IR 05000364/1978021
| ML19263B328 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/22/1978 |
| From: | Herdt A, Hunt M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263B322 | List: |
| References | |
| 50-364-78-21, NUDOCS 7901180041 | |
| Download: ML19263B328 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o,,
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Report No.: 50-364/78-21 Docket No.: 50-364 License No.: CPPR-86
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Category: A2 Licensee: Alabama Power Company P. O. Box 2641 Birmingham, Alabama 35291 Facility Name: Joseph M. Farley Plant, Unit 2 Inspection at: Ashford, Alabama Inspection Conducted: December 12-14, 1978 Inspector:
M. D. Hunt.
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Reviewed by:
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Herdt, ief Date Projects Sec ion
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Reactor Cons ruction and Engineering Support Branch Inspection Summary Inspection on December 12-14, 1978 (Report No. 50-364/78-21)
Areas Inspected:
QA audits, licensee identified items, unresolved items, infractions, IE circulars and bulletins. This inspection involved 21 inspector-hours on site by one NRC inspector.
Results: Of the five areas inspected, no apparent items of noncompliance or deviations were identified in four areas, one apparent item of noncompliance (Deviation - Audit closures, Details I, paragraph 4) was identified in one area.
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RII Rpt. No. 50-364/78-21 1-1
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DETAILS I Preparec by:
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M. D. Hunt, Principal Inspector hati Projects Section Reactor Construction and Engineering Support Branch Dat w of Inspection: December 12-14, 1978 Reviewed by:
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A.Rl.HerdL, Chief Date rojects Section
- Reactor Construction and Engineering Support Branch 1.
Persons Contacted a.
Alabama Power Company (APCO)
- J. A. Mooney, Project Manager - Construction
- R. E. Hollands, QA Supervisor
- C. R. Kualheim, QA Engineer
- A. W. Hankins, QA Engineer N. R. Collins, Material Coordinator b.
Daniel Construction Company of Alabama (DCC)
- D. L. Garrison, QA Manager
- R. Roehn, QA Engineer
- R. F. McCraney, QC Coordinator
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item 364/78-09-01, Verification of Anchor Be t Lengths. The licensee has used a statistical approach to determine he extent of existing anchor bolt problems in bolts installed before an addition was added to the checklist of QC Procedure 5.4.2.1 Addendum I, Installation and Inspection of Pipe Hangers, Supports and Restraints which requires bolt length measurement by the UT method. Field Change Requests (FCR) 2M-3391 and 2M-3397 have been issued to cover 18 hangers which did not conform to specifications and require evaluation by the designers.
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RII Rpt. No. 50-364/78-21 I-2
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3.
Unresolved Items No new unresolved items were identified during this inspection.
4.
Independent Inspection The inspector reviewed approximately 35 QA audits performed by the APC0 QA section during the past 11 months. Audit Finding Report (AFR) No.
FNP-78-19-I3 dated April 7, 1978, was examined in detail. This AFR identified several conditions relating to the storage of some safety-related and non-safety-related filters.
Several recommended corrective actions for the various problems cited were listed. However only one of the problems was addressed in the CORRECTIVE ACTION TAKEN section of the AFR prior to closing the AFR. Further investigation revealed that a nonconforming report (NCR) had been written to cover parts of the audit finding. The corrective action had been taken and the NCR was closed.
Additional testing is required but will be completed when the filters are installed.
No mention was made concerning the related NCR or the required additional testing in the CORRECTIVE ACTION TAKEN section of the AFR.
This is identified as deficiency 364/78-21-01, Audit Closures. While the inspector was at the site the AFR was revised to include the corrective action taken under the NCR and a statement added to insure testing after installation. The inspector witnessed a meeting of the QA auditors to instruct them in proper closure of AFRs. They were further directed to review all audits for the past year to insure that all were properly closed. The corrective actic.s taken by the licensee appear adequate and no response to this defic ency (364/78-21-01) is required.
However, the testing of these filters at startup will be carried as inspector followup item 364/78-21-02, Testing of HEPA filters.
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Licensee Identified Items (LII) (10 CFR 50.55(e))
(Closed) LII 364/78-16-02, Terminal blocks in containment do not meet gralifications specified in the FSAR.
The licensee advised the i*spector on October 16, 1978, that further investigation has vetermined that this was not a significant deficiency. The inspector reviewed the basis for this determination during this inspection. On the basis of the evaluation made by the licensee's A-E, RII has no further questionr. at this time.
(Closed) LII 364/78-07-06, Used unapproved aluminum tape. All the unapproved tape has been removed from safety-related cables. Twelve cables which were wrapped with the unapproved tape have not had the
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RII'Rpt. No. 50-364/78-21 I-3 tape removed but have been found to be non-safeguard cables in that they terminate in non-safety-related metering and relay panels. RII has no further questions at this time.
6.
IE Bulletins (IEB) and Circulars (IEC)
IEC 78-08 Environmental Qualification of Safety-Related Electrical Equipment at Nuclear Power Plants. The inspector reviewed the purchase specifications and manufacturers certifications for the stem mounted limit switches received at the site. The replacement limit switches are certified as being in compliance with IEEE Standards 323(1974),
344(1975) and 382(1972) per report of March 3,1978. The certificati<n further states that they meet the specification which includes the requirement of the FSAR.
These switches will be installed by the construction forces. This installation will be followed by the inspector and is identified as inspector followup item 364/78-21-03, Installation of qualified stem mounted lis. it switches.
7.
10 CFR 50 Part 21 Items (Closed) IFI 364/78-16-03, Diesel generator manufacturer reported deficiency, Part 21.
The licensee advised the inspector that the diesel generators had been released to the APC0 Production Department for operation with Unit 1 (Docket 50-348). The followup of the action to be taken regarding the rocker arms and fuel pump discrepancies will be addressed as open item in NRC Report 50-348/78-34.
8.
Exit Interview The inspector met with the licensee representatives and others denoted in paragraph I at the close of the inspection. The scope and findings of the inspection of QA audits, licensee identified items, unresolved items, infractions and IECs were discussed. The deficiency identified as 364/78-21-01, Audit Closures was discussed in detail.