nuclear Regulatory Commission Reporting Requirements" and discussed the subject with the QA manager, Engineering and Services Department, and the Senior QA Engineer onsite.
The current procedures reference 10 CFR 21 and 10 CFR 50.55(e),
but do not enclose copies of the regulations nor provide other documenta-tion nor training aids to provide guidance to the DPC staff for determining reportable items. The referenced procedures provide procedures for process-ing the reportable items, but not for the basic determination of reportable events. The QA orientation / indoctrination outline, procedure QA-131, provides for a copy of 10 CFR 50.55(e) to be a handout for new employees.
The need for further documentation for providing DPC staff with adequate instructions to determine reportable items will be Inspector Followup Item 413-414/79-15-02, Reportable Items Instructions.
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